Powered by Deep Web Technologies
Note: This page contains sample records for the topic "reheat packaged single-zone" 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.


1

Air-Side Energy Use Calculations for Four HVAC Systems: Dual Duct Constant Volume (DDCAV), Dual Duct Variable Volume (DDVAV), Constant Volume with Reheat (CAVRH), Variable Volume with Reheat (VAVRH), Four Pipe Fan Coil Unit (FC), Four Pipe Induction Unit (FI), and Single Zone (SZ) Systems, Revised June 2002  

E-Print Network [OSTI]

(CAVRH), and variable volume with reheat (VAVRH), four pipe fan coil unit (FC), four pipe induction unit (FI), and a single zone air conditioning system (SZ). These calculations are presented in spreadsheets that include a running commentary so...

Haberl, J. S.; Bou-Saada, T. E.; Saman, N. F.

2001-01-01T23:59:59.000Z

2

Probing reheating with primordial spectrum  

E-Print Network [OSTI]

We study the impacts of reheating temperature on the inflationary predictions of the spectral index and tensor-to-scalar ratio. Assuming that reheating process is very fast, the reheating temperature can be constrained for sinusoidal oscillation within a factor of 10 - 100 or even better with the prospect of future observations. Beyond this, we find that the predictions can also be insensitive to the reheating temperature in certain models, including the Higgs inflation.

Gong, Jinn-Ouk; Leung, Godfrey

2015-01-01T23:59:59.000Z

3

Reheating and causal thermodynamics  

Science Journals Connector (OSTI)

The reheating process in inflationary universe models is considered as an out-of-equilibrium mixture of two interacting and reacting fluids, and studied within the framework of causal, irreversible thermodynamics. The evolution of the temperature and the decay rate as determined by causal thermodynamics are estimated at different stages of the process. A simple model is also used to find the perturbations of the expansion rate, including the possibility of damped oscillations.

Winfried Zimdahl; Diego Pavón; Roy Maartens

1997-04-15T23:59:59.000Z

4

Advanced steel reheat furnace  

SciTech Connect (OSTI)

Energy and Environmental Research Corp. (EER) under a contract from the Department of Energy is pursuing the development and demonstration of an Advanced Steel Reheating Furnace. This paper reports the results of Phase 1, Research, which has evaluated an advanced furnace concept incorporating two proven and commercialized technologies previously applied to other high temperature combustion applications: EER`s gas reburn technology (GR) for post combustion NOx control; and Air Product`s oxy-fuel enrichment air (OEA) for improved flame heat transfer in the heating zones of the furnace. The combined technologies feature greater production throughput with associated furnace efficiency improvements; lowered NOx emissions; and better control over the furnace atmosphere, whether oxidizing or reducing, leading to better control over surface finish.

Moyeda, D.; Sheldon, M.; Koppang, R. [Energy and Environmental Research Corp., Irvine, CA (United States); Lanyi, M.; Li, X.; Eleazer, B. [Air Products and Chemicals, Inc., Allentown, PA (United States)

1997-10-01T23:59:59.000Z

5

Healthcare Energy: Spotlight on Reheat and Heating  

Broader source: Energy.gov [DOE]

The Building Technologies Office conducted a healthcare energy end-use monitoring project in partnership with two hospitals. Read highlights from monitoring heating and reheating energy.

6

GAS TURBINE REHEAT USING IN SITU COMBUSTION  

SciTech Connect (OSTI)

In situ reheat is an alternative to traditional gas turbine reheat design in which fuel is fed through airfoils rather than in a bulky discrete combustor separating HP and LP turbines. The goals are to achieve increased power output and/or efficiency without higher emissions. In this program the scientific basis for achieving burnout with low emissions has been explored. In Task 1, Blade Path Aerodynamics, design options were evaluated using CFD in terms of burnout, increase of power output, and possible hot streaking. It was concluded that Vane 1 injection in a conventional 4-stage turbine was preferred. Vane 2 injection after vane 1 injection was possible, but of marginal benefit. In Task 2, Combustion and Emissions, detailed chemical kinetics modeling, validated by Task 3, Sub-Scale Testing, experiments, resulted in the same conclusions, with the added conclusion that some increase in emissions was expected. In Task 4, Conceptual Design and Development Plan, Siemens Westinghouse power cycle analysis software was used to evaluate alternative in situ reheat design options. Only single stage reheat, via vane 1, was found to have merit, consistent with prior Tasks. Unifying the results of all the tasks, a conceptual design for single stage reheat utilizing 24 holes, 1.8 mm diameter, at the trailing edge of vane 1 is presented. A development plan is presented.

D.M. Bachovchin; T.E. Lippert; R.A. Newby P.G.A. Cizmas

2004-05-17T23:59:59.000Z

7

Superheated steam power plant with steam to steam reheater. [LMFBR  

SciTech Connect (OSTI)

A desuperheater is disposed in a steam supply line supplying superheated steam to a shell and tube reheater.

Silvestri, G.J.

1981-06-23T23:59:59.000Z

8

Reheating in chaotic D-term inflation  

Science Journals Connector (OSTI)

A simple model is discussed to give rise to successful reheating in chaotic D-term inflation with a quadratic inflaton potential, introducing a trilinear coupling in the Kähler potential. Leptogenesis through the inflaton decay is also discussed in this model.

Teruhiko Kawano and Masahide Yamaguchi

2008-12-05T23:59:59.000Z

9

Gas Turbine Reheat Using In-Situ Combustion  

SciTech Connect (OSTI)

Siemens Westinghouse Power Corporation (SWPC) is developing in-situ reheat (fuel injection via airfoil injection) as a means for increasing cycle efficiency and power output, with possibly reduced emissions. This report discusses engineering cycle evaluations on various reheat approaches, using GateCycle and ChemCad software simulations of typical F-class and G-class engines, modified for alternative reheat cycles. The conclusion that vane 1 reheat offers the most advantageous design agrees with the conclusions of the detailed chemical kinetics (Task 2) as verified by high temperature testing (Task 3) and Blade path CFD (Task 1) tasks. The second choice design option (vane 2 reheat after vane 1 reheat) is also validated in all tasks. A conceptual design and next recommended development tasks are presented.

R.A. Newby; D.M. Bachovchin; T.E. Lippert

2004-04-29T23:59:59.000Z

10

Dehumidification Without Re-heat Using Face and Bypass Dampers  

E-Print Network [OSTI]

Installations with chill water cooling, needing constant air volume and dehumidification, traditionally use a draw through air handling unit with a cooling coil and a re-heat coil. Dehumidification is achieved by overcooling the discharge air...

Warila, D. T.

1994-01-01T23:59:59.000Z

11

Exploring Maximum Humidity Control and Energy Conservation Opportunities with Single Duct Single Zone Air-Handling Units  

E-Print Network [OSTI]

Humidity control for single-duct single-zone (SDSZ) constant volume air handling units is known to be a challenge. The operation of these systems is governed by space temperature only. Under mild weather conditions, discharge air temperature can get...

Zhou, J.; Wei, G.; Turner, W. D.; Deng, S.; Claridge, D.

2006-01-01T23:59:59.000Z

12

Development of Next Generation Heating System for Scale Free Steel Reheating  

SciTech Connect (OSTI)

Teh report describes methods of reheating of steel billets and slabs for hot rolling or forging without forming steel scale.

Dr. Arvind C. Thekdi

2006-09-26T23:59:59.000Z

13

Steel project fact sheet: Steel reheating for further processing  

SciTech Connect (OSTI)

Steel reheating is an energy-intensive process requiring uniform temperature distribution within reheating furnaces. Historically, recuperators have ben used to preheat combustion air, thereby conserving energy. More recent innovations include oxygen enrichment and the use of regenerative burners, which provide higher preheat air temperatures than recuperators. These processes have limitations such as equipment deterioration, decreasing energy efficiency over time, high maintenance costs, and increased NO{sub x} emissions with increased air preheat temperature, unless special equipment is used. Praxair, Inc., supplier of oxygen and other industrial gases to the steel industry, proposes to introduce an innovative oxy-fuel burner technology (using 100% oxygen) to the steel reheating industry. Oxy-fuel combustion reduces or eliminates nitrogen in combustion air and substantially reduces waste heat carried out with flue gas. Based on technology currently used in the glass, hazardous waste, and aluminum industries, Praxair has developed and patented low temperature, oxy-fuel burners that can be used in high temperature industrial furnaces where temperature uniformity is critical and extremely low NO{sub x} emissions are desired. The technical goal of the project is to demonstrate the use of oxy-fuel burners in a slab reheat furnace while reducing energy consumption by 45% and NO{sub x} emissions by 90% within the converted furnace zones. Successful implementation of this technology also will eliminate the need to periodically replace recuperators and install NO{sub x} removal equipment.

NONE

1998-04-01T23:59:59.000Z

14

Reheating via a generalized nonminimal coupling of curvature to matter  

SciTech Connect (OSTI)

In this work, one shows that a generalized nonminimal coupling between geometry and matter is compatible with Starobinsky inflation and leads to a successful process of preheating, a reheating scenario based on the production of massive particles via parametric resonance. The model naturally extends the usual preheating mechanism, which resorts to an ad hoc scalar curvature-dependent mass term for a scalar field {chi}, and also encompasses a previously studied preheating channel based upon a nonstandard kinetic term.

Bertolami, Orfeu; Frazao, Pedro; Paramos, Jorge [Departamento de Fisica e Astronomia, Faculdade de Ciencias, Universidade do Porto, Rua do Campo Alegre 687, 4169-007 Porto (Portugal); Instituto de Plasmas e FuSao Nuclear, Instituto Superior Tecnico Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal)

2011-02-15T23:59:59.000Z

15

Multiple reheat helium Brayton cycles for sodium fast reactors  

SciTech Connect (OSTI)

Sodium fast reactors (SFR) traditionally adopt the steam Rankine cycle for power conversion. The resulting potential for water-sodium reaction remains a continuing concern which at least partly delays the SFR technology commercialization and is a contributor to higher capital cost. Supercritical CO2 provides an alternative, but is also capable of sustaining energetic chemical reactions with sodium. Recent development on advanced inert-gas Brayton cycles could potentially solve this compatibility issue, increase thermal efficiency, and bring down the capital cost close to light water reactors. In this paper, helium Brayton cycles with multiple reheat and intercooling states are presented for SFRs with reactor outlet temperatures in the range of 510°C to 650°C. The resulting thermal efficiencies range from 39% and 47%, which is comparable with supercritical recompression CO2 cycles (SCO2 cycle). A systematic comparison between multiple reheat helium Brayton cycle and the SCO2 cycle is given, considering compatibility issues, plant site cooling temperature effect on plant efficiency, full plant cost optimization, and other important factors. The study indicates that the multiple reheat helium cycle is the preferred choice over SCO2 cycle for sodium fast reactors.

Haihua Zhao; Per F. Peterson

2008-07-01T23:59:59.000Z

16

Improving the efficiency and availability analysis of a modified reheat regenerative Rankine cycle  

SciTech Connect (OSTI)

Reheating in a reheat regenerative steam power cycle increases efficiency by increasing the average temperature of heat reception, but also increases the irreversibility of feed water heaters by raising the temperature of the superheated steam used for the regenerative process. This paper introduces some modifications to the regular reheat regenerative steam power cycle that reduce the irreversibility of the regenerative process. An availability analysis of the modified cycle and the regular reheat regenerative cycle as well as a comparison study between both cycles is done. The results indicate that a gain in energy efficiency of up to 2.5% as the steam generator pressure varies is obtained when applying such modifications at the same conditions of pressure, temperature's number of reheating stages, and feed water heaters. The availability analysis showed that such increase in efficiency is due to the reduction of the irreversibility of the regeneration process of the modified cycle.

Bassily, A.M.

1999-07-01T23:59:59.000Z

17

Modeling fuzzy state space of reheater system for simulation and analysis  

Science Journals Connector (OSTI)

Reheater is one of the important heat exchange components in a high capacity power plant of a boiler system. The aim of this study is to improve heat transfer of a reheater system. The method is to maximize steam production and at the same time keeping variables within constraints. Fuzzy arithmetic is a powerful tool used to solve engineering problems with uncertain parameters. Therefore in order to determine heat transfer efficiency the state space of reheater is simulated using fuzzy arithmetic by taking into account the uncertainties in the reheater system. The uncertain model parameters and the model inputs are represented by fuzzy numbers with their shape derived from quasi-Gaussian function. Finally this paper discusses how the mathematical model can be manipulated in order to produce maximum heat transfer with least loss of energy. Furthermore the improvement of the reheater efficiency and the quantification of the heat supplied parameters are presented in this paper.

2014-01-01T23:59:59.000Z

18

ElectronicPackaging  

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

Packaging Packaging Manufacturing Technologies The Electronic Packaging technologies in the Thin Film, Vacuum, and Packaging Department are a resource for all aspects of microelectronic packag- ing. From design and layout to fabrication of proto- type samples, the staff offers partners the opportu- nity for concurrent engineering and development of a variety of electronic packaging concepts. This includes assistance in selecting the most appropri- ate technology for manufacturing, analysis of per- formance characteristics and development of new and unique processes. Capabilities 1. Network Fabrication * Low Temperature Co-Fired Ceramic (LTCC) * Thick Film * Thin Film 2. Packaging and Assembly * Chip Level Packaging * MEMs Packaging * Hermetic Sealing * Surface Mount Technology

19

Microsoft Word - 40913_SWPC_GT Reheat Insitu Combustion_Factsheet_Rev01_00-00-03.doc  

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

0913_SWPC_GT REHEAT INSITU COMBUSTION_FACTSHEET_REV01_00-00-03.DOC 0913_SWPC_GT REHEAT INSITU COMBUSTION_FACTSHEET_REV01_00-00-03.DOC Gas Turbine Reheat Using In-Situ Combustion FACT SHEET I. PROJECT PARTICIPANTS A. Prime Participant: Siemens Westinghouse Power Corp. B. Sub-Award Participant: Texas A&M University II. PROJECT DESCRIPTION A. Objectives: The overall objective of this project is to develop a novel gas reheat concept for gas turbine engines, in which fuel is injected directly into the turbine through one or more stages of vanes and/or blades. The key research goals involved in concept selection are to understand the combustion kinetics (burnout, emissions), blade performance and effects on turbine power output and efficiency. The concept is being evaluated for maximum energy efficiency (full reheat) and as a means to achieve power boost

20

Cost Estimation Package  

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

This chapter focuses on the components (or elements) of the cost estimation package and their documentation.

1997-03-28T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Study of structure formation and reheating in the D3/D7 brane inflation model  

Science Journals Connector (OSTI)

We study the spectrum of cosmological fluctuations in the D3/D7 brane inflationary universe with particular attention to the parametric excitation of entropy modes during the reheating stage. The same tachyonic instability which renders reheating in this model very rapidly leads to an exponential growth of entropy fluctuations during the preheating stage which in turn may induce a large contribution to the large-scale curvature fluctuations. We take into account the effects of long wavelength quantum fluctuations in the matter fields. As part of this work, we perform an analytical analysis of the reheating process. We find that the initial stage of preheating proceeds by the tachyonic instability channel. An upper bound on the time it takes for the energy initially stored in the inflaton field to convert into fluctuations is obtained by neglecting the local fluctuations produced during the period of tachyonic decay and analyzing the decay of the residual homogeneous field oscillations, which proceeds by parametric resonance. We show that, in spite of the fact that the resonance is of the narrow-band type, it is sufficiently efficient to rapidly convert most of the energy of the background fields into matter fluctuations.

Robert H. Brandenberger; Keshav Dasgupta; Anne-Christine Davis

2008-10-02T23:59:59.000Z

22

CH Packaging Operations Manual  

SciTech Connect (OSTI)

This procedure provides instructions for assembling the CH Packaging Drum payload assembly, Standard Waste Box (SWB) assembly, Abnormal Operations and ICV and OCV Preshipment Leakage Rate Tests on the packaging seals, using a nondestructive Helium (He) Leak Test.

Washington TRU Solutions LLC

2005-06-13T23:59:59.000Z

23

CH Packaging Operations Manual  

SciTech Connect (OSTI)

Introduction - This procedure provides instructions for assembling the following CH packaging payload: -Drum payload assembly -Standard Waste Box (SWB) assembly -Ten-Drum Overpack (TDOP).

Washington TRU Solutions LLC

2003-06-26T23:59:59.000Z

24

Packaging of agrochemicals  

Science Journals Connector (OSTI)

Viewed from a historical perspective, those engaged in development and selection of packaging for agrochemicals were interested primarily in getting products to...

P. D. Curle; C. D. Emmerson; A. H. Gregory…

1998-01-01T23:59:59.000Z

25

NRF TRIGA packaging  

SciTech Connect (OSTI)

Training Reactor Isotopes, General Atomics (TRIGA{reg_sign}) Reactors are in use at four US Department of Energy (DOE) complex facilities and at least 23 university, commercial, or government facilities. The development of the Neutron Radiography Facility (NRF) TRIGA packaging system began in October 1993. The Hanford Site NRF is being shut down and requires an operationally user-friendly transportation and storage packaging system for removal of the TRIGA fuel elements. The NRF TRIGA packaging system is designed to remotely remove the fuel from the reactor and transport the fuel to interim storage (up to 50 years) on the Hanford Site. The packaging system consists of a cask and an overpack. The overpack is used only for transport and is not necessary for storage. Based upon the cask`s small size and light weight, small TRIGA reactors will find it versatile for numerous refueling and fuel storage needs. The NRF TRIGA packaging design also provides the basis for developing a certifiable and economical packaging system for other TRIGA reactor facilities. The small size of the NRF TRIGA cask also accommodates placing the cask into a larger certified packaging for offsite transport. The Westinghouse Hanford Company NRF TRIGA packaging, as described herein can serve other DOE sites for their onsite use, and the design can be adapted to serve university reactor facilities, handling a variety of fuel payloads.

Clements, M.D.

1995-11-01T23:59:59.000Z

26

RH Packaging Operations Manual  

SciTech Connect (OSTI)

This procedure provides operating instructions for the RH-TRU 72-B Road Cask, Waste Shipping Package. In this document, ''Packaging'' refers to the assembly of components necessary to ensure compliance with the packaging requirements (not loaded with a payload). ''Package'' refers to a Type B packaging that, with its radioactive contents, is designed to retain the integrity of its containment and shielding when subject to the normal conditions of transport and hypothetical accident test conditions set forth in 10 CFR Part 71. Loading of the RH 72-B cask can be done two ways, on the RH cask trailer in the vertical position or by removing the cask from the trailer and loading it in a facility designed for remote-handling (RH). Before loading the 72-B cask, loading procedures and changes to the loading procedures for the 72-B cask must be sent to CBFO at sitedocuments@wipp.ws for approval.

Washington TRU Solutions LLC

2003-09-17T23:59:59.000Z

27

Surveying and Cartography Packages  

Science Journals Connector (OSTI)

In attempting to meet the need for the very large number of different calculations that surveyors have to perform, surveying packages become collections of many diverse computation routines. For example, Survey S...

Howard Falk

1986-01-01T23:59:59.000Z

28

Packaging and Transportation Safety  

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

Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1.

1996-10-02T23:59:59.000Z

29

Packaging and Transportation Safety  

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

Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Canceled by DOE 460.1A

1995-09-27T23:59:59.000Z

30

Nuclear Material Packaging Manual  

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

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

2008-03-07T23:59:59.000Z

31

CH Packaging Program Guidance  

SciTech Connect (OSTI)

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP charges the WIPP management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document provides the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

Washington TRU Solutions LLC

2003-04-30T23:59:59.000Z

32

CH Packaging Program Guidance  

SciTech Connect (OSTI)

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT Shipping Package, and directly related components. This document complies with the minimum requirements as specified in TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event there is a conflict between this document and the SARP or C of C, the SARP and/or C of C shall govern. C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SAR P charges the WIPP Management and Operation (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize these operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

Washington TRU Solutions LLC

2002-03-04T23:59:59.000Z

33

RH Packaging Program Guidance  

SciTech Connect (OSTI)

The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

Washington TRU Solutions LLC

2008-01-12T23:59:59.000Z

34

RH Packaging Program Guidance  

SciTech Connect (OSTI)

The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

Washington TRU Solutions LLC

2006-11-07T23:59:59.000Z

35

CH Packaging Program Guidance  

SciTech Connect (OSTI)

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.

Washington TRU Solutions LLC

2005-02-28T23:59:59.000Z

36

Radioactive waste disposal package  

DOE Patents [OSTI]

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

37

Packaging and Transportation Safety  

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

To establish safety requirements for the proper packaging and transportation of Department of Energy (DOE)/National Nuclear Security Administration (NNSA) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1A. Canceled by DOE O 460.1C.

2003-04-04T23:59:59.000Z

38

Packaging and Transportation Safety  

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

The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of radioactive and other hazardous materials and for modal transportation. Cancels DOE O 460.1B, 5-14-10

2010-05-14T23:59:59.000Z

39

Waste disposal package  

DOE Patents [OSTI]

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Smith, M.J.

1985-06-19T23:59:59.000Z

40

RH Packaging Program Guidance  

SciTech Connect (OSTI)

The purpose of this program guidance document is to provide technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the SARP and/or C of C shall govern. The C of C states: ''...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, ''Operating Procedures,'' of the application.'' It further states: ''...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, ''Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC approved, users need to be familiar with 10 CFR {section} 71.11, ''Deliberate Misconduct.'' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions. Following these instructions assures that operations are safe and meet the requirements of the SARP. This document is available on the Internet at: ttp://www.ws/library/t2omi/t2omi.htm. Users are responsible for ensuring they are using the current revision and change notices. Sites may prepare their own document using the word-for-word steps in th is document, in sequence, including Notes and cautions. Site specific information may be included as necessary. The document, and revisions, must then be submitted to CBFO at sitedocuments@wipp.ws for approval. A copy of the approval letter from CBFO shall be available for audit purposes. Users may develop site-specific procedures addressing preoperational activities, quality assurance (QA), hoisting and rigging, and radiation health physics to be used with the instructions contained in this document. Users may recommend changes to this document by submitting their recommendations (in writing) to the WIPP M&O Contractor RH Packaging Maintenance Engineer for evaluation. If approved, the change(s) will be incorporated into this document for use by ALL users. Before first use and every 12 months after, user sites will be audited to this document to ensure compliance. They will also be audited within one year from the effective date of revisions to this document.

Washington TRU Solutions, LLC

2003-08-25T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Optimal segmentation and packaging process  

DOE Patents [OSTI]

A process for improving packaging efficiency uses three dimensional, computer simulated models with various optimization algorithms to determine the optimal segmentation process and packaging configurations based on constraints including container limitations. The present invention is applied to a process for decontaminating, decommissioning (D&D), and remediating a nuclear facility involving the segmentation and packaging of contaminated items in waste containers in order to minimize the number of cuts, maximize packaging density, and reduce worker radiation exposure. A three-dimensional, computer simulated, facility model of the contaminated items are created. The contaminated items are differentiated. The optimal location, orientation and sequence of the segmentation and packaging of the contaminated items is determined using the simulated model, the algorithms, and various constraints including container limitations. The cut locations and orientations are transposed to the simulated model. The contaminated items are actually segmented and packaged. The segmentation and packaging may be simulated beforehand. In addition, the contaminated items may be cataloged and recorded.

Kostelnik, Kevin M. (Idaho Falls, ID); Meservey, Richard H. (Idaho Falls, ID); Landon, Mark D. (Idaho Falls, ID)

1999-01-01T23:59:59.000Z

42

Apparatus and methods of reheating gas turbine cooling steam and high pressure steam turbine exhaust in a combined cycle power generating system  

DOE Patents [OSTI]

In a combined cycle system having a multi-pressure heat recovery steam generator, a gas turbine and steam turbine, steam for cooling gas turbine components is supplied from the intermediate pressure section of the heat recovery steam generator supplemented by a portion of the steam exhausting from the HP section of the steam turbine, steam from the gas turbine cooling cycle and the exhaust from the HP section of the steam turbine are combined for flow through a reheat section of the HRSG. The reheated steam is supplied to the IP section inlet of the steam turbine. Thus, where gas turbine cooling steam temperature is lower than optimum, a net improvement in performance is achieved by flowing the cooling steam exhausting from the gas turbine and the exhaust steam from the high pressure section of the steam turbine in series through the reheater of the HRSG for applying steam at optimum temperature to the IP section of the steam turbine.

Tomlinson, Leroy Omar (Niskayuna, NY); Smith, Raub Warfield (Ballston Lake, NY)

2002-01-01T23:59:59.000Z

43

The rotfloat package* Axel Sommerfeldt  

E-Print Network [OSTI]

What has changed since version 1.0? Version 1.0 of this package was a quick & dirty hack. The version

Mintmire, John W.

44

BEA Benefits Programs and Packages  

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

Plant Docs CONTACT US Center for Advanced Energy Studies Benefits Battelle Energy Alliance, LLC, offers a comprehensive and competitive benefits package designed to provide...

45

Use of Multiple Reheat Helium Brayton Cycles to Eliminate the Intermediate Heat Transfer Loop for Advanced Loop Type SFRs  

SciTech Connect (OSTI)

The sodium intermediate heat transfer loop is used in existing sodium cooled fast reactor (SFR) plant design as a necessary safety measure to separate the radioactive primary loop sodium from the water of the steam Rankine power cycle. However, the intermediate heat transfer loop significantly increases the SFR plant cost and decreases the plant reliability due to the relatively high possibility of sodium leakage. A previous study shows that helium Brayton cycles with multiple reheat and intercooling for SFRs with reactor outlet temperature in the range of 510°C to 650°C can achieve thermal efficiencies comparable to or higher than steam cycles or recently proposed supercritical CO2 cycles. Use of inert helium as the power conversion working fluid provides major advantages over steam or CO2 by removing the requirement for safety systems to prevent and mitigate the sodium-water or sodium-CO2 reactions. A helium Brayton cycle power conversion system therefore makes the elimination of the intermediate heat transfer loop possible. This paper presents a pre-conceptual design of multiple reheat helium Brayton cycle for an advanced loop type SFR. This design widely refers the new horizontal shaft distributed PBMR helium power conversion design features. For a loop type SFR with reactor outlet temperature 550°C, the design achieves 42.4% thermal efficiency with favorable power density comparing with high temperature gas cooled reactors.

Haihua Zhao; Hongbin Zhang; Samuel E. Bays

2009-05-01T23:59:59.000Z

46

The Packaging Handbook -- A guide to package design  

SciTech Connect (OSTI)

The Packaging Handbook is a compilation of 14 technical chapters and five appendices that address the life cycle of a packaging which is intended to transport radioactive material by any transport mode in normal commerce. Although many topics are discussed in depth, this document focuses on the design aspects of a packaging. The Handbook, which is being prepared under the direction of the US Department of Energy, is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators in specific aspects of packaging design, and the types of analyses that should be seriously considered when developing the packaging design. Even though the Handbook is concerned with all packagings, most of the emphasis is placed on large packagings that are capable of transporting large radioactive sources that are also fissile (e.g., spent fuel). These are the types of packagings that must address the widest range of technical topics in order to meet domestic and international regulations. Most of the chapters in the Handbook have been drafted and submitted to the Oak Ridge National Laboratory for editing; the majority of these have been edited. This report summarizes the contents.

Shappert, L.B.

1995-12-31T23:59:59.000Z

47

Building an R package Division of Biostatistics  

E-Print Network [OSTI]

Building an R package Yen-Yi Ho Division of Biostatistics School of Public Health, University of Minnesota Yen-Yi Ho Building an R package #12;Steps Prepare your functions, example data sets Build package in man subdirectory) Write a package vignette Build and install the R package (R CMD build) Check the R

Carlin, Bradley P.

48

Tritium waste package  

DOE Patents [OSTI]

A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

49

Tritium waste package  

DOE Patents [OSTI]

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

50

( 'tams Dlvllan LSPE EXPLOSIVE PACKAGE  

E-Print Network [OSTI]

requirement from a thermal standpoint is that the thermal battery and safe-arm timers be at 40°F minimum and thermal battery timers be at +40°F minimum operating temperature immediately at the time of treir~ ( ·'tams Dlvl·lan LSPE EXPLOSIVE PACKAGE STOWAGE THERMAL CONSTRAINTS LSPE EXPLOSIVE PACKAGE

Rathbun, Julie A.

51

Chapter 21 - Recycling of Packaging  

Science Journals Connector (OSTI)

Abstract Packaging is so common throughout our lives and the world that we hardly realize the massive volume of material consumed for packaging. Packaging is the key factor determining the volume and composition of municipal solid waste in many countries. The volume and composition of packaging waste are affected by a number of factors. Economic development, population, and a variety of national factors are key drivers for the total volume. The composition changes over time due to technology and economic drivers, but it is also affected by national traditions and policies. Due to the important contribution to the total volume of waste generated, packaging has historically received a lot of attention in waste management policy. This had led to a range of experiences with different ways to collect packaging waste throughout the world. The type of collection scheme is driven by the type of packaging or material (i.e. reuse, recycling, or waste treatment). Recycling rates vary by material type, with the highest collection and recycling rates found for metals, glass, and paper. Collection and recycling rates of plastics are generally still very low. The effectiveness and efficiency of collection are affected by a variety of factors, including cultural, economic, and organizational factors.

Ernst Worrell

2014-01-01T23:59:59.000Z

52

Review of SAR for Packaging Report  

Broader source: Energy.gov [DOE]

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material.

53

Power Device Packaging | Department of Energy  

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

Power Device Packaging Power Device Packaging 2011 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation...

54

Power Device Packaging | Department of Energy  

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

Power Device Packaging Power Device Packaging 2010 DOE Vehicle Technologies and Hydrogen Programs Annual Merit Review and Peer Evaluation Meeting, June 7-11, 2010 -- Washington...

55

FAQS Qualification Card - NNSA Package Certification Engineer...  

Office of Environmental Management (EM)

Qualification Card - NNSA Package Certification Engineer FAQS Qualification Card - NNSA Package Certification Engineer A key element for the Department's Technical Qualification...

56

Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings  

SciTech Connect (OSTI)

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope and requirements of reviews; and (5) Provide the above information to DOE organizations, contractors, other government agencies, and interested members of the general public. This PRG was originally published in September 1987. Revision 1, issued in October 1988, added new review sections on quality assurance and penetrations through the containment boundary, along with a few other items. Revision 2 was published October 1999. Revision 3 of this PRG is a complete update, and supersedes Revision 2 in its entirety.

DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

2007-04-12T23:59:59.000Z

57

The reduction of packaging waste  

SciTech Connect (OSTI)

Nationwide, packaging waste comprises approximately one-third of the waste disposed in sanitary landfills. the US Department of Energy (DOE) generated close to 90,000 metric tons of sanitary waste. With roughly one-third of that being packaging waste, approximately 30,000 metric tons are generated per year. The purpose of the Reduction of Packaging Waste project was to investigate opportunities to reduce this packaging waste through source reduction and recycling. The project was divided into three areas: procurement, onsite packaging and distribution, and recycling. Waste minimization opportunities were identified and investigated within each area, several of which were chosen for further study and small-scale testing at the Hanford Site. Test results, were compiled into five ``how-to`` recipes for implementation at other sites. The subject of the recipes are as follows: (1) Vendor Participation Program; (2) Reusable Containers System; (3) Shrink-wrap System -- Plastic and Corrugated Cardboard Waste Reduction; (4) Cardboard Recycling ; and (5) Wood Recycling.

Raney, E.A.; Hogan, J.J.; McCollom, M.L.; Meyer, R.J.

1994-04-01T23:59:59.000Z

58

Reference waste package environment report  

SciTech Connect (OSTI)

One of three candidate repository sites for high-level radioactive waste packages is located at Yucca Mountain, Nevada, in rhyolitic tuff 700 to 1400 ft above the static water table. Calculations indicate that the package environment will experience a maximum temperature of {similar_to}230{sup 0}C at 9 years after emplacement. For the next 300 years the rock within 1 m of the waste packages will remain dehydrated. Preliminary results suggest that the waste package radiation field will have very little effect on the mechanical properties of the rock. Radiolysis products will have a negligible effect on the rock even after rehydration. Unfractured specimens of repository rock show no change in hydrologic characteristics during repeated dehydration-rehydration cycles. Fractured samples with initially high permeabilities show a striking permeability decrease during dehydration-rehydration cycling, which may be due to fracture healing via deposition of silica. Rock-water interaction studies demonstrate low and benign levels of anions and most cations. The development of sorptive secondary phases such as zeolites and clays suggests that anticipated rock-water interaction may produce beneficial changes in the package environment.

Glassley, W.E.

1986-10-01T23:59:59.000Z

59

Package for integrated optic circuit and method  

DOE Patents [OSTI]

A structure and method for packaging an integrated optic circuit. The package comprises a first wall having a plurality of microlenses formed therein to establish channels of optical communication with an integrated optic circuit within the package. A first registration pattern is provided on an inside surface of one of the walls of the package for alignment and attachment of the integrated optic circuit. The package in one embodiment may further comprise a fiber holder for aligning and attaching a plurality of optical fibers to the package and extending the channels of optical communication to the fibers outside the package. In another embodiment, a fiber holder may be used to hold the fibers and align the fibers to the package. The fiber holder may be detachably connected to the package.

Kravitz, Stanley H. (26 Aspen Rd., Placitas, NM 87043); Hadley, G. Ronald (6012 Annapolis NE., Albuquerque, NM 87111); Warren, Mial E. (3825 Mary Ellen NE., Albuquerque, NM 87111); Carson, Richard F. (1036 Jewel Pl. NE., Albuquerque, NM 87123); Armendariz, Marcelino G. (1023 Oro Real NE., Albuquerque, NM 87123)

1998-01-01T23:59:59.000Z

60

Package for integrated optic circuit and method  

DOE Patents [OSTI]

A structure and method are disclosed for packaging an integrated optic circuit. The package comprises a first wall having a plurality of microlenses formed therein to establish channels of optical communication with an integrated optic circuit within the package. A first registration pattern is provided on an inside surface of one of the walls of the package for alignment and attachment of the integrated optic circuit. The package in one embodiment may further comprise a fiber holder for aligning and attaching a plurality of optical fibers to the package and extending the channels of optical communication to the fibers outside the package. In another embodiment, a fiber holder may be used to hold the fibers and align the fibers to the package. The fiber holder may be detachably connected to the package. 6 figs.

Kravitz, S.H.; Hadley, G.R.; Warren, M.E.; Carson, R.F.; Armendariz, M.G.

1998-08-04T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Chapter 7: Integration and Packaging Page 127 Integration and Packaging  

E-Print Network [OSTI]

and bonded to its package. The chemical sensors are suspended on a platform, thermally isolated from the circuits in a sacrificial layer of opaque material such as metal. The fabrication of chemical sensors temperature) do not operate well at typical operating temperatures for chemical sensors (over 100°C

Wilson, Denise

62

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect (OSTI)

The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

McCarthy, T.L.

1995-12-01T23:59:59.000Z

63

Examples of Cost Estimation Packages  

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

Estimates can be performed in a variety of ways. Some of these are for projects for an undefined scope, a conventional construction project, or where there is a level of effort required to complete the work. Examples of cost estimation packages for these types of projects are described in this appendix.

1997-03-28T23:59:59.000Z

64

EM Office of Packaging and Transportation | Department of Energy  

Office of Environmental Management (EM)

EM Office of Packaging and Transportation EM Office of Packaging and Transportation EM Office of Packaging and Transportation More Documents & Publications 2009 TEPP Annual Report...

65

Departmental Materials Transportation and Packaging Management  

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

Establishes requirements and responsibilities for management of Department of Energy (DOE), including National Nuclear Security Administration, materials transportation and packaging and ensures the safe, secure, efficient packaging and transportation of materials, both hazardous and non-hazardous.

2010-11-18T23:59:59.000Z

66

Material efficiency in Dutch packaging policy  

Science Journals Connector (OSTI)

...Dutch packaging policy history: three voluntary agreements (1991-2005...global language for packaging and sustainability; a framework and a measurement...Part of The Consumer Goods Forum Sustainability Pillar. See http://www.vics...

2013-01-01T23:59:59.000Z

67

ASSISTANT PROFESSOR (SEMI-RIGID PLASTIC PACKAGING)  

E-Print Network [OSTI]

ASSISTANT PROFESSOR (SEMI-RIGID PLASTIC PACKAGING) IN FOOD, NUTRITION, & PACKAGING SCIENCES/rigid plastics packaging. The successful candidate will be responsible for teaching undergraduate and graduate in university teaching, experience in designing and implementing semi-rigid/rigid plastics research, a record

Stuart, Steven J.

68

YUCCA MOUNTAIN WASTE PACKAGE CLOSURE SYSTEM  

SciTech Connect (OSTI)

The method selected for dealing with spent nuclear fuel in the US is to seal the fuel in waste packages and then to place them in an underground repository at the Yucca Mountain Site in Nevada. This article describes the Waste Package Closure System (WPCS) currently being designed for sealing the waste packages.

G. Housley; C. Shelton-davis; K. Skinner

2005-08-26T23:59:59.000Z

69

LM337...KTE, KTP, OR KVU PACKAGE LM337...KTT (TO-263) PACKAGE  

E-Print Network [OSTI]

1FEATURES LM337...KTE, KTP, OR KVU PACKAGE (TOP VIEW) OUTPUT INPUT ADJUSTMENT INPUT INPUT LM337...KTT (TO-263) PACKAGE (TOP VIEW) OUTPUT INPUT ADJUSTMENT LM237, LM337...KC (TO-220) PACKAGE (TOP VIEW) INPUT OUTPUT ADJUSTMENT INPUT OUTPUT LM337...KCS (TO-220) PACKAGE (TOP VIEW) ADJUSTMENT INPUT INPUT

Ravikumar, B.

70

Packaging and Transportation | Department of Energy  

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

Packaging and Transportation Packaging and Transportation Packaging and Transportation Packaging and Transportation Radiological shipments are accomplished safely. Annually, about 400 million hazardous materials shipments occur in the United States by rail, air, sea, and land. Of these shipments, about three million are radiological shipments. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material/waste. Please click here to see Office of Packaging and Transportation Fiscal Year 2012 Annual Report. SUPPORTING PROGRAMS SAFE TRANSPORTATION OF RADIOLOGICAL SHIPMENTS Transportation Emergency Preparedness Program (TEPP) TEPP provides the tools for planning, training and exercises, and technical assistance to assist State and Tribal authorities in preparing for response

71

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect (OSTI)

Radioactive material packages are withdrawn from use for various reasons; loss of mission, decertification, damage, replacement, etc. While the packages themselves may be decertified, various components may still be able to perform to their required standards and find useful service. The Packaging Technology and Pressurized Systems group of the Savannah River National Laboratory has been reducing the cost of producing new Type B Packagings by reclaiming, refurbishing, and returning to service the containment vessels from older decertified packagings. The program and its benefits are presented.

Abramczyk, G.; Nathan, S.; Loftin, B.; Bellamy, S.

2011-06-06T23:59:59.000Z

72

Radioactive material package seal tests  

SciTech Connect (OSTI)

General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

1990-01-01T23:59:59.000Z

73

Packaging  

E-Print Network [OSTI]

products to building brand images. An Infiniti automobilea clearly defined brand image. ” 114 The growth of theof presenting a meta-brand or image appealing to so many but

Galloway, Catherine Suzanne

2012-01-01T23:59:59.000Z

74

Packaging of electro-microfluidic devices  

DOE Patents [OSTI]

A new architecture for packaging surface micromachined electro-microfluidic devices is presented. This architecture relies on two scales of packaging to bring fluid to the device scale (picoliters) from the macro-scale (microliters). The architecture emulates and utilizes electronics packaging technology. The larger package consists of a circuit board with embedded fluidic channels and standard fluidic connectors (e.g. Fluidic Printed Wiring Board). The embedded channels connect to the smaller package, an Electro-Microfluidic Dual-Inline-Package (EMDIP) that takes fluid to the microfluidic integrated circuit (MIC). The fluidic connection is made to the back of the MIC through Bosch-etched holes that take fluid to surface micromachined channels on the front of the MIC. Electrical connection is made to bond pads on the front of the MIC.

Benavides, Gilbert L. (Albuquerque, NM); Galambos, Paul C. (Albuquerque, NM); Emerson, John A. (Albuquerque, NM); Peterson, Kenneth A. (Albuquerque, NM); Giunta, Rachel K. (Albuquerque, NM); Zamora, David Lee (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2003-04-15T23:59:59.000Z

75

Packaging of electro-microfluidic devices  

DOE Patents [OSTI]

A new architecture for packaging surface micromachined electro-microfluidic devices is presented. This architecture relies on two scales of packaging to bring fluid to the device scale (picoliters) from the macro-scale (microliters). The architecture emulates and utilizes electronics packaging technology. The larger package consists of a circuit board with embedded fluidic channels and standard fluidic connectors (e.g. Fluidic Printed Wiring Board). The embedded channels connect to the smaller package, an Electro-Microfluidic Dual-Inline-Package (EMDIP) that takes fluid to the microfluidic integrated circuit (MIC). The fluidic connection is made to the back of the MIC through Bosch-etched holes that take fluid to surface micromachined channels on the front of the MIC. Electrical connection is made to bond pads on the front of the MIC.

Benavides, Gilbert L. (Albuquerque, NM); Galambos, Paul C. (Albuquerque, NM); Emerson, John A. (Albuquerque, NM); Peterson, Kenneth A. (Albuquerque, NM); Giunta, Rachel K. (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2002-01-01T23:59:59.000Z

76

FAQS Qualification Card - NNSA Package Certification Engineer |  

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

NNSA Package Certification Engineer NNSA Package Certification Engineer FAQS Qualification Card - NNSA Package Certification Engineer A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NNSAPackageCertificationEngineer.docx Description NNSA Package Certification Engineer Qualification Card

77

FAQS Reference Guide – NNSA Package Certification Engineer  

Broader source: Energy.gov [DOE]

This reference guide addresses the competency statements in the February 2009 edition of DOE-STD-1026-2009, NNSA Package Certification Engineer Functional Area Qualification Standard.

78

CH Packaging Operations for High Wattage Waste  

SciTech Connect (OSTI)

This document provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)

Washington TRU Solutions LLC

2006-01-06T23:59:59.000Z

79

Hazardous Material Packaging for Transport - Administrative Procedures  

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

To establ1sh administrative procedures for the certification and use of radioactive and other hazardous materials packaging by the Department of Energy (DOE).

1986-09-30T23:59:59.000Z

80

Departmental Materials Transportation and Packaging Management  

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

The Order establishes requirements and responsibilities for management of Department of Energy (DOE), including National Nuclear Security Administration (NNSA), materials transportation and packaging to ensure the safe, secure, efficient packaging and transportation of materials, both hazardous and nonhazardous. Cancels DOE O 460.2 and DOE O 460.2 Chg 1

2004-12-22T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Depleted Uranium (DU) Cermet Waste Package  

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

Package Package Depleted Uranium (DU) Cermet Waste Package The steel components of the waste package could be replaced with a uranium cermet. The cermet contains uranium dioxide particulates, which are embedded in steel. Cermets are made with outer layers of clean steel; thus, there is no radiation-contamination hazard in handling the waste packages. Because cermets are made of the same materials that would normally be found in the YM repository (uranium dioxide and steel), there are no chemical compatibility issues. From half to all of the DU inventory in the United States could be used for this application. Depleted Uranium Dioxide Steel Cermet Cross Section of a Depleted Uranium Dioxide Steel Cermet Follow the link below for more information on Cermets:

82

The bracket-hack package Christopher Roman Nerz  

E-Print Network [OSTI]

The bracket-hack package Christopher Roman Nerz June 5, 2014 Abstract This small LATEX-package1 := and =: to be \\coloneqq (..=) and \\eqqcolon (=..), respectively. brackethack@phoenixes.de 1This package is a `dirty-hack

Ould Ahmedou, Mohameden

83

Simplification of Diesel Emission Control System Packaging Using...  

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

Simplification of Diesel Emission Control System Packaging Using SCR Coated on DPF Simplification of Diesel Emission Control System Packaging Using SCR Coated on DPF Study...

84

Electronic Packaging Materials and Their Functions in Thermal Managements  

Science Journals Connector (OSTI)

Advanced electronic packaging materials play a key role in the proper functioning and useful life of the packaged electronic assembly. These functions mainly include electrical conduction, electrical insulatio...

Xingcun Colin Tong

2011-01-01T23:59:59.000Z

85

CRAD, Packaging and Transfer of Hazardous Materials and Materials...  

Office of Environmental Management (EM)

and a Packaging, Transfer, and Transportation Plan DOE O 461.1, 4b(2)e, "Quality Assurance Plan and Packaging, Transfer, and Transportation Plan".. Training...

86

Low-Cost Packaged CHP System with Reduced Emissions - Presentation...  

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

Low-Cost Packaged CHP System with Reduced Emissions - Presentation by Cummins Power Generation, June 2011 Low-Cost Packaged CHP System with Reduced Emissions - Presentation by...

87

2014-08-28 Issuance: Energy Conservation Standards for Packaged...  

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

Conservation Standards for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps; Notice of Proposed Rulemaking and Public Meeting 2014-08-28 Issuance: Energy...

88

High-Temperature, Air-Cooled Traction Drive Inverter Packaging...  

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

Temperature, Air-Cooled Traction Drive Inverter Packaging High-Temperature, Air-Cooled Traction Drive Inverter Packaging 2010 DOE Vehicle Technologies and Hydrogen Programs Annual...

89

Hail Impact Testing on Crystalline Si Modules with Flexible Packaging...  

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

Hail Impact Testing on Crystalline Si Modules with Flexible Packaging Hail Impact Testing on Crystalline Si Modules with Flexible Packaging Presented at the PV Module Reliability...

90

Combined Heat and Power (CHP) Integrated with Burners for Packaged...  

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

Combined Heat and Power (CHP) Integrated with Burners for Packaged Boilers Combined Heat and Power (CHP) Integrated with Burners for Packaged Boilers Providing Clean, Low-Cost,...

91

Pre-Packaged Commercial Property-Accessed Clean Energy Financing...  

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

Packaged Commercial Property-Accessed Clean Energy Financing Solutions - 2014 BTO Peer Review Pre-Packaged Commercial Property-Accessed Clean Energy Financing Solutions - 2014 BTO...

92

Direct Water-Cooled Power Electronics Substrate Packaging | Department...  

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

Direct Water-Cooled Power Electronics Substrate Packaging Direct Water-Cooled Power Electronics Substrate Packaging 2010 DOE Vehicle Technologies and Hydrogen Programs Annual Merit...

93

FAQS Job Task Analyses - NNSA Package Certification Engineer...  

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

NNSA Package Certification Engineer FAQS Job Task Analyses - NNSA Package Certification Engineer FAQS Job Task Analyses are performed on the Function Area Qualification Standards....

94

National Defense University (NDU) Nomination Package Checklist  

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

- November 2012 - November 2012 National Defense University (NDU) Nomination Package Checklist SEND 2 COPIES OF THE NOMINATION PACKAGE TO THE NDU UNIVERSITY REGISTRAR'S OFFICE Each student nomination package must include the following items: NDU Student Nomination Form One official transcript (highest degree earned) One-page student biography or résumé (include education and career history) Two Letters of Recommendation World-Wide Travel Statement Statement of Purpose (No more than two pages) Signed National Defense University Privacy Act Statement Signed Education Release Form (if nominating agency requires copies of final student evaluation and/or transcript) SAC students must also include: Senior Acquisition Course Nomination Form

95

Status and Trend of Automotive Power Packaging  

SciTech Connect (OSTI)

Comprehensive requirements in aspects of cost, reliability, efficiency, form factor, weight, and volume for power electronics modules in modern electric drive vehicles have driven the development of automotive power packaging technology intensively. Innovation in materials, interconnections, and processing techniques is leading to enormous improvements in power modules. In this paper, the technical development of and trends in power module packaging are evaluated by examining technical details with examples of industrial products. The issues and development directions for future automotive power module packaging are also discussed.

Liang, Zhenxian [ORNL

2012-01-01T23:59:59.000Z

96

Yield learning model for integrated circuit package  

E-Print Network [OSTI]

, and has a major influence on product perfo rmance and reliability. Increasing the yield in package assembly influence on product perfo will reduce the effective manufacturing cost during assembly. Hence integrated circuit manufacturers try to improve...

Balasubramaniam, Gaurishankar

2012-06-07T23:59:59.000Z

97

Departmental Materials Transportation and Packaging Management  

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

Establishes Department of Energy (DOE) policies and requirements to supplement applicable laws, rules, regulations, and other DOE Orders for materials transportation and packaging operations. Cancels: DOE 1540.1A, DOE 1540.2, and DOE 1540.3A.

1995-10-26T23:59:59.000Z

98

Departmental Materials Transportation and Packaging Management  

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

Establishes Department of Energy (DOE) policies and requirements to supplement applicable laws, rules, regulations, and other DOE Orders for materials transportation and packaging operations. Cancels DOE 1540.1A, DOE 1540.2, DOE 1540.3A.

1995-09-27T23:59:59.000Z

99

Completion of the Radioactive Materials Packaging Handbook  

SciTech Connect (OSTI)

The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance, which will serve as a replacement for the Cask Designers Guide (Shappert, 1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US Department of Energy (DOE) and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials.

Shappert, L.B.

1998-02-01T23:59:59.000Z

100

Aerogel Package for Fused Fibre Couplers  

Science Journals Connector (OSTI)

Fused fibre couplers were encapsulated in hydrophobic aerogel. This provides an epoxy-free all-silica package that is low-loss, waterproof, supports the whole coupler waist and is...

Xiao, Limin; Grogan, Michael; England, Richard; Wadsworth, William; Birks, Tim

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

CERAMIC WASTE FORM DATA PACKAGE  

SciTech Connect (OSTI)

The purpose of this data package is to provide information about simulated crystalline waste forms that can be used to select an appropriate composition for a Cold Crucible Induction Melter (CCIM) proof of principle demonstration. Melt processing, viscosity, electrical conductivity, and thermal analysis information was collected to assess the ability of two potential candidate ceramic compositions to be processed in the Idaho National Laboratory (INL) CCIM and to guide processing parameters for the CCIM operation. Given uncertainties in the CCIM capabilities to reach certain temperatures throughout the system, one waste form designated 'Fe-MP' was designed towards enabling processing and another, designated 'CAF-5%TM-MP' was designed towards optimized microstructure. Melt processing studies confirmed both compositions could be poured from a crucible at 1600{degrees}C although the CAF-5%TM-MP composition froze before pouring was complete due to rapid crystallization (upon cooling). X-ray diffraction measurements confirmed the crystalline nature and phase assemblages of the compositions. The kinetics of melting and crystallization appeared to vary significantly between the compositions. Impedance spectroscopy results indicated the electrical conductivity is acceptable with respect to processing in the CCIM. The success of processing either ceramic composition will depend on the thermal profiles throughout the CCIM. In particular, the working temperature of the pour spout relative to the bulk melter which can approach 1700{degrees}C. The Fe-MP composition is recommended to demonstrate proof of principle for crystalline simulated waste forms considering the current configuration of INL's CCIM. If proposed modifications to the CCIM can maintain a nominal temperature of 1600{degrees}C throughout the melter, drain, and pour spout, then the CAF-5%TM-MP composition should be considered for a proof of principle demonstration.

Amoroso, J.; Marra, J.

2014-06-13T23:59:59.000Z

102

Glass Ceramic Formulation Data Package  

SciTech Connect (OSTI)

A glass ceramic waste form is being developed for treatment of secondary waste streams generated by aqueous reprocessing of commercial used nuclear fuel (Crum et al. 2012b). The waste stream contains a mixture of transition metals, alkali, alkaline earths, and lanthanides, several of which exceed the solubility limits of a single phase borosilicate glass (Crum et al. 2009; Caurant et al. 2007). A multi-phase glass ceramic waste form allows incorporation of insoluble components of the waste by designed crystallization into durable heat tolerant phases. The glass ceramic formulation and processing targets the formation of the following three stable crystalline phases: (1) powellite (XMoO4) where X can be (Ca, Sr, Ba, and/or Ln), (2) oxyapatite Yx,Z(10-x)Si6O26 where Y is alkaline earth, Z is Ln, and (3) lanthanide borosilicate (Ln5BSi2O13). These three phases incorporate the waste components that are above the solubility limit of a single-phase borosilicate glass. The glass ceramic is designed to be a single phase melt, just like a borosilicate glass, and then crystallize upon slow cooling to form the targeted phases. The slow cooling schedule is based on the centerline cooling profile of a 2 foot diameter canister such as the Hanford High-Level Waste canister. Up to this point, crucible testing has been used for glass ceramic development, with cold crucible induction melter (CCIM) targeted as the ultimate processing technology for the waste form. Idaho National Laboratory (INL) will conduct a scaled CCIM test in FY2012 with a glass ceramic to demonstrate the processing behavior. This Data Package documents the laboratory studies of the glass ceramic composition to support the CCIM test. Pacific Northwest National Laboratory (PNNL) measured melt viscosity, electrical conductivity, and crystallization behavior upon cooling to identify a processing window (temperature range) for melter operation and cooling profiles necessary to crystallize the targeted phases in the waste form.

Crum, Jarrod V.; Rodriguez, Carmen P.; McCloy, John S.; Vienna, John D.; Chung, Chul-Woo

2012-06-17T23:59:59.000Z

103

Quality of vacuum packaged lamb retail cuts  

E-Print Network [OSTI]

QUALITY OF VACUUM PACKAGED LAMB RETAIL CUTS A Thesis by KRISTEN GAE WANSTEDT Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1982 Major Subject...: Food Science and Technology QUALITY OF VACUUM PACKAGED LAMB RETAIL CUTS A Thesis by KRISTEN GAE WANSTEDT Approved as to style and content by: '(xi' (Chairman of Committee) (Member) o p (Member) (Head of Department) August 1982 ABSTRACT...

Wanstedt, Kristen Gae

2012-06-07T23:59:59.000Z

104

Protection of microelectronic devices during packaging  

DOE Patents [OSTI]

The present invention relates to a method of protecting a microelectronic device during device packaging, including the steps of applying a water-insoluble, protective coating to a sensitive area on the device; performing at least one packaging step; and then substantially removing the protective coating, preferably by dry plasma etching. The sensitive area can include a released MEMS element. The microelectronic device can be disposed on a wafer. The protective coating can be a vacuum vapor-deposited parylene polymer, silicon nitride, metal (e.g. aluminum or tungsten), a vapor deposited organic material, cynoacrylate, a carbon film, a self-assembled monolayered material, perfluoropolyether, hexamethyldisilazane, or perfluorodecanoic carboxylic acid, silicon dioxide, silicate glass, or combinations thereof. The present invention also relates to a method of packaging a microelectronic device, including: providing a microelectronic device having a sensitive area; applying a water-insoluble, protective coating to the sensitive area; providing a package; attaching the device to the package; electrically interconnecting the device to the package; and substantially removing the protective coating from the sensitive area.

Peterson, Kenneth A. (Albuquerque, NM); Conley, William R. (Tijeras, NM)

2002-01-01T23:59:59.000Z

105

Example Performance Targets and Efficiency Packages Greensburg, Kansas (Presentation)  

SciTech Connect (OSTI)

This presentation shows the energy performance targets and efficiency packages for residential buildings in Greensburg, Kansas.

Anderson, R.

2008-01-01T23:59:59.000Z

106

Microvias: The Next Generation of Substrates and Packages  

Science Journals Connector (OSTI)

The silicon revolution continues its rapid advances. New functionality in silicon, more I/Os per components and shrinking discreet components sizes are providing the opportunity for rapid product enhancements. Area array packages and now the new chip-size ... Keywords: PCB packaging, PCM density, array packages, chip-size packaging

Happy Holden

1998-07-01T23:59:59.000Z

107

TYPE B RADIOACTIVE MATERIAL PACKAGE FAILURE MODES AND CONTENTS COMPLIANCE  

SciTech Connect (OSTI)

Type B radioactive material package failures can occur due to any one of the following: inadequate design, manufacture, and maintenance of packages, load conditions beyond those anticipated in the regulations, and improper package loading and operation. The rigorous package design evaluations performed in the certification process, robust package manufacture quality assurance programs, and demanding load conditions prescribed in the regulations are all well established. This paper focuses on the operational aspects of Type B package loading with respect to an overbatch which may cause a package failure.

Watkins, R; Steve Hensel, S; Allen Smith, A

2007-02-21T23:59:59.000Z

108

ORISE Resources: Radiation Treatment Medication Package Inserts  

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

Radiation Treatment Medication Package Inserts Radiation Treatment Medication Package Inserts The Oak Ridge Institute for Science and Education (ORISE) maintains a repository of clinical information and data on calcium and zinc diethylenetriaminepentaacetic acid (DTPA) and ferric hexacyanoferrate, also known as Prussian Blue. Calcium-DTPA and zinc-DTPA are injectable chelating agents used to enhance the excretion of plutonium and other transuranics from the body. Prussian Blue binds to radioactive cesium and thallium in the stomach, thereby enhancing their excretion from the body. Package inserts are available for radiation treatment pharmaceuticals calcium-DTPA, zinc-DTPA and Radiogardase (Prussian Blue). To view these files, you will need the Adobe Acrobat Reader, which can be downloaded free from the Adobe Web site.

109

DEVELOPMENT OF THE H1700 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The H1700 Package is based on the DOE-EM Certified 9977 Packaging. The H1700 will be certified by the Packaging Certification Division of the National Nuclear Security Administration for the shipment of plutonium by air by the United Stated Military both within the United States and internationally. The H1700 is designed to ship radioactive contents in assemblies of Radioisotope Thermoelectric Generators (RTGs) or arrangements of nested food-pack cans. The RTG containers are designed and tested to remain leaktight during transport, handling, and storage; however, their ability to remain leaktight during transport in the H1700 is not credited. This paper discusses the design and special operation of the H1700.

Abramczyk, G.; Loftin, B.; Mann, P.

2009-06-05T23:59:59.000Z

110

DEPLOYMENT OF THE BULK TRITIUM SHIPPING PACKAGE  

SciTech Connect (OSTI)

A new Bulk Tritium Shipping Package (BTSP) was designed by the Savannah River National Laboratory to be a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The BTSP was certified by the National Nuclear Safety Administration in 2011 for shipments of up to 150 grams of Tritium. Thirty packages were procured and are being delivered to various DOE sites for operational use. This paper summarizes the design features of the BTSP, as well as associated engineered material improvements. Fabrication challenges encountered during production are discussed as well as fielding requirements. Current approved tritium content forms (gas and tritium hydrides), are reviewed, as well as, a new content, tritium contaminated water on molecular sieves. Issues associated with gas generation will also be discussed.

Blanton, P.

2013-10-10T23:59:59.000Z

111

Safety evaluation for packaging (onsite) SERF cask  

SciTech Connect (OSTI)

This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.

Edwards, W.S.

1997-10-24T23:59:59.000Z

112

Project-led Education in Packaging Development and Management  

Science Journals Connector (OSTI)

Abstract As an implicit subset of industrial design engineering, packaging development and management thereof has long been a changeling, because product and packaging development are usually regarded in a similar manner. At the same time, there is a clear difference between packaging design and product design. The packaging explicitly serves the content and, therefore, in most cases, packaging is of low economic value. For this reason, new packaging design is all too often subject to standard or existing packaging solutions. Besides this, packaging development has specific requirements, because it has to preserve and protect its content, which gives many technical requirements. Other important requirements are based on legislation, market acceptance, the environmental impact and usability. This implies that education in packaging development cannot be a carbon copy of the education in product development. Often, even more fields of expertise are involved, while having to meet all restrictions related to developing feasible and realistic packages in a shorter time-frame. This publication describes how project-led education is employed in an educational approach that allows students to adequately address the development of content-packaging combinations in a structured, effective and efficient manner. With this, the development efforts spent on product and packaging can become more in balance, not only doing justice to the separate life cycles of the two, but especially to the benefit of the combined life cycle of the content-packaging combination.

E.J. Oude Luttikhuis; J. de Lange; R. ten Klooster; E. Lutters

2014-01-01T23:59:59.000Z

113

Material efficiency in Dutch packaging policy  

Science Journals Connector (OSTI)

...Currently, PET bottles are recycled as material, incinerated...to be abolished for plastic bottles (reusable or...g. through applying recycled content or specific...applied are inclusion of recycled materials or recycling...packaging materials (plastic (62%) and paper...

2013-01-01T23:59:59.000Z

114

Second Generation Waste Package Design Study  

SciTech Connect (OSTI)

The following describes the objectives of Project Activity 023 “Second Generation Waste Package Design Study” under DOE Cooperative Agreement DE-FC28-04RW12232. The objectives of this activity are: to review the current YMP baseline environment and establish corrosion testenvironments representative of the range of dry to intermittently wet conditions expected in the drifts as a function of time; to demonstrate the oxidation and corrosion resistance of A588 weathering steel and reference Alloy 22 samples in the representative dry to intermittently dry conditions; and to evaluate backfill and design features to improve the thermal performance analyses of the proposed second-generation waste packages using existing models developed at the University of Nevada, Reno(UNR). The work plan for this project activity consists of three major tasks: Task 1. Definition of expected worst-case environments (humidity, liquid composition and temperature) at waste package outer surfaces as a function of time, and comparison with environments defined in the YMP baseline; Task 2. Oxidation and corrosion tests of proposed second-generation outer container material; and Task 3. Second Generation waste package thermal analyses. Full funding was not provided for this project activity.

Armijo, J.S.; Misra, M.; Kar, Piyush

2007-06-28T23:59:59.000Z

115

Work Package 3 Research & Development Centre  

E-Print Network [OSTI]

Durability : tasks & leaders T3.6 Work package coordination Gaz de France T3.2 Transmission pipelines, best practices, service history (maintenance & repair), integrity management #12;Development&Research Centre January 5, 2005 5 T3.2 Transmission pipelines Objectives Testing of steels and high pressure grid

116

44-BWR WASTE PACKAGE LOADING CURVE EVALUATION  

SciTech Connect (OSTI)

The objective of this calculation is to evaluate the required minimum burnup as a function of initial boiling water reactor (BWR) assembly enrichment that would permit loading of spent nuclear fuel into the 44 BWR waste package configuration as provided in Attachment IV. This calculation is an application of the methodology presented in ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent (wt%) U-235, and a burnup range of 0 through 40 GWd/MTU. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing BWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results of 100 percent of the current BWR projected waste stream being able to be disposed of in the 44-BWR waste package with Ni-Gd Alloy absorber plates is contingent upon the referenced waste stream being sufficiently similar to the waste stream received for disposal. (3) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials.

J.M. Scaglione

2004-08-25T23:59:59.000Z

117

Packaging and transportation manual. Chapter on the packaging and transportation of hazardous and radioactive waste  

SciTech Connect (OSTI)

The purpose of this chapter is to outline the requirements that Los Alamos National Laboratory employees and contractors must follow when they package and ship hazardous and radioactive waste. This chapter is applied to on-site, intra-Laboratory, and off-site transportation of hazardous and radioactive waste. The chapter contains sections on definitions, responsibilities, written procedures, authorized packaging, quality assurance, documentation for waste shipments, loading and tiedown of waste shipments, on-site routing, packaging and transportation assessment and oversight program, nonconformance reporting, training of personnel, emergency response information, and incident and occurrence reporting. Appendices provide additional detail, references, and guidance on packaging for hazardous and radioactive waste, and guidance for the on-site transport of these wastes.

NONE

1998-03-01T23:59:59.000Z

118

NNSA PACKAGE CERTIFICATION ENGINEER QUALIFICATION STANDARD REFERENCE GUIDE  

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

NNSA Package NNSA Package Certification Engineer Qualification Standard Reference Guide FEBRUARY 2010 This page is intentionally blank. i Table of Contents LIST OF FIGURES ...................................................................................................................... ii LIST OF TABLES ........................................................................................................................ ii ACRONYMS ................................................................................................................................ iii PURPOSE...................................................................................................................................... 1 SCOPE ...........................................................................................................................................

119

An assessment of the value of retail ready packaging  

E-Print Network [OSTI]

Use of retail-ready packaging reduces the costs of replenishing store shelves by eliminating the labor of removing packaging materials and stocking individual items on shelves. While reducing costs for retailers, retail-ready ...

Jackson, Kathleen Anne

2008-01-01T23:59:59.000Z

120

Low-Cost Packaged Combined Heat and Power System | Department...  

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

Low-Cost Packaged Combined Heat and Power System Low-Cost Packaged Combined Heat and Power System Introduction Many combined heat and power (CHP) systems less than 1 megawatt (MW)...

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Universal software packages to model the distributed-parameter systems  

Science Journals Connector (OSTI)

Consideration was given to the universal software packages for modeling objects and distributed-parameter systems obeying the partial differential equations. The packages may serve as important tools for industrial automation because the majority of ... Keywords: 07.05.Tp

E. E. Dudnikov

2009-01-01T23:59:59.000Z

122

The C-Cat Wordnet Package: An Open Source Package for modifying andapplying Wordnet  

SciTech Connect (OSTI)

We present the C-Cat Wordnet package, an open source library for using and modifying Wordnet. The package includes four key features: an API for modifying Synsets; implementations of standard similarity metrics, implementations of well known Word Sense Disambiguation algorithms, and an implementation of the Castanet algorithm. The library is easily extendible and usable in many runtime environments. We demonstrate it's use on two standard Word Sense Disambiguation tasks and apply the Castanet algorithm to a corpus.

Stevens, K; Huang, T; Buttler, D

2011-09-16T23:59:59.000Z

123

Safety analysis report for packaging (onsite) steel drum  

SciTech Connect (OSTI)

This Safety Analysis Report for Packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the steel drum packaging system meets the transportation safety requirements of HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments, for an onsite packaging containing Type B quantities of solid and liquid radioactive materials. The basic component of the steel drum packaging system is the 208 L (55-gal) steel drum.

McCormick, W.A.

1998-09-29T23:59:59.000Z

124

Human Portable Radiation Detection System Communications Package Evaluation  

SciTech Connect (OSTI)

Testing and valuation of the Human Portable Radiation Detection System Communications Package for the US Coast Guard.

Morgen, Gerald P.; Peterson, William W.

2009-06-11T23:59:59.000Z

125

Film Badge Application Radioactive Material Package Receipt Log  

E-Print Network [OSTI]

;RADIOACTIVE MATERIAL PACKAGE RECEIPT LOG DATE: DELIVERED BY: AUTHORIZED BY: Contamination Check DPM/100 cm2APPENDIX A Film Badge Application Radioactive Material Package Receipt Log Radioactive Material Package Receipt Form (Off-Campus Locations) Radiation / Contamination Survey Form #12;PERSONNEL MONITORING

Slatton, Clint

126

Two practical packages for computational physics — GCPM, RLFI  

Science Journals Connector (OSTI)

Two handy computer-program packages for technical support of the work in two different branches of the computational physics are reported: 1. (1) A genral Package for the symbolic and numerical transformation of expressions from one system of units to another. 2. (2) A package allowing high-quality two-dimensional of mathematical formulas from the computer-algebra system REDUCE.

Ladislav Drska; Richard Liska; Milan Sinor

1990-01-01T23:59:59.000Z

127

Silicon microbench heater elements for packaging opto-electronic devices  

SciTech Connect (OSTI)

Examples are presented of the application of Lawrence Livermore National Laboratory`s expertise in photonics packaging. Several examples of packaged devices will be described. Particular attention is given to silicon microbenches incorporating heaters and their use in semiconductor optical amplifier fiber pigtailing and packaging.

Combs, R.; Keiser, P.; Kleint, K.; Pocha, M.; Patterson, F.; Strand, O.T.

1995-09-01T23:59:59.000Z

128

WASTE PACKAGE REMEDIATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect (OSTI)

The Waste Package Remediation System remediates waste packages (WPs) and disposal containers (DCs) in one of two ways: preparation of rejected DC closure welds for repair or opening of the DC/WP. DCs are brought to the Waste Package Remediation System for preparation of rejected closure welds if testing of the closure weld by the Disposal Container Handling System indicates an unacceptable, but repairable, welding flaw. DC preparation of rejected closure welds will require removal of the weld in such a way that the Disposal Container Handling System may resume and complete the closure welding process. DCs/WPs are brought to the Waste Package Remediation System for opening if the Disposal Container Handling System testing of the DC closure weld indicates an unrepairable welding flaw, or if a WP is recovered from the subsurface repository because suspected damage to the WP or failure of the WP has occurred. DC/WP opening will require cutting of the DC/WP such that a temporary seal may be installed and the waste inside the DC/WP removed by another system. The system operates in a Waste Package Remediation System hot cell located in the Waste Handling Building that has direct access to the Disposal Container Handling System. One DC/WP at a time can be handled in the hot cell. The DC/WP arrives on a transfer cart, is positioned within the cell for system operations, and exits the cell without being removed from the cart. The system includes a wide variety of remotely operated components including a manipulator with hoist and/or jib crane, viewing systems, machine tools for opening WPs, and equipment used to perform pressure and gas composition sampling. Remotely operated equipment is designed to facilitate DC/WP decontamination and hot cell equipment maintenance, and interchangeable components are provided where appropriate. The Waste Package Remediation System interfaces with the Disposal Container Handling System for the receipt and transport of WPs and DCs. The Waste Handling Building System houses the system, and provides the facility, safety, and auxiliary systems required to support operations. The system receives power from the Waste Handling Building Electrical System. The system also interfaces with the various DC systems.

N.D. Sudan

2000-06-22T23:59:59.000Z

129

White LED with High Package Extraction Efficiency  

Office of Scientific and Technical Information (OSTI)

WHITE LED WITH HIGH PACKAGE WHITE LED WITH HIGH PACKAGE EXTRACTION EFFICIENCY Final Report Report Period Start Date: 10/01/2006 Report Period End Date: 09/30/2008 Authors: Yi Zheng and Matthew Stough Report Submission Date: November 2008 DOE Award Number: DE-FC26-06NT42935 Project Manager: Ryan Egidi OSRAM SYLVANIA Product Inc Central Research and Service Laboratory 71 Cherry Hill Dr., Beverly, MA 01915 2 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor an agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus,

130

The Package Matters | Advanced Photon Source  

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

Disarming Deadly South American Hemorrhagic Fever Viruses Disarming Deadly South American Hemorrhagic Fever Viruses Pull-Chain "Polymer" Solves Puzzle of Complex Molecular Packing Discovering New Talents for Diamond Science Highlights Archives: 2013 | 2012 | 2011 | 2010 2009 | 2008 | 2007 | 2006 2005 | 2004 | 2003 | 2002 2001 | 2000 | 1998 | Subscribe to APS Science Highlights rss feed The Package Matters MARCH 23, 2010 Bookmark and Share Packing ammonia borane into mesoporous silica leads to a remarkable enhancement of the hydrogen storage properties. This image shows the molecular configuration of the packed ammonia borane (while spheres are hydrogen). When it comes to squeezing hydrogen out of ammonia borane the packaging matters, according to scientists from three U.S. Department of Energy national labs. Ammonia borane releases hydrogen with heating by a

131

DOE-Idaho's Packaging and Transportation Perspective  

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

Idaho's Packaging and Idaho's Packaging and T t ti P ti Transportation Perspective Richard Provencher Manager DOE Idaho Operations Office DOE Idaho Operations Office Presented to the DOE National Transportation Stakeholders Forum Stakeholders Forum May 12, 2011 DOE's Idaho site ships and receives a wide variety of radioactive materials 2 Engineering Test Reactor vessel excavated, transported across the site and disposed 3 Navy SNF moved from wet to dry storage storage 4 5 Left: Contact-handled TRU shipments Right: A remote-handled TRU shipment Right: A remote handled TRU shipment 6 NAC spent nuclear fuel container on its trailer, prior to installation of its impact limiters 7 Examples of dry (CPP-603) and wet (CPP-666) storage in Idaho (CPP 666) storage in Idaho 8 INL's Materials and Fuels Complex Hot Fuel Examination

132

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

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

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Emergency Response to a Transportation Accident Involving Radioactive Material Radioactive Materials Transportation and Incident Response

133

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

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

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

134

Operating experience with industrial packaged FBC boilers  

SciTech Connect (OSTI)

Jonston Boiler company has developed a packaged fluidized bed combustion firetube boiler which burns coal within a bed of inert material (limestone) efficiently and cleanly. The firetube boiler cross section is schematized and explained. After one year demonstration, a sale was made to Central Soya of Marion, Ohio. The control system, drum level control draft, baghouse control system and emissions tests are highlighted. A few incidents of defluidization are noted.

Hutchinson, B.

1982-06-01T23:59:59.000Z

135

Copper vapor laser modular packaging assembly  

DOE Patents [OSTI]

A modularized packaging arrangement for one or more copper vapor lasers and associated equipment is disclosed herein. This arrangement includes a single housing which contains the laser or lasers and all their associated equipment except power, water and neon, and means for bringing power, water, and neon which are necessary to the operation of the lasers into the container for use by the laser or lasers and their associated equipment.

Alger, Terry W. (Tracy, CA); Ault, Earl R. (Dublin, CA); Moses, Edward I. (Castro Valley, CA)

1992-01-01T23:59:59.000Z

136

Review of SAR for Packaging Report  

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

March 2010 March 2010 Standard Review Plan (SRP) E n v i r o n m e n t a l M a n a g e m e n t DOE - EM - SRP - 2010 2nd Edition Review of SAR for Packaging Report UCID-21218 Rev. 3 Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings Revision 3 A. A. DiSabatino D. Biswas M. DeMicco L. E. Fischer R. S. Hafner L. B. Hagler J. J. Haslam G. C. Mok C. S. Patel E. W. Russell S. Sitaraman C. K. Syn J. Wen M. H. West LAWRENCE N A T I O N A L LABORATORY LIVERMORE February 2008 DISCLAIMER This document was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor Lawrence Livermore National Security, LLC, nor any of their employees makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information,

137

Reactor Pressure Vessel Head Packaging & Disposal  

SciTech Connect (OSTI)

Reactor Pressure Vessel (RPV) Head replacements have come to the forefront due to erosion/corrosion and wastage problems resulting from the susceptibility of the RPV Head alloy steel material to water/boric acid corrosion from reactor coolant leakage through the various RPV Head penetrations. A case in point is the recent Davis-Besse RPV Head project, where detailed inspections in early 2002 revealed significant wastage of head material adjacent to one of the Control Rod Drive Mechanism (CRDM) nozzles. In lieu of making ASME weld repairs to the damaged head, Davis-Besse made the decision to replace the RPV Head. The decision was made on the basis that the required weld repair would be too extensive and almost impractical. This paper presents the packaging, transport, and disposal considerations for the damaged Davis-Besse RPV Head. It addresses the requirements necessary to meet Davis Besse needs, as well as the regulatory criteria, for shipping and burial of the head. It focuses on the radiological characterization, shipping/disposal package design, site preparation and packaging, and the transportation and emergency response plans that were developed for the Davis-Besse RPV Head project.

Wheeler, D. M.; Posivak, E.; Freitag, A.; Geddes, B.

2003-02-26T23:59:59.000Z

138

Long-term Repository Benefits of Using Cermet Waste Packages  

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

Long-Term Benefits Long-Term Benefits Long-term Repository Benefits of Using Cermet Waste Packages A cermet waste package may improve the long-term performance of the YM repository by two mechanisms: reducing (1) the potential for nuclear criticality in the repository and (2) the long-term release rate of radionuclides from the waste package. In the natural environment, the centers of uranium ore deposits have remained intact for very long time periods while the outer edges of the ore deposit have degraded. A cermet waste package may operate in the same way. The sacrificial, slow degradation of the waste package and the DU oxide protects the SNF uranium dioxide in the interior of the package long after the package has failed. Page 2 of 4 Follow the link below to learn more about Cermets:

139

U-003:RPM Package Manager security update | Department of Energy  

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

03:RPM Package Manager security update 03:RPM Package Manager security update U-003:RPM Package Manager security update October 4, 2011 - 1:30pm Addthis PROBLEM: A vulnerability was reported in RPM Package Manager. A remote user can cause arbitrary code to be executed on the target user's system. PLATFORM: Version(s): 4.9.1.1 and prior versions. ABSTRACT: RPM Package Manager Header Validation Flaws Let Remote Users Execute Arbitrary Code. reference LINKS: RPM Package Manager Advisory RHSA-2011:1349-1 SecurityTracker Alert ID: 1026134 CVE-2011-3378 IMPACT ASSESSMENT: Medium Discussion: A remote user can create a specially crafted RPM package that, when queried or installed by the target user, will trigger a buffer overflow or memory corruption error and execute arbitrary code on the target system. The code

140

THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL PACKAGES IN TRANSPORT CONFIGURATION  

SciTech Connect (OSTI)

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR Part 71. The packages are transported in specially designed vehicles like Safe Secure Transport (SST) for safety and security. In the transport vehicles, the packages are placed close to each other to maximize the number of units in the vehicle. Since the RAM contents in the packagings produce decay heat, it is important that they are spaced sufficiently apart to prevent overheating of the containment vessel (CV) seals and the impact limiter to ensure the structural integrity of the package. This paper presents a simple methodology to assess thermal performance of a typical 9975 packaging in a transport configuration.

Gupta, N.

2010-03-04T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Approval of Existent Waste Packages and New Package Designs in Preparation for the Konrad Repository  

SciTech Connect (OSTI)

Low and intermediate level radioactive waste from German nuclear and other industries, research facilities and increasingly decommissioned nuclear installations is handled and prepared for interim storage and later disposal in the licensed KONRAD repository. This paper presents aspects, experiences and perspectives of container design testing and qualification procedures. Several new container designs, in particular different types of steel plate containers, have been tested and licensed; some are handled at present or just applied. Examples from typical qualification procedures including drop tests from 0.8 and 5 m height with prototype containers are presented. On the other hand several thousand waste packages are currently stored in interim storage facilities, many of them for more than 10 or 15 years. Based on existing package documentation applications and safety assessments for KONRAD are prepared and have to be evaluated. The paper discusses aspects, difficulties and strategies to demonstrate sufficient compliance to the current KONRAD repository requirements for the large number of existent waste packages. (authors)

Volzke, H.; Nieslony, G.; Hagenow, P. [BAM Bundesanstalt fur Materialforschung und - prufung, Federal Institute for Materials Research and Testing, Berlin (Germany)

2008-07-01T23:59:59.000Z

142

THERMAL UPGRADING OF 9977 RADIOACTIVE MATERIAL (RAM) TYPE B PACKAGE  

SciTech Connect (OSTI)

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3013 aluminum spacer and an external aluminum sleeve for enhanced heat transfer. The 7th Addendum to the original 9977 package Safety Basis Report describing these modifications is under review for the DOE certification. The analyses described in this paper show that this well-designed and conservatively analyzed package can be upgraded to carry contents with decay heat up to 38 watts with some simple design modifications. The Model 9977 package has been designed as a replacement for the Department of Transportation (DOT) Fissile Specification 6M package. The 9977 package is a very versatile Type B package which is certified to transport and store a wide spectrum of radioactive materials. The package was analyzed quite conservatively to increase its usefulness and store different payload configurations. Its versatility is evident from several daughter packages such as the 9978 and H1700, and several addendums where the payloads have been modified to suit the Shipper's needs without additional testing.

Gupta, N.; Abramczyk, G.

2012-03-26T23:59:59.000Z

143

Groundwater Data Package for Hanford Assessments  

SciTech Connect (OSTI)

This report presents data and interpreted information that supports the groundwater module of the System Assessment Capability (SAC) used in Hanford Assessments. The objective of the groundwater module is to predict movement of radioactive and chemical contaminants through the aquifer to the Columbia River or other potential discharge locations. This data package is being revised as part of the deliverables under the Characterization of Systems Project (#49139) aimed at providing documentation for assessments being conducted under the Hanford Assessments Project (#47042). Both of these projects are components of the Groundwater Remediation and Closure Assessments Projects, managed by the Management and Integration Project (#47043).

Thorne, Paul D.; Bergeron, Marcel P.; Williams, Mark D.; Freedman, Vicky L.

2006-01-31T23:59:59.000Z

144

CRAD, Packaging and Transfer of Hazardous Materials and Materials of  

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

Packaging and Transfer of Hazardous Materials and Materials Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan CRAD, Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan Performance Objective: Verify that packaging and transportation safety requirements of hazardous materials and materials of national security interest have been established and are in compliance with DOE Orders 461.1 and 460.1B Criteria: Verify that safety requirements for the proper packaging and transportation of DOE/NNSA offsite shipments and onsite transfers of hazardous materials and for modal transport have been established [DOE O 460.1B, 1, "Objectives"]. Verify that the contractor transporting a package of hazardous materials is in compliance with the requirements of the Hazardous Materials

145

Waste Package Materials Performance Peer Review | Department of Energy  

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

Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review A consensus peer review of the current technical basis and the planned experimental and modeling program for the prediction of the long-term performance of waste package materials being considered for use in a proposed repository at Yucca Mountain, Nevada. Waste Package Materials Performance Peer Review A Compilation of Special Topic Reports Wastepackagematerials_PPRP_final.pdf Evaluation of the Final Report: Waste Package Materials Performance Peer Review Panel Multi-Purpose_Canister_System_Evaluation.pdf More Documents & Publications Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water

146

TYPE A FISSILE PACKAGING FOR AIR TRANSPORT PROJECT OVERVIEW  

SciTech Connect (OSTI)

This paper presents the project status of the Model 9980, a new Type A fissile packaging for use in air transport. The Savannah River National Laboratory (SRNL) developed this new packaging to be a light weight (<150-lb), drum-style package and prepared a Safety Analysis for Packaging (SARP) for submission to the DOE/EM. The package design incorporates unique features and engineered materials specifically designed to minimize packaging weight and to be in compliance with 10CFR71 requirements. Prototypes were fabricated and tested to evaluate the design when subjected to Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC). An overview of the design details, results of the regulatory testing, and lessons learned from the prototype fabrication for the 9980 will be presented.

Eberl, K.; Blanton, P.

2013-10-11T23:59:59.000Z

147

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

148

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

149

Method Of Packaging And Assembling Electro-Microfluidic Devices  

DOE Patents [OSTI]

A new architecture for packaging surface micromachined electro-microfluidic devices is presented. This architecture relies on two scales of packaging to bring fluid to the device scale (picoliters) from the macro-scale (microliters). The architecture emulates and utilizes electronics packaging technology. The larger package consists of a circuit board with embedded fluidic channels and standard fluidic connectors (e.g. Fluidic Printed Wiring Board). The embedded channels connect to the smaller package, an Electro-Microfluidic Dual-Inline-Package (EMDIP) that takes fluid to the microfluidic integrated circuit (MIC). The fluidic connection is made to the back of the MIC through Bosch-etched holes that take fluid to surface micromachined channels on the front of the MIC. Electrical connection is made to bond pads on the front of the MIC.

Benavides, Gilbert L. (Albuquerque, NM); Galambos, Paul C. (Albuquerque, NM); Emerson, John A. (Albuquerque, NM); Peterson, Kenneth A. (Albuquerque, NM); Giunta, Rachel K. (Albuquerque, NM); Zamora, David Lee (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2004-11-23T23:59:59.000Z

150

PROCEDURE FOR OPENING PACKAGES CONTAINING RADIONUCLIDES Laboratory personnel should open and inspect packages immediately upon receipt.  

E-Print Network [OSTI]

as soon as possible to the vendor. Return of radioactive material to the vendor must be coordinated of absorbing material. 5. The inner packaging which includes the liner, shield, and absorbent materials may be contaminated; they are to be discarded in the radioactive waste container unless shown to be uncontaminated

Slatton, Clint

151

Using the scalable nonlinear equations solvers package  

SciTech Connect (OSTI)

SNES (Scalable Nonlinear Equations Solvers) is a software package for the numerical solution of large-scale systems of nonlinear equations on both uniprocessors and parallel architectures. SNES also contains a component for the solution of unconstrained minimization problems, called SUMS (Scalable Unconstrained Minimization Solvers). Newton-like methods, which are known for their efficiency and robustness, constitute the core of the package. As part of the multilevel PETSc library, SNES incorporates many features and options from other parts of PETSc. In keeping with the spirit of the PETSc library, the nonlinear solution routines are data-structure-neutral, making them flexible and easily extensible. This users guide contains a detailed description of uniprocessor usage of SNES, with some added comments regarding multiprocessor usage. At this time the parallel version is undergoing refinement and extension, as we work toward a common interface for the uniprocessor and parallel cases. Thus, forthcoming versions of the software will contain additional features, and changes to parallel interface may result at any time. The new parallel version will employ the MPI (Message Passing Interface) standard for interprocessor communication. Since most of these details will be hidden, users will need to perform only minimal message-passing programming.

Gropp, W.D.; McInnes, L.C.; Smith, B.F.

1995-02-01T23:59:59.000Z

152

Waste package and underground facility design  

SciTech Connect (OSTI)

The design of the waste package and the underground facility for radioactive waste disposal presents many challenges never before addressed in an engineering design effort. The designs must allow for handling and emplacement of the waste and must ensure that the waste will be isolated over time periods that extend beyond those normally dealt with in engineering solutions. Once developed, these designs must be defended in a licensing arena to allow construction and operation of the disposal system. The design of the waste package and the repository is being conducted iteratively. Each iteration of the design is accompanied by an assessment of the performance of the design and an assessment of remaining design issues. These assessments are used to establish the basis for the next design phase. Design requirements are assessed and revised as necessary before the initiation of each design phase. In addition, the design effort is being closely integrated with the siting effort through the application of an issue identification and resolution strategy.

Frei, M.W.; Dayem, N.J.

1988-01-01T23:59:59.000Z

153

Release Data Package for Hanford Site Assessments  

SciTech Connect (OSTI)

Beginning in fiscal year (FY) 2003, the U.S. Department of Energy (DOE) Richland Operations Office initiated activities, including the development of data packages, to support a Hanford assessment. This report describes the data compiled in FY 2003 through 2005 to support the Release Module of the System Assessment Capability (SAC) for the updated composite analysis. This work was completed as part of the Characterization of Systems Project, part of the Remediation and Closure Science Project, the Hanford Assessments Project, and the Characterization of Systems Project managed by Pacific Northwest National Laboratory. Related characterization activities and data packages for the vadose zone and groundwater are being developed under the remediation Decision Support Task of the Groundwater Remediation Project managed by Fluor Hanford, Inc. The Release Module applies release models to waste inventory data from the Inventory Module and accounts for site remediation activities as a function of time. The resulting releases to the vadose zone, expressed as time profiles of annual rates, become source terms for the Vadose Zone Module. Radioactive decay is accounted for in all inputs and outputs of the Release Module. The Release Module is implemented as the VADER (Vadose zone Environmental Release) computer code. Key components of the Release Module are numerical models (i.e., liquid, soil-debris, cement, saltcake, and reactor block) that simulate contaminant release from the different waste source types found at the Hanford Site. The Release Module also handles remediation transfers to onsite and offsite repositories.

Riley, Robert G.; Lopresti, Charles A.; Engel, David W.

2006-07-01T23:59:59.000Z

154

Improvements to the SHDOM Radiative Transfer Modeling Package  

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

to the SHDOM Radiative Transfer Modeling Package K. F. Evans University of Colorado Boulder, Colorado W. J. Wiscombe National Aeronautics and Space Administration...

155

Excellent color rendering indexes of multi-package white LEDs  

Science Journals Connector (OSTI)

This study introduces multi-package white light-emitting diodes (LEDs) system with the ability to realize high luminous efficacy and an excellent color rendering index (CRI,...

Oh, Ji Hye; Yang, Su Ji; Sung, Yeon-Goog; Do, Y R

2012-01-01T23:59:59.000Z

156

CH Packaging Operations for High Wattage Waste at LANL  

SciTech Connect (OSTI)

This procedure provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP).

Washington TRU Solutions LLC

2005-04-04T23:59:59.000Z

157

CH Packaging Operations for High Wattage Waste at LANL  

SciTech Connect (OSTI)

This procedure provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP).

Washington TRU Solutions LLC

2005-04-13T23:59:59.000Z

158

UNC Charlotte PORTAL Building Trade Package Base Bid  

E-Print Network [OSTI]

UNC Charlotte PORTAL Building Trade Package Base Bid Alternate #1 Office curtains/ double Alternate #6 Telecom cabling system Prefered Alternate #7 Pedestrian lighting fixture P and P Bond

Kelly, Scott David

159

Structural analysis for horizontal storage of 9975 shipping packages  

SciTech Connect (OSTI)

This paper presents a nonlinear dynamic analysis for a 9975 shipping package to evaluate its structural response while stored in a horizontal assembly of packages. The structural response of the 9975 shipping package stored on a 24-inch-wide bottom rack while the upper two tiers of 9975 shipping packages are being loaded on top of it is analyzed. The upper two tiers of the packages are lifted by a forklift truck and then loaded onto the bottom tier of the packages. A nonlinear finite-element dynamic analysis with explicit time integration was performed for a 9975 shipping package to evaluate the consequence of the loading process described above. The effect of the impact load generated by the sudden release of the upper two tiers of the packages to the deformation of the bottom package is accounted for. The ABAQUS/Explicit computer code (Reference 1) was used to perform the computations. The time histories of the deflections and stresses were generated.

Wu, T.

2000-03-16T23:59:59.000Z

160

ANNUAL MAINTENANCE AND LEAK TESTING FOR THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The purpose of this document is to provide step-by-step instructions for the annual helium leak test certification and maintenance of the 9975 Shipping Package.

Trapp, D.

2014-08-25T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Direct Water-Cooled Power Electronics Substrate Packaging  

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

Water-Cooled Power Electronics Substrate Packaging Randy H. Wiles Oak Ridge National Laboratory June 10, 2010 Project ID: APE001 This presentation does not contain any proprietary,...

162

Single molecule studies of DNA packaging by bacteriophages  

E-Print Network [OSTI]

for the study of single molecule protein- DNA interactions.Physics Studies in Single Molecule Biophysics ProfessorOF THE DISSERTATION Single Molecule Studies of DNA Packaging

Fuller, Derek Nathan

2008-01-01T23:59:59.000Z

163

Hail Impact Testing on Crystalline Si Modules with Flexible Packaging  

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

% Semi-flexible packaging of silicon solar cells has potential applications in BIPV and consumer electronics. One of the more difficult reliability requirements for...

164

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...  

Office of Scientific and Technical Information (OSTI)

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor Design and Feasibility Problem Re-direct Destination: Temp Data Fields Rosen, M. A.; Coburn, D. B.; Flynn, T....

165

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

A. Alsaed

2005-07-28T23:59:59.000Z

166

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

J.K. Knudson

2003-10-02T23:59:59.000Z

167

DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-00600  

SciTech Connect (OSTI)

The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the K-Area Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) [1] credits the Model 9975 package to perform several safety functions, including criticality, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program [2-3], destructive examination of package 9975-00600 was performed following field surveillance in accordance with Reference [4]. Field surveillance of the Model 9975 package in KAC included nondestructive examination of the drum, fiberboard, lead shield and containment vessels [5]. Results of the field surveillance are provided in Attachment 1. Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-00600. For those attributes that were also measured during the field surveillance, no significant changes were observed. Three conditions were identified that do not meet inspection criteria. These conditions are subject to additional investigation and disposition by the Surveillance Program Authority. The conditions include: (1) The lead shield was covered with a white corrosion layer; (2) The lead shield height dimension exceeded drawing requirements; and (3) Fiberboard thermal conductivity in the axial direction exceeded the specified range. The Surveillance Program Authority was notified of these conditions. All other observations and test results met identified criteria, or were collected for information and trending purposes.

Daugherty, W

2007-10-29T23:59:59.000Z

168

Laser diode package with enhanced cooling  

DOE Patents [OSTI]

A laser diode package assembly includes a reservoir filled with a fusible metal in close proximity to a laser diode. The fusible metal absorbs heat from the laser diode and undergoes a phase change from solid to liquid during the operation of the laser. The metal absorbs heat during the phase transition. Once the laser diode is turned off, the liquid metal cools off and resolidifies. The reservoir is designed such that that the liquid metal does not leave the reservoir even when in liquid state. The laser diode assembly further includes a lid with one or more fin structures that extend into the reservoir and are in contact with the metal in the reservoir.

Deri, Robert J. (Pleasanton, CA); Kotovsky, Jack (Oakland, CA); Spadaccini, Christopher M. (Oakland, CA)

2012-06-12T23:59:59.000Z

169

Laser diode package with enhanced cooling  

DOE Patents [OSTI]

A laser diode package assembly includes a reservoir filled with a fusible metal in close proximity to a laser diode. The fusible metal absorbs heat from the laser diode and undergoes a phase change from solid to liquid during the operation of the laser. The metal absorbs heat during the phase transition. Once the laser diode is turned off, the liquid metal cools off and resolidifies. The reservoir is designed such that that the liquid metal does not leave the reservoir even when in liquid state. The laser diode assembly further includes a lid with one or more fin structures that extend into the reservoir and are in contact with the metal in the reservoir.

Deri, Robert J.; Kotovsky, Jack; Spadaccini, Christopher M.

2012-06-26T23:59:59.000Z

170

Laser diode package with enhanced cooling  

DOE Patents [OSTI]

A laser diode package assembly includes a reservoir filled with a fusible metal in close proximity to a laser diode. The fusible metal absorbs heat from the laser diode and undergoes a phase change from solid to liquid during the operation of the laser. The metal absorbs heat during the phase transition. Once the laser diode is turned off, the liquid metal cools off and resolidifies. The reservoir is designed such that that the liquid metal does not leave the reservoir even when in liquid state. The laser diode assembly further includes a lid with one or more fin structures that extend into the reservoir and are in contact with the metal in the reservoir.

Deri, Robert J. (Pleasanton, CA); Kotovsky, Jack (Oakland, CA); Spadaccini, Christopher M. (Oakland, CA)

2011-09-13T23:59:59.000Z

171

AGC-2 Graphite Preirradiation Data Package  

SciTech Connect (OSTI)

The NGNP Graphite R&D program is currently establishing the safe operating envelope of graphite core components for a Very High Temperature Reactor (VHTR) design. The program is generating quantitative data necessary for predicting the behavior and operating performance of the new nuclear graphite grades. To determine the in-service behavior of the graphite for pebble bed and prismatic designs, the Advanced Graphite Creep (AGC) experiment is underway. This experiment is examining the properties and behavior of nuclear grade graphite over a large spectrum of temperatures, neutron fluences and compressive loads. Each experiment consists of over 400 graphite specimens that are characterized prior to irradiation and following irradiation. Six experiments are planned with the first, AGC-1, currently being irradiated in the Advanced Test Reactor (ATR) and pre-irradiation characterization of the second, AGC-2, completed. This data package establishes the readiness of 512 specimens for assembly into the AGC-2 capsule.

David Swank; Joseph Lord; David Rohrbaugh; William Windes

2012-10-01T23:59:59.000Z

172

High voltage photo switch package module  

DOE Patents [OSTI]

A photo-conductive switch package module having a photo-conductive substrate or wafer with opposing electrode-interface surfaces, and at least one light-input surface. First metallic layers are formed on the electrode-interface surfaces, and one or more optical waveguides having input and output ends are bonded to the substrate so that the output end of each waveguide is bonded to a corresponding one of the light-input surfaces of the photo-conductive substrate. This forms a waveguide-substrate interface for coupling light into the photo-conductive wafer. A dielectric material such as epoxy is then used to encapsulate the photo-conductive substrate and optical waveguide so that only the metallic layers and the input end of the optical waveguide are exposed. Second metallic layers are then formed on the first metallic layers so that the waveguide-substrate interface is positioned under the second metallic layers.

Sullivan, James S; Sanders, David M; Hawkins, Steven A; Sampayan, Stephen E

2014-02-18T23:59:59.000Z

173

Energy implications of recycling packaging materials  

SciTech Connect (OSTI)

In 1992, Congress sought to rewrite the United States comprehensive solid waste legislation -- the Resource Conservation and Recovery Act (RCRA). Commodity-specific recycling rates were proposed for consumer-goods packaging materials and newsprint We compare the impacts on energy, materials use, and landfill volume of recycling at those rates to the impacts for alternative methods of material disposition to determine the optimum for each material. After products have served their intended uses, there are several alternative paths for material disposition. These include reuse, recycling to the same product, recycling to a lower-valued product, combustion for energy recovery, incineration without energy recovery, and landfill. Only options considered to be environmentally sound are Included. Both houses of Congress specifically excluded combustion for energy recovery from counting towards the recovery goats, probably because combustion is viewed as a form of disposal and is therefore assumed to waste resources and have n environmental effects. However, co-combustion in coal-fired plants or combustion in appropriately pollution-controlled waste-to-energy plants Is safe, avoids landfill costs, and can displace fossil fuels. In some cases, more fossil fuels can be displaced by combustion than by recycling. We compare the alternative life-cycle energies to the energies for producing the products from virgin materials. Results depend on the material and on the objective to be achieved. There are trade-offs among possible goals. For instance, paper packaging recycling conserves trees but may require greater fossil-fuel input than virgin production. Therefore, the objectives for proposed legislation must be examined to see whether they can most effectively be achieved by mandated recycling rates or by other methods of disposition. The optimal choices for the United States may not necessarily be the same as those for Europe and other parts of the world.

Gaines, L.L. [Argonne National Lab., IL (United States); Stodolsky, F. [Argonne National Lab., Washington, DC (United States)

1994-03-01T23:59:59.000Z

174

River Data Package for Hanford Assessments  

SciTech Connect (OSTI)

This data package documents the technical basis for selecting physical and hydraulic parameters and input values that will be used in river modeling for Hanford assessments. This work was originally conducted as part of the Characterization of Systems Task of the Groundwater Remediation Project managed by Fluor Hanford, Inc. and revised as part of the Characterization of Systems Project managed by PNNL for DOE. The river data package provides calculations of flow and transport in the Columbia River system. The module is based on the legacy code for the Modular Aquatic Simulation System II (MASS2), which is a two-dimensional, depth-averaged model that provides the capability to simulate the lateral (bank-to-bank) variation of flow and contaminants. It simulates river hydrodynamics (water velocities and surface elevations), sediment transport, contaminant transport, biotic transport, and sediment-contaminant interaction, including both suspended sediments and bed sediments. This document presents the data assembled to run the river module components for the section of the Columbia River from Vernita Bridge to the confluence with the Yakima River. MASS2 requires data on the river flow rate, downstream water surface elevation, groundwater influx and contaminants flux, background concentrations of contaminants, channel bathymetry, and the bed and suspended sediment properties. Stochastic variability for some input parameters such as partition coefficient (kd) values and background radionuclide concentrations is generated by the Environmental Stochastic Preprocessor. River flow is randomized on a yearly basis. At this time, the conceptual model does not incorporate extreme flooding (for example, 50 to 100 years) or dam removal scenarios.

Rakowski, Cynthia L.; Guensch, Gregory R.; Patton, Gregory W.

2006-08-01T23:59:59.000Z

175

UNC Charlotte PORTAL Building Trade Package Base Bid  

E-Print Network [OSTI]

UNC Charlotte PORTAL Building Trade Package Base Bid Alternate #1 Office curtains/ double glazing Telecom cabling system Prefered Alternate #7 Pedestrian lighting fixture P and P Bond 02001 Site Work,000 SteelFab, Inc. 2,554,007 21,709 Page 1 of 4 #12;UNC Charlotte PORTAL Building Trade Package Base Bid

Kelly, Scott David

176

The gensymb package for LATEX 2" Walter Schmidt*  

E-Print Network [OSTI]

is a workaround to provide at least the # - see below. The symbol \\ohm is particular, too: Loading the textcomp. The default behavior of the gensymb package can be modified using the follow- ing options: upmu this macro lies with you; for instanc* *e, load the package upgreek1 or use a set of math fonts which

Mintmire, John W.

177

Cost Modeling and Design Techniques for Integrated Package Distribution Systems  

E-Print Network [OSTI]

Cost Modeling and Design Techniques for Integrated Package Distribution Systems Karen R. Smilowitz and Carlos F. Daganzo December 23, 2005 Abstract Complex package distribution systems are designed using-scale integrated distribution networks. While the network design problem is quite complex, we demonstrate

Smilowitz, Karen

178

DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-06100  

SciTech Connect (OSTI)

Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-06100. This package was selected for examination based on several characteristics: - This was the first destructively examined package in which the fiberboard assembly was fabricated from softwood fiberboard. - The package contained a relatively high heat load to contribute to internal temperature, which is a key environmental factor for fiberboard degradation. - The package has been stored in the middle or top of a storage array since its receipt in K- Area, positions that would contribute to increased service temperatures. No significant changes were observed for attributes that were measured during both field surveillance and destructive examination. Except for the axial gap, all observations and test results met identified criteria, or were collected for information and trending purposes. The axial gap met the 1 inch maximum criterion during field surveillance, but was just over the criterion during SRNL measurements. When re-measured at a later date, it again met the criterion. The bottom of the lower fiberboard assembly and the drum interior had two small stains at matching locations, suggestive of water intrusion. However, the fiberboard assembly did not contain any current evidence of excess moisture. No evidence of a degraded condition was found in this package. Despite exposure to the elevated temperatures of this higher-then-average wattage package, properties of the fiberboard and O-rings are consistent with those of new packages.

Daugherty, W.

2014-11-07T23:59:59.000Z

179

Packaging Research and Routing Optimization - Research Area - National  

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

Packaging Research Packaging Research The Packaging Research Facility conducts research for DOE National Nuclear Security Administration, as well as for commercial customers. The facility specializes in testing packaging systems for the transportation of nuclear fuel. Once a package design has been successfully tested, it can then be certified by one of several regulatory authorities, usually DOE, the National Nuclear Security Administration, or the Nuclear Regulatory Commission, for use on the road. Welcome EESD Programs EES Directorate ORNL Web Contact Disclaimer Oak Ridge National Laboratory is a national multi-program research and development facility managed by UT-Battelle, LLC for the U.S. Department of Energy UT-Battelle, LLC U.S. Department of Energy Contact Scott Ludwig

180

FINITE ELEMENT ANALYSIS OF BULK TRITIUM SHIPPING PACKAGE  

SciTech Connect (OSTI)

The Bulk Tritium Shipping Package was designed by Savannah River National Laboratory. This package will be used to transport tritium. As part of the requirements for certification, the package must be shown to meet the scenarios of the Hypothetical Accident Conditions (HAC) defined in Code of Federal Regulations Title 10 Part 71 (10CFR71). The conditions include a sequential 30-foot drop event, 30-foot dynamic crush event, and a 40-inch puncture event. Finite Element analyses were performed to support and expand upon prototype testing. Cases similar to the tests were evaluated. Additional temperatures and orientations were also examined to determine their impact on the results. The peak stress on the package was shown to be acceptable. In addition, the strain on the outer drum as well as the inner containment boundary was shown to be acceptable. In conjunction with the prototype tests, the package was shown to meet its confinement requirements.

Jordan, J.

2010-06-02T23:59:59.000Z

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


181

Waste package/repository impact study: Final report  

SciTech Connect (OSTI)

The Waste Package/Repository Impact Study was conducted to evaluate the feasibility of using the current reference salt waste package in the salt repository conceptual design. All elements of the repository that may impact waste package parameters, i.e., (size, weight, heat load) were evaluated. The repository elements considered included waste hoist feasibility, transporter and emplacement machine feasibility, subsurface entry dimensions, feasibility of emplacement configuration, and temperature limits. The evaluations are discussed in detail with supplemental technical data included in Appendices to this report, as appropriate. Results and conclusions of the evaluations are discussed in light of the acceptability of the current reference waste package as the basis for salt conceptual design. Finally, recommendations are made relative to the salt project position on the application of the reference waste package as a basis for future design activities. 31 refs., 11 figs., 11 tabs.

Not Available

1985-09-01T23:59:59.000Z

182

Digital Radiography of a Drop Tested 9975 Radioactive Materials Packaging  

SciTech Connect (OSTI)

This paper discusses the use of radiography as a tool for evaluating damage to radioactive material packaging subjected to regulatory accident conditions. The Code of Federal Regulations, 10 CFR 71, presents the performance based requirements that must be used in the development (design, fabrication and testing) of a radioactive material packaging. The use of various non-destructive examination techniques in the fabrication of packages is common. One such technique is the use of conventional radiography in the examination of welds. Radiography is conventional in the sense that images are caught one at a time on film stock. Most recently, digital radiography has been used to characterize internal damage to a package subjected to the 30-foot hypothetical accident conditions (HAC) drop. Digital radiography allows for real time evaluation of the item being inspected. This paper presents a summary discussion of the digital radiographic technique and an example of radiographic results of a 9975 package following the HAC 30-foot drop.

Blanton, P.S.

2001-05-30T23:59:59.000Z

183

Pre-release plastic packaging of MEMS and IMEMS devices  

DOE Patents [OSTI]

A method is disclosed for pre-release plastic packaging of MEMS and IMEMS devices. The method can include encapsulating the MEMS device in a transfer molded plastic package. Next, a perforation can be made in the package to provide access to the MEMS elements. The non-ablative material removal process can include wet etching, dry etching, mechanical machining, water jet cutting, and ultrasonic machining, or any combination thereof. Finally, the MEMS elements can be released by using either a wet etching or dry plasma etching process. The MEMS elements can be protected with a parylene protective coating. After releasing the MEMS elements, an anti-stiction coating can be applied. The perforating step can be applied to both sides of the device or package. A cover lid can be attached to the face of the package after releasing any MEMS elements. The cover lid can include a window for providing optical access. The method can be applied to any plastic packaged microelectronic device that requires access to the environment, including chemical, pressure, or temperature-sensitive microsensors; CCD chips, photocells, laser diodes, VCSEL's, and UV-EPROMS. The present method places the high-risk packaging steps ahead of the release of the fragile portions of the device. It also provides protection for the die in shipment between the molding house and the house that will release the MEMS elements and subsequently treat the surfaces.

Peterson, Kenneth A. (Albuquerque, NM); Conley, William R. (Tijeras, NM)

2002-01-01T23:59:59.000Z

184

E-Print Network 3.0 - automated software packages Sample Search...  

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

and Michele Lanza Summary: is providing a way to automate the package characterization process. To ad- dress this challenge, we propose... that automate the package patterns...

185

T-529: Apple Mac OS PackageKit Distribution Script Remote Code...  

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

29: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability T-529: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability January...

186

Low-Cost Packaged CHP System with Reduced Emissions - Fact Sheet...  

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

Cost Packaged CHP System with Reduced Emissions - Fact Sheet, 2011 Low-Cost Packaged CHP System with Reduced Emissions - Fact Sheet, 2011 Cummins Power Generation, in collaboration...

187

2014-03-06 Issuance: Test Procedures for Packaged Terminal Air...  

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

3-06 Issuance: Test Procedures for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps; Notice of Proposed Rulemaking 2014-03-06 Issuance: Test Procedures for...

188

Radioisotope thermoelectric generator licensed hardware package and certification tests  

SciTech Connect (OSTI)

This paper presents the Licensed Hardware package and the Certification Test portions of the Radioisitope Themoelectric Generator Transportation System. This package has been designed to meet those portions of the {ital Code} {ital of} {ital Federal} {ital Regulations} (10 CFR 71) relating to ``Type B`` shipments of radioactive materials. The licensed hardware is now in the U. S. Department of Energy licensing process that certifies the packaging`s integrity under accident conditions. The detailed information for the anticipated license is presented in the safety analysis report for packaging, which is now in process and undergoing necessary reviews. As part of the licensing process, a full-size Certification Test Article unit, which has modifications slightly different than the Licensed Hardware or production shipping units, is used for testing. Dimensional checks of the Certification Test Article were made at the manufacturing facility. Leak testing and drop testing were done at the 300 Area of the U.S. Department of Energy`s Hanford Site near Richland, Washington. The hardware includes independent double containments to prevent the environmental spread of {sup 238}Pu, impact limiting devices to protect portions of the package from impacts, and thermal insulation to protect the seal areas from excess heat during accident conditions. The package also features electronic feed-throughs to monitor the Radioisotope Thermoelectric Generator`s temperature inside the containment during the shipment cycle. This package is designed to safely dissipate the typical 4,500 thermal watts produced in the largest Radioisotope Thermoelectric Generators. The package also contains provisions to ensure leak tightness when radioactive materials, such as a Radioisotope Thermoelectric Generator for the Cassini Mission, planned for 1997 by the National Aeronautics and Space Administration, are being prepared for shipment. (Abstract Truncated)

Goldmann, L.H.; Averette, H.S. [Westinghouse Hanford Company, P.O. Box 1970, M/S R3-86 or N1-32, Richland, Washington 99352 (United States)

1995-01-20T23:59:59.000Z

189

General Corrosion and Localized Corrosion of Waste Package Outer Barrier  

SciTech Connect (OSTI)

The waste package design for the License Application is a double-wall waste package underneath a protective drip shield (BSC 2004 [DIRS 168489]; BSC 2004 [DIRS 169480]). The purpose and scope of this model report is to document models for general and localized corrosion of the waste package outer barrier (WPOB) to be used in evaluating waste package performance. The WPOB is constructed of Alloy 22 (UNS N06022), a highly corrosion-resistant nickel-based alloy. The inner vessel of the waste package is constructed of Stainless Steel Type 316 (UNS S31600). Before it fails, the Alloy 22 WPOB protects the Stainless Steel Type 316 inner vessel from exposure to the external environment and any significant degradation. The Stainless Steel Type 316 inner vessel provides structural stability to the thinner Alloy 22 WPOB. Although the waste package inner vessel would also provide some performance for waste containment and potentially decrease the rate of radionuclide transport after WPOB breach before it fails, the potential performance of the inner vessel is far less than that of the more corrosion-resistant Alloy 22 WPOB. For this reason, the corrosion performance of the waste package inner vessel is conservatively ignored in this report and the total system performance assessment for the license application (TSPA-LA). Treatment of seismic and igneous events and their consequences on waste package outer barrier performance are not specifically discussed in this report, although the general and localized corrosion models developed in this report are suitable for use in these scenarios. The localized corrosion processes considered in this report are pitting corrosion and crevice corrosion. Stress corrosion cracking is discussed in ''Stress Corrosion Cracking of the Drip Shield, the Waste Package Outer Barrier, and the Stainless Steel Structural Material'' (BSC 2004 [DIRS 169985]).

K.G. Mon

2004-10-01T23:59:59.000Z

190

Packaging and Transfer of Materials of National Security Interest Manual  

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

This Technical Manual establishes requirements for operational safety controls for onsite operations and provides Department of Energy (DOE) technical safety requirements and policy objectives for development of an Onsite Packaging and Transfer Program, pursuant to DOE O 461.1A, Packaging and Transfer or Transportation of Materials of National Security Interest. The DOE contractor must document this program in its Onsite Packaging and Transfer Manual/Procedures. Admin Chg 1, 7-26-05. Certified 2-2-07. Canceled by DOE O 461.2.

2000-09-29T23:59:59.000Z

191

Advanced packaging technology for high frequency photonic applications  

SciTech Connect (OSTI)

An advanced packaging concept has been developed for optical devices. This concept allows multiple fibers to be coupled to photonic integrated circuits, with no fiber penetration of the package walls. The principles used to accomplish this concept involves a second-order grating to couple light in or out of the photonic circuit, and a binary optic lens which receives this light and focuses it into a single-mode optical fiber. Design, fabrication and electrical/optical measurements of this packaging concept are described.

Armendariz, M.G.; Hadley, G.R.; Warren, M.E.

1996-03-01T23:59:59.000Z

192

Safety analysis report for packaging (onsite) multicanister overpack cask  

SciTech Connect (OSTI)

This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the MUlticanister Overpack (MCO) and MCO Cask for a highway route controlled quantity, Type B fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.

Edwards, W.S.

1997-07-14T23:59:59.000Z

193

INSTRUCTIONS FOR OPENING RADIONUCLIDE SHIPMENTS All packages containing radioactive material are physically received at the Department of Environmental  

E-Print Network [OSTI]

are monitored and contamination of the package exterior is assessed. The radioactive stock vialINSTRUCTIONS FOR OPENING RADIONUCLIDE SHIPMENTS All packages containing radioactive material radionuclide packages. GENERAL PROCEDURES 1. Radioactive packages must be opened and inspected as soon

Firestone, Jeremy

194

LAC Regional Platform Workshop Participant Package | Open Energy  

Open Energy Info (EERE)

Participant Package Participant Package Jump to: navigation, search LEDSGP Logo.png Advancing climate-resilient low emission development around the world Home About Tools Expert Assistance Events Publications Join Us LAC Workshop Announcement Agenda Participant Package Accommodations Location & Transportation Insurance & Visas Participants Presentations Outcomes Report Links Contact Us General Information (Español) Participant Package.pdf Powered by OpenEI ledsgp.org is built on the same platform as the popular Wikipedia site. Like Wikipedia, it is a "wiki" or website developed collaboratively by a community of users. Thanks to our unique relationship with OpenEI.org, you can add or edit most content on ledsgp.org. For more information about this unique collaboration, contact us. View or edit this page on OpenEI.org.

195

Wien Automatic System Planning (WASP) Package | Open Energy Information  

Open Energy Info (EERE)

Wien Automatic System Planning (WASP) Package Wien Automatic System Planning (WASP) Package Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Wien Automatic System Planning (WASP) Package Agency/Company /Organization: International Atomic Energy Agency Sector: Energy Focus Area: Renewable Energy, Energy Efficiency Topics: Pathways analysis Resource Type: Software/modeling tools Website: www-pub.iaea.org/MTCD/publications/PDF/CMS-16.pdf Cost: Free References: WASP[1] "The WASP-IV code permits finding the optimal expansion plan for a power generating system over a period of up to thirty years, within constraints given by the planner." References ↑ "WASP" Retrieved from "http://en.openei.org/w/index.php?title=Wien_Automatic_System_Planning_(WASP)_Package&oldid=403685

196

Data Domain to Model Domain Conversion Package | Argonne National  

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

Data Domain to Model Domain Conversion Package Data Domain to Model Domain Conversion Package Data Domain to Model Domain Conversion Package The Data Domain to Model Domain Conversion Package project will develop methods and implement a novel approach for generating data ensembles by using the latest available statistical modeling tools and knowledge of relevant physical and chemical process to develop climatologically aware methods for processing ACRF and other spatially sparse data sets. Data collected at the Atmospheric Radiation Measurement Program Climate Research Facility (ACRF) sites are employed mainly in column radiation models, to validate the models and develop new parameterizations. Currently, no single methodology can be used with data collected at the spatial scale of the ACRF sites or from specific AmeriFlux locations, to

197

Guidelines for commercial off-the-shelf simulation package interoperability  

Science Journals Connector (OSTI)

Commercial-off-the-shelf (COTS) Simulation Packages (CSPs) are widely used visual interactive modeling environments such as Arena™, Anylogic™, Flexsim™, Simul8™, Witness™, etc. CSP Interoperability (or distributed simulation) ...

Simon J. E. Taylor; Stephen J. Turner; Steffen Strassburger

2008-12-01T23:59:59.000Z

198

Building Energy-Efficiency Best Practice Policies and Policy Packages  

E-Print Network [OSTI]

Energy Efficiency Market in India - Lessons from the USA.market share of advanced energy- BEE Best Practice Policies and Policy Packages Chapter 2 - BEE Policies Review (U.S.A. )

Levine, Mark

2014-01-01T23:59:59.000Z

199

Optimization Online - SDPT3 - a MATLAB software package for ...  

E-Print Network [OSTI]

SDPT3 - a MATLAB software package for semidefinite-quadratic-linear programming, version 3.0. R.H. Tutuncu (reha ***at*** qwes.math.cmu.edu) K.C. Toh ...

R.H. Tutuncu

200

Heart Rate Variability Analysis Using Threshold of Wavelet Package Coefficients  

E-Print Network [OSTI]

In this paper, a new efficient feature extraction method based on the adaptive threshold of wavelet package coefficients is presented. This paper especially deals with the assessment of autonomic nervous system using the background variation of the signal Heart Rate Variability HRV extracted from the wavelet package coefficients. The application of a wavelet package transform allows us to obtain a time-frequency representation of the signal, which provides better insight in the frequency distribution of the signal with time. A 6 level decomposition of HRV was achieved with db4 as mother wavelet, and the above two bands LF and HF were combined in 12 specialized frequencies sub-bands obtained in wavelet package transform. Features extracted from these coefficients can efficiently represent the characteristics of the original signal. ANOVA statistical test is used for the evaluation of proposed algorithm.

Kheder, G; Massoued, M Ben; Samet, M

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

SCR Performance Optimization Through Advancements in Aftertreatment Packaging  

Broader source: Energy.gov [DOE]

The impact of improved urea mixing designs on urea vaporization and ammonia distribution is presented, along with a comparison of single and dual walled packaging for SCR systems. Urea doser integration is also investigated.

202

Hawaii Information Package for Chemical Inventory Form (HCIF...  

Open Energy Info (EERE)

II Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Hawaii Information Package for Chemical Inventory Form (HCIF)Tier II Form Type Required Reporting...

203

Thermal Management Fundamentals and Design Guides in Electronic Packaging  

Science Journals Connector (OSTI)

The objective of thermal management in electronic packaging is to efficiently remove heat from ... paths requires a thorough understanding of heat transfer fundamentals as well as knowledge of available interface...

Xingcun Colin Tong

2011-01-01T23:59:59.000Z

204

Office of Packaging and Transportation Fiscal Year 2012 Annual Report |  

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

Packaging and Transportation Fiscal Year 2012 Annual Packaging and Transportation Fiscal Year 2012 Annual Report Office of Packaging and Transportation Fiscal Year 2012 Annual Report The Office of Environmental Management (EM) was established to mitigate the risks and hazards posed by the legacy of nuclear weapons production and research. The most ambitious and far ranging of these missions is dealing with the environmental legacy of the Cold War. Many problems posed by its operations are unique, and include the transportation of unprecedented amounts of contaminated waste, water, and soil, and a vast number of contaminated structures during remediation of the contaminated sites. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material and waste. The mission of the Department of Energy (DOE) Office of Packaging and

205

Adaptable Sensor Packaging for High Temperature Fossil Fuel Energy System  

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

Adaptable Sensor Packaging for High Adaptable Sensor Packaging for High Temperature Fossil Fuel Energy Systems Background The Advanced Research Sensors and Controls Program is leading the effort to develop sensing and control technologies and methods to achieve automated and optimized intelligent power systems. The program is led by the U.S. Department of Energy (DOE) Office of Fossil Energy National Energy Technology Laboratory (NETL) and is implemented through research and development agreements with other

206

Packaging and Transfer of Materials of National Security Interest Manual  

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

The purpose of this Technical Manual is to establish requirements for operational safety controls for onsite operations. This Technical Manual provides Department of Energy (DOE) technical safety requirements and policy objectives for development of an onsite packaging and transfer program, pursuant to DOE O 461.1; the DOE contractor must document this program in its onsite packaging and transfer manual/procedures. Does not cancel other directives.

2000-09-29T23:59:59.000Z

207

Safety Evaluation for Packaging (onsite) T Plant Canyon Items  

SciTech Connect (OSTI)

This safety evaluation for packaging (SEP) evaluates and documents the ability to safely ship mostly unique inventories of miscellaneous T Plant canyon waste items (T-P Items) encountered during the canyon deck clean off campaign. In addition, this SEP addresses contaminated items and material that may be shipped in a strong tight package (STP). The shipments meet the criteria for onsite shipments as specified by Fluor Hanford in HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments.

OBRIEN, J.H.

2000-07-14T23:59:59.000Z

208

Packaging review guide for reviewing safety analysis reports for packagings: Revision 1  

SciTech Connect (OSTI)

The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs.

Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

1988-10-01T23:59:59.000Z

209

Fast Evaluation Method for Transient Hot Spots in VLSI ICs in Packages Je-Hyoung Park  

E-Print Network [OSTI]

by 1-D equivalent thermal resistance network. Ignoring the lateral heat spreading in realistic packages

210

Design and Criticality Considerations for 9977 and 9978 Shipping Packages  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) has developed two new, Type B, state-of-the-art, general purpose, fissile material Shipping Packages, designated 9977 and 9978, as replacements for the U.S. DOT specification 6M container, phased out in September 30, 2008 due to non-compliance with current requirements 10CFR71 regulation. The packages accommodate plutonium, uranium and other special nuclear materials in bulk quantities and in many forms with capabilities exceeding those of the 6M. These packages provide a high degree of single containment and comply with 10CFR71, Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10CFR20 (As Low As Reasonably Achievable (ALARA)). Allowed package contents were determined accounting for nuclear criticality, radiation shielding, and decay heat rate. The Criticality Safety Index (CSI) for the package is 1.0. The package utilizes passive cooling to maintain internal temperatures within limits. Radiation shielding analyses have established the contents for which the packages can be shipped under non-exclusive use in the Safe-Secure Trailer or under exclusive use. The packages are designed to ship radioactive contents in several configurations; Radioisotope Thermoelectric Generators (RTGs), nested food-pack cans, site specific containers, and DOE-STD-3013 containers. Each shipping package includes a 35-gallon stainless steel outer drum, insulation, a drum liner, and a single containment vessel (CV). The 9977 includes a 6-inch ID CV while the 9978 includes a 5-inch ID CV. One inch of Fiberfrax{reg_sign} insulation is wrapped around and attached to the sides and bottom of the liner. The volume between the Fiberfrax{reg_sign} and the drum wall is filled with polyurethane foam. Top and bottom aluminum Load Distribution Fixtures (LDFs) within the drum liner cavity, above and below the CV, center the CV in the liner, stiffen the package radially, and distribute loads away from the CV. The 6CV fits directly into the LDFs while honeycomb spacers position the 5CV in the LDFs.

Reed, R; Biswas, D; Abramczyk, G

2008-11-25T23:59:59.000Z

211

Surveillance Guides - PTS 13.2 Packaging and Preparation for Shipment  

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

PACKAGING AND PREPARATION FOR SHIPMENT PACKAGING AND PREPARATION FOR SHIPMENT 1.0 Objective The objective of this surveillance is to evaluate the effectiveness of the contractor's programs for packaging radioactive and hazardous wastes for shipment. The Facility Representative examines packages ready for shipment, observes preparation of packages, and reviews documents that establish the acceptability of packages. The Facility Representative verifies compliance with DOE requirements including requirements established by the Department of Transportation and the U.S. Nuclear Regulatory Commission. 2.0 References 2.1 DOE 5480.3, Safety Requirements for the Packaging and Transportation of Hazardous Materials, Hazardous Substances, and Hazardous Wastes

212

9975 SHIPPING PACKAGE LIFE EXTENSION SURVEILLANCE PROGRAM RESULTS SUMMARY  

SciTech Connect (OSTI)

Results from the 9975 shipping package Storage and Surveillance Program at the Savannah River Site (SRS) are summarized for justification to extend the life of the 9975 packages currently stored in the K-Area Complex (KAC). This justification is established with the stipulation that surveillance activities will continue throughout the extended time to ensure the continued integrity of the 9975 materials of construction and to further understand the currently identified degradation mechanisms. The 10 year storage life justification was developed prior to storage. A subsequent report was later used to validate the qualification of the 9975 shipping packages for 10 years in storage. However the qualification for the storage period was provided by the monitoring requirements of the 9975 Storage and Surveillance Program. This report summarizes efforts to determine a new safe storage limit for the 9975 shipping package based on the surveillance data collected since 2005 when the 9975 Storage and Surveillance Program began. The Program has demonstrated that the 9975 package has a robust design that can perform under a variety of conditions. The primary emphasis of the on-going 9975 Storage and Surveillance Program is an aging study of the 9975 Viton{reg_sign} containment vessel O-rings and the Celotex{reg_sign} fiberboard thermal insulation at bounding conditions of radiation, elevated temperatures and/or elevated humidity.

Dunn, K.; Daugherty, W.; Hackney, B.; Hoffman, E.; Skidmore, E.

2011-05-27T23:59:59.000Z

213

EFFECTS OF MOISTURE IN THE 9975 SHIPPING PACKAGE FIBERBOARD ASSEMBLY  

SciTech Connect (OSTI)

The fiberboard assembly used in 9975 shipping packages as an impact-absorption and insulation component has the capacity to absorb moisture, with an accompanying change to its properties. While package fabrication requirements generally maintain the fiberboard moisture content within manufacturing range, there is the potential during use or storage for atypical handling or storage practices which result in the absorption of additional moisture. In addition to performing a transportation function, the 9975 shipping packages are used as a facility storage system for special nuclear materials at the Savannah River Site. A small number of packages after extended storage have been found to contain elevated moisture levels. Typically, this condition is accompanied by an axial compaction of the bottom fiberboard layers, and the growth of mold. In addition to potential atypical practices, fiberboard can exchange moisture with the surrounding air, depending on the ambient humidity. Laboratory data have been generated to correlate the equilibrium moisture content of cane fiberboard with the humidity of the surrounding air. These data are compared to measurements taken within shipping packages. With a reasonable measurement of the fiberboard moisture content, an estimate of the fiberboard properties can be made. Over time, elevated moisture levels will negatively impact performance properties, and promote fiberboard mold growth and resultant degradation.

Daugherty, W.; Dunn, K.; Murphy, J.; Hackney, B.

2010-02-11T23:59:59.000Z

214

General Equilibrium Modeling Package (GEMPACK) | Open Energy Information  

Open Energy Info (EERE)

General Equilibrium Modeling Package (GEMPACK) General Equilibrium Modeling Package (GEMPACK) Jump to: navigation, search LEDSGP green logo.png FIND MORE DIA TOOLS This tool is part of the Development Impacts Assessment (DIA) Toolkit from the LEDS Global Partnership. Tool Summary LAUNCH TOOL Name: General Equilibrium Modeling Package (GEMPACK) Agency/Company /Organization: Centre of Policy Studies, Monash University Sector: Climate Topics: Analysis Tools Complexity/Ease of Use: Advanced Website: www.monash.edu.au/policy/gempack.htm Cost: Paid Related Tools Ex Ante Appraisal Carbon-Balance Tool (EX-ACT) MIT Emissions Prediction and Policy Analysis (EPPA) Model Energy Forecasting Framework and Emissions Consensus Tool (EFFECT) ... further results A system for computable general equilibrium economic modeling, produced and

215

Stailization, Packaging, and Storage of Plutonium-Bearing Materials  

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

DOE-STD-3013-2012 MARCH 2012 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS Available on the Department of Energy Technical Standards Program Web site at http://www.hss.energy.gov/NuclearSafety/ns/techstds/ DOE-STD-3013-2012 iii ABSTRACT This Standard provides guidance for the stabilization, packaging, and safe storage of plutonium- bearing metals and oxides containing at least 30 wt% plutonium plus uranium. It supersedes DOE-STD-3013-2004, "Stabilization, Packaging, and Storage of Plutonium-Bearing Materials," and is approved for use by all DOE organizations and their contractors. Metals are stabilized by

216

Preliminary safety evaluation for the plutonium stabilization and packaging system  

SciTech Connect (OSTI)

This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS.

Shapley, J.E., Fluor Daniel Hanford

1997-03-14T23:59:59.000Z

217

Mass Transfer Model for a Breached Waste Package  

SciTech Connect (OSTI)

The degradation of waste packages, which are used for the disposal of spent nuclear fuel in the repository, can result in configurations that may increase the probability of criticality. A mass transfer model is developed for a breached waste package to account for the entrainment of insoluble particles. In combination with radionuclide decay, soluble advection, and colloidal transport, a complete mass balance of nuclides in the waste package becomes available. The entrainment equations are derived from dimensionless parameters such as drag coefficient and Reynolds number and based on the assumption that insoluble particles are subjected to buoyant force, gravitational force, and drag force only. Particle size distributions are utilized to calculate entrainment concentration along with geochemistry model abstraction to calculate soluble concentration, and colloid model abstraction to calculate colloid concentration and radionuclide sorption. Results are compared with base case geochemistry model, which only considers soluble advection loss.

C. Hsu; J. McClure

2004-07-26T23:59:59.000Z

218

Technology transfer package on seismic base isolation - Volume II  

SciTech Connect (OSTI)

This Technology Transfer Package provides some detailed information for the U.S. Department of Energy (DOE) and its contractors about seismic base isolation. Intended users of this three-volume package are DOE Design and Safety Engineers as well as DOE Facility Managers who are responsible for reducing the effects of natural phenomena hazards (NPH), specifically earthquakes, on their facilities. The package was developed as part of DOE's efforts to study and implement techniques for protecting lives and property from the effects of natural phenomena and to support the International Decade for Natural Disaster Reduction. Volume II contains the proceedings for the Short Course on Seismic Base Isolation held in Berkeley, California, August 10-14, 1992.

NONE

1995-02-14T23:59:59.000Z

219

Thermal Analysis of the SAFKEG Package for Long Term Storage  

SciTech Connect (OSTI)

Interim plutonium storage for up to 10 years in the K-reactor building is currently being planned at Savannah River Site (SRS). SAFKEG package could be used to store Pu metal and oxide (PuO2) in the K-reactor complex with other packagings like 9975. The SAFKEG is designed for carrying Type-B materials across the DOE complex and meets the 10CFR71 requirements. Thermal analyses were performed to ensure that the temperatures of the SAFKEG components will not exceed their temperature limits under the K-reactor storage conditions. Thermal analyses of the SAFKEG packaging with three content configurations using BNFL 3013 outer container (Rocky Flats, SRS bagless transfer cans, and BNFL inner containers) were performed for storage of PuO2 and plutonium metal

NARENDRA, GUPTA

2005-01-10T23:59:59.000Z

220

MODEL 9975 SHIPPING PACKAGE FABRICATION PROBLEMS AND SOLUTIONS  

SciTech Connect (OSTI)

The Model 9975 Shipping Package is the latest in a series (9965, 9968, etc.) of radioactive material shipping packages that have been the mainstay for shipping radioactive materials for several years. The double containment vessels are relatively simple designs using pipe and pipe cap in conjunction with the Chalfont closure to provide a leak-tight vessel. The fabrication appears simple in nature, but the history of fabrication tells us there are pitfalls in the different fabrication methods and sequences. This paper will review the problems that have arisen during fabrication and precautions that should be taken to meet specifications and tolerances. The problems and precautions can also be applied to the Models 9977 and 9978 Shipping Packages.

May, C; Allen Smith, A

2008-05-07T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

COMPACTION OF FIBERBOARD OVERPACK MATERIALS IN A 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Compaction of lower layers in the 9975 fiberboard overpack has been observed in packages that contain excess moisture. Dynamic loading of the package during transportation may also contribute to compaction of the fiberboard. This condition is being tested and analyzed to better understand these compaction mechanisms and provide a basis from which to evaluate their impact to the safety basis for transportation (Safety Analysis Report for Packaging) and storage (facility Design Safety Analysis) at the Savannah River Site (SRS). A test program has been developed and is being implemented to identify the extent of the compaction as a function of fiberboard moisture and typical transport dynamic loadings. Test conditions will be compared to regulatory requirements for dynamic loading. Characterization of the recovery of short-term compaction following the application of dynamic loading is also being evaluated. Interim results from this test program will be summarized.

Stefek, T.; Daugherty, W.; Estochen, E.; Murphy, J.

2010-05-27T23:59:59.000Z

222

CORROSION OF LEAD SHIELDING IN NUCLEAR MATERIALS PACKAGES  

SciTech Connect (OSTI)

Inspection of United States-Department of Energy (US-DOE) model 9975 nuclear materials shipping package revealed corrosion of the lead shielding induced by off-gas constituents from organic components in the package. Experiments were performed to determine the corrosion rate of lead when exposed to off-gas or degradation products of these organic materials. The results showed that the room temperature vulcanizing (RTV) sealant was the most corrosive organic species followed by the polyvinyl acetate (PVAc) glue. The fiberboard material induced corrosion to a much lesser extent than the PVAc glue and RTV, and only in the presence of condensed water. The results indicated faster corrosion at temperatures higher than ambient and with condensed water as expected. A corrosion rate of 0.05 mm/year measured for coupons exposed to the most aggressive conditions was recommended as a conservative estimate for use in package performance calculations.

Subramanian, K; Kerry Dunn, K

2007-11-16T23:59:59.000Z

223

CMSG - A PUBLISH/SUBSCRIBE INTERPROCESS COMMUNICATION PACKAGE  

SciTech Connect (OSTI)

Publish/subscribe message passing is an extremely simple, flexible, and powerful interprocess communication (IPC) paradigm. It is widely used in industry, but not nearly so in High Energy and Nuclear Physics (HENP), perhaps due to the cost of commercial implementations. cMsg, developed at Jefferson Lab in the US, contains a full-featured pub/sub interprocess communication package that is simple to install and use. It is very efficient, and implements both point-to-point and pub/sub communications, server redundancy, hot server failover, and a server discovery service. In addition, for developers cMsg provides a framework within which one can deploy multiple underlying communication packages that do not necessarily need to implement the full pub/sub paradigm. This allows for unification of all communication in a control system under a single API, shortens development time, and allows for simple upgrade or replacement of underlying communication packages and protocols.

Wolin, Elliott; Timmer, Carl; Gyurjyan, Vardan; Heyes, William; Jastrzembski, Edward; Lawrence, David; Abbott, David

2008-10-01T23:59:59.000Z

224

Expanded Content Envelope For The Model 9977 Packaging  

SciTech Connect (OSTI)

An Addendum was written to the Model 9977 Safety Analysis Report for Packaging adding a new content consisting of DOE-STD-3013 stabilized plutonium dioxide materials to the authorized Model 9977 contents. The new Plutonium Oxide Content (PuO{sub 2}) Envelope will support the Department of Energy shipment of materials between Los Alamos National Laboratory and Savannah River Site facilities. The new content extended the current content envelope boundaries for radioactive material mass and for decay heat load and required a revision to the 9977 Certificate of Compliance prior to shipment. The Addendum documented how the new contents/configurations do not compromise the safety basis presented in the 9977 SARP Revision 2. The changes from the certified package baseline and the changes to the package required to safely transport this material is discussed.

Abramczyk, G. A.; Loftin, B. M.; Nathan, S. J.; Bellamy, J. S.

2013-07-30T23:59:59.000Z

225

Summary of packaging operational reviews, March 1988 through August 1988  

SciTech Connect (OSTI)

Packaging Operational Reviews were conducted during fiscal year 1987 at Rocky Flats, Mound Research Laboratories, LANL, Fernald, ORNL, Y-12, LLNL, HEDL, PNL, and RHO which are under the auspices of the Albuquerque, Oak Ridge, San Francisco, and Richland Operations Offices, respectively. Packaging Operational Reviews were continued during fiscal year 1988 at sites under the cognizance of the Albuquerque, Chicago, Idaho, Nevada, and Savannah River Operations Offices. A listing of these sites, dates visited, packages reviewed, and citation to the site visit report is included in this report. The review at Portsmouth Gaseous Diffusion Plant has been delayed and the results will be reported separately. No regulation violations or safety issues were found. A few recommendations were made and several unanswered questions surfaced during the reviews. Almost all questions dealt with documentation and many questions concerned how comprehensive must the documentation be to provide assurance that all requirements are met.

Jackson, R.J.; Smith, R.J.

1988-09-01T23:59:59.000Z

226

Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners  

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

Bridging Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners John Shugars, Consultant Philip Coleman, Lawrence BerkeleyNational Laboratory ChristopherPayne, Lawrence Berkeley National Laboratory Laura Van Wie McGrory, Lawrence Berkeley National Laboratory ABSTRACT The energy efficiency ofmany products has increased markedly over the past decade. A conspicuous exception to this trend is commercial packaged rooftop air conditioners, which have experiencedlittle to no efficiency improvement since 1992 when the Energy Policy Act of 1992 imposed federal minimum standards. Packaged rooftop units have been estimated to use on the order of76 billion kWh annually in the US, at a cost ofroughly $5.6 billion. Sales of these units are growing, and the majority of units sold have energy efficiency ratios (EERs) at orjust above the current national minimum efficiency

227

Work Packages for Site Support Service at Los Alamos National  

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

Work Packages for Site Support Service at Los Alamos National Work Packages for Site Support Service at Los Alamos National Laboratory-IG-0746 Work Packages for Site Support Service at Los Alamos National Laboratory-IG-0746 The Department of Energy's Los Alarnos National Laboratory (LANL) enhances global security by ensuring the safety and reliability of the U.S. nuclear weapons stockpile; developing technical solutioils to reduce the threat of weapons of mass destnlction; and solving problems related to energy, environn~ent,i nfrastructure, healtl~a, nd national security. Site support services at the Laboratory, iilcludiilg maintenance and repairs, are provided by the contractor KSL. Maintenance and repair work perfomled by KSL are controlled by the requirements of LANL Irnplementation Procedure IMP 300.2, Integrated Work Management for Work

228

9975 SHIPPING PACKAGE LIFE EXTENSION SURVEILLANCE PROGRAM RESULTS SUMMARY  

SciTech Connect (OSTI)

Results from the 9975 Surveillance Program at the Savannah River Site (SRS) are summarized for justification to extend the life of the 9975 packages currently stored in the K-Area Materials Storage (KAMS) facility from 10 years to 15 years. This justification is established with the stipulation that surveillance activities will continue throughout this extended time to ensure the continued integrity of the 9975 materials of construction and to further understand the currently identified degradation mechanisms. The current 10 year storage life was developed prior to storage. A subsequent report was later used to extend the qualification of the 9975 shipping packages for 2 years for shipping plus 10 years for storage. However the qualification for the storage period was provided by the monitoring requirements of the Storage and Surveillance Program. This report summarizes efforts to determine a new safe storage limit for the 9975 shipping package based on the surveillance data collected since 2005 when the surveillance program began. KAMS is a zero-release facility that depends upon containment by the 9975 to meet design basis storage requirements. Therefore, to confirm the continued integrity of the 9975 packages while stored in KAMS, a 9975 Storage and Surveillance Program was implemented alongside the DOE required Integrated Surveillance Program (ISP) for 3013 plutonium-bearing containers. The 9975 Storage and Surveillance Program performs field surveillance as well as accelerated aging tests to ensure any degradation due to aging, to the extent that could affect packaging performance, is detected in advance of such degradation occurring in the field. The Program has demonstrated that the 9975 package has a robust design that can perform under a variety of conditions. As such the primary emphasis of the on-going 9975 Surveillance Program is an aging study of the 9975 Viton(reg.sign) GLT containment vessel O-rings and the Celotex(reg.sign) fiberboard thermal insulation at bounding conditions of radiation and elevated temperatures. Other materials of construction, however, are also discussed.

Daugherty, W.; Dunn, K.; Hackney, B.; Hoffman, E.; Skidmore, E.

2011-01-06T23:59:59.000Z

229

ISSUES ASSOCIATED WITH SAFE PACKAGING AND TRANSPORT OF NANOPARTICLES  

SciTech Connect (OSTI)

Nanoparticles have long been recognized a hazardous substances by personnel working in the field. They are not, however, listed as a separate, distinct category of dangerous goods at present. As dangerous goods or hazardous substances, they require packaging and transportation practices which parallel the established practices for hazardous materials transport. Pending establishment of a distinct category for such materials by the Department of Transportation, existing consensus or industrial protocols must be followed. Action by DOT to establish appropriate packaging and transport requirements is recommended.

Gupta, N.; Smith, A.

2011-02-14T23:59:59.000Z

230

Technical Review Report for the Model 9978-96 Package Safety Analysis Report for Packaging (S-SARP-G-00002, Revision 1, March 2009)  

SciTech Connect (OSTI)

This Technical Review Report (TRR) documents the review, performed by Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the Department of Energy (DOE), on the 'Safety Analysis Report for Packaging (SARP), Model 9978 B(M)F-96', Revision 1, March 2009 (S-SARP-G-00002). The Model 9978 Package complies with 10 CFR 71, and with 'Regulations for the Safe Transport of Radioactive Material-1996 Edition (As Amended, 2000)-Safety Requirements', International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9978 Packaging is designed, analyzed, fabricated, and tested in accordance with Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PVC). The review presented in this TRR was performed using the methods outlined in Revision 3 of the DOE's 'Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages'. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's Regulatory Guide 7.9, i.e., 'Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material'. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9978 Packaging is a single containment package, using a 5-inch containment vessel (5CV). It uses a nominal 35-gallon drum package design. In comparison, the Model 9977 Packaging uses a 6-inch containment vessel (6CV). The Model 9977 and Model 9978 Packagings were developed concurrently, and they were referred to as the General Purpose Fissile Material Package, Version 1 (GPFP). Both packagings use General Plastics FR-3716 polyurethane foam as insulation and as impact limiters. The 5CV is used as the Primary Containment Vessel (PCV) in the Model 9975-96 Packaging. The Model 9975-96 Packaging also has the 6CV as its Secondary Containment Vessel (SCV). In comparison, the Model 9975 Packagings use Celotex{trademark} for insulation and as impact limiters. To provide a historical perspective, it is noted that the Model 9975-96 Packaging is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then-newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The Model 9978 Package has six Content Envelopes: C.1 ({sup 238}Pu Heat Sources), C.2 ( Pu/U Metals), C.3 (Pu/U Oxides, Reserved), C.4 (U Metal or Alloy), C.5 (U Compounds), and C.6 (Samples and Sources). Per 10 CFR 71.59 (Code of Federal Regulations), the value of N is 50 for the Model 9978 Package leading to a Criticality Safety Index (CSI) of 1.0. The Transport Index (TI), based on dose rate, is calculated to be a maximum of 4.1.

West, M

2009-03-06T23:59:59.000Z

231

Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners  

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

Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners Title Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners Publication Type Conference Proceedings Year of Publication 2000 Authors Shugars, John, Philip Coleman, Christopher T. Payne, and Laura Van Wie McGrory Conference Name Proceedings from the 2000 ACEEE Summer Study on Energy Efficiency in Buildings Volume 10 Pagination 217-226 Date Published 01/2000 Abstract The energy efficiency ofmany products has increased markedly over the past decade. A conspicuous exception to this trend is commercialpackaged rooftop air conditioners, which have experiencedlittle to no efficiency improvement since 1992 when the Energy Policy Act of 1992 imposed federal minimum standards. Packaged rooftop units have been estimated to use on the order of76 billion kWh annually in the US, at a cost ofroughly $5.6 billion. Sales of these units are growing, and the majority of units sold have energy efficiency ratios (EERs) at orjust above the current national minimum efficiency standards. In this paper we document the static efficiencies ofcommercialpackaged air conditioners, explore the reasons behindthis efficiency gap, and assess opportunities for overcoming the barriers to efficiency improvements in these products.

232

Cost Modeling and Design Techniques for Integrated Package Distribution Systems  

E-Print Network [OSTI]

Cost Modeling and Design Techniques for Integrated Package Distribution Systems Karen R. Smilowitz idealizations of network geometries, operating costs, demand and customer distributions, and routing patterns that approximate the total cost of operation. The design problem is then reduced to a series of optimization

Daganzo, Carlos F.

233

Portal control of viral prohead expansion and DNA packaging  

SciTech Connect (OSTI)

Bacteriophage T4 terminase packages DNA in vitro into empty small or large proheads (esps or elps). In vivo maturation of esps yields the more stable and voluminous elps required to contain the 170 kb T4 genome. Functional proheads can be assembled containing portal-GFP fusion proteins. In the absence of terminase activity these accumulated in esps in vivo, whereas wild-type portals were found in elps. By nuclease protection assay dsDNAs of lengths 0.1, 0.2, 0.5, 5, 11, 20, 40 or 170 kb were efficiently packaged into wild-type elps in vitro, but less so into esps and gp20-GFP elps; particularly with DNAs shorter than 11 kb. However, 0.1 kb substrates were equally efficiently packaged into all types of proheads as judged by fluorescence correlation spectroscopy. These data suggest the portal controls the expansion of the major capsid protein lattice during prohead maturation, and that this expansion is necessary for DNA protection but not for packaging.

Ray, Krishanu, E-mail: krishanu@cfs.umbi.umd.ed [Department of Biochemistry and Molecular Biology, University of Maryland School of Medicine, 108 N. Greene St., Baltimore, MD 21201 (United States); Center for Fluorescence Spectroscopy, University of Maryland School of Medicine, 725 W. Lombard St., Baltimore, MD 21201 (United States); Oram, Mark, E-mail: moram@umaryland.ed [Department of Biochemistry and Molecular Biology, University of Maryland School of Medicine, 108 N. Greene St., Baltimore, MD 21201 (United States); Ma, Jinxia, E-mail: JMa@som.umaryland.ed [Department of Biochemistry and Molecular Biology, University of Maryland School of Medicine, 108 N. Greene St., Baltimore, MD 21201 (United States); Black, Lindsay W., E-mail: lblack@umaryland.ed [Department of Biochemistry and Molecular Biology, University of Maryland School of Medicine, 108 N. Greene St., Baltimore, MD 21201 (United States)

2009-08-15T23:59:59.000Z

234

Cleanup Verification Package for the 118-F-6 Burial Ground  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 118-F-6 Burial Ground located in the 100-FR-2 Operable Unit of the 100-F Area on the Hanford Site. The trenches received waste from the 100-F Experimental Animal Farm, including animal manure, animal carcasses, laboratory waste, plastic, cardboard, metal, and concrete debris as well as a railroad tank car.

H. M. Sulloway

2008-10-02T23:59:59.000Z

235

Cleanup Verification Package for the 300 VTS Waste Site  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 300 Area Vitrification Test Site, also known as the 300 VTS site. The site was used by Pacific Northwest National Laboratory as a field demonstration site for in situ vitrification of soils containing simulated waste.

S. W. Clark and T. H. Mitchell

2006-03-13T23:59:59.000Z

236

ADAGE: A software package for analyzing graph evolution  

E-Print Network [OSTI]

graph evolution. 2.2 Using ADAGE 2.2.1 Installation ADAGE was built for use on MATLAB 2007 version. In this case input is a string. If the MATLAB matrix has already been saved, simply run > input = loadADAGE: A software package for analyzing graph evolution Mary McGlohon, Christos Faloutsos May 2007

237

Vadose Zone Hydrogeology Data Package for Hanford Assessments  

SciTech Connect (OSTI)

This data package documents the technical basis for selecting physical and geochemical parameters and input values that will be used in vadose zone modeling for Hanford assessments. This work was originally conducted as part of the Characterization of Systems Task of the Groundwater Remediation Project managed by Fluor Hanford, Inc., Richland, Washington, and revised as part of the Characterization of Systems Project managed by the Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy, Richland Operations Office (DOE-RL). This data package describes the geologic framework, the physical, hydrologic, and contaminant transport properties of the geologic materials, and deep drainage (i.e., recharge) estimates, and builds on the general framework developed for the initial assessment conducted using the System Assessment Capability (SAC) (Bryce et al. 2002). The general approach for this work was to update and provide incremental improvements over the previous SAC data package completed in 2001. As with the previous SAC data package, much of the data and interpreted information were extracted from existing documents and databases. Every attempt was made to provide traceability to the original source(s) of the data or interpretations.

Last, George V.; Freeman, Eugene J.; Cantrell, Kirk J.; Fayer, Michael J.; Gee, Glendon W.; Nichols, William E.; Bjornstad, Bruce N.; Horton, Duane G.

2006-06-01T23:59:59.000Z

238

Release Data Package for the 2004 Composite Analysis  

SciTech Connect (OSTI)

This data package contains all the key parameter data necessary for implementation of the Release Module to conduct the 2004 Composite Analysis. A composite analysis is required by DOE Order 435.1 to ensure public safety through the management of active and planned low-level radioactive waste disposal facilities associated with Hanford.

Riley, Robert G.; Lopresti, Charles A.

2004-08-02T23:59:59.000Z

239

Testing hadronic-interaction packages at cosmic-ray energies  

SciTech Connect (OSTI)

A comparative analysis of the secondary particles output of the main hadronic interaction packages used in simulations of extensive air showers is presented. Special attention is given to the study of events with very energetic leading secondary particles, including diffractive interactions.

Canal, C. A. Garcia; Sciutto, S. J. [Departamento de Fisica, Universidad Nacional de La Plata, C.C. 67-1900 La Plata (Argentina); IFLP - CONICET, Universidad Nacional de La Plata, C.C. 67-1900 La Plata (Argentina); Tarutina, T. [Departamento de Fisica, Universidad Nacional de La Plata, C.C. 67-1900 La Plata (Argentina)

2009-03-01T23:59:59.000Z

240

International MODIS and AIRS processing package: AIRS products and applications  

E-Print Network [OSTI]

International MODIS and AIRS processing package: AIRS products and applications Elisabeth Weisz presented and discussed in this paper demonstrate that the IMAPP AIRS retrieval product is rigorously parameters from the operational AIRS L2 product and data from other instruments. Keywords: AIRS, IMAPP

Li, Jun

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

HSL HSL MI20 PACKAGE SPECIFICATION HSL 2007  

E-Print Network [OSTI]

HSL HSL MI20 PACKAGE SPECIFICATION HSL 2007 1 SUMMARY Given an nĂ?n sparse matrix A and an n-vector z, HSL MI20 computes the vector x = Mz, where M is an algebraic multigrid (AMG) v allocatable dummy arguments and allocatable components of derived types. Remark: The development of HSL MI20

Silvester, David J.

242

EXAMINATION OF FIBERBOARD FROM SHIPPING PACKAGE 9975-01819  

SciTech Connect (OSTI)

Upon opening package 9975-01819 following approximately 5.5 years storage in KAMS, it was observed that the fiberboard was moldy, and the total height of the fiberboard assemblies was less than normal. Observations and measurements have since been made on three subsequent occasions. The available information indicates that the package contained approximately 2.5 liters of water in excess of what would normally exist within the fiberboard. This excess moisture led to a significant loss of fiberboard strength, the subsequent compression of the bottom layers, and the growth of mold observed on both the upper and lower fiberboard assemblies. In its current state, the fiberboard from this package retains a density (related to the criticality control function) within the range measured in other packages. The amount of excess moisture present is modest throughout most of the fiberboard, and its effect on thermal conductivity should be small. The thermal conductivity should increase significantly only near the bottom of the lower fiberboard assembly where the majority of excess moisture was found. The impact absorption capability is affected, and the ability of the fiberboard to perform this function in the current state must be evaluated. The longer such a condition persists, the greater the impact on fiberboard mechanical properties.

Daugherty, W

2009-04-14T23:59:59.000Z

243

Drop Tests of the Closure Ring for the 9975 Package  

SciTech Connect (OSTI)

The drop tests of the closure ring for 9975 packages, described here, were performed to answer questions raised by the regulatory authority as a result of deformation of the closure ring and drum rim observed during drop tests conducted in September 1998.

Smith, A.C

1999-09-29T23:59:59.000Z

244

System specification for the plutonium stabilization and packaging system  

SciTech Connect (OSTI)

This document describes functional design requirements for the Plutonium Stabilization and Packaging System (Pu SPS), as required by DOE contract DE-AC03-96SF20948 through contract modification 9 for equipment in Building 707 at Rocky Flats Environmental Technology Site (RFETS).

NONE

1996-07-01T23:59:59.000Z

245

Testing of the CANDU Spent Fuel Storage Basket Package  

SciTech Connect (OSTI)

The paper described the results of testing for a CANDU Spent Fuel Storage Basket Package Prototype intended to be used for transport and storage of the CANDU spent fuel bundles within NPP CANDU Cernavoda, Romania. The results obtained proved that the objectives of those tests were achieved

Vieru, G.

2002-02-28T23:59:59.000Z

246

WAPDEG Analysis of Waste Package and Drip shield Degradation  

SciTech Connect (OSTI)

As directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]), an analysis of the degradation of the engineered barrier system (EBS) drip shields and waste packages at the Yucca Mountain repository is developed. The purpose of this activity is to provide the TSPA with inputs and methodologies used to evaluate waste package and drip shield degradation as a function of exposure time under exposure conditions anticipated in the repository. This analysis provides information useful to satisfy ''Yucca Mountain Review Plan, Final Report'' (NRC 2003 [DIRS 163274]) requirements. Several features, events, and processes (FEPs) are also discussed (Section 6.2, Table 15). The previous revision of this report was prepared as a model report in accordance with AP-SIII.10Q, Models. Due to changes in the role of this report since the site recommendation, it no longer contains model development. This revision is prepared as a scientific analysis in accordance with AP-SIII.9Q, ''Scientific Analyses'' and uses models previously validated in (1) ''Stress Corrosion Cracking of the Drip Shield, the Waste Package Outer Barrier, and the Stainless Steel Structural Material'' (BSC 2004 [DIRS 169985]); (2) ''General Corrosion and Localized Corrosion of Waste Package Outer Barrier'' (BSC 2004 [DIRS 169984]); and (3) ''General Corrosion and Localized Corrosion of Drip Shield'' (BSC 2004 [DIRS 169845]). The integrated waste package degradation (IWPD) analysis presented in this report treats several implementation-related issues, such as defining the number and size of patches per waste package that undergo stress corrosion cracking; recasting the weld flaw analysis in a form as implemented in the Closure Weld Defects (CWD) software; and, general corrosion rate manipulations (e.g., change of scale in Section 6.3.4). The weld flaw portion of this report takes input from an engineering calculation (BSC 2004 [DIRS 170024]) and uses standard mathematical methods to enable easier implementation. The IWPD analysis also provides guidance on implementation of early failures (importance sampling and multinomial distribution usage). These manipulations are evident from standard scientific practices, approaches, or methods and do not require changes to the previously validated models. The IWPD analysis itself (Section 6.4), not the resultant curves from executing the IWPD analysis presented in Section 6.5 (which are for illustrative purposes), is used directly in total system performance assessment (TSPA). The IWPD analysis simulates general corrosion and stress corrosion cracking of the waste package outer barrier and general corrosion of the drip shield. The effects of igneous and seismic events and localized corrosion on drip shield and waste package performance are not evaluated in this report. The outputs of this report are inputs and methodologies used by TSPA to evaluate waste package and drip shield degradation as a function of exposure time under exposure conditions anticipated in the repository. The analyses presented in this report are for the current repository design (BSC 2004 [DIRS 168489]).

K. Mon

2004-09-29T23:59:59.000Z

247

Complex-wide representation of material packaged in 3013 containers  

SciTech Connect (OSTI)

The DOE sites packaging plutonium oxide materials packaged according to Department of Energy 3013 Standard (DOE-STD-3013) are responsible for ensuring that the materials are represented by one or more samples in the Materials Identification and Surveillance (MIS) program. The sites categorized most of the materials into process groups, and the remaining materials were characterized, based on the prompt gamma analysis results. The sites issued documents to identify the relationships between the materials packaged in 3013 containers and representative materials in the MIS program. These “Represented” documents were then reviewed and concurred with by the MIS Working Group. However, these documents were developed uniquely at each site and were issued before completion of sample characterization, small-scale experiments, and prompt gamma analysis, which provided more detailed information about the chemical impurities and the behavior of the material in storage. Therefore, based on the most recent data, relationships between the materials packaged in 3013 containers and representative materials in the MIS program been revised. With the prompt gamma analysis completed for Hanford, Rocky Flats, and Savannah River Site 3013 containers, MIS items have been assigned to the 3013 containers for which representation is based on the prompt gamma analysis results. With the revised relationships and the prompt gamma analysis results, a Master “Represented” table has been compiled to document the linkages between each 3013 container packaged to date and its representative MIS items. This table provides an important link between the Integrated Surveillance Program database, which contains information about each 3013 container to the MIS items database, which contains the characterization, prompt gamma data, and storage behavior data from shelf-life experiments for the representative MIS items.

Narlesky, Joshua E.; Peppers, Larry G.; Friday, Gary P.

2009-06-01T23:59:59.000Z

248

Engineering design automation tool for yield learning model for IC packaging  

E-Print Network [OSTI]

The leading edge of semiconductor manufacturing is the high yield production of semiconductor devices of which integrated circuit packaging has a continuous increasing demand along with integrated circiut functionality. IC packaging manufacturing...

Sarwar, Abul Kalam

2012-06-07T23:59:59.000Z

249

The Future of Injection Molding in Food Packaging for the United States  

E-Print Network [OSTI]

The injection molding process has been used for many years to produce food packaging in the United States. It is important to understand the forces in both the food industry and packaging industry to determine the role ...

Meissbach, Kenneth

2005-05-20T23:59:59.000Z

250

736 IEEE TRANSACTIONS ON ADVANCED PACKAGING, VOL. 28, NO. 4, NOVEMBER 2005 Simulation of Lossy Package Transmission Lines  

E-Print Network [OSTI]

Package Transmission Lines Using Extracted Data From One-Port TDR Measurements and Nonphysical RLGC Models, the frequency-dependent characteristic impedance and propagation constant of lossy transmission lines have been ( ), conductance ( ) and capacitance ( ) (RLGC) models have been developed for simulating lossy transmission lines

Swaminathan, Madhavan

251

Performance and Reliability of Bonded Interfaces for High-Temperature Packaging (Presentation)  

SciTech Connect (OSTI)

This presentation reviews the status of the performance and reliability of bonded interfaces for high-temperature packaging.

Devoto, D.

2014-06-01T23:59:59.000Z

252

Packaging and Transportation Support at LANL CTMA 2012  

SciTech Connect (OSTI)

Operations Support Packaging and Transportation (OS-PT) supports LANL in various functions. Some highlights of the past year have been with the work relating to environmental remediation, type B packaging, non-DOT compliant transfers, and special permit training. The TA-21 remediation project was part of the ARRA funding that LANL received. The $212 million in funding was used to demolish 24 buildings at TA-21, excavate the lab's oldest waste disposal site, and install 16 groundwater monitoring wells. The project was completed ahead of schedule and under budget. More than 300 tons of metal was recycled and all the soil excavated from MDA-B was replaced with clean fill. OS-PT supported this projected by transporting more than 7 million pounds of waste to TA-54 Area G with an addendum to their TSD. Because of the public access on the transfer route, Los Alamos County restricted the transfer to happen from 2:00 AM to 4:00 AM. OS-PT conducted 8 transfers in support of this project. Some concerns included the contaminated trailers at receipt facilities when transferring filled Super Sacks. Future Super Sacks were over packed into new IP-2 Super Sacks before shipping. OS-PT is also supporting the remediation of TA-54 Area G. LANL has an agreement with the State of New Mexico to remove all TRU waste currently stored above ground from at Area G. OS-PT supports this initiative with transfers of TRU waste under LANL's TSD and support of TRU shipments to WIPP. Another project supported by our organization is gas cylinder/dewar recycling and remediation. We are focusing on reducing risk associated with unneeded gasses at LANL. To minimized excessive ordering, to save money and time, and to minimize hazards OS-PT is supporting a gas recycling program. This program will allow programmatic organization across LANL to share unused/unneeded gasses. Instead of old dewars being disposed of, OS-PT has began identifying these dewars and sending them for refurbishment. To date, this effort has saved LANL $450K and estimated saving for future efforts will be more than $1.5 million. Some Projects that are happening here at LANL are offsite source recovery, weapon component transfers, and isotope science production. There are specific packages that help support these projects for the shipment of related materials. OS-PT provides support to these packages to ensure they are and will be available to continue this support. The Areva 435-B Overpack will help the Offsite Source Recovery Project recover high activity gamma sources from various locations across the globe. The Safety Analysis for Packaging is scheduled for initial completion June of 2012. The DPP-1 package is designed to replace the Model FL, which was designed by Rocky Flats and began service in 1990. LANL has collaborated on package design with LLNL, Pantex, Y-12, and KCP. LANL is supporting LLNL on component fixture development. Testing to 10 CFR 71 is to be completed in the Fall of 2012 and scheduled for NA-174 approval in 2014. The SAFESHIELD package helps supports LANL's Isotope production projects. This package can transfer highly irradiated materials from LANL's accelerator to material processing facilities. LANL worked to renew the SAFESHEILD's Certification for 5 more years.

Salazar, Nick [Los Alamos National Laboratory

2012-06-08T23:59:59.000Z

253

The Recycling Models and Its Research Progress of the Packaging Waste Polymer in China  

Science Journals Connector (OSTI)

With the rapid development of economy as well as the rise of packaging industry in China, the polymer packaging products also increases gradually. However, most of these products are one-off products, which mean after being used for once, they are always ... Keywords: packaging, waste, polymer, recycling, mode

Changqing Fang; Maorong Zhang; Shisheng Zhou; Xin Wang

2008-12-01T23:59:59.000Z

254

Project management: A Handbook of fundamentals for the packaging student and professional with a review of current literature.  

E-Print Network [OSTI]

??This thesis seeks to introduce the basic concepts and techniques of project management to packaging students and professionals. After reviewing these fundamentals, packaging students and… (more)

Fischer, Kenneth

2001-01-01T23:59:59.000Z

255

Developing Energy Efficiency Packages for ENERGY STAR New Homes  

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

Developing Energy Efficiency Packages for ENERGY STAR New Homes Developing Energy Efficiency Packages for ENERGY STAR New Homes Speaker(s): Rich Brown Date: July 23, 1998 - 12:00pm Location: 90-3148 The Environmental Protection Agency's ENERGY STAR Homes program promotes the construction of new homes that consume at least 30% less energy than homes meeting the 1993 Model Energy Code. Thus far, builders participating in the program have needed an individual Home Energy Rating System (HERS) rating for each house certified under the program. Tract-home builders have been reluctant to participate in the program, however, because of the time and cost of HERS ratings, as well as the uncertainty about precisely what measures their homes will need to meet the ENERGY STAR guidelines. To make it easier for large production builders

256

Cermet Waste Packages Using Depleted Uranium Dioxide and Steel  

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

CERMET WASTE PACKAGES USING DEPLETED URANIUM DIOXIDE AND STEEL CERMET WASTE PACKAGES USING DEPLETED URANIUM DIOXIDE AND STEEL Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6180 Tel: (865) 574-6783 Fax: (865) 574-9512 Email: forsbergcw@ornl.gov Manuscript Number: 078 File Name: DuCermet.HLWcon01.article.final Article Prepared for 2001 International High-Level Radioactive Waste Management Conference American Nuclear Society Las Vegas, Nevada April 29-May 3, 2001 Limits: 1500 words; 3 figures Actual: 1450 words; 3 figures Session: 3.6 Disposal Container Materials and Designs The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution,

257

Stabilization, Packaging, and Storage of Plutonium-Bearing Materials  

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

DOE-STD-3013-2000 September 2000 Superseding DOE-STD-3013-99 November 1999 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced 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; (703) 605-6000. DOE-STD-3013-2000 iii ABSTRACT This Standard provides guidance for the stabilization, packaging and safe storage of plutonium-

258

EVALUATION OF THE FINAL REPORT: WASTE PACKAGE MATERIALS PERFORMANCE PEER  

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

EVALUATION OF THE FINAL REPORT: WASTE EVALUATION OF THE FINAL REPORT: WASTE PACKAGE MATERIALS PERFORMANCE PEER REVIEW PANEL B00000000-01717-5700-00005 REV 00 August 2002 This document is not an official copy and is for informational purposes only. QA: QA B00000000-01717-5700-00005 REV 00 August 2002 Evaluation of the Final Report: Waste Package Materials Performance Peer Review Panel Prepared by: Jack N. Bailey, Jack D. Cloud, Thomas E. Rodgers, and Tammy S.E. Summers Prepared for: U.S. Department of Energy Yucca Mountain Site Characterization Office P.O. Box 364629 North Las Vegas, Nevada 89036-8629 Prepared by: Bechtel SAIC Company, LLC 1180 Town Center Drive Las Vegas, Nevada 89144 Under Contract Number DE-AC28-01RW12101 Disclaimer Signature Page Change History Acknowledgments

259

Criteria for Packaging and Storing Uranium-233-Bearing Materials  

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

3028-2000 3028-2000 July 2000 DOE STANDARD CRITERIA FOR PACKAGING AND STORING URANIUM-233-BEARING MATERIALS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced 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; (703) 605-6000. DOE-STD-3028-2000 iii ABSTRACT This Standard provides guidance for the packaging and long-term (50 years) storage of stabilized, separated uranium-233(

260

The radioactive materials packaging handbook: Design, operations, and maintenance  

SciTech Connect (OSTI)

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

1998-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Strategy for experimental validation of waste package performance assessment  

SciTech Connect (OSTI)

A strategy for the experimental validation of waste package performance assessment has been developed as part of a program supported by the Repository Technology Program. The strategy was developed by reviewing the results of laboratory analog experiments, in-situ tests, repository simulation tests, and material interaction tests. As a result of the review, a listing of dependent and independent variables that influence the ingress of water into the near-field environment, the reaction between water and the waste form, and the transport of radionuclides from the near-field environment was developed. The variables necessary to incorporate into an experimental validation strategy were chosen by identifying those which had the greatest effect of each of the three major events, i.e., groundwater ingress, waste package reactions, and radionuclide transport. The methodology to perform validation experiments was examined by utilizing an existing laboratory analog approach developed for unsaturated testing of glass waste forms. 185 refs., 9 figs., 2 tabs.

Bates, J.K.; Abrajano, T.A. Jr.; Wronkiewicz, D.J.; Gerding, T.J.; Seils, C.A.

1990-07-01T23:59:59.000Z

262

FAQS Job Task Analyses - NNSA Package Certification Engineer FAQS  

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

NNSA Package Certification Engineer Functional Area NNSA Package Certification Engineer Functional Area Qualification Standard DOE-STD-1026-2009 Step 1 Identify and evaluate tasks - Develop a comprehensive list of tasks that define the job. o A great starting point is the list of Duties and Responsibilities from the FAQS. o Give careful thought to additional tasks that could be considered. o Don't worry about deleting tasks at this point - that is a part of the process further down. - List the tasks (and their sources, e.g., Duties and Responsibilities #1) in the chart below. - Discuss each task as a group and come to a consensus pertaining to Importance and Frequency of the task (i.e., each team member can consent to the assigned value, even if they don't exactly agree with it).

263

ORISE Contract, PART 1 Â… THE SCHEDULE, Section D Packaging and Marking  

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

THE SCHEDULE THE SCHEDULE SECTION D PACKAGING AND MARKING D.1 PACKAGING (NOV 2004) .................................................................................................. 3 D.2 MARKING (MAY 1997)...................................................................................................... 3 Section D - Page 1 of 4 DE-AC05-06OR23100 Blank Page Section D - Page 2 of 4 DE-AC05-06OR23100 PART I - THE SCHEDULE SECTION D PACKAGING AND MARKING D.1 PACKAGING (NOV 2004) Preservation, packaging, and packing for shipment or mailing of all work delivered hereunder shall be in accordance with good commercial practice and adequate to insure acceptance by common carrier and safe transportation at the most economical rate(s). The Contractor shall not utilize certified or registered

264

FABRICATION AND DEPLOYMENT OF THE 9979 TYPE AF RADIOACTIVE WASTE PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

This paper summarizes the development, testing, and certification of the 9979 Type A Fissile Packaging that replaces the UN1A2 Specification Shipping Package eliminated from Department of Transportation (DOT) 49 CFR 173. The DOT Specification Package was used for many decades by the U.S. nuclear industry as a fissile waste container until its removal as an authorized container by DOT. This paper will discuss stream lining procurement of high volume radioactive material packaging manufacturing, such as the 9979, to minimize packaging production costs without sacrificing Quality Assurance. The authorized content envelope (combustible and non-combustible) as well as planned content envelope expansion will be discussed.

Blanton, P.; Eberl, K.

2013-10-10T23:59:59.000Z

265

Energy Management Systems Package for Small Commercial Buildings  

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

EnMS (energy management EnMS (energy management systems) Package for Small Commercial Buildings Jessica Granderson Lawrence Berkeley National Laboratory JGranderson@lbl.gov 510.486.6792 April 4, 2013 2 | Building Technologies Office eere.energy.gov Purpose & Objectives Problem Statement: Small commercial buildings present two challenges for implementing energy efficiency strategies 1) high transaction cost relative to total savings 2) lack of personnel time or skill available for energy management

266

Numerical experiments with the LANCELOT package (Release A)  

E-Print Network [OSTI]

by A.R. Conn 1 , Nick Gould 2 , and Ph.L. Toint 3 Report 92/16 (3rd revision) September 5, 1995 1 IBM T with the LANCELOT package (Release A) for large­scale nonlinear optimization A.R. Conn Nick Gould Ph.L. Toint numerical tests and discuss the relative merits of the options. The experiments described involve both

Toint, Philippe

267

Contact-Handled and Remote-Handled Transuranic Waste Packaging  

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

Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel other directives.

2011-08-09T23:59:59.000Z

268

Heat Exchanger Network Targeting, Design and Analysis: The MIDAS Package  

E-Print Network [OSTI]

HEAT EXCHANGER NETWORK TARGETING, DESIGN AND ANALYSIS: THE MIDAS PACKAGE I. BARTON, D.H. JONES AND G.J. SMITH TENSA Services, Houston, Texas ICI PLC, Wilton England ABSTRACT Recent work to consolidate pinch-based procedures for targeting... was reduced to industrial practice by the U.K. major, ICI PLC. A wide range of pinch-based procedures have been developed for process energy efficiency applications. These incl~de heat exchanger network (HEN) design [2,3], distillation system...

Barton, I.; Jones, D. H.; Smith, G. J.

269

21-PWR WASTE PACKAGE WITH ABSORBER PLATES LOADING CURVE EVALUATION  

SciTech Connect (OSTI)

The objective of this calculation is to evaluate the required minimum burnup as a function of initial pressurized water reactor (PWR) assembly enrichment that would permit loading of spent nuclear fuel into the 21 PWR waste package with absorber plates design as provided in Attachment IV. This calculation is an example of the application of the methodology presented in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent U-235, and a burnup range of 0 through 45 GWd/MTU. Higher burnups were not necessary because 45 GWd/MTU was high enough for the loading curve determination. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing PWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials. This calculation is subject to the ''Quality Assurance Requirements and Description'' (QARD) (DOE 2004) because it concerns engineered barriers that are included in the ''Q-List'' (BSC 2004k, Appendix A) as items important to safety and waste isolation.

J.M. Scaglione

2004-12-17T23:59:59.000Z

270

Safety evaluation for packaging (onsite) depleted uranium waste boxes  

SciTech Connect (OSTI)

This safety evaluation for packaging (SEP) allows the one-time shipment of ten metal boxes and one wooden box containing depleted uranium material from the Fast Flux Test Facility to the burial grounds in the 200 West Area for disposal. This SEP provides the analyses and operational controls necessary to demonstrate that the shipment will be safe for the onsite worker and the public.

McCormick, W.A.

1997-08-27T23:59:59.000Z

271

Cleanup Verification Package for the 618-8 Burial Ground  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 618-8 Burial Ground, also referred to as the Solid Waste Burial Ground No. 8, 318-8, and the Early Solid Waste Burial Ground. During its period of operation, the 618-8 site is speculated to have been used to bury uranium-contaminated waste derived from fuel manufacturing, and construction debris from the remodeling of the 313 Building.

M. J. Appel

2006-08-10T23:59:59.000Z

272

Borehole completion data package for well 199-N-81  

SciTech Connect (OSTI)

Well 199-N-81 was drilled in 1993 as a RCRA groundwater monitoring for the 1324-N network. The well is completed at the top of the uppermost aquifer, in the Ringold Formation. This data package includes information on drilling, construction, development, and aquifer testing. Copies of forms, notes, and diagrams completed in the field comprise the bulk of this document. Few interpretations are included. Lithologic contacts were picked by the site geologist. An attempt was made to interpret aquifer test data.

Hartman, M.J.

1994-05-05T23:59:59.000Z

273

NEW APPROACH TO ADDRESSING GAS GENERATION IN RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect (OSTI)

Safety Analysis Reports for Packaging (SARP) document why the transportation of radioactive material is safe in Type A(F) and Type B shipping containers. The content evaluation of certain actinide materials require that the gas generation characteristics be addressed. Most packages used to transport actinides impose extremely restrictive limits on moisture content and oxide stabilization to control or prevent flammable gas generation. These requirements prevent some users from using a shipping container even though the material to be shipped is fully compliant with the remaining content envelope including isotopic distribution. To avoid these restrictions, gas generation issues have to be addressed on a case by case basis rather than a one size fits all approach. In addition, SARP applicants and review groups may not have the knowledge and experience with actinide chemistry and other factors affecting gas generation, which facility experts in actinide material processing have obtained in the last sixty years. This paper will address a proposal to create a Gas Generation Evaluation Committee to evaluate gas generation issues associated with Safety Analysis Reports for Packaging material contents. The committee charter could include reviews of both SARP approved contents and new contents not previously evaluated in a SARP.

Watkins, R; Leduc, D; Askew, N

2009-06-25T23:59:59.000Z

274

COMPACTION OF FIBERBOARD IN A 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Compaction of lower layers in the fiberboard overpack has been observed in 9975 packages that contain elevated moisture. Lab testing has resulted in a better understanding of (1) the relationship between the fiberboard moisture level and compaction of the lower fiberboard assembly, and (2) the behavior of the fiberboard during transport. In laboratory tests, higher moisture content has been shown to correspond to higher total compaction of fiberboard material, greater rate of compaction, and continued compaction over a longer period of time. In addition, laboratory tests have shown that the application of a dynamic load results in higher fiberboard compaction. The test conditions and sample geometric/loading configurations were chosen to simulate the regulatory requirements for 9975 package input dynamic loading. Dynamic testing was conducted over a period of several months to acquire immediate and cumulative changes in geometric data for various moisture levels. Currently, one sample set has undergone a complete dynamic test regimen, while testing of another set is still in-progress. The dynamic input, data acquisition, test effects on sample dynamic parameters, and interim results from this test program will be summarized and compared to regulatory specifications for dynamic loading. This will provide a basis from which to evaluate the impact of moisture and fiberboard compaction on the safety basis for transportation (Safety Analysis Report for Packaging) and storage (facility Documented Safety Analysis) at the Savannah River Site (SRS).

Stefek, T.; Daugherty, W.; Estochen, E.; Leduc, D.

2011-05-11T23:59:59.000Z

275

Initial Package Design Concepts Integrated Product Team (IPT) Summary Report  

SciTech Connect (OSTI)

Initially, the question of transporting TRU waste to WIPP was raised as part of the EM Integration activities. The issue was re-examined as part of the system-wide view to re-engineer the TRU waste program. Consequently, the National Transportation Program and the National TRU Waste Program, in a cooperative effort, made a commitment to EM-20 to examine the feasibility of using rail to transport TRU waste material to WIPP. In December of 1999 Mr. Philip Altomare assembled a team of subject matter experts (SME) to define initial concepts for a Type B package capable of shipping TRU waste by rail (see Attachment 1 for a list of team members). This same team of experts also provided input to a preliminary study to determine if shipping TRU waste by rail could offer cost savings or other significant advantages over the current mode of operation using TRUPACT-II packages loaded on truck. As part of the analysis, the team also identified barriers to implementing rail shipments to WIPP and outlined a path forward. This report documents the findings of the study and its initial set of recommendations. As the study progressed, it was expanded to include new packages for truck as well as rail in recognition of the benefits of shipping large boxes and contaminated equipment.

Moss, J.; Luke, Dale Elden

2000-03-01T23:59:59.000Z

276

PTS 13.2 Packaging and Preparation for Shipment 4/10/95 | Department of  

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

PTS 13.2 Packaging and Preparation for Shipment 4/10/95 PTS 13.2 Packaging and Preparation for Shipment 4/10/95 PTS 13.2 Packaging and Preparation for Shipment 4/10/95 The objective of this surveillance is to evaluate the effectiveness of the contractor's programs for packaging radioactive and hazardous wastes for shipment. The Facility Representative examines packages ready for shipment, observes preparation of packages, and reviews documents that establish the acceptability of packages. The Facility Representative verifies compliance with DOE requirements including requirements established by the Department of Transportation and the U.S. Nuclear Regulatory Commission. PTS13-02.doc More Documents & Publications PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 CMS 3.4 Temporary Changes, 4/10/95

277

Validation of the guidelines for portable meteorological instrument packages. Task IV. Development of an insolation handbook and instrumentation package  

SciTech Connect (OSTI)

The purpose of this report is to show how the objective of developing guidelines for a solar energy related portable meteorology instrument package, under the auspices of the International Energy Agency (IEA), was carried out and preliminarily demonstrated and validated. A project to develop guidelines for such packages was initiated at IEA's Solar Heating and Cooling of Buildings Program Expert's Meeting held in Norrkoping, Sweden in February 1976. An international comparison of resultant devices was conducted on behalf of the IEA at a conference held in Hamburg, Federal Republic of Germany, in 1978. Results of the 1978 Hamburg comparison of two devices and the Swiss Mobile Solar Radiation System, using German meteorological standards, are discussed. The consensus of the IEA Task Group is that the objective of the subtask has been accomplished.

None

1980-10-01T23:59:59.000Z

278

Assessment of microelectronics packaging for high temperature, high reliability applications  

SciTech Connect (OSTI)

This report details characterization and development activities in electronic packaging for high temperature applications. This project was conducted through a Department of Energy sponsored Cooperative Research and Development Agreement between Sandia National Laboratories and General Motors. Even though the target application of this collaborative effort is an automotive electronic throttle control system which would be located in the engine compartment, results of this work are directly applicable to Sandia`s national security mission. The component count associated with the throttle control dictates the use of high density packaging not offered by conventional surface mount. An enabling packaging technology was selected and thermal models defined which characterized the thermal and mechanical response of the throttle control module. These models were used to optimize thick film multichip module design, characterize the thermal signatures of the electronic components inside the module, and to determine the temperature field and resulting thermal stresses under conditions that may be encountered during the operational life of the throttle control module. Because the need to use unpackaged devices limits the level of testing that can be performed either at the wafer level or as individual dice, an approach to assure a high level of reliability of the unpackaged components was formulated. Component assembly and interconnect technologies were also evaluated and characterized for high temperature applications. Electrical, mechanical and chemical characterizations of enabling die and component attach technologies were performed. Additionally, studies were conducted to assess the performance and reliability of gold and aluminum wire bonding to thick film conductor inks. Kinetic models were developed and validated to estimate wire bond reliability.

Uribe, F.

1997-04-01T23:59:59.000Z

279

Building Energy-Efficiency: Best Practice Policies and Policy Packages  

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

Extended Summary Extended Summary Mark Levine, Stephane de la Rue de Can, Nina Zheng, Christopher Williams Lawrence Berkeley National Laboratory Jennifer Amann American Council for Energy-Efficient Economy Dan Staniaszek Sustainability Consulting Ltd. October 2012 This work was supported by the Global Building Performance Network of ClimateWorks Foundation through the U.S. Department of Energy under Contract No. DE-AC02- 05CH11231. ERNEST ORLANDO LAWRENCE BERKELEY NATIONAL LABORATORY LBNL-6006E BEE Best Practice Policies and Policy Packages (Extended Summary) Disclaimer 2 Disclaimer This document was prepared as an account of work sponsored by the United States Government. While

280

Method for Determining Optimal Residential Energy Efficiency Retrofit Packages  

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

Method for Determining Method for Determining Optimal Residential Energy Efficiency Retrofit Packages B. Polly, M. Gestwick, M. Bianchi, R. Anderson, S. Horowitz, C. Christensen, and R. Judkoff National Renewable Energy Laboratory April 2011 ii NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process,

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

NNSA Package Certification Engineer Functional Area Qualification Standard  

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

DOE-STD-1026-2009 February 2009 DOE STANDARD NNSA PACKAGE CERTIFICATION ENGINEER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1026-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1026-2009 iv INTENTIONALLY BLANK DOE-STD-1026-2009 v TABLE OF CONTENTS ACKNOWLEDGMENT ................................................................................................................ vii PURPOSE ....................................................................................................................................1

282

Cleanup Verification Package for the 118-F-1 Burial Ground  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 118-F-1 Burial Ground on the Hanford Site. This burial ground is a combination of two locations formerly called Minor Construction Burial Ground No. 2 and Solid Waste Burial Ground No. 2. This waste site received radioactive equipment and other miscellaneous waste from 105-F Reactor operations, including dummy elements and irradiated process tubing; gun barrel tips, steel sleeves, and metal chips removed from the reactor; filter boxes containing reactor graphite chips; and miscellaneous construction solid waste.

E. J. Farris and H. M. Sulloway

2008-01-10T23:59:59.000Z

283

Low-cost flexible packaging materials for batteries.  

SciTech Connect (OSTI)

Considerable cost savings can be realized if the metal container used for lithium-based batteries is replaced with a flexible multi-laminate containment commonly used in the food packaging industry. This laminate structure must have air, moisture, and electrolyte barrier capabilities, be resistant to hydrogen-fluoride attack, and be heat-sealable. After extensive screening of commercial films, the polyethylene and polypropylene classes of polymers were found to have an adequate combination of mechanical, permeation, and seal-strength properties. The search for a better film and adhesive is ongoing.

Jansen, A. N.; Amine, K.; Newman, A. E.; Vissers, D. R.; Henriksen, G. L.; Chemical Engineering

2002-03-01T23:59:59.000Z

284

Cleanup Verification Package for the 116-K-2 Effluent Trench  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 116-K-2 effluent trench, also referred to as the 116-K-2 mile-long trench and the 116-K-2 site. During its period of operation, the 116-K-2 site was used to dispose of cooling water effluent from the 105-KE and 105-KW Reactors by percolation into the soil. This site also received mixed liquid wastes from the 105-KW and 105-KE fuel storage basins, reactor floor drains, and miscellaneous decontamination activities.

J. M. Capron

2006-04-04T23:59:59.000Z

285

FRAMES Software System: Linking to the Statistical Package R  

SciTech Connect (OSTI)

This document provides requirements, design, data-file specifications, test plan, and Quality Assurance/Quality Control protocol for the linkage between the statistical package R and the Framework for Risk Analysis in Multimedia Environmental Systems (FRAMES) Versions 1.x and 2.0. The requirements identify the attributes of the system. The design describes how the system will be structured to meet those requirements. The specification presents the specific modifications to FRAMES to meet the requirements and design. The test plan confirms that the basic functionality listed in the requirements (black box testing) actually functions as designed, and QA/QC confirms that the software meets the client’s needs.

Castleton, Karl J.; Whelan, Gene; Hoopes, Bonnie L.

2006-12-11T23:59:59.000Z

286

MODEL 9975 SHIPPING PACKAGE: IMPACT OF CAPLUG REMOVAL ON FIBERBOARD MOISTURE LEVEL  

SciTech Connect (OSTI)

Two 9975 shipping packages were removed from KAC and provided to SRNL for test purposes, after both packages were found to exceed the 1 inch maximum criterion for the axial gap at the top of the package. Package 9975-01818 was found with an axial gap of 1.437 inch, and an estimated 2.5 liters of excess moisture in the lower fiberboard layers. Package 9975-02287 was found with an axial gap of 1.008 inch, and only slightly elevated moisture levels relative to typical packages. Prior data from the 9975 Surveillance Program has shown that the 9975 drum provides a degree of isolation, and will tend to preserve fiberboard moisture levels for an extended period of time. Both packages were provided to SRNL to identify whether removal of the 4 caplugs in each package would allow moisture to escape the package. Following testing with the caplugs removed for approximately 1 year, this report documents the findings from this effort. Two 9975 shipping packages removed from service in K-Area Complex (KAC) due to an excessive axial gap have been tested in SRNL to determine if caplug removal would facilitate the reduction of excess fiberboard moisture. An additional question to be answered through this testing was whether the resulting moisture loss would reduce the axial gap, reversing the effect seen during storage with excess moisture present. These packages have completed approximately 1 year in test, during which time the weight of each package has steadily decreased as a result of moisture migration out of the package. However, elevated moisture levels still remain in the packages. During this test period, the bottom fiberboard layers of package 9975-01818 (which contained the greater amount of excess moisture) experienced further compaction, and the axial gap of both packages has increased. This effort has shown that removal of the caplugs may not be a sufficient measure to rehabilitate packages with excess moisture or excess axial gaps in a timely manner. However, this measure might make a meaningful contribution in combination with other actions (to be determined). It is recommended that the caplug removal tests in SRNL be discontinued at this time.

Daugherty, W.

2011-06-23T23:59:59.000Z

287

THERMAL TESTING OF PROTOTYPE GENERAL PURPOSE FISSILE PACKAGES USING A FURNACE  

SciTech Connect (OSTI)

The 9977/9978 General Purpose Fissile Package (GPFP) was designed by SRNL to replace the DOT 6M Specification Package and ship Plutonium and Uranium metals and oxides. Urethane foam was used for the overpack to ensure the package would withstand the 10CFR71.73(c)(2) crush test, which is a severe test for drum-type packages. In addition, it was necessary to confirm that the urethane foam configuration provided adequate thermal protection for the containment vessel during the subsequent 10CFR71.73(c)(4) thermal test. Development tests were performed on early prototype test specimens of different diameter overpacks and a range of urethane foam densities. The thermal test was performed using an industrial furnace. Test results were used to optimize the selection of package diameter and foam density, and provided the basis for design enhancements incorporated into the final package design.

Smith, A; Lawrence Gelder, L; Paul Blanton, P

2007-02-16T23:59:59.000Z

288

DEVELOPMENT OF A NEW TYPE A(F)RADIOACTIVE MATERIAL PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

In a coordinated effort, the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) proposed the elimination of the Specification Packaging from 49 CFR 173.[1] In accordance with the Federal Register, issued on October 1, 2004, new fabrication of Specification Packages would no longer be authorized. In accordance with the NRC final rulemaking published January 26, 2004, Specification Packagings are mandated by law to be removed from service no later than October 1, 2008. This coordinated effort and resulting rulemaking initiated a planned phase out of Specification Type B and Type A fissile (F) material transportation packages within the Department of Energy (DOE) and its subcontractors. One of the Specification Packages affected by this regulatory change is the UN1A2 Specification Package, per DOT 49 CFR 173.417(a)(6). To maintain continuing shipments of DOE materials currently transported in UN1A2 Specification Package after the existing authorization expires, a replacement Type A(F) material packaging design is under development by the Savannah River National Laboratory. This paper presents a summary of the prototype design effort and testing of the new Type A(F) Package development for the DOE. This paper discusses the progress made in the development of a Type A Fissile Packaging to replace the expiring 49 CFR UN1A2 Specification Fissile Package. The Specification Package was mostly a single-use waste disposal container. The design requirements and authorized radioactive material contents of the UN1A2 Specification Package were defined in 49 CFR. A UN1A2 Specification Package was authorized to ship up to 350 grams of U-235 in any enrichment and in any non-pyrophoric form. The design was specified as a 55-gallon 1A2 drum overpack with a body constructed from 18 gauge steel with a 16 gauge drum lid. Drum closure was specified as a standard 12-gauge ring closure. The inner product container size was not specified but was listed as any container that met Specification 7A requirements per 49 CFR 178.350. Specification 7A containers were required to withstand Type A packaging tests required by 49CFR173.465 with compliance demonstrated through testing, analysis or similarity to other containers. The maximum weight of the 7A product container, the radioactive content, and any internal packaging was limited to 200 lbs. The total gross weight for the UN1A2 Specification Package was limited to 350 lbs. No additional restrictions were applied. Authorization for use did not require the UN1A2 Specification Package to be tested to the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) required for performance based, Type A(F) packages certified by the NRC or DOE. The Type A(F) Packaging design discussed in this paper is required to be in compliance with the regulatory safety requirements defined in Code of Federal Regulations (CFR) 10 CFR 71.41 through 71.47 and 10 CFR71.71. Sub-criticality of content must be maintained under the Hypothetical Accident Conditions specified under 10 CFR71.73. These federal regulations, and other applicable DOE Orders and Guides, govern design requirements for a Type A(F) package. Type A(F) packages with less than an A2 quantity of radioactive material are not required to have a leak testable boundary. With this exception a Type A(F) package design is subject to the same test requirements set forth for the design of a performance based Type B packaging.

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

289

Responses of Conventional Ring Closures of Drum Type Packages to Regulatory Drop Tests with Application to the 9974/9975 Package  

SciTech Connect (OSTI)

DOT, DOE and NRC Type A and Type B radioactive material (RAM) transport packages routinely use industrial or military specification drums with conventional clamp ring closures as an overpack. Considerable testing has been performed on these type packages over the past 30 years. Observations from test data have resulted in various design changes and recommendations to the standard drum specification and use, enhancing the reliability of the overpack. Recently, performance capability of the 9975 conventional clamp ring closure design was questioned by the Regulatory Authority. This paper highlights the observations of recent 9974 and 9975 package testing that led to redesign of the 9975, replacing the standard clamp ring closure with a bolted ring closure. In the course of this review and redesign effort, 18 package designs and approximately 100 Hypothetical Accident Condition (HAC) drops of various size and weight drum packages were evaluated. A trend was observed with respect to overpack lid failures for packages utilizing conventional ring closure. Based on this trend, a limit on the ratio of the content weight to total package weight was identified, beyond which clamp ring closure failure may be expected.

Blanton, P.S.

2002-05-31T23:59:59.000Z

290

Remote Handling Equipment for a High-Level Waste Waste Package Closure System  

SciTech Connect (OSTI)

High-level waste will be placed in sealed waste packages inside a shielded closure cell. The Idaho National Laboratory (INL) has designed a system for closing the waste packages including all cell interior equipment and support systems. This paper discusses the material handling aspects of the equipment used and operations that will take place as part of the waste package closure operations. Prior to construction, the cell and support system will be assembled in a full-scale mockup at INL.

Kevin M. Croft; Scott M. Allen; Mark W. Borland

2006-04-01T23:59:59.000Z

291

EXAMINATION OF SHIPPING PACKAGES 9975-01818, 9975-01903 AND 9975-02287  

SciTech Connect (OSTI)

Three 9975 shipping packages were examined to investigate the non-conforming condition of an axial air gap greater than 1 inch. This condition typically indicates the presence of excess moisture in the fiberboard overpack, and may be accompanied by degradation in the fiberboard properties. The package with the largest axial air gap (9975-01818, with an air gap of 1.437 inches) was found to contain significant excess moisture, and the lower fiberboard assembly was covered with mold and was significantly degraded in strength. This condition is very similar to that observed previously in package 9975-01819. Both packages (-1818 and -1819) appear to contain a similar amount of excess moisture, which was previously estimated for 9975-01819 as {approx}2.5 liters. The condition of 9975-01818 was also evidenced by several rust spots along the bottom chime of the drum, although no significant rust was noted on the closure bolts. Packages 9975-01903 and 9975-02287 were also examined. The axial air gap in these two packages was less than in 9975-01818, but still exceeded 1 inch. These two packages contained elevated moisture levels, although not significantly higher than seen in other 'typical' packages. The fiberboard in these two packages was of sound integrity, and appeared generally consistent with undegraded material. A few small patches of mold on and near the bottom of the fiberboard in 9975-01903 appeared dormant. No mold was observed on package 9975-02287. The SPA will provide recommendations on possible follow-up activities with these three packages. This might include a demonstration in SRNL of whether removal of the caplugs from similar packages would facilitate removal of excess moisture. Future efforts should also include an assessment of using the 1 inch axial gap criterion as a valid indicator of fiberboard degradation.

Daugherty, W.

2009-11-18T23:59:59.000Z

292

Headspace profiles of modified atmosphere packaged fresh red snapper (Lutjanus campechanus) by gas liquid chromatography  

E-Print Network [OSTI]

activity. Typical components found in the headspace were, butanal, ethanol, hexanal, dimethylamine and trimethylamine. During storage at 4 C, the microbial population within the packages containing C02 tended to shift from an initial gram negative... dioxide (CO2) enriched atmospheres and vacuum packaging have become important new technologies that will improve the quality and shelf-life of fresh seafood products. This type of packaging not only extends the shelf-life of seafoods, it also makes...

Scorah, Craig Darrell Allen

1988-01-01T23:59:59.000Z

293

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

SciTech Connect (OSTI)

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

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

2008-05-27T23:59:59.000Z

294

External Corrosion Analysis of Model 9975 Packaging Container  

SciTech Connect (OSTI)

The Materials Consultation Group of SRTC has completed an external corrosion analysis of the Model 9975 packaging container for storage in K Reactor under ambient conditions for a period of 12 years. The 12-year storage period includes two years for shipping and ten years for storage. Based on review of existing literature and stated building storage conditions, corrosion degradation of the 304L Stainless Steel (SS) packaging container (drum and vessels) should be minimal during the 12 year time period. There may be visible corrosion on the galvanized carbon steel pallet due to initial drum handling. The visible corrosion will not be sufficient to cause significant degradation during the 12-year storage period. The Materials Consultation Group concludes that there are sufficient data to establish the technical basis for safe storage of the Model 9975 container in the 105-K building for up to 10 years following the 2-year shipping period. The data are sufficient to allow the 304L SS containers to be stored for a total period of 15 years.

Vormelker, P.

1999-02-23T23:59:59.000Z

295

FOAM DENSITY SENSITIVITY STUDY FOR THE 9977 PACKAGE  

SciTech Connect (OSTI)

Two layers of insulation fill the volume of the 9977 package between the drum liner and the shell. One of these layers is composed of General Plastics FR-3716 polyurethane foam (also known as Last-A-Foam{reg_sign}), poured through fill holes in the drum bottom and foamed in place. There was concern that the density of the foam insulating layer may vary due to the manufacturing process and that variations in foam density would compromise the safety basis of the package. Thus, a structural finite element analysis was performed to investigate this concern. The investigation examined the effect of replacing the material properties for the FR-3716 polyurethane foam, which has a density equal to 16 lb{sub m}/ft{sup 3}, with material properties of similar foam with varying densities through finite element analysis of hypothetical accident conditions (HAC) pertaining to impact conditions. The results showed that the functional performance of the containment vessel (CV) was not compromised under the conditions investigated.

Gorczyca, J; Tsu-Te Wu, T

2008-05-02T23:59:59.000Z

296

SDLS: a Matlab package for solving conic least-squares problems  

E-Print Network [OSTI]

Jun 28, 2007 ... This document is an introduction to the Matlab package SDLS (Semi-Definite. Least-Squares) for solving least-squares problems over convex ...

2007-06-28T23:59:59.000Z

297

Low-Cost and Low-Electromagnetic-Interference Packaging of Optical Transceiver Modules  

Science Journals Connector (OSTI)

The low-cost and low-electromagnetic-interference (EMI) packaging of optical transceiver modules employing housings of plastic composites are developed and fabricated. Optical...

Cheng, Wood-Hi; Hung, Wen-Chi; Lee, Chien-Hui; Hwang, Gan-Lin; Jou, Wern-Shiang; Wu, Tzong-Lin

2004-01-01T23:59:59.000Z

298

Hypothetical accident condition thermal analysis and testing of a Type B drum package  

SciTech Connect (OSTI)

A thermophysical property model developed to analytically determine the thermal response of cane fiberboard when exposed to temperatures and heat fluxes associated with the 10 CFR 71 hypothetical accident condition (HAC) has been benchmarked against two Type B drum package fire test results. The model 9973 package was fire tested after a 30 ft. top down drop and puncture, and an undamaged model 9975 package containing a heater (21W) was fire tested to determine content heat source effects. Analysis results using a refined version of a previously developed HAC fiberboard model compared well against the test data from both the 9973 and 9975 packages.

Hensel, S.J.; Alstine, M.N. van; Gromada, R.J. [Westinghouse Savannah River Co., Aiken, SC (United States)

1995-11-01T23:59:59.000Z

299

Hypothetical accident condition thermal analysis and testing of a Type B drum package  

SciTech Connect (OSTI)

A thermophysical property model developed to analytically determine the thermal response of cane fiberboard when exposed to temperatures and heat fluxes associated with the 10 CFR 71 hypothetical accident condition (HAC) has been benchmarked against two Type B drum package fire test results. The model 9973 package was fire tested after a 30 ft. top down drop and puncture, and an undamaged model 9975 package containing a heater (21W) was fire tested to determine content heat source effects. Analysis results using a refined version of a previously developed HAC fiberboard model compared well against the test data from both the 9973 and 9975 packages.

Hensel, S.J.; Alstine, M.N. Van; Gromada, R.J.

1995-07-01T23:59:59.000Z

300

E-Print Network 3.0 - analysis software package Sample Search...  

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

and King Fahd University of Petroleum & Minerals Summary: : Software Design & Architecture Semester: 072 12;SWE 316 (072) Principles of Package Cohesion and Coupling......

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Safety analysis report for packaging: the ORNL DOT specification 6M - tritium trap package. [Tritium absorbed as solid uranium tritide in depleted uranium trap  

SciTech Connect (OSTI)

The ORNL DOT Specification 6M--Tritium Trap Package was fabricated at the Oak Ridge National Laboratory (ORNL) for the transport of Type B quantities of tritium as solid uranium tritide. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container, a drop test performed by the ORNL Operations Division, and International Atomic Energy Agency (IAEA) approvals on a similar tritium transport container. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities of tritium. 4 references, 8 figures.

DeVore, J.R.

1984-04-01T23:59:59.000Z

302

DOE Order Self Study Modules - DOE O 460.1C Packaging and Transportation Safety and DOE O 460.2A Departmental Materials Transportation and Packaging Management  

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

60.1C 60.1C PACKAGING AND TRANSPORTATION SAFETY DOE O 460.2A DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT DOE O 460.1C and 460.2A Familiar Level June 2011 1 DOE O 460.1C PACKAGING AND TRANSPORTATION SAFETY DOE O 460.2A DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT FAMILIAR LEVEL _________________________________________________________________________ OBJECTIVES Given the familiar level of this module and the resources, you will be able to perform the following: 1. What are the objectives of U.S. Department of Energy (DOE) O 460.1C? 2. What is the DOE/National Nuclear Security Administration (NNSA) exemption process in DOE O 460.1C? 3. What are the onsite safety requirements specified by DOE O 460.1C? 4. What are the objectives of DOE O 460.2A?

303

FINAL REPORT WASTE PACKAGE MATERIALS PERFORMANCE PEER REVIEW PANEL  

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

REPORT REPORT WASTE PACKAGE MATERIALS PERFORMANCE PEER REVIEW PANEL FEBRUARY 28, 2002 This document is not an official copy and is for informational purposes only. Signature Page Preface Executive Summary TABLE OF CONTENTS 1. INTRODUCTION 1.1 Organization of the Peer Review 1.2 Objectives of the Review 1.3 Content of the Final Report 2. MAIN FINDINGS 2.1 Perspective 2.2 Overall Findings 2.3 Corrosion Degradation Modes 2.4 Higher or Lower Temperature Operating Modes 2.5 Long-Term Uniform Corrosion of Passive Metal 2.6 Alloy Specification and Comparison 2.7 Technical Issues to be Resolved 2.8 Organizational-Managerial Issues 3. SUMMARY OF DEGRADATION MODES AND CONTRIBUTING FACTORS 3.1 Introduction 3.2 Repository Conditions: Overview of Time, Temperature, Environment

304

Parametric Analysis of Environmental Performance of Reused/Recycled Packaging  

Science Journals Connector (OSTI)

Much higher targets are now required:? paper and glass 60%, metals 50%, plastics 22.5%, and overall recycling between 55% and 80% (1). ... If the systems have the same net imports, that is, if Inet1 = Inet2, or ?Inet = 0, the system with higher ? is associated with lower environmental impacts from production (K3) at steady state, if and only if its production level, Pe2, remains below a critical level given by Pe2 recycle flow remains below a critical value, R2 recycled material and virgin resources, respectively (values for p and q, related to various impacts, for glass, aluminum, ferrous, and various plastic packaging materials are given in ref 15). ...

C. A. Tsiliyannis

2005-11-16T23:59:59.000Z

305

Sintered silver joints via controlled topography of electronic packaging subcomponents  

SciTech Connect (OSTI)

Disclosed are sintered silver bonded electronic package subcomponents and methods for making the same. Embodiments of the sintered silver bonded EPSs include topography modification of one or more metal surfaces of semiconductor devices bonded together by the sintered silver joint. The sintered silver bonded EPSs include a first semiconductor device having a first metal surface, the first metal surface having a modified topography that has been chemically etched, grit blasted, uniaxial ground and/or grid sliced connected to a second semiconductor device which may also include a first metal surface with a modified topography, a silver plating layer on the first metal surface of the first semiconductor device and a silver plating layer on the first metal surface of the second semiconductor device and a sintered silver joint between the silver plating layers of the first and second semiconductor devices which bonds the first semiconductor device to the second semiconductor device.

Wereszczak, Andrew A.

2014-09-02T23:59:59.000Z

306

High Availability Instrumentation Packaging Standards for the ILC and Detectors  

SciTech Connect (OSTI)

ILC designers are exploring new packaging standards for Accelerator Controls and Instrumentation, particularly high-speed serial interconnect systems for intelligent instruments versus the existing parallel backplanes of VME, VXI and CAMAC. The High Availability Advanced Telecom Computing Architecture (ATCA) system is a new industrial open standard designed to withstand single-point hardware or software failures. The standard crate, controller, applications module and sub-modules are being investigated. All modules and sub-modules are hot-swappable. A single crate is designed for a data throughput in communications applications of 2 Tb/s and an Availability of 0.99999, which translates into a downtime of five minutes per year. The ILC is planning to develop HA architectures for controls, beam instrumentation and detector systems.

Downing, R.W.; Larsen, R.S.; /SLAC

2006-11-30T23:59:59.000Z

307

OFFICE OF HEALH, SAFETY AND SECURITY INFORMATION COLLECTION PACKAGE  

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

HEALH, SAFETY AND SECURITY HEALH, SAFETY AND SECURITY INFORMATION COLLECTION PACKAGE OMB 1910-0300: ES&H Reporting Systems Description of Collections April 10, 2012 The information obtained from DOE contractors by this information collection is used by Department management at the appropriate levels to manage the work pertaining to environment, safety and health throughout DOE and will include automated reporting of information into the following systems: Computerized Accident/Incident Reporting System (CAIRS) - The CAIRS is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE operations as described in DOE O 231.1B, Environment, Safety and Health Reporting. This system contains information from reporting contractors and

308

Value Engineering Study for Closing Waste Packages Containing TAD Canisters  

SciTech Connect (OSTI)

The Office of Civilian Radioactive Waste Management announced their intention to have the commercial utilities package spent nuclear fuel in shielded, transportable, ageable, and disposable containers prior to shipment to the Yucca Mountain repository. This will change the conditions used as a basis for the design of the waste package closure system. The environment is now expected to be a low radiation, low contamination area. A value engineering study was completed to evaluate possible modifications to the existing closure system using the revised requirements. Four alternatives were identified and evaluated against a set of weighted criteria. The alternatives are (1) a radiation-hardened, remote automated system (the current baseline design); (2) a nonradiation-hardened, remote automated system (with personnel intervention if necessary); (3) a nonradiation-hardened, semi-automated system with personnel access for routine manual operations; and (4) a nonradiation-hardened, fully manual system with full-time personnel access. Based on the study, the recommended design is Alternative 2, a nonradiation-hardened, remote automated system. It is less expensive and less complex than the current baseline system, because nonradiation-hardened equipment can be used and some contamination control equipment is no longer needed. In addition, the inclusion of remote automation ensures throughput requirements are met, provides a more reliable process, and provides greater protection for employees from industrial accidents and radiation exposure than the semi-automated or manual systems. Other items addressed during the value engineering study as requested by OCRWM include a comparison to industry canister closure systems and corresponding lessons learned; consideration of closing a transportable, ageable, and disposable canister; and an estimate of the time required to perform a demonstration of the recommended closure system.

Colleen Shelton-Davis

2005-11-01T23:59:59.000Z

309

Adaptable Chip-Level Microfluidic Packaging for a Micro-Scale Gas Chromatograph  

E-Print Network [OSTI]

Adaptable Chip-Level Microfluidic Packaging for a Micro-Scale Gas Chromatograph Nathan Ward1@egr.msu.edu Abstract-- In this paper, we present a robust and adaptable technique to integrate microfluidics with an on the microfluidic package with non-sorbent epoxy. The stability and efficacy of the integrated detector cell

Mason, Andrew

310

EXAMINATION OF SHIPPING PACKAGES 9975-02274 AND 9975-04769  

SciTech Connect (OSTI)

Shipping packages 9975-02274 and 9975-04769 were examined in K-Area following the identification of a non-conforming condition; the axial gap between the drum flange and upper fiberboard assembly exceeded the maximum allowed value of 1 inch. The fiberboard in package 9975-02274 had slightly elevated moisture content, up to 19% wood moisture equivalent (WME). Other compliant packages have displayed similar moisture levels locally, but not as consistently throughout the entire fiberboard assembly. Evidence of mold was observed on the lower assembly, although it appeared relatively dormant. Relatively little compaction or physical degradation was observed in this package. Due to the mold, it is recommended that the fiberboard in this package not be re-used. The fiberboard in package 9975-04769 was relatively dry (7-10% WME) and showed no sign of compaction or physical degradation. Variations in the axial gap that have been measured on this package result from variations in the height of the upper and lower fiberboard assemblies, and their relative orientation to each other. The fiberboard in this package is physically sound and considered fit for continued use.

Daugherty, W.

2011-12-20T23:59:59.000Z

311

Criteria for Preparing and Packaging Plutonium Metals and Oxides for Long-Term Storage  

SciTech Connect (OSTI)

This Standard provides criteria for packaging of plutonium metals and stabilized oxides for storage periods of at least 50 years. To meet the criteria, plutonium-bearing materials must be in stable forms and be packaged in containers designed to maintain their integrity both under normal storage conditions and during anticipated handling accidents.

NONE

1994-12-01T23:59:59.000Z

312

The SISO CSPI PDG standard for COTS simulation package interoperability reference models  

Science Journals Connector (OSTI)

Discrete-event simulation is used to analyze production and logistics problems in many areas such as commerce, defense, health, manufacturing and logistics. Commercial-off-the-shelf (COTS) Simulation Packages (CSPs) are black box visual interactive modelling ... Keywords: COTS simulation package, discrete-event simulation, distributed simulation, interoperability, standards

Simon J. E. Taylor; Steffen Strassburger; Stephen J. Turner

2008-06-01T23:59:59.000Z

313

Sustainability assessment of renovation packages for increased energy efficiency for multi-family buildings in Sweden  

Science Journals Connector (OSTI)

In this paper, we propose a method for assessing renovation packages drawn up with the goal of increasing energy efficiency. The method includes calculation of bought energy demand, life-cycle cost (LCC) analysis and assessment of the building according to the Swedish environmental rating tool Miljöbyggnad (MB). In this way the methodology assesses economic, indoor environmental quality (IEQ) and specifically environmental aspects associated with energy demand of such packages from a sustainability point-of-view. Through MB, energy efficiency packages are placed in context with other necessary measures required to improve environmental performance in buildings, providing a consistent and systematic basis other than simply financial performance by which to compare capital improvements. The method is further explained and analyzed by applying it in three case studies. In each case study a multi-family building representing a typologically significant class in the Swedish building stock is considered, and for each building a base case and two renovation packages with higher initial investment requirement and higher energy efficiency are defined. It is shown that higher efficiency packages can impact IEQ indicators both positively and negatively and that packages reducing energy demand by approx. 50% have somewhat higher LCC. Identified positive IEQ impacts point to added value for packages that may not otherwise be communicated, while negative impacts identify areas where packages need to be improved, or where MB indicators may be referred to as specifications in procurement procedures.

Nils W.O. Brown; Tove Malmqvist; Wei Bai; Marco Molinari

2013-01-01T23:59:59.000Z

314

Integration Methodologies for Disparate Software Packages with an Emphasis on Usability  

E-Print Network [OSTI]

on electric motor design is presented for which early results are encouraging. Future development of CAD software packages supplied to the electric motor industry by Motor Design Ltd. Each package University, Wales, UK 2 Motor Design Ltd., Ellesmere, Shropshire, UK {lyndon.evans|dave.staton|dougie.hawkins}@motor

Grout, Vic

315

StochDecomp—Matlab package for noise decomposition in stochastic biochemical systems  

Science Journals Connector (OSTI)

......solved using the Matlab ODE solver...Analysis (PUA) Matlab package (Vanlier...and integrative Matlab package for computational...al. Detailed simulations of cell biology...in mesoscopic chemical systems. Nat...Stochastic Processes in Physics and...Supplementary Data - pdf file Supplementary......

Tomasz Jetka; Agata Charzynska; Anna Gambin; Michael P.H. Stumpf; Michal Komorowski

2014-01-01T23:59:59.000Z

316

Method of forming a package for MEMS-based fuel cell  

DOE Patents [OSTI]

A MEMS-based fuel cell package and method thereof is disclosed. The fuel cell package comprises seven layers: (1) a sub-package fuel reservoir interface layer, (2) an anode manifold support layer, (3) a fuel/anode manifold and resistive heater layer, (4) a Thick Film Microporous Flow Host Structure layer containing a fuel cell, (5) an air manifold layer, (6) a cathode manifold support structure layer, and (7) a cap. Fuel cell packages with more than one fuel cell are formed by positioning stacks of these layers in series and/or parallel. The fuel cell package materials such as a molded plastic or a ceramic green tape material can be patterned, aligned and stacked to form three dimensional microfluidic channels that provide electrical feedthroughs from various layers which are bonded together and mechanically support a MEMS-based miniature fuel cell. The package incorporates resistive heating elements to control the temperature of the fuel cell stack. The package is fired to form a bond between the layers and one or more microporous flow host structures containing fuel cells are inserted within the Thick Film Microporous Flow Host Structure layer of the package.

Morse, Jeffrey D; Jankowski, Alan F

2013-05-21T23:59:59.000Z

317

Tomoeye: A Matlab package for visualization of three-dimensional tomographic models  

E-Print Network [OSTI]

Tomoeye: A Matlab package for visualization of three-dimensional tomographic models A. Gorbatov models. Using a set of four Matlab programs, multiscale tomographic models can be explored in Cartesian. Sambridge (2004), Tomoeye: A Matlab package for visualization of three-dimensional tomographic models

Sambridge, Malcolm

318

Using fuzzy theory for packaging attribute deployment for new notebook computer introduction  

Science Journals Connector (OSTI)

The purpose of this study is to focus on the packaging issues at the new product introduction (NPI) stage of notebook computer that enterprises encounter when practicing global logistics. It acquires the weight of product design by quality function deployment ... Keywords: FMEA, QFD, TOPIS, new product introduction, packaging

Hsin Rau; Chien-Ping Liao; Wei-Jung Shiang; Chiu-Hsiang Lin

2007-06-01T23:59:59.000Z

319

Chitosan-mediated in situ biomolecule assembly in completely packaged microfluidic devices  

E-Print Network [OSTI]

Chitosan-mediated in situ biomolecule assembly in completely packaged microfluidic devices Jung Jin biomolecule assembly at readily addressable sites in microfluidic channels after complete fabrication and packaging of the microfluidic device. Aminopolysaccharide chitosan's pH responsive and chemically reactive

Rubloff, Gary W.

320

Physical test report for drop test of a 9974 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9974 radioactive material shipping package being dropped onto 6-inch diameter, 40-inch long puncture pin. Also reported are the drop test resuls for a 30-foot impact that failed the drum confinement boundary. The purpose of these drops was to show that the package lid would remain attached to the drum.

Blanton, P.S. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Assessment of Aging of Cork and TISAF Materials in the SAFKEG 3940A Package in KAMS  

SciTech Connect (OSTI)

This report provides an assessment of the potential for aging and degradation of the resin-bonded cork and the Thermal-Insulating, Shock-Absorbing Foam materials that are components of the SAFKEG 3940A package. This package may be used for interim storage of plutonium materials in the Savannah River Site K-Area Materials Storage.

Vormelker, P.R.

2003-12-10T23:59:59.000Z

322

T-529: Apple Mac OS PackageKit Distribution Script Remote Code Execution  

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

29: Apple Mac OS PackageKit Distribution Script Remote Code 29: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability T-529: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability January 6, 2011 - 2:53pm Addthis PROBLEM: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability PLATFORM: Apple Mac OS X Server 10.6 - 10.6.5, Apple Mac OS X 10.6 - 10.6.5 Vulnerable Platforms Details ABSTRACT: A format string issue exists in PackageKit's handling of distribution scripts. A man-in-the-middle attacker may be able to cause an unexpected application termination or arbitrary code execution when Software Update checks for new updates. This issue is addressed through improved validation of distribution scripts. This issue does not affect systems prior to Mac OS

323

Order Module--DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O  

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

O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O 460.2A, DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT Order Module--DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O 460.2A, DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT "The familiar level of this module is divided into two sections. The objectives and requirements of DOE O 460.1C and DOE O 460.2A will be discussed in the first and second sections, respectively. Several examples and practices throughout the module are provided to help familiarize you with the material. The practices will also help prepare you for the criterion test. Before continuing, you should obtain a copy of the Orders and implementation guides and manuals for this module. Copies of the Orders are available on the internet

324

INVESTIGATION OF THE PRESENCE OF DRUGSTORE BEETLES WITHIN CELOTEX ASSEMBLIES IN RADIOACTIVE MATERIAL PACKAGINGS  

SciTech Connect (OSTI)

During normal operations at the Department of Energy's Hanford Site in Hanford, WA, drugstore beetles, (Stegobium paniceum (L.) Coleoptera: Anobiidae), were found within the fiberboard subassemblies of two 9975 Shipping Packages. Initial indications were that the beetles were feeding on the Celotex{trademark} assemblies within the package. Celotex{trademark} fiberboard is used in numerous radioactive material packages serving as both a thermal insulator and an impact absorber for both normal conditions of transport and hypothetical accident conditions. The Department of Energy's Packaging Certification Program (EM-63) directed a thorough investigation to determine if the drugstore beetles were causing damage that would be detrimental to the safety performance of the Celotex{trademark}. The Savannah River National Laboratory is conducting the investigation with entomological expertise provided by Clemson University. The two empty 9975 shipping packages were transferred to the Savannah River National Laboratory in the fall of 2007. This paper will provide details and results of the ongoing investigation.

Loftin, B; Glenn Abramczyk, G

2008-06-04T23:59:59.000Z

325

Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings  

SciTech Connect (OSTI)

In the post 6M era, radioactive materials package users are faced with the disciplined operations associated with use of Certified Type B packagings. Many DOE, commercial and academic programs have a requirement to ship and/or store small masses of poorly characterized or unspecified radioactive material. For quantities which are small enough to be fissile exempt and have low radiation levels, the materials could be transported in a package which provides the required containment level. Because their Chalfant type containment vessels meet the highest standard of containment (helium leak-tight), the 9975, 9977, and 9978 are capable of transporting any of these contents. The issues associated with certification of a high-integrity, general purpose package for shipping small quantities of unspecified radioactive material are discussed and certification of the packages for this mission is recommended.

Smith, Allen; Abramczyk, Glenn; Nathan, Steven; Bellamy, Steve

2009-06-12T23:59:59.000Z

326

Control Humidity With Single-Duct, Single-Zone, Constant Air Volume System  

E-Print Network [OSTI]

for the AHLJ after Adjusted Conditions I I Return Fan: off; Return Damper: closed; Outside Air Damper: closed (signal) I 7- 14-99 9:44 AM AHU Dimensions Total Air Flow (CW Average Velocity (FPM) Temperature ("F) Humidity (% RH) Dew Point (OF... (FPM) Humidity (% RH) 1 83.0 -... r------ L -/ Dew Point (OF) Static Pressure supply 24" x 24" 4450 1180 Outside Air N/ A 2490 N/ A Mix Air 20" x 36" 4530 1091 T~mnrmt~w~ (OF) I 67.6 1 73.0 I 72.1 I 85.7 I . - 62.9 10.75 Return Air...

Chen, H.; Deng, S.; Bruner, H. L.; Claridge, D. E.

2000-01-01T23:59:59.000Z

327

Evaluation of moisture limits for uranium and plutonium mixed oxides to support on-site transportation packaging  

SciTech Connect (OSTI)

This report contains supporting documentation for onsite shipment of uranium and plutonium mixed oxide materials in the 9975 package.

Livingston, R.R.

2000-08-09T23:59:59.000Z

328

Aging and Phase Stability of Waste Package Outer Barrier  

SciTech Connect (OSTI)

This report was prepared in accordance with ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]). This report provides information on the phase stability of Alloy 22, the current waste package outer barrier material. The goal of this model is to determine whether the single-phase solid solution is stable under repository conditions and, if not, how fast other phases may precipitate. The aging and phase stability model, which is based on fundamental thermodynamic and kinetic concepts and principles, will be used to provide predictive insight into the long-term metallurgical stability of Alloy 22 under relevant repository conditions. The results of this model are used by ''General Corrosion and Localized Corrosion of Waste Package Outer Barrier'' as reference-only information. These phase stability studies are currently divided into three general areas: Tetrahedrally close-packed (TCP) phase and carbide precipitation in the base metal; TCP and carbide precipitation in welded samples; and Long-range ordering reactions. TCP-phase and carbide precipitates that form in Alloy 22 are generally rich in chromium (Cr) and/or molybdenum (Mo) (Raghavan et al. 1984 [DIRS 154707]). Because these elements are responsible for the high corrosion resistance of Alloy 22, precipitation of TCP phases and carbides, especially at grain boundaries, can lead to an increased susceptibility to localized corrosion in the alloy. These phases are brittle and also tend to embrittle the alloy (Summers et al. 1999 [DIRS 146915]). They are known to form in Alloy 22 at temperatures greater than approximately 600 C. Whether these phases also form at the lower temperatures expected in the repository during the 10,000-year regulatory period must be determined. The kinetics of this precipitation will be determined for both the base metal and the weld heat-affected zone (HAZ). The TCP phases (P, {mu}, and {sigma}) are present in the weld metal in the as-welded condition. It may be possible to eliminate these phases through a solution anneal heat treatment, but that may not be possible for the closure weld because the spent nuclear fuel cladding cannot be heated to more than 350 C. The effects of any stress mitigation techniques (such as laser peening or solution heat treating) that may be used to reduce the tensile stresses on the closure welds must also be determined. Cold-work will cause an increase in dislocation density, and such an increase in dislocation density may cause an increase in diffusion rates that control precipitation kinetics (Porter et al. 1992 [DIRS 161265]; Tawancy et al. 1983 [DIRS 104991]). Long-range order (LRO) occurs in nickel (Ni)-Cr-Mo alloys (such as Alloy 22) at temperatures less than approximately 600 C. This ordering has been linked to an increased susceptibility of Ni-Cr-Mo alloys to stress corrosion cracking and hydrogen embrittlement (Tawancy et al. 1983 [DIRS 104991]). These analyses provide information on the rate at which LRO may occur in Alloy 22 under repository conditions. Determination of the kinetics of transformations through experimental techniques requires that the transformations being investigated be accelerated due to the fact that the expected service life is at least 10,000 years. Phase transformations are typically accelerated through an increase in temperature. The rate of transformation is determined at the higher temperature and is extrapolated to the lower temperatures of interest.

F. Wong

2004-09-28T23:59:59.000Z

329

Containment analysis of the 9975 transportation package with multiple barriers  

SciTech Connect (OSTI)

A containment analysis has been performed for the scenario of non-routine transfer of a damaged 9975 package containing plutonium metal from K-area monitored storage to F-area on the Savannah River Site. A multiple barrier system with each barrier having a defined leakage rate of less than 1{times}10{sup {minus}3} cm{sup 3}/sec of air at Standard Temperature and Pressure was analyzed to determine the number of barriers needed to transport the package under normal transportation conditions to meet transportation requirements for containment. The barrier system was analyzed parametrically to achieve a composite system that met the federal requirements for the maximum permissible release rate given in Title 10 of the Code of Federal Regulations, Part 71. The multiple barrier system acts to retard the release of radioactivity. That is, a build-up in the radioactivity release rate occurs with time. For example, a system with three barriers (e.g., sealed plastic barrier) with a total free volume of 4,500 cm{sup 3} could be transported for a total time of up to approximately 10 days with a release rate within the permissible rate. Additional number of barriers, or volume of the barriers, or both, would extend to this period of time. For example, a system with seven barriers with a total free volume of 4,500 cm{sup 3} could be transported for up to 100 days. Plastic bags are one type of barrier used in movement of radioactive materials and capable of achieving a leak rate of 1{times}10{sup {minus}3} cm{sup 3}/sec of air at STP. Low-density polyethylene bags can withstand high temperature (up to 180 degrees C); a barrier thickness of 10 mils should be suitable for the barrier system. Additional requirements for barriers are listed in Section 4.2 of this report. Container testing per ANSI N14.5 is required to demonstrate leak rates for the individual barriers of less than 1{times}10{sup {minus}3} cm{sup 3}/sec.

Vinson, D.W.

2000-01-20T23:59:59.000Z

330

Performance-oriented packaging: A guide to identifying and designing. Identifying and designing hazardous materials packaging for compliance with post HM-181 DOT Regulations  

SciTech Connect (OSTI)

With the initial publication of Docket HM-181 (hereafter referred to as HM-181), the U.S. Department of Energy (DOE), Headquarters, Transportation Management Division decided to produce guidance to help the DOE community transition to performance-oriented packagings (POP). As only a few individuals were familiar with the new requirements, elementary guidance was desirable. The decision was to prepare the guidance at a level easily understood by a novice to regulatory requirements. This document identifies design development strategies for use in obtaining performance-oriented packagings that are not readily available commercially. These design development strategies will be part of the methodologies for compliance with post HM-181 U.S. Department of Transportation (DOT) packaging regulations. This information was prepared for use by the DOE and its contractors. The document provides guidance for making decisions associated with designing performance-oriented packaging, and not for identifying specific material or fabrication design details. It does provide some specific design considerations. Having a copy of the regulations handy when reading this document is recommended to permit a fuller understanding of the requirements impacting the design effort. While this document is not written for the packaging specialist, it does contain guidance important to those not familiar with the new POP requirements.

Not Available

1994-08-01T23:59:59.000Z

331

A comparison and benchmark of two electron cloud packages  

SciTech Connect (OSTI)

We present results from precision simulations of the electron cloud (EC) problem in the Fermilab Main Injector using two distinct codes. These two codes are (i)POSINST, a F90 2D+ code, and (ii)VORPAL, a 2D/3D electrostatic and electromagnetic code used for self-consistent simulations of plasma and particle beam problems. A specific benchmark has been designed to demonstrate the strengths of both codes that are relevant to the EC problem in the Main Injector. As differences between results obtained from these two codes were bigger than the anticipated model uncertainties, a set of changes to the POSINST code were implemented. These changes are documented in this note. This new version of POSINST now gives EC densities that agree with those predicted by VORPAL, within {approx}20%, in the beam region. The root cause of remaining differences are most likely due to differences in the electrostatic Poisson solvers. From a software engineering perspective, these two codes are very different. We comment on the pros and cons of both approaches. The design(s) for a new EC package are briefly discussed.

Lebrun, Paul L.G.; Amundson, James F.; Spentzouris, Panagiotis G.; Veitzer, Seth A.

2012-01-01T23:59:59.000Z

332

Unconventional Staging Package Selection Leads to Cost Savings  

SciTech Connect (OSTI)

In late 2010, U.S. Department of Energy (DOE) Deputy Secretary of Energy, Daniel Poneman, directed that an analysis be conducted on the U-233 steel-clad, Zero Power Reactor (ZPR) fuel plates that were stored at Oak Ridge National Laboratory (ORNL), focusing on cost savings and any potential DOE programmatic needs for the special nuclear material (SNM). The NA-162 Nuclear Criticality Safety Program requested retention of these fuel plates for use in experiments at the Nevada National Security Site (NNSS). A Secretarial Initiative challenged ORNL to make the first shipment to the NNSS by the end of the 2011 calendar year, and this effort became known as the U-233 Project Accelerated Shipping Campaign. To meet the Secretarial Initiative, National Security Technologies, LLC (NSTec), the NNSS Management and Operations contractor, was asked to facilitate the receipt and staging of the U-233 fuel plates in the Device Assembly Facility (DAF). Because there were insufficient staging containers available for the fuel plates, NSTec conducted an analysis of alternatives. The project required a staging method that would reduce the staging footprint while addressing nuclear criticality safety and radiation exposure concerns. To accommodate an intermediate staging method of approximately five years, the NSTec project team determined that a unique and unconventional staging package, the AT-400R, was available to meet the project requirements. By using the AT-400R containers, NSTec was able to realize a cost savings of approximately $10K per container, a total cost savings of nearly $450K.

,

2012-06-07T23:59:59.000Z

333

Integrated head package for top mounted nuclear instrumentation  

DOE Patents [OSTI]

A nuclear reactor such as a pressurized water reactor has an integrated head package providing structural support and increasing shielding leading toward the vessel head. A reactor vessel head engages the reactor vessel, and a control rod guide mechanism over the vessel head raises and lowers control rods in certain of the thimble tubes, traversing penetrations in the reactor vessel head, and being coupled to the control rods. An instrumentation tube structure includes instrumentation tubes with sensors movable into certain thimble tubes disposed in the fuel assemblies. Couplings for the sensors also traverse penetrations in the reactor vessel head. A shroud is attached over the reactor vessel head and encloses the control rod guide mechanism and at least a portion of the instrumentation tubes when retracted. The shroud forms a structural element of sufficient strength to support the vessel head, the control rod guide mechanism and the instrumentation tube structure, and includes radiation shielding material for limiting passage of radiation from retracted instrumentation tubes. The shroud is thicker at the bottom adjacent the vessel head, where the more irradiated lower ends of retracted sensors reside. The vessel head, shroud and contents thus can be removed from the reactor as a unit and rested safely and securely on a support.

Malandra, Louis J. (McKeesport, PA); Hornak, Leonard P. (Forest Hills, PA); Meuschke, Robert E. (Monroeville, PA)

1993-01-01T23:59:59.000Z

334

REVIEW OF CLEANING SOLUTIONS FOR USE ON COMPONENTS OF THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Several candidate cleaning products have been reviewed for use as a disinfectant on 9975 shipping package components which contain or have contacted mold. Following review of the compatibility of these products with each component, ammonia (ammonium hydroxide diluted to 1.5 wt% concentration) appears compatible with all package components that it might contact. Each of the other candidate products is incompatible with one or more package components. Accordingly, ammonia is recommended for this purpose. It is further recommended that all components which are disinfected be subsequently rinsed with di-ionized or distilled water.

Daugherty, W.

2013-09-30T23:59:59.000Z

335

Thermal Analysis and Test Results for the Overpack of a Typical Radioactive Materials Package  

SciTech Connect (OSTI)

In the course of the development and certification of the 9975 Package, extensive thermal analyses were performed and the package subjected to the regulatory HAC thermal test. The results of the thermal analysis and materials tests of the cane fiberboard overpack material were evaluated in comparison with the package HAC thermal test results. The evaluation confirmed that the thermal analysis correctly predicted the performance of the 9975 in the HAC fire test. The post test examination revealed that the heat affected region of the Celotex(R) overpack correlated well with the calculated temperature distribution

Smith, A.C.

2003-05-06T23:59:59.000Z

336

2014-08-28 Issuance: Energy Conservation Standards for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps; Notice of Proposed Rulemaking and Public Meeting  

Broader source: Energy.gov [DOE]

This document is a pre-publication Federal Register notice of proposed rulemaking and public meeting regarding energy conservation standards for packaged terminal air conditioners and packaged terminal heat pumps, as issued by the Assistant Secretary for Energy Efficiency and Renewable Energy on August 28, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

337

Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2  

SciTech Connect (OSTI)

This Technical Review Report (TRR) summarizes the review findings for the Safety Analysis Report for Packaging (SARP) for the Model 9977 B(M)F-96 shipping container. The content analyzed for this submittal is Content Envelope C.1, Heat Sources, in assemblies of Radioisotope Thermoelectric Generators or food-pack cans. The SARP under review, i.e., S-SARP-G-00001, Revision 2 (August 2007), was originally referred to as the General Purpose Fissile Material Package. The review presented in this TRR was performed using the methods outlined in Revision 3 of the Department of Energy's (DOE's) Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's, Regulatory Guide 7.9, i.e., Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9977 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. The Model 9977 Package design includes a single, 6-inch diameter, stainless steel pressure vessel containment system (i.e., the 6CV) that was designed and fabricated in accordance with Section III, Subsection NB, of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code. The earlier package designs, i.e., the Model 9965, 9966, 9967 and 9968 Packages, were originally designed and certified in the 1980s. In the 1990s, updated package designs that incorporated design features consistent with new safety requirements, based on International Atomic Energy Agency guidelines, were proposed. The updated package designs were the Model 9972, 9973, 9974 and 9975 Packages, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. Differences between the Model 9975 Package and the Model 9977 Package include: (1) The lead shield present in the Model 9975 Package is absent in the Model 9977 Package; (2) The Model 9975 Package has eight allowable contents, while the Model 9977 Package has a single allowable content. (3) The 6CV of the Model 9977 Package is similar in design to the outer Containment Vessel of the Model 9975 Package that also incorporates a 5-inch Containment Vessel as the inner Containment Vessel. (4) The Model 9975 Package uses a Celotex{reg_sign}-based impact limiter while the Model 9977 Package uses Last-A-Foam{reg_sign}, a polyurethane foam, for the impact limiter. (5) The Model 9975 Package has two Containment Vessels, while the Model 9977 Package has a single Containment Vessel.

DiSabatino, A; Hafner, R; West, M

2007-10-04T23:59:59.000Z

338

DEVELOPMENT OF THE HS99 AIR TRANSPORT TYPE A FISSILE PACKAGE  

SciTech Connect (OSTI)

An air-transport Type A Fissile radioactive shipping package for the transport of special form uranium sources has been developed by the Savannah River National Laboratory (SRNL) for the Department of Homeland Security. The Package model number is HS99 for Homeland Security Model 99. This paper presents the major design features of the HS99 and highlights engineered materials necessary for meeting the design requirements for this light-weight Type AF packaging. A discussion is provided demonstrating how the HS99 complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper summarizes the results of structural testing to specified in 10 CFR 71 for Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and proposed future missions for this packaging are also addressed.

Blanton, P.; Eberl, K.

2012-07-10T23:59:59.000Z

339

Lightweight Torsen style limited slip differential and rear driveline package for Formula SAE  

E-Print Network [OSTI]

This document describes the design and fabrication of a complete driveline package for the MIT Formula SAE race car. The driveline is centered around a custom aluminum housing for a Torsen® T 1I gearing. This gearing ...

Scelfo, Tony (Tony W.)

2006-01-01T23:59:59.000Z

340

Design and manufacture of a rear driveline package including limited slip differential for Formula SAE applications  

E-Print Network [OSTI]

This document describes the design and manufacture of a lightweight rear driveline package for a Formula SAE race car. The design focuses on all components needed to transfer power from the chain driven Honda CBR600 F4i ...

Yazicioglu, Tolga T

2008-01-01T23:59:59.000Z

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


341

THE StageTools PACKAGE FOR CREATING GEOMETRY FOR THE WEB  

E-Print Network [OSTI]

THE StageTools PACKAGE FOR CREATING GEOMETRY FOR THE WEB DAVIDE P. CERVONE Abstract. A number- ically for use on the web, or recorded on traditional video tape. Together, these modules form a powerful

Cervone, Davide P.

342

Decontamination of Bacillus subtilis Spores in a Sealed Package Using a Non-thermal Plasma System  

Science Journals Connector (OSTI)

The safety of packaged food and medical devices is a major concern to consumers and government officials. Recent inventions (PK-1 and PK-2) based on the principles of non-thermal, atmospheric plasma has shown sig...

Kevin M. Keener; J. L. Jensen…

2012-01-01T23:59:59.000Z

343

The SISO CSPI PDG standard for commercial off-the-shelf simulation package interoperability reference models  

Science Journals Connector (OSTI)

For many years discrete-event simulation has been used to analyze production and logistics problems in manufacturing and defense. Commercial-off-the-shelf Simulation Packages (CSPs), visual interactive modelling environments such as Arena, Anylogic, ...

Simon J. E. Taylor; Navonil Mustafee; Steffen Strassburger; Stephen J. Turner; Malcolm Y. H. Low; John Ladbrook

2007-12-01T23:59:59.000Z

344

Solar Energy Concentrators and their Optimization and Analysis with the OptisWorks Solar Package  

Science Journals Connector (OSTI)

Optis has developed tools put together in the OptisWorks Solar Package which can change the sun position by macros calculating and optimizing the efficiency of such concentrators based...

Hasna, Günther

345

Global Structure of a Three-Way Junction in a Phi29 Packaging...  

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

that aids investigations of phi29 packaging motor and developments of pRNA-based nanomedicine and nanomaterial. Citation: Zhang X, CS Tung, G Sowa, MM Hatmal, IS Haworth, and PZ...

346

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR GENERAL PURPOSE RADIOACTIVE MATERIALS PACKAGINGS  

SciTech Connect (OSTI)

Polyurethane foam has been employed in impact limiters for large radioactive materials packagings since the early 1980's. Its consistent crush response, controllable structural properties and excellent thermal insulating characteristics have made it attractive as replacement for the widely used cane fiberboard for smaller, drum size packagings. Accordingly, polyurethane foam was chosen for the overpack material for the 9977 and 9978 packagings. The study reported here was undertaken to provide data to support the analyses performed as part of the development of the 9977 and 9978, and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2009-02-18T23:59:59.000Z

347

Operations to be Performed in the Waste Package Dry Remediation Cell  

SciTech Connect (OSTI)

Describes planned and proposed operations for remediating damaged and/or out-of-compliance waste packages, casks, DPCs, overpacks, and containers at the Yucca Mountain Dry Transfer Facility.

Norman E. Cole; Randy K. Elwood

2003-10-01T23:59:59.000Z

348

Implementation Guide for Use with DOE O 460.2 Departmental Materials Transportation and Packaging Management  

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

The purpose of this guide is to assist those responsible for transporting and packaging Department materials, and to provide an understanding of Department policies on activities which supplement regulatory requirements.

1996-11-15T23:59:59.000Z

349

9977 TYPE B PACKAGING INTERNAL DATA COLLECTION FEASIBILITY TESTING - MAGNETIC FIELD COMMUNICATIONS  

SciTech Connect (OSTI)

The objective of this report is to document the findings from proof-of-concept testing performed by the Savannah River National Laboratory (SRNL) R&D Engineering and Visible Assets, Inc. for the DOE Packaging Certification Program (PCP) to determine if RuBee (IEEE 1902.1) tags and readers could be used to provide a communication link from within a drum-style DOE certified Type B radioactive materials packaging. A Model 9977 Type B Packaging was used to test the read/write capability and range performance of a RuBee tag and reader. Testing was performed with the RuBee tags placed in various locations inside the packaging including inside the drum on the outside of the lid of the containment vessel and also inside of the containment vessel. This report documents the test methods and results. A path forward will also be recommended.

Shull, D.

2012-06-18T23:59:59.000Z

350

Low-Cost Packaged CHP System with Reduced Emissions - Fact Sheet...  

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

system for a CHP project less than 1 megawatt (MW) in size. Low-Cost Packaged Combined Heat and Power System with Reduced Emissions More Documents & Publications Low-Cost...

351

Dynamic Analysis of 9975 Shipping Package without Overpack Subjected to 55-Foot Drop  

SciTech Connect (OSTI)

This paper discusses the evaluation of the dynamic response of a 9975 shipping package subjected to a load of 55-foot lateral drop without its overpack structure (fiberboard and drum).

Wu, T.

2001-05-30T23:59:59.000Z

352

Environmental, operational and financial sustainability of packaging methods in delivery businesses  

E-Print Network [OSTI]

In retail delivery companies, packaging is used to transport goods to customers while preventing damage, shrinkage and loss of the contents. With consumer preferences reflecting the growing concern for the environment, ...

Ng, Joshua (Zi Jie Joshua)

2010-01-01T23:59:59.000Z

353

Integration of numerical analysis tools for automated numerical optimization of a transportation package design  

SciTech Connect (OSTI)

The use of state-of-the-art numerical analysis tools to determine the optimal design of a radioactive material (RAM) transportation container is investigated. The design of a RAM package`s components involves a complex coupling of structural, thermal, and radioactive shielding analyses. The final design must adhere to very strict design constraints. The current technique used by cask designers is uncoupled and involves designing each component separately with respect to its driving constraint. With the use of numerical optimization schemes, the complex couplings can be considered directly, and the performance of the integrated package can be maximized with respect to the analysis conditions. This can lead to more efficient package designs. Thermal and structural accident conditions are analyzed in the shape optimization of a simplified cask design. In this paper, details of the integration of numerical analysis tools, development of a process model, nonsmoothness difficulties with the optimization of the cask, and preliminary results are discussed.

Witkowski, W.R.; Eldred, M.S.; Harding, D.C.

1994-09-01T23:59:59.000Z

354

Building America Webinar: Standardized Retrofit Packages — What Works to Meet Consistent Levels of Performance?  

Broader source: Energy.gov [DOE]

This webinar will focus on specific Building America projects that have examined methods to consistently meet high levels of energy performance in existing homes, with a focus on retrofit packages that can be replicated across many homes.

355

CHP Integrated with Packaged Boilers- Presentation by CMCE, Inc., June 2011  

Broader source: Energy.gov [DOE]

Presentation on CHP Integrated with Packaged Boilers, given by Carlo Castaldini of CMCE, Inc., at the U.S. DOE Industrial Distributed Energy Portfolio Review Meeting in Washington, D.C. on June 1-2, 2011.

356

2014-02-07 Issuance: Test Procedure for Commercial Packaged Boilers; Request for Information  

Broader source: Energy.gov [DOE]

This document is a pre-publication Federal Register request for information regarding test procedures for commercial packaged boilers, as issued by the Deputy Assistant Secretary for Energy Efficiency on February 7, 2014.

357

Collaborative direct to store distribution : the consumer packaged goods network of the future  

E-Print Network [OSTI]

Promotional events are a common occurrence in the grocery and drug industries. These events require consumer packaged goods manufacturers to deliver a large volume of product, beyond the typical demand, to the retailer in ...

Le, Nanette Thi

2011-01-01T23:59:59.000Z

358

cMsg - A publish/subscribe interprocess communication package and framework  

SciTech Connect (OSTI)

Asynchronous publish/subscribe messaging is a simple but powerful interprocess communication technique that is widely used in industry. It is less widely used in the academic/research world, partly because commercial implementations are fairly expensive. cMsg is both a full-featured publish/subscribe package and a framework within which one can deploy multiply underlying communication packages. The underlying packages need not implement asynchronous publish/subscribe messaging. This framework feature allows one to unify all communications under a single, flexible API, and allows for integration of legacy communication packages. Performance is excellent, making cMsg suitable for use in controls applications as well as in high-speed data transfer applications. cMsg will be used extensively by the next generation of experiments at JLab.

E. Wolin, D. Abbott, V. Gurjyan, G. Heyes, E. Jastrzembski, D. Lawrence, C. Timmer

2008-01-01T23:59:59.000Z

359

Philips Lumileds Develops a Low-Cost, High-Power, Warm-White LED Package  

Broader source: Energy.gov [DOE]

With the help of DOE funding, Philips Lumileds has developed a low-cost, high-power, warm-white LED package for general illumination. During the course of the two-year project, this package was used to commercialize a series of products with correlated color temperatures (CCTs) ranging from 2700 to 5700 K, under the product name LUXEON M. A record efficacy of nearly 125 lm/W was demonstrated at a flux of 1023 lumens, a CCT of 3435 K, and a color rendering index (CRI) of more than 80 at room temperature in the productized package. In an R&D package, a record efficacy of more than 133 lm/W at a flux of 1015 lumens, a CCT of 3475 K, and a CRI greater than 80 at room temperature were demonstrated.

360

Determination of Radioisotope Content by Measurement of Waste Package Dose Rates - 13394  

SciTech Connect (OSTI)

The objective of this communication is to report the observed correlation between the calculated air kerma rates produced by radioactive waste drums containing untreated ion-exchange resin and activated charcoal slurries with the measured radiation field of each package. Air kerma rates at different distances from the drum surface were calculated with the activity concentrations previously determined by gamma spectrometry of waste samples and the estimated mass, volume and geometry of solid and liquid phases of each waste package. The water content of each waste drum varies widely between different packages. Results will allow determining the total activity of wastes and are intended to complete the previous steps taken to characterize the radioisotope content of wastes packages. (authors)

Souza, Daiane Cristini B.; Gimenes Tessaro, Ana Paula; Vicente, Roberto [Nuclear and Energy Research Institute Brazil, Radioactive Waste Management Department IPEN/GRR, Sao Paulo. SP. (Brazil)] [Nuclear and Energy Research Institute Brazil, Radioactive Waste Management Department IPEN/GRR, Sao Paulo. SP. (Brazil)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Compilation of current literature on seals, closures, and leakage for radioactive material packagings  

SciTech Connect (OSTI)

This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs.

Warrant, M.M.; Ottinger, C.A.

1989-01-01T23:59:59.000Z

362

Lessons Learned in the Design and Use of IP1 / IP2 Flexible Packaging - 13621  

SciTech Connect (OSTI)

For many years in the USA, Low Level Radioactive Waste (LLW), contaminated soils and construction debris, have been transported, interim stored, and disposed of, using IP1 / IP2 metal containers. The performance of these containers has been more than adequate, with few safety occurrences. The containers are used under the regulatory oversight of the US Department of Transportation (DOT), 49 Code of Federal Regulations (CFR). In the late 90's the introduction of flexible packaging for the transport, storage, and disposal of low level contaminated soils and construction debris was introduced. The development of flexible packaging came out of a need for a more cost effective package, for the large volumes of waste generated by the decommissioning of many of the US Department of Energy (DOE) legacy sites across the US. Flexible packaging had to be designed to handle a wide array of waste streams, including soil, gravel, construction debris, and fine particulate dust migration. The design also had to meet all of the IP1 requirements under 49CFR 173.410, and be robust enough to pass the IP2 testing 49 CFR 173.465 required for many LLW shipments. Tens of thousands of flexible packages have been safely deployed and used across the US nuclear industry as well as for hazardous non-radioactive applications, with no recorded release of radioactive materials. To ensure that flexible packages are designed properly, the manufacturer must use lessons learned over the years, and the tests performed to provide evidence that these packages are suitable for transporting low level radioactive wastes. The design and testing of flexible packaging for LLW, VLLW and other hazardous waste streams must be as strict and stringent as the design and testing of metal containers. The design should take into consideration the materials being loaded into the package, and should incorporate the right materials, and manufacturing methods, to provide a quality, safe product. Flexible packaging can be shown to meet the criteria for safe and fit for purpose packaging, by meeting the US DOT regulations, and the IAEA Standards for IP-1 and IP-2 including leak tightness. (authors)

Sanchez, Mike [VP Global Sales, PacTec, Inc. (United States)] [VP Global Sales, PacTec, Inc. (United States); Reeves, Wendall [National Sales Manager, PacTec, Inc. (United States)] [National Sales Manager, PacTec, Inc. (United States); Smart, Bill [Nuclear Sales Director, PacTec, Inc. (United States)] [Nuclear Sales Director, PacTec, Inc. (United States)

2013-07-01T23:59:59.000Z

363

Parametric Thermal Analysis for Codisposal Waste Package Canister  

SciTech Connect (OSTI)

The engineering viability of disposal of aluminum-clad, aluminum-based spent nuclear fuel (Al-SNF) in a geologic repository requires a thermal analysis to provide the temperature history of the waste form. Calculated temperatures are used to demonstrate compliance with criteria for waste acceptance into the Mined Geologic Disposal System and as input to assess the chemical and physical behavior of the waste form within the waste package (WP).A thermal analysis methodology was developed to calculate peak temperatures and temperature profiles of Al-SNF in the DOE spent nuclear fuel canister within a codisposal WP. A two-dimensional baseline model with conduction and radiation coupled heat transport was developed to evaluate the thermal performance of Al-SNF directly stored in a canister in a codisposal WP over the range of possible heat loads and boundary conditions. In addition, a conduction model and a detailed model which includes convection were developed to identify the dominant cooling mechanism under the present WP configuration, to investigate physical cooling mechanism in detail, and to estimate the conservatism imbedded in the baseline model.The results of the baseline model showed that the direct disposal configuration with a helium-filled WP satisfied the present waste acceptance criteria (WAC) for the WP design in terms of the peak temperature criterion, Tmax {lt} 350 degrees C, under the reference boundary conditions. A period of 10 years` cooling time for the decay heat loads of the SNF and the High-level Waste Glass Log (HWGL) regions was used as one of the reference design conditions.

Lee, S.Y.; Sindelar, R.L.

1998-09-01T23:59:59.000Z

364

Evaluation of Packaging Film Mechanical Integrity Using a Standardized Scratch Test  

E-Print Network [OSTI]

EVALUATION OF PACKAGING FILM MECHANICAL INTEGRITY USING A STANDARDIZED SCRATCH TEST A Thesis by BRIAN ANTHONY HARE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 2011 Major Subject: Materials Science and Engineering Evaluation of Packaging Film Mechanical Integrity Using a Standardized Scratch Test Copyright 2011 Brian...

Hare, Brian

2012-10-19T23:59:59.000Z

365

Considerations for centralized packaging of beef retail cuts / by Davey Brian Griffin  

E-Print Network [OSTI]

CONSIDERATIONS FOR CENTRALIZED PACKAGING OF BEEF RETAIL CUTS A Thesis by DAVEY BRIAN GRIFFIN Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE December... 1981 Major Subject: Animal Science CONSIDERATIONS FOR CENTRALIZED PACKAGING OF BEEF RETAIL CUTS A Thesis by DAVEY BRIAN GRIFFIN Approved as to style and content by: (Co-Ch of Committee) o rman of Committee) (Member) ember) ( ber) ead of Depart...

Griffin, Davey Brian

2012-06-07T23:59:59.000Z

366

Packaging and fabrication systems for extending storage life and subsequent retail caselife of pork  

E-Print Network [OSTI]

PACKAGING AND FABRICATION SYSTEMS FOR EXTENDING STORAGE LIFE AND SUBSEQUENT RETAIL CASELIPE OF PORK A Thesis STEVEN WAYNE RAPE Submitted to the Graduate College of Texas ASM University in partial fulfillment to the requirements for the degree... of MASTER OF SCIENCE December 1973 Major Subject: Animal Science (Meat Science) PACKAGING AND FABRICATION SYSTEMS FOR EXTENDING STORAGE LIFE AND SUBSEQUENT RETAIL CASELIFE OF PORK A Thesis by STEVEN WAYNE RAPE Approved as to style and content by...

Rape, Steven Wayne

2012-06-07T23:59:59.000Z

367

Energy Savings and Economics of Advanced Control Strategies for Packaged Heat Pumps  

SciTech Connect (OSTI)

Pacific Northwest National Laboratory (PNNL), with funding from the U.S. Department of Energy’s (DOE’s) Building Technologies Program (BTP), evaluated a number of control strategies for packaged cooling equipment that can be implemented in an advanced controller, which can be retrofit into existing packaged heat pump units to improve their operational efficiency. This report documents the results of that analysis.

Wang, Weimin; Huang, Yunzhi; Katipamula, Srinivas

2012-10-31T23:59:59.000Z

368

LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE  

SciTech Connect (OSTI)

Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

Dunn, K. [Savannah River National Laboratory; Bellamy, S. [Savannah River National Laboratory; Daugherty, W. [Savannah River National Laboratory; Sindelar, R. [Savannah River National Laboratory; Skidmore, E. [Savannah River National Laboratory

2013-08-18T23:59:59.000Z

369

Leveraging a Cohesive Supply Chain to Close the Loop on EPS Packaging  

E-Print Network [OSTI]

Leveraging a Cohesive Supply Chain to Close the Loop on EPS Packaging Katherine Hang, UC San Diego Carbon Conversion Guide #12;1.09 2.08 0.97 0.0 0.5 1.0 1.5 2.0 2.5L Amber Glass 7L Returnable Stainless Filling Packaging Distribution Collection Cleaning Disposal Mail-back Carbon Footprint Results Steel

Russell, Lynn

370

Normal Condition on Transport Thermal Analysis and Testing of a Type B Drum Package  

SciTech Connect (OSTI)

Increasing the content limits of radioactive material packagings can save money and increase transportation safety by decreasing the total number of shipments required to transport large quantities of material. The contents of drum packages can be limited by unacceptable containment vessel pressures and temperatures due to the thermal properties of the insulation. The purpose of this work is to understand and predict the effects of insulation properties on containment system performance.

Jerrell, J.W.; van Alstine, M.N.; Gromada, R.J.

1995-03-21T23:59:59.000Z

371

Changes in atmospheric gases during isobaric storage of beef packaged pre- and post-rigor  

E-Print Network [OSTI]

displacement measurements of the head- space volume were conducted during two weeks of storage. Males of the headspace gases were calculated using the general gas law (PU = nRT). Carbon dioxide absorption by the meat was greatest in steaks stored in 100% C... OF FIGURES INTRODUCTION LITERATURE REV IELV Microbiol ogical Aspects of Packaging Meat Shelf-Life of Packaged Meat Respiration . Carbon Dioxide Absorption OBJECTIVES EXPERIMENTAL PROCEDURES RESULTS AND DISCUSSION Description of Meat Samples . Molar...

Hoermann, Karen Lee

1980-01-01T23:59:59.000Z

372

Short time scale thermal mechanical shock wave propagation in high performance microelectronic packaging configuration  

E-Print Network [OSTI]

SHORT TIME SCALE THERMAL MECHANICAL SHOCK WAVE PROPAGATION IN HIGH PERFORMANCE MICROELECTRONIC PACKAGING CONFIGURATION A Thesis by MAHAVIR NAGARAJ Submitted to the Office of Graduate Studies of Texas A&M University... MICROELECTRONIC PACKAGING CONFIGURATION A Thesis by MAHAVIR NAGARAJ Submitted to Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved as to style and content by: Chii...

Nagaraj, Mahavir

2004-11-15T23:59:59.000Z

373

Uv-Light Stabilization Additive Package For Solar Cell Module And Laminated Glass Applications  

DOE Patents [OSTI]

An ultraviolet light stabilization additive package is used in an encapsulant material that may be used in solar cell modules, laminated glass and a variety of other applications. The ultraviolet light stabilization additive package comprises a first hindered amine light stabilizer and a second hindered amine light stabilizer. The first hindered amine light stabilizer provides thermal oxidative stabilization, and the second hindered amine light stabilizer providing photo-oxidative stabilization.

Hanoka, Jack I. (Brookline, MA); Klemchuk, Peter P. (Watertown, CT)

2002-03-05T23:59:59.000Z

374

A comparison of vacuum packaging systems for the distribution and storage of primal beef cuts  

E-Print Network [OSTI]

A COMPARISON OF VACUUM PACKAGING SYSTEMS FOR THE / DISTRIBUTION AND STORAGE OF PRIMAL BEEP CUTS A Thesis by RODNEY AMES BOWLING Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement of the degree... of MASTER OP SCIENCE December 1974 Major Subject: Animal Science A COMPARISON OF VACUUM PACKAGING SYSTEMS FOR THE DISTRIBUTION AND STORAGE OF PRIMAL BEEF CUTS A Thesis by RODNEY AMES BOWLING Approved as to style and content by: (C hairman...

Bowling, Rodney Ames

1974-01-01T23:59:59.000Z

375

Cutability, bacterial control and packaging effects on the merchandising of lamb  

E-Print Network [OSTI]

). 20 respectively, than cuts which were packaged in 90 gauge PVC, 50 gauge PVC and barrier bags filled with carbon dioxide. If a mean odor score of 2. 5 or less is considered unacceptable, cuts from all 4 treatments maintained acceptable odor scores...-life, quality and palata- bility of lamb cuts. Lamb carcasses were fabricated into 384 primal cuts which were used in packaging studies designed to compare chamber, rotating nozzle and stationary nozzle vacuum machines; barrier bags, saran bags, soft film...

Varnadore, William Lee

2012-06-07T23:59:59.000Z

376

A review of the safety features of 6M packagings for DOE programs  

SciTech Connect (OSTI)

This report, prepared by a US Department of Energy (DOE) Task Force and organized for clarity into two-page modules, argues that the US Department of Transportation (DOT) Specification-6M packagings (hereafter referred to as 6M packaging, or simply 6M) merit continued DOE use and, if necessary, DOE certification. This report is designed to address the specific requirements of a Safety Analysis Report for Packaging (SARP). While not a SARP, this report constitutes a compilation of all available documentation on 6M packagings. The authors individually, and the Task Force collectively, believe their investigation provides justification for the continued use of 6M packagings because they meet criteria for quality assurance and for safety under normal and accident conditions as defined by the US Nuclear Regulatory Commission (NRC) regulations. This report may be used by DOE managers to assist in deliberations on future requirements for 6M packagings as they are required to support DOE programs. For the purpose of ready evaluation, this report includes categorical topics found in Nuclear Regulatory Guide 7.9, the topical guideline for SARPs. The format, however, will (it is hoped) pleasantly surprise customary reader expectations. For, while maintaining categorical headings and subheadings found in SARPs as a skeleton, the Task Force chose to adopt the document design principles developed by Hughes Aircraft in the 1960s, ''Sequential Thematic Organization of Publications'' (STOP). 37 figs.

Not Available

1988-12-01T23:59:59.000Z

377

A Fruit of Yucca Mountain: The Remote Waste Package Closure System  

SciTech Connect (OSTI)

Was the death of the Yucca Mountain repository the fate of a technical lemon or a political lemon? Without caution, this debate could lure us away from capitalizing on the fruits of the project. In March 2009, Idaho National Laboratory (INL) successfully demonstrated the Waste Package Closure System, a full-scale prototype system for closing waste packages that were to be entombed in the now abandoned Yucca Mountain repository. This article describes the system, which INL designed and built, to weld the closure lids on the waste packages, nondestructively examine the welds using four different techniques, repair the welds if necessary, mitigate crack initiating stresses in the surfaces of the welds, evacuate and backfill the packages with an inert gas, and perform all of these tasks remotely. As a nation, we now have a proven method for securely sealing nuclear waste packages for long term storage—regardless of whether or not the future destination for these packages will be an underground repository. Additionally, many of the system’s features and concepts may benefit other remote nuclear applications.

Kevin Skinner; Greg Housley; Colleen Shelton-Davis

2011-11-01T23:59:59.000Z

378

Potential materials for food packaging from nanoclay/natural fibres filled hybrid composites  

Science Journals Connector (OSTI)

The increasing demand for new food packaging materials which satisfy people requirements provided thrust for advancement of nano-materials science. Inherent permeability of polymeric materials to gases and vapours; and poor barrier and mechanical properties of biopolymers have boosted interest in developing new strategies to improve these properties. Research and development in polymeric materials coupled with appropriate filler, matrix-filler interaction and new formulation strategies to develop composites have potential applications in food packaging. Advancement in food packaging materials expected to grow with the advent of cheap, renewable and sustainable materials with enhanced barrier and mechanical properties. Nanoparticles have proportionally larger surface area and significant aspect ratio than their micro-scale counterparts, which promotes the development of mechanical and barrier properties. Nanocomposites are attracting considerable interest in food packaging because of these fascinating features. On the other hand, natural fibres are susceptible to microorganisms and their biodegradability is one of the most promising aspects of their incorporation in polymeric materials. Present review article explain about different categories of nanoclay and natural fibre based composite with particular regard to its applications as packaging materials and also gives an overview of the most recent advances and emerging new aspects of nanotechnology for development of hybrid composites for environmentally compatible food packaging materials.

K. Majeed; M. Jawaid; A. Hassan; A. Abu Bakar; H.P.S. Abdul Khalil; A.A. Salema; I. Inuwa

2013-01-01T23:59:59.000Z

379

Physical test report to drop test of a 9975 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9975 radioactive material shipping package being dropped 30 feet onto a unyielding surface followed by a 40-inch puncture pin drop. The purpose of these drops was to show that the package lid would remain attached to the drum. The 30-foot drop was designed to weaken the lid closure lug while still maintaining maximum extension of the lugs from the drum surface. This was accomplished by angling the drum approximately 30 degrees from horizontal in an inverted position. In this position, the drum was rotated slightly so as not to embed the closure lugs into the drum as a result of the 30-foot drop. It was determined that this orientation would maximize deformation to the closure ring around the closure lug while still maintaining the extension of the lugs from the package surface. The second drop was from 40 inches above a 40-inch tall 6-inch diameter puncture pin. The package was angled 10 degrees from vertical and aligned over the puncture pin to solidly hit the drum lug(s) in an attempt to disengage the lid when dropped.Tests were performed in response to DOE EM-76 review Q5 inquires that questioned the capability of the 9975 drum lid to remain in place under this test sequence. Two packages were dropped utilizing this sequence, a 9974 and 9975. Test results for the 9974 package are reported in WSRC-RP-97-00945. A series of 40-inch puncture pin tests were also performed on undamaged 9975 and 9974 packages.

Blanton, P.S.

1997-11-11T23:59:59.000Z

380

Temperature-package power correlations for open-mode geologic disposal concepts.  

SciTech Connect (OSTI)

Logistical simulation of spent nuclear fuel (SNF) management in the U.S. combines storage, transportation and disposal elements to evaluate schedule, cost and other resources needed for all major operations leading to final geologic disposal. Geologic repository reference options are associated with limits on waste package thermal power output at emplacement, in order to meet limits on peak temperature for certain key engineered and natural barriers. These package power limits are used in logistical simulation software such as CALVIN, as threshold requirements that must be met by means of decay storage or SNF blending in waste packages, before emplacement in a repository. Geologic repository reference options include enclosed modes developed for crystalline rock, clay or shale, and salt. In addition, a further need has been addressed for open modes in which SNF can be emplaced in a repository, then ventilated for decades or longer to remove heat, prior to permanent repository closure. For each open mode disposal concept there are specified durations for surface decay storage (prior to emplacement), repository ventilation, and repository closure operations. This study simulates those steps for several timing cases, and for SNF with three fuel-burnup characteristics, to develop package power limits at which waste packages can be emplaced without exceeding specified temperature limits many years later after permanent closure. The results are presented in the form of correlations that span a range of package power and peak postclosure temperature, for each open-mode disposal concept, and for each timing case. Given a particular temperature limit value, the corresponding package power limit for each case can be selected for use in CALVIN and similar tools.

Hardin, Ernest L.

2013-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Practical Thermal Evaluation Methods For HAC Fire Analysis In Type B Radiaoactive Material (RAM) Packages  

SciTech Connect (OSTI)

Title 10 of the United States Code of Federal Regulations Part 71 for the Nuclear Regulatory Commission (10 CFR Part 71.73) requires that Type B radioactive material (RAM) packages satisfy certain Hypothetical Accident Conditions (HAC) thermal design requirements to ensure package safety during accidental fire conditions. Compliance with thermal design requirements can be met by prototype tests, analyses only or a combination of tests and analyses. Normally, it is impractical to meet all the HAC using tests only and the analytical methods are too complex due to the multi-physics non-linear nature of the fire event. Therefore, a combination of tests and thermal analyses methods using commercial heat transfer software are used to meet the necessary design requirements. The authors, along with his other colleagues at Savannah River National Laboratory in Aiken, SC, USA, have successfully used this 'tests and analyses' approach in the design and certification of several United States' DOE/NNSA certified packages, e.g. 9975, 9977, 9978, 9979, H1700, and Bulk Tritium Shipping Package (BTSP). This paper will describe these methods and it is hoped that the RAM Type B package designers and analysts can use them for their applications.

Abramczyk, Glenn; Hensel, Stephen J; Gupta, Narendra K.

2013-03-28T23:59:59.000Z

382

TEST & EVALUATION REPORT FOR THE HEDGEHOG-II PACKAGING SYSTEMS DOT-7A TYPE A CONTAINER  

SciTech Connect (OSTI)

This report documents the US. Department of Transportation Specification 7A (DOT-7A) Type A compliance test and evaluation results for the Hedgehog-II packaging systems. The approved Hedgehog-II packaging configurations provide primary and secondary containment. The approved packaging configurations described within this report are designed to ship Type A quantities of radioactive materials, normal form. Contents may be in solid or liquid form. Liquids transported in the approved 1 L glass bottle assembly shall have a specific gravity of less than or equal to 1.6. Liquids transported in all other approved configurations shall have a specific gravity of less than or equal to 2.0. The solid contents, including packaging, are limited in weight to the gross weight of the as-tested liquids and bottles. The approved Hedgehog-II packaging configurations described in this report may be transported by air, and have been evaluated as meeting the applicable International Air Transport Association/International Civil Aviation Organization (IATA/ICAO) Dangerous Goods Regulations in addition to the DOT requirements.

KELLY, D.L.

2003-12-29T23:59:59.000Z

383

Productivity Techniques and Quality Aspects in the Criticality Safety Evaluation of Y-12 Type-B Fissile Material Packages  

SciTech Connect (OSTI)

The inventory of certified Type-B fissile material packages consists of ten performance-based packages for offsite transportation purposes, serving transportation programs at the Y-12 National Security Complex. The containment vessels range from 5 to 19 in. in diameter and from 17 to 58 in. in height. The drum assembly external to the containment vessel ranges from 18 to 34 in. in diameter and from 26 to 71 in. in height. The weight of the packaging (drum assembly and containment vessel) ranges from 239 to 1550 lb. The older DT-nn series of Cellotex-based packages are being phased-out and replaced by a new generation of Kaolite-based ('Y-12 patented insulation') packages capable of withstanding the dynamic crush test 10 CFR 71.73(c)(2). Three replacement packages are in various stages of development; two are in use. The U.S. Department of Transportation (DOT) 6M specification package, which does not conform to the U.S. Nuclear Regulatory Commission requirements for Type-B packages, is no longer authorized for service on public roads. The ES-3100 shipping package is an example of a Kaolite-based Type-B fissile material package developed as a replacement package for the DOT 6M. With expanded utility, the ES-3100 is designed and licensed for transporting highly enriched uranium and plutonium materials on public roads. The ES-3100 provides added capability for air transport of up to 7-kg quantities of uranium material. This paper presents the productivity techniques and quality aspects in the criticality safety evaluation of Y-12 packages using the ES-3100 as an example.

DeClue, J. F.

2011-06-28T23:59:59.000Z

384

Heat dissipation performance of a high-brightness LED package assembly using high-thermal conductivity filler  

Science Journals Connector (OSTI)

This paper presents a thermal analysis and experimental validation of natural convective heat transfer of a high-brightness light-emitting diode (LED) package assembly. The substrate...

Yung, K C; Liem, H; Choy, H S

2013-01-01T23:59:59.000Z

385

Test plan/procedure for the shock limiting device of the radioisotope thermoelectric generator package mounting subsystem 145. Revision 1  

SciTech Connect (OSTI)

This document defines the procedure to be used in the 18 inch drop test to be used for design verification of the RTG Transportation System Package Mounting.

Satoh, J.A.

1995-05-25T23:59:59.000Z

386

SHIPMENT OF NON-TRADITIONAL CONTENTS IN THE 9977 TYPE B PACKAGE  

SciTech Connect (OSTI)

The 9977 is a certified Type B Packaging authorized to ship uranium and plutonium in metal and oxide forms. These materials are typically confined within metallic containers designed for ease of handling and to prevent the spread of contamination. The Pacific Northwest National Laboratory (PNNL) uses Pu and U sources for the training of domestic and international customs agents in the identification and detection of radioactive materials (RAM). These materials are packed in polycarbonate containers which permit the trainees to view the RAM. The safety basis was made to authorize the use of these unusual containers. The inclusion of the PNNL Training Source Contents into the 9977 Packaging imposed unique conditions previously unanalyzed. The use of polycarbonate as a content container material, while different from any configuration previously considered, does not raise any safety issues with the package which continues to operate with a large safety margin for temperatures, pressures, containment, dose rates, and subcriticality.

Abramczyk, G.; Loftin, B.; Bellamy, S.; Nathan, S.

2011-06-06T23:59:59.000Z

387

Vertical Drop of the Naval SNF Long Waste Package On Unyielding Surface  

SciTech Connect (OSTI)

The purpose of this calculation is to determine the structural response of a Naval SNF (Spent Nuclear Fuel) Long Waste Package (WP) subjected to 2 m-vertical drop on unyielding surface (US). The scope of this document is limited to reporting the calculation results in terms of maximum stress intensities. This calculation is associated with the waste package design; calculation is performed by the Waste Package Design group. AP-3.12Q, Revision 0, ICN 0, Calculations, is used to perform the calculation and develop the document. The finite element calculation is performed by using the commercially available ANSYS Version (V) 5.4 finite element code. The result of this calculation is provided in terms of maximum stress intensities.

S. Mastilovic

2006-07-21T23:59:59.000Z

388

USING A CONTAINMENT VESSEL LIFTING APPARATUS FOR REMOTE OPERATIONS OF SHIPPING PACKAGES  

SciTech Connect (OSTI)

The 9977 and the 9975 shipping packages are used in various nuclear facilities within the Department of Energy. These shipping packages are often loaded in designated areas with designs using overhead cranes or A-frames with lifting winches. However, there are cases where loading operations must be performed in remote locations where these facility infrastructures do not exist. For these locations, a lifting apparatus has been designed to lift the containment vessels partially out of the package for unloading operations to take place. Additionally, the apparatus allows for loading and closure of the containment vessel and subsequent pre-shipment testing. This paper will address the design of the apparatus and the challenges associated with the design, and it will describe the use of the apparatus.

Loftin, Bradley [Savannah River National Laboratory; Koenig, Richard [Savannah River National Laboratory

2013-08-08T23:59:59.000Z

389

The Effect of an Annular Celotex(r) Gap on the 9975 Package  

SciTech Connect (OSTI)

Following a drop test at the Westinghouse Savannah River Company (WSRC), radiographs of a 9975 drum package showed that separations, normal to the axial direction, had formed in the Celotex(R). Because the Celotex(R) acts as a thermal insulator, concerns arose as to the effect gaps in the material would have on the packaging components during and after a hypothetical fire transient. The effect of Celotex(R) gaps on the content temperature was estimated using a thermal model developed with the MSC/THERMAL(R) heat transfer software. The model included the effects of internal heat conduction and thermal radiation. Convection and thermal radiation boundary conditions were applied to the model. The thermal analysis supported the expectation that small separations in the fiberboard insulation will not degrade the thermal performance of the 9975 package in a Hypothetical Accident Conditions (HAC) fire.

Hardy, B.J.

2001-02-20T23:59:59.000Z

390

Evaluation Framework and Analyses for Thermal Energy Storage Integrated with Packaged Air Conditioning  

SciTech Connect (OSTI)

Few third-party guidance documents or tools are available for evaluating thermal energy storage (TES) integrated with packaged air conditioning (AC), as this type of TES is relatively new compared to TES integrated with chillers or hot water systems. To address this gap, researchers at the National Renewable Energy Laboratory conducted a project to improve the ability of potential technology adopters to evaluate TES technologies. Major project outcomes included: development of an evaluation framework to describe key metrics, methodologies, and issues to consider when assessing the performance of TES systems integrated with packaged AC; application of multiple concepts from the evaluation framework to analyze performance data from four demonstration sites; and production of a new simulation capability that enables modeling of TES integrated with packaged AC in EnergyPlus. This report includes the evaluation framework and analysis results from the project.

Kung, F.; Deru, M.; Bonnema, E.

2013-10-01T23:59:59.000Z

391

Tabulation of thermodynamic data for chemical reactions involving 58 elements common to radioactive waste package systems  

SciTech Connect (OSTI)

The rate of release and migration of radionuclides from a nuclear waste repository to the biosphere is dependent on chemical interactions between groundwater, the geologic host rock, and the radioactive waste package. For the purpose of this report, the waste package includes the wasteform, canister, overpack, and repository backfill. Chemical processes of interest include sorption (ion exchange), dissolution, complexation, and precipitation. Thermochemical data for complexation and precipitation calculations for 58 elements common to the radioactive waste package are presented. Standard free energies of formation of free ions, complexes, and solids are listed. Common logarithms of equilibrium constants (log K's) for speciation and precipitation reactions are listed. Unless noted otherwise, all data are for 298.15/sup 0/K and one atmosphere.

Benson, L.V.; Teague, L.S.

1980-08-01T23:59:59.000Z

392

JOINT UNITED STATES/IAEA PROPOSED APPROACH FOR SAFEGUARDS DURING PLUTONIUM STABILIZATION, PACKAGING, AND SHIPMENT  

SciTech Connect (OSTI)

For safety reasons, the U.S. Department of Energy (DOE) is preparing to stabilize and package plutonium oxide currently subject to International Atomic Energy Agency safeguards at the Rocky Flats Environmental Technology Site (RFETS) beginning in the year 2001. The Hanford Site will also stabilize and package plutonium materials under IAEA safeguards. The U.S. and the IAEA began consultations in late 1996 to develop an approach to the application of safeguards during stabilization and packaging. With the plans to ship RFETS plutonium to Savannah River for interim storage prior to final disposition, this work has been extended to include safeguards during shipment. This paper will discuss the elements of a joint U.S./IAEA proposal for this task.

L. KWEI; B. SMITH; ET AL

2001-02-01T23:59:59.000Z

393

ANALYSIS OF THE AXIAL GAP VS FIBERBOARD MOISTURE CONTENT IN A 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The fiberboard assembly within a 9975 shipping package contains a modest amount of moisture, which can migrate to the cooler regions of the package when an internal heat load is present. Typically, this leads to increased moisture levels in the bottom fiberboard layers, along with elevated chloride levels which can leach from the fiberboard. Concerns have been raised that this condition could lead to corrosion of the stainless steel drum. It has been postulated that checking the axial gap at the top of the package against the current 1 inch maximum criterion provides a sufficient indication regarding the integrity of the fiberboard and drum. This report estimates the increase in axial gap that might be expected for a given moisture increase in the bottom fiberboard layers, and the likelihood that the increase will create a nonconforming condition that will lead to identification of the moisture increase. Using data relating the fiberboard moisture content with the degree of compaction under load, the present analysis indicates that the axial gap will increase by 0.282 inch as the bottom fiberboard layers approach the saturation point. This increase will cause approximately 58% of packages with otherwise nominal package component dimensions to fail the axial gap criterion, based on a survey of axial gap values recorded in K-Area surveillance activities. As the moisture content increases above saturation, the predicted increase in axial gap jumps to 0.405 inch, which would result in 92% or more of all packages failing the axial gap criterion. The data and analysis described in this report are specific to cane fiberboard. While it is expected that softwood fiberboard will behave similarly, such behavior has not yet been demonstrated.

Daugherty, W.

2013-09-30T23:59:59.000Z

394

Scale-up considerations relevant to experimental studies of nuclear waste-package behavior  

SciTech Connect (OSTI)

Results from a study that investigated whether testing large-scale nuclear waste-package assemblages was technically warranted are reported. It was recognized that the majority of the investigations for predicting waste-package performance to date have relied primarily on laboratory-scale experimentation. However, methods for the successful extrapolation of the results from such experiments, both geometrically and over time, to actual repository conditions have not been well defined. Because a well-developed scaling technology exists in the chemical-engineering discipline, it was presupposed that much of this technology could be applicable to the prediction of waste-package performance. A review of existing literature documented numerous examples where a consideration of scaling technology was important. It was concluded that much of the existing scale-up technology is applicable to the prediction of waste-package performance for both size and time extrapolations and that conducting scale-up studies may be technically merited. However, the applicability for investigating the complex chemical interactions needs further development. It was recognized that the complexity of the system, and the long time periods involved, renders a completely theoretical approach to performance prediction almost hopeless. However, a theoretical and experimental study was defined for investigating heat and fluid flow. It was concluded that conducting scale-up modeling and experimentation for waste-package performance predictions is possible using existing technology. A sequential series of scaling studies, both theoretical and experimental, will be required to formulate size and time extrapolations of waste-package performance.

Coles, D.G.; Peters, R.D.

1986-04-01T23:59:59.000Z

395

Packaging waste recycling in Europe: Is the industry paying for it?  

SciTech Connect (OSTI)

Highlights: • We study the recycling schemes of France, Germany, Portugal, Romania and the UK. • The costs and benefits of recycling are compared for France, Portugal and Romania. • The balance of costs and benefits depend on the perspective (strictly financial/economic). • Financial supports to local authorities ought to promote cost-efficiency. - Abstract: This paper describes and examines the schemes established in five EU countries for the recycling of packaging waste. The changes in packaging waste management were mainly implemented since the Directive 94/62/EC on packaging and packaging waste entered into force. The analysis of the five systems allowed the authors to identify very different approaches to cope with the same problem: meet the recovery and recycling targets imposed by EU law. Packaging waste is a responsibility of the industry. However, local governments are generally in charge of waste management, particularly in countries with Green Dot schemes or similar extended producer responsibility systems. This leads to the need of establishing a system of financial transfers between the industry and the local governments (particularly regarding the extra costs involved with selective collection and sorting). Using the same methodological approach, the authors also compare the costs and benefits of recycling from the perspective of local public authorities for France, Portugal and Romania. Since the purpose of the current paper is to take note of who is paying for the incremental costs of recycling and whether the industry (i.e. the consumer) is paying for the net financial costs of packaging waste management, environmental impacts are not included in the analysis. The work carried out in this paper highlights some aspects that are prone to be improved and raises several questions that will require further research. In the three countries analyzed more closely in this paper the industry is not paying the net financial cost of packaging waste management. In fact, if the savings attained by diverting packaging waste from other treatment (e.g. landfilling) and the public subsidies to the investment on the “recycling system” are not considered, it seems that the industry should increase the financial support to local authorities (by 125% in France, 50% in Portugal and 170% in Romania). However, in France and Portugal the industry is paying local authorities more than just the incremental costs of recycling (full costs of selective collection and sorting minus the avoided costs). To provide a more definitive judgment on the fairness of the systems it will be necessary to assess the cost efficiency of waste management operators (and judge whether operators are claiming costs or eliciting “prices”)

Ferreira da Cruz, Nuno, E-mail: nunocruz@ist.utl.pt; Ferreira, Sandra; Cabral, Marta; Simőes, Pedro; Marques, Rui Cunha

2014-02-15T23:59:59.000Z

396

Yucca Mountain Waste Package Closure System Robotic Welding and Inspection System  

SciTech Connect (OSTI)

The Waste Package Closure System (WPCS), for the closure of radioactive waste in canisters for permanent storage of spent nuclear fuel (SNF) and high-level waste in the Yucca Mountain Repository was designed, fabricated, and successfully demonstrated at the Idaho National Laboratory (INL). This article focuses on the robotic hardware and tools necessary to remotely weld and inspect the closure lid welds. The system was operated remotely and designed for use in a radiation field, due to the SNF contained in the waste packages being closed.

C. I. Nichol; D. P. Pace; E. D. Larsen; T. R. McJunkin; D. E. Clark; M. L. Clark; K. L. Skinner; A. D. Watkins; H. B. Smartt

2011-10-01T23:59:59.000Z

397

Test and evaluation document for DOT Specification 7A Type A Packaging. Revision 3  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has been conducting, through several of its operating contractors, an evaluation and testing program to qualify Type A radioactive material packagings per US Department of Transportation (DOT) Specification 7A (DOT-7A) of the Code of Federal Regulations (CFR), Title 49, Part 178 (49 CFR 178). The program is currently administered by the DOE, Office of Facility Safety Analysis, DOE/EH-32, at DOE-Headquarters (DOE-HQ) in Germantown, Maryland. This document summarizes the evaluation and testing performed for all of the packagings successfully qualified in this program.

NONE

1996-01-30T23:59:59.000Z

398

Calculation of the Naval Long and Short Waste Package Three-Dimensional Thermal Interface Temperatures  

SciTech Connect (OSTI)

The purpose of this calculation is to evaluate the thermal performance of the Naval Long and Naval Short spent nuclear fuel (SNF) waste packages (WP) in the repository emplacement drift. The scope of this calculation is limited to the determination of the temperature profiles upon the surfaces of the Naval Long and Short SNF waste package for up to 10,000 years of emplacement. The temperatures on the top of the outside surface of the naval canister are the thermal interfaces for the Naval Nuclear Propulsion Program (NNPP). The results of this calculation are intended to support Licensing Application design activities.

H. Marr

2006-10-25T23:59:59.000Z

399

Work plan for the fabrication of the radioisotope thermoelectric generator transportation system package mounting  

SciTech Connect (OSTI)

The Radioisotope Thermoelectric Generator (RTG) has available a dedicated system for the transportation of RTG payloads. The RTG Transportation System (System 100) is comprised of four systems; the Package (System 120), the Semi-trailer (System 140), the Gas Management (System 160), and the Facility Transport (System 180). This document provides guidelines on the fabrication, technical requirements, and quality assurance of the Package Mounting (Subsystem 145), part of System 140. The description follows the Development Control Requirements of WHC-CM-6-1, EP 2.4, Rev. 3.

Satoh, J.A.

1994-11-09T23:59:59.000Z

400

QLib - A Matlab Package for Quantum Information Theory Calculations with Applications  

E-Print Network [OSTI]

Developing intuition about quantum information theory problems is difficult, as is verifying or ruling-out of hypothesis. We present a Matlab package intended to provide the QIT community with a new and powerful tool-set for quantum information theory calculations. The package covers most of the "QI textbook" and includes novel parametrization of quantum objects and a robust optimization mechanism. New ways of re-examining well-known results is demonstrated. QLib is designed to be further developed and enhanced by the community and is available for download at www.qlib.info

Shai Machnes

2007-08-03T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Quality assurance guidance for TRUPACT-II (Transuranic Package Transporter-II) payload control  

SciTech Connect (OSTI)

The Transuranic Package Transporter-II (TRUPACT-II) Safety Analysis Report for Packaging (SARP) approved by the Nuclear Regulatory Commission (NRC), discusses authorized methods for payload control in Appendix 1.3.7 and the Quality Assurance (QA) requirements in Section 9.3. Subsection 9.3.2.1 covers maintenance and use of the TRUPACT-II and the specific QA requirements are given in DOE/WIPP 89-012. Subsection 9.3.2.2 covers payload compliance, for which this document was written. 6 refs.

Not Available

1989-10-01T23:59:59.000Z

402

CANE FIBERBOARD DEGRADATION WITHIN THE 9975 SHIPPING PACKAGE DURING LONG-TERM STORAGE APPLICATION  

SciTech Connect (OSTI)

The 9975 shipping package is used as part of the configuration for long-term storage of special nuclear materials in the K Area Complex at the Savannah River Site. The cane fiberboard overpack in the 9975 package provides thermal insulation, impact absorption and criticality control functions relevant to this application. The Savannah River National Laboratory has conducted physical, mechanical and thermal tests on aged fiberboard samples to identify degradation rates and support the development of aging models and service life predictions in a storage environment. This paper reviews the data generated to date, and preliminary models describing degradation rates of cane fiberboard in elevated temperature – elevated humidity environments.

Daugherty, W.; Dunn, K.; Hackney, B.

2013-06-19T23:59:59.000Z

403

Packaging- and transportation-related occurrence reports, January--March 1995  

SciTech Connect (OSTI)

Reports on transportation/packaging incidents, from the Occurrence Reporting and Processing System, are being analyzed for trends, impact on DOE EH-32 policies and concerns, and lessons learned concerning transportation and packaging safety. Besides keeping EH-32 aware of current incidents and potential problems that may need attention on DOE sites, this task allows future dissemination of lessons learned to the Operations Offices and to management and operating contractors. This report covers the weekly tabular reports OR-95-01 through OR-95-13, which contained a total of 50 occurrence reports.

Dickerson, L.S.; Welch, M.J.; Armstrong, C.J.

1995-04-01T23:59:59.000Z

404

Thermal performance evaluation of SiC power devices packaging A.GRACIA, S.AZZOPARDI, E.WOIRGARD  

E-Print Network [OSTI]

impedance and the thermal resistance and also finite elements simulations. The correlation between methods. 2 High temperature device packaging concepts The selection of materials for a high temperature package (figure 1) is based on a combination of material properties: conductivity, Coefficient of Thermal

Boyer, Edmond

405

Computers & Industrial Engineering (In Press) Wu & Liu Development and Evaluation of an Ergonomic Software Package  

E-Print Network [OSTI]

Computers & Industrial Engineering (In Press) Wu & Liu 1 Development and Evaluation of an Ergonomic-MHP are also discussed on how to make it a comprehensive proactive ergonomic design and analysis tool. Keywords: Ergonomics, Software package, Queueing Network, Human performance, Mental workload #12;Computers & Industrial

Wu, Changxu (Sean)

406

t -software package for numerical simulations of radioactive contaminant transport in groundwater  

E-Print Network [OSTI]

r3 t - software package for numerical simulations of radioactive contaminant transport equations that arise from the modelling of radioactive contaminant transport in porous media. It can solve, see [6]) can help to numerically simulate the spreading of radioactive contaminants in flowing ground

Frolkovic, Peter

407

The effect of thermal contact resistance on heat management in the electronic packaging  

E-Print Network [OSTI]

The effect of thermal contact resistance on heat management in the electronic packaging M. Grujicic the role of thermal contact resistance on heat management within a simple central processing unit (CPU interface materials on the maximum temperature experienced by the CPU. Two classes of thermal interface

Grujicic, Mica

408

THE REGULATION AND PACKAGING OF SYNAPTIC VESICLES AS RELATED TO RECRUITMENT WITHIN GLUTAMATERGIC SYNAPSES  

E-Print Network [OSTI]

THE REGULATION AND PACKAGING OF SYNAPTIC VESICLES AS RELATED TO RECRUITMENT WITHIN GLUTAMATERGIC SYNAPSES W.-H. WU AND R. L. COOPER * Department of Biology and Center for muscle Biology, University activated dur- ing rapid electrical stimulation (20 Hz) sparing the RP. When stimulation frequency is high

Cooper, Robin L.

409

Packaging and transportation of radioactive liquid at the U.S. Department of Energy Hanford Site  

SciTech Connect (OSTI)

Beginning in the 1940`s, radioactive liquid waste has been generated at the US Department of Energy (DOE) Hanford Site as a result of defense material production. The liquid waste is currently stored in 177 underground storage tanks. As part of the tank remediation efforts, Type B quantity packagings for the transport of large volumes of radioactive liquids are required. There are very few Type B liquid packagings in existence because of the rarity of large-volume radioactive liquid payloads in the commercial nuclear industry. Development of aboveground transport systems for large volumes of radioactive liquids involves institutional, economic, and technical issues. Although liquid shipments have taken place under DOE-approved controlled conditions within the boundaries of the Hanford Site for many years, offsite shipment requires compliance with DOE, US Nuclear Regulatory Commission (NRC), and US Department of Transportation (DOT) directives and regulations. At the present time, no domestic DOE nor NRC-certified Type B packagings with the appropriate level of shielding are available for DOT-compliant transport of radioactive liquids in bulk volumes. This paper will provide technical details regarding current methods used to transport such liquids on and off the Hanford Site, and will provide a status of packaging development programs for future liquid shipments.

Smith, R.J.

1995-02-01T23:59:59.000Z

410

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package  

SciTech Connect (OSTI)

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig.

Manaktala, H.K. (Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses); Interrante, C.G. (Nuclear Regulatory Commission, Washington, DC (USA). Div. of High-Level Waste Management)

1990-12-01T23:59:59.000Z

411

Cleanup Verification Package for the 118-F-5 PNL Sawdust Pit  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action, sampling activities, and compliance with cleanup criteria for the 118-F-5 Burial Ground, the PNL (Pacific Northwest Laboratory) Sawdust Pit. The 118-F-5 Burial Ground was an unlined trench that received radioactive sawdust from the floors of animal pens in the 100-F Experimental Animal Farm.

L. D. Habel

2008-05-20T23:59:59.000Z

412

Cleanup Verification Package for the 118-F-7, 100-F Miscellaneous Hardware Storage Vault  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 118-F-7, 100-F Miscellaneous Hardware Storage Vault. The site consisted of an inactive solid waste storage vault used for temporary storage of slightly contaminated reactor parts that could be recovered and reused for the 100-F Area reactor operations.

M. J. Appel

2006-11-02T23:59:59.000Z

413

Implementation Guide for Use with DOE O 460.1A, Packaging and Transportation Safety  

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

This Guide provides information concerning the use of current principles and practices, including regulatory guidance from the U. S. Department of Transportation and the U. S. Nuclear Regulatory Commission, where available, to establish and implement effective packaging and transportation safety programs.

1997-06-05T23:59:59.000Z

414

Antimicrobial packaging system for optimization of electron beam irradiation of fresh produce  

E-Print Network [OSTI]

This study evaluated the potential use of an antimicrobial packaging system in combination with electron beam irradiation to enhance quality of fresh produce. Irradiated romaine lettuce up to 3.2 kGy showed negligible (p > 0.05) changes in color...

Han, Jaejoon

2006-10-30T23:59:59.000Z

415

Fatigue life evaluation of wire bonds in LED packages using numerical analysis  

Science Journals Connector (OSTI)

Abstract Reliability of LED packages is evaluated using several tests. When a thermal shock test, which is one of the reliability tests, is conducted, the most common failure mode is wire neck breakage. In order to evaluate the wire bonding reliability of LED packages, performing the thermal shock test is time-consuming. In this paper the wire bonding reliability for LED packages is evaluated by using numerical analysis. A wire bonding lifetime model for the thermal shock test was developed, which is based on Coffin-Manson fatigue law. The model was calibrated from fatigue data of thermal shock tests and volume averaging accumulated plastic strains. The accumulated plastic strains were calculated by using finite element analysis corresponding to the test conditions. The test conditions were changed by silicones, package sizes, wire bonding diameters, heights, and lengths. The calibrated model was used to estimate the number cycle to failure so that the wire bonding reliability for the thermal shock test was evaluated by performing the numerical analysis. Furthermore, we used a response surface methodology to study the relationship between the wire loop and the accumulated plastic strain to determine the optimal wire loop. The plastic strain was a function of diameter, height and length. At the optimal point, the number of cycle to failure for the thermal shock test was suggested using the wire bonding lifetime model.

Sung-Uk Zhang; Bang Weon Lee

2014-01-01T23:59:59.000Z

416

Integrated packaging allows for improvement in switching characteristics of silicon carbide devices  

E-Print Network [OSTI]

Integrated packaging allows for improvement in switching characteristics of silicon carbide devices will be available after the conference. Abstract Silicon Carbide devices can achieve very high switching speed-mode filtering). The consequences on the switching speed are discussed. 1. Introduction Silicon carbide (Si

Paris-Sud XI, Université de

417

SPSens: a software package for stochastic parameter sensitivity analysis of biochemical reaction networks  

Science Journals Connector (OSTI)

......simulates coupled processes for each...stochastic chemical kinetics...computed during simulation to give an...run from MATLAB using the...of coupled chemical reactions...stochastic simulation of coupled chemical reactions...Stochsens-MATLAB package for...Supplementary Data - pdf file Supplementary......

Patrick W. Sheppard; Muruhan Rathinam; Mustafa Khammash

2013-01-01T23:59:59.000Z

418

Design of a nuclear-waste package for emplacement in tuff  

SciTech Connect (OSTI)

Design, modeling, and testing activities are under way at LLNL in the development of high level nuclear waste package designs. We discuss the geological characteristics affecting design, the 10CFR60 design requirements, conceptual designs, metals for containment barriers, economic analysis, thermal modeling, and performance modeling.

O`Neal, W.C.; Rothman, A.J.; Gregg, D.W.; Hockman, J.N.; Revelli, M.A.; Russell, E.W.; Schornhorst, J.R.

1983-02-01T23:59:59.000Z

419

Sintered molybdenum for a metallized ceramic substrate packaging for the wide-  

E-Print Network [OSTI]

of thermal expansion (CTE) matching that of SiC are needed. A metallized ceramic substrate based on aluminium the metal layer) and thermal conductivity (of the metal and ceramic layers). The most substrate usedSintered molybdenum for a metallized ceramic substrate packaging for the wide- bandgap devices

Boyer, Edmond

420

The Need for a Full-Chip and Package Thermal Model for Thermally Optimized IC Designs  

E-Print Network [OSTI]

ceramic ball-grid array (CBGA) pack- age consisting of the chip (die), thermal interface material, heatThe Need for a Full-Chip and Package Thermal Model for Thermally Optimized IC Designs Wei Huang detailed die temperature with a full-chip thermal model at early design stages is important to discover

Skadron, Kevin

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

System Level Signal and Power Integrity Analysis Methodology for System-In-Package Applications  

E-Print Network [OSTI]

. The in the system, and 3) efficiently handle large sized problems so as paper briefly outlines some new modeling for these package using a range of technologies from new materials and effects accurately and hence, compromises systems, where milli-volt amplitude schematic diagram of a SiP with integrated RF / Digital, levels matter

Swaminathan, Madhavan

422

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory. TRU curium shipping container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory Transuranium (TRU) Curium Shipping Container was made to demonstrate its compliance with the regulations governing offsite shipment of packages containing radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicable regulations.

Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Aramayo, G.A.

1980-06-01T23:59:59.000Z

423

The effect of cargo on the crush loading of RAM transportation packages in ship collisions  

SciTech Connect (OSTI)

Recent intercontinental radioactive material shipping campaigns have focused public and regulatory attention on the safety of transport of this material by ocean-going vessels. One major concern is the response of the vessel and onboard radioactive material (RAM) packages during a severe ship-to-ship collision. These collisions occur at velocities less than the velocity obtained in the Type B package regulatory impact event and the bow of the striking ship is less rigid than the unyielding target used in those tests (Ammerman and Daidola, 1996). This implies that ship impact is not a credible scenario for damaging the radioactive material packages during ship collisions. It is possible, however, for these collisions to generate significant amounts of crush force by the bow of the impacting ship overrunning the package. It is the aim of this paper to determine an upper bound on the magnitude of this crush force taking into account the strength of the radioactive material carrying vessel and any other cargo that may be stowed in the same hold as the radioactive material.

Radloff, H.D.; Ammerman, D.J.

1998-03-01T23:59:59.000Z

424

The comparison of four dynamic systems-based software packages: Translation and sensitivity analysis  

E-Print Network [OSTI]

The comparison of four dynamic systems-based software packages: Translation and sensitivity Wetness Energy Balance (SWEB) model for canopy surface wetness has been translated into four software pack of the model. Ă? 2005 Elsevier Ltd. All rights reserved. Keywords: Model comparison; Dynamic simulation; System

Vermont, University of

425

Packaging and Transfer or Transportation of Materials of National Security Interest  

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

To establish requirements and responsibilities for the Transportation Safeguards System (TSS) packaging and transportation and onsite transfer of nuclear explosives, nuclear components, Naval nuclear fuel elements, Category I and Category II special nuclear materials, special assemblies, and other materials of national security interest. Cancels: DOE 5610.12 and DOE 5610.14.

2000-09-29T23:59:59.000Z

426

Cleanup Verification Package for the 126-F-1, 184-F Powerhouse Ash Pit  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 126-F-1, 184-F Powerhouse Ash Pit. This waste site received coal ash from the 100-F Area coal-fired steam plant. Leakage of process effluent from the 116-F-14 , 107-F Retention Basins flowed south into the ash pit, contaminating the northern portion.

S. W. Clark and H. M Sulloway

2007-10-31T23:59:59.000Z

427

Cleanup Verification Package for the 126-F-1, 184-F Powerhouse Ash Pit  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 126-F-1, 184-F Powerhouse Ash Pit. This waste site received coal ash from the 100-F Area coal-fired steam plant. Leakage of process effluent from the 116-F-14 , 107-F Retention Basins flowed south into the ash pit, contaminating the northern portion.

S. W. Clark and H. M. Sulloway

2007-09-26T23:59:59.000Z

428

Risk Analysis and Decision-Making Software Package (1997 Version) User Manual  

SciTech Connect (OSTI)

This manual provides instructions for using the U.S. Department of Energy's (DOE) risk analysis and decision making software (1997 version) developed at BDM Petroleum Technologies by BDM-Oklahoma, Inc. for DOE, under contract No. DE-AC22-94PC91OO8. This software provides petroleum producers with a simple, handy tool for exploration and production risk analysis and decision-making. It collects useful risk analysis tools in one package so that users do not have to use several programs separately. The software is simple to use, but still provides many functions. The 1997 version of the software package includes the following tools: (1) Investment risk (Gambler's ruin) analysis; (2) Monte Carlo simulation; (3) Best fit for distribution functions; (4) Sample and rank correlation; (5) Enhanced oil recovery method screening; and (6) artificial neural network. This software package is subject to change. Suggestions and comments from users are welcome and will be considered for future modifications and enhancements of the software. Please check the opening screen of the software for the current contact information. In the future, more tools will be added to this software package. This manual includes instructions on how to use the software but does not attempt to fully explain the theory and algorithms used to create it.

Chung, F.T.H.

1999-02-11T23:59:59.000Z

429

Proposal for Qualification of Gas-Generating Radioactive Payloads for Transportation within a Type B Package  

SciTech Connect (OSTI)

Characterization data describing radioactive materials (RAM) in storage are likely those associated with the processes that produced the materials or with the mission for which they were produced. Along with impurity data, often absent or unknown as a result of post-processing storage environment is moisture content. Radiolysis of moisture may lead to a hydrogen flammability hazard within a closed volume such as a storage can or a transportation package. This paper offers a practical means of qualifying payloads of unknown moisture content for shipment within Type B packaging, while supporting the DOE program to maintain radworker dose as low as reasonable achievable (ALARA). Specifically, the paper discusses part of a qualification program carried out at the Savannah River Site for onsite shipment of legacy RAM within the DDF-1 package. The DDF-1 is an onsite-only prototype of the currently certified 9975 package. Measurement of storage-can lid bulge can provide an upper bound for pressure within a storage can. Subsequent belljar testing can measure the rate of gas leakage from a storage can. These actions are shown sufficient to ensure that the performance of the 9975 containment vessels can accommodate the deflagration energy from flammable gas mixtures within Normal Conditions of Transport, and, and the consequences of a detonation shock wave within Hypothetical Accident Conditions.

Houghtaling, T.K.

2002-06-07T23:59:59.000Z

430

DEMONSTRATION OF EQUIVALENCY OF CANE AND SOFTWOOD BASED CELOTEX FOR MODEL 9975 SHIPPING PACKAGES  

SciTech Connect (OSTI)

Cane-based Celotex{trademark} has been used extensively in various Department of Energy (DOE) packages as a thermal insulator and impact absorber. Cane-based Celotex{trademark} fiberboard was only manufactured by Knight-Celotex Fiberboard at their Marrero Plant in Louisiana. However, Knight-Celotex Fiberboard shut down their Marrero Plant in early 2007 due to impacts from hurricane Katrina and other economic factors. Therefore, cane-based Celotex{trademark} fiberboard is no longer available for use in the manufacture of new shipping packages requiring the material as a component. Current consolidation plans for the DOE Complex require the procurement of several thousand new Model 9975 shipping packages requiring cane-based Celotex{trademark} fiberboard. Therefore, an alternative to cane-based Celotex{trademark} fiberboard is needed. Knight-Celotex currently manufactures Celotex{trademark} fiberboard from other cellulosic materials, such as hardwood and softwood. A review of the relevant literature has shown that softwood-based Celotex{trademark} meets all parameters important to the Model 9975 shipping package.

Watkins, R; Jason Varble, J

2008-05-27T23:59:59.000Z

431

Cleanup Verification Package for the 100-F-20, Pacific Northwest Laboratory Parallel Pits  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 100-F-20, Pacific Northwest Laboratory Parallel Pits waste site. This waste site consisted of two earthen trenches thought to have received both radioactive and nonradioactive material related to the 100-F Experimental Animal Farm.

M. J. Appel

2007-01-22T23:59:59.000Z

432

Cleanup Verification Package for the 118-C-1, 105-C Solid Waste Burial Ground  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 118-C-1, 105-C Solid Waste Burial Ground. This waste site was the primary burial ground for general wastes from the operation of the 105-C Reactor and received process tubes, aluminum fuel spacers, control rods, reactor hardware, spent nuclear fuel and soft wastes.

M. J. Appel and J. M. Capron

2007-07-25T23:59:59.000Z

433

THERMAL TESTING OF 9977 GENERAL PURPOSE FISSILE PACKAGE USING A POOL FIRE  

SciTech Connect (OSTI)

The 9977/9978 General Purpose Fissile Package (GPFP), has been designed as a cost-effective, user-friendly replacement for the DOT 6M Specification Package for transporting Plutonium and Uranium metals and oxides. To ensure the capability of the 9977 GPFP to withstand the regulatory crush test, urethane foam was chosen for the impact absorbing overpack. As part of the package development it was necessary to confirm that the urethane foam overpack would provide the required protection for the containment vessel during the thermal test portion of the Hypothetical Accident Conditions Sequential Tests. Development tests of early prototypes were performed, using a furnace. Based on the results of the development tests, detailed design enhancements were incorporated into the final design. Examples of the definitive 9977 design configuration were subjected to an all-engulfing pool fire test, as part of the HAC Sequential Tests, to support the application for certification. Testing has confirmed the package's ability to withstand the HAC thermal tests.

Smith, A; Cecil May, C; Lawrence Gelder, L; Glenn Abramczyk, G

2007-02-15T23:59:59.000Z

434

Self-Assembly Techniques for Massively Parallel Packaging of MEMS Devices  

E-Print Network [OSTI]

Self-Assembly Techniques for Massively Parallel Packaging of MEMS Devices Jiandong Fang-1346, or to the author. Signature Date July 31, 2006 #12;#12;University of Washington Abstract Self-Assembly Techniques. B¨ohringer Electrical Engineering This dissertation investigates applications of self-assembly

435

HIGH YIELD BATCH PACKAGING OF MICRO DEVICES WITH UNIQUELY ORIENTING SELF-ASSEMBLY  

E-Print Network [OSTI]

HIGH YIELD BATCH PACKAGING OF MICRO DEVICES WITH UNIQUELY ORIENTING SELF-ASSEMBLY Jiandong Fang of uniquely orienting self-assembly with 2mm square diced silicon parts. Each silicon part has one hydrophobic shape-directed self-assembly assigns parts to complementary trenches in parallel [2]; (3) capillary

436

Rotavirus protein involved in genome replication and packaging exhibits a HIT-like fold  

Science Journals Connector (OSTI)

... three concentric capsid layers, consists of 11 segments of double-stranded RNA (dsRNA) that code for six structural and six non-structural proteins (NSPs). Several in vivo and ... hydrolysis to package the viral genome. In its function, NSP2 may be homologous to NS2 (refs 15, 16) of bluetongue virus and ?NS of orthoreovirus. To understand the ...

Hariharan Jayaram; Zenobia Taraporewala; John T. Patton; B. V. Venkataram Prasad

2002-05-16T23:59:59.000Z

437

Developing a Standard Method of Test for Packaged, Solid-Desiccant Based Dehumidification Systems  

E-Print Network [OSTI]

for moving process and regeneration air; · May include other system components for filtering, pre of the dehumidification system is presented in terms that would be most familiar and useful to designers of building HVAC that include many of the ancillary components mentioned above. An HVAC system designer who considers a packaged

Oak Ridge National Laboratory

438

DEVELOPMENT OF BURN TEST SPECIFICATIONS FOR FIRE PROTECTION MATERIALS IN RAM PACKAGES  

SciTech Connect (OSTI)

The regulations in 10 CFR 71 require that the radioactive material (RAM) packages must be able to withstand specific fire conditions given in 10 CFR 71.73 during Hypothetical Accident Conditions (HAC). This requirement is normally satisfied by extensive testing of full scale test specimens under required test conditions. Since fire test planning and execution is expensive and only provides a single snapshot into a package performance, every effort is made to minimize testing and supplement tests with results from computational thermal models. However, the accuracy of such thermal models depends heavily on the thermal properties of the fire insulating materials that are rarely available at the regulatory fire temperatures. To the best of authors knowledge no test standards exist that could be used to test the insulating materials and derive their thermal properties for the RAM package design. This paper presents a review of the existing industry fire testing standards and proposes testing methods that could serve as a standardized specification for testing fire insulating materials for use in RAM packages.

Gupta, N.

2010-03-03T23:59:59.000Z

439

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR RADIOACTIVE MATERIALS PACKAGINGS.  

SciTech Connect (OSTI)

Polyurethane foam has been widely used as an impact absorbing and thermal insulating material for large radioactive materials packages, since the 1980's. With the adoption of the regulatory crush test requirement, for smaller packages, polyurethane foam has been adopted as a replacement for cane fiberboard, because of its ability to withstand the crush test. Polyurethane foam is an engineered material whose composition is much more closely controlled than that of cane fiberboard. In addition, the properties of the foam can be controlled by controlling the density of the foam. The conditions under which the foam is formed, whether confined or unconfined have an affect on foam properties. The study reported here reviewed the application of polyurethane foam in RAM packagings and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2007-05-15T23:59:59.000Z

440

Geology Data Package for the Single-Shell Tank Waste Management Areas at the Hanford Site  

SciTech Connect (OSTI)

This data package discusses the geology of the single-shell tank (SST) farms and the geologic history of the area. The focus of this report is to provide the most recent geologic information available for the SST farms. This report builds upon previous reports on the tank farm geology and Integrated Disposal Facility geology with information available after those reports were published.

Reidel, Steve P.; Chamness, Mickie A.

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment  

SciTech Connect (OSTI)

This data package documents the experimentally derived input data on the representative waste glasses; LAWA44, LAWB45, and LAWC22. This data will be used for Subsurface Transport Over Reactive Multi-phases (STORM) simulations of the Integrated Disposal Facility (IDF) for immobilized low-activity waste (ILAW). The STORM code will be used to provide the near-field radionuclide release source term for a performance assessment to be issued in July 2005. Documented in this data package are data related to 1) kinetic rate law parameters for glass dissolution, 2) alkali (Na+)-hydrogen (H+) ion exchange rate, 3) chemical reaction network of secondary phases that form in accelerated weathering tests, and 4) thermodynamic equilibrium constants assigned to these secondary phases. The kinetic rate law and Na+-H+ ion exchange rate were determined from single-pass flow-through experiments. Pressurized unsaturated flow (PUF) and product consistency (PCT) tests where used for accelerated weathering or aging of the glasses in order to determine a chemical reaction network of secondary phases that form. The majority of the thermodynamic data used in this data package were extracted from the thermody-namic database package shipped with the geochemical code EQ3/6, version 8.0. Because of the expected importance of 129I release from secondary waste streams being sent to IDF from various thermal treatment processes, parameter estimates for diffusional release and solubility-controlled release from cementitious waste forms were estimated from the available literature.

Pierce, Eric M.; McGrail, B. Peter; Rodriguez, Elsa A.; Schaef, Herbert T.; Saripalli, Prasad; Serne, R. Jeffrey; Krupka, Kenneth M.; Martin, P. F.; Baum, Steven R.; Geiszler, Keith N.; Reed, Lunde R.; Shaw, Wendy J.

2004-09-01T23:59:59.000Z

442

AGING BEHAVIOR OF VITON O-RING SEALS IN THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is storing plutonium (Pu) materials in the K-Area Materials Storage (KAMS) facility. The Pu materials were packaged according to the DOE-STD-3013 standard and shipped to the SRS in Type B 9975 packages. The robust 9975 shipping package was not designed for long-term product storage, but it is a specified part of the storage configuration and the KAMS facility safety basis credits the 9975 design with containment. Within the 9975 package, nested stainless steel containment vessels are closed with dual O-ring seals based on Viton{reg_sign} GLT or GLT-S fluoroelastomer. The aging behavior of the O-ring compounds is being studied to provide the facility with advanced notice of nonconformance and to develop life prediction models. A combination of field surveillance, leak testing of surrogate fixtures aged at bounding service temperatures, and accelerated-aging methodologies based on compression stress-relaxation and oxygen consumption analysis is being used to evaluate seal performance. A summary of the surveillance program relative to seal aging behavior is presented.

Skidmore, E.; Daugherty, W.; Hoffman, E.; Dunn, K.; Bellamy, S.

2012-01-13T23:59:59.000Z

443

Retail appearance and microbiological characteristics of vacuum packaged pork loin chops  

E-Print Network [OSTI]

perpendicularly cut in half form1ng thirty loin sections. Ten sections were wrapped in wax-coated parchment paper and stored in boxes at 5 C - 2 for s1x days before fabrication; ten sections were vacuum o + packaged for e1ght days using plast1c bags and a...

Vrana, Julie Ann

1982-01-01T23:59:59.000Z

444

Design of Compact Stacked-Patch Antennas in LTCC multilayer packaging modules for Wireless Applications  

E-Print Network [OSTI]

Design of Compact Stacked-Patch Antennas in LTCC multilayer packaging modules for Wireless: 404-894-3360 Fax: 404-894-4641 Abstract A simple procedure for the design of compact stacked-patch module was proposed for compact RF front-end, which is integrated with a patch antenna [2]. However

Tentzeris, Manos

445

Vendor Assessment for the Waste Package Closure System (Yucca Mountain Project)  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) has been tasked with developing, designing, constructing, and operating a full-scale prototype of the work package closure system. As a precursor to developing the conceptual design, all commercially available equipment was assessed to identify any existing technology gaps. This report presents the results of that assessment for all major equipment.

Shelton-Davis, C.V.

2003-09-26T23:59:59.000Z

446

Vendor Assessment for the Waste Package Closure System (Yucca Mtn. Project)  

SciTech Connect (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) has been tasked with developing, designing, constructing, and operating a full-scale prototype of the work package closure system. As a precursor to developing the conceptual design, all commercially available equipment was assessed to identify any existing technology gaps. This report presents the results of that assessment for all major equipment.

Colleen Shelton-Davis

2003-09-01T23:59:59.000Z

447

V-band Transmission and Reflection Grid Amplifier Packaged in Waveguide  

E-Print Network [OSTI]

for thermal management by allowing the heat sink to be mounted on one side of the grid array. It also reduces and cooling fan were used to remove heat from the chip. The temperature distribution across the grid aperture1 V-band Transmission and Reflection Grid Amplifier Packaged in Waveguide Chun-Tung Cheung1 , Roger

448

Environmental restoration risk-based prioritization work package planning and risk ranking methodology. Revision 2  

SciTech Connect (OSTI)

This document presents the risk-based prioritization methodology developed to evaluate and rank Environmental Restoration (ER) work packages at the five US Department of Energy, Oak Ridge Field Office (DOE-ORO) sites [i.e., Oak Ridge K-25 Site (K-25), Portsmouth Gaseous Diffusion Plant (PORTS), Paducah Gaseous Diffusion Plant (PGDP), Oak Ridge National Laboratory (ORNL), and the Oak Ridge Y-12 Plant (Y-12)], the ER Off-site Program, and Central ER. This prioritization methodology was developed to support the increased rigor and formality of work planning in the overall conduct of operations within the DOE-ORO ER Program. Prioritization is conducted as an integral component of the fiscal ER funding cycle to establish program budget priorities. The purpose of the ER risk-based prioritization methodology is to provide ER management with the tools and processes needed to evaluate, compare, prioritize, and justify fiscal budget decisions for a diverse set of remedial action, decontamination and decommissioning, and waste management activities. The methodology provides the ER Program with a framework for (1) organizing information about identified DOE-ORO environmental problems, (2) generating qualitative assessments of the long- and short-term risks posed by DOE-ORO environmental problems, and (3) evaluating the benefits associated with candidate work packages designed to reduce those risks. Prioritization is conducted to rank ER work packages on the basis of the overall value (e.g., risk reduction, stakeholder confidence) each package provides to the ER Program. Application of the methodology yields individual work package ``scores`` and rankings that are used to develop fiscal budget requests. This document presents the technical basis for the decision support tools and process.

Dail, J.L.; Nanstad, L.D.; White, R.K.

1995-06-01T23:59:59.000Z

449

AUTHORIZING THE DOT SPECIFICATION 6M PACKAGING FOR CONTINUED USE AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

The U.S. Department of Transportation (DOT) Specification 6M packaging was in extensive use for more than 40 years for in-commerce shipments of Type B quantities of fissile and radioactive material (RAM) across the USA, among the Department of Energy (DOE) laboratories, and between facilities in the DOE production complex. In January 2004, the DOT Research and Special Programs Administration (RSPA) Agency issued a final rule in the Federal Register to ammend requirements in the Hazardous Materials Regulations (HMR) pertaining to the transportation of radioactive materials. The final rule became effective on October 1, 2004. One of those changes discontinued the use of the DOT specification 6M, along with other DOT specification packagings, on October 1, 2008. A main driver for the change was due to the fact that 6M specification packagings were not supported by a Safety Analysis Report for Packagings (SARP) that was compliant with Title 10 of the Code of Federal Regulations (CFR) Part 71 (10 CFR 71). The regulatory rules for the discontinued use have been edited in Title 49 of the CFR Parts 100-185, 2004 edition and thereafter. Prior to October 1, 2008, the use of the 6M within the boundaries of the Savannah River Site (SRS), called an onsite transfer, was governed by an onsite transportation document that referenced 49 CFR Parts 100-185. SRS had to develop an Onsite Safety Assessment (OSA) which was independent of 49 CFR in order to justify the continued use of the DOT Specification 6M for the transfer of radioactive material (RAM) at the SRS after October 1, 2008. This paper will discuss the methodology for and difficulties associated with authorizing the DOT Specification 6M Packaging for continued use at the Savannah River Site.

Watkins, R.; Loftin, B.; Hoang, D.

2010-03-04T23:59:59.000Z

450

Waste Form Release Data Package for the 2001 Immobilized Low-Activity Waste Performance Assessment  

SciTech Connect (OSTI)

This data package documents the experimentally derived input data on the representative waste glasses LAWABP1 and HLP-31 that will be used for simulations of the immobilized lowactivity waste disposal system with the Subsurface Transport Over Reactive Multiphases (STORM) code. The STORM code will be used to provide the near-field radionuclide release source term for a performance assessment to be issued in March of 2001. Documented in this data package are data related to 1) kinetic rate law parameters for glass dissolution, 2) alkali-H ion exchange rate, 3) chemical reaction network of secondary phases that form in accelerated weathering tests, and 4) thermodynamic equilibrium constants assigned to these secondary phases. The kinetic rate law and Na+-H+ ion exchange rate were determined from single-pass flow-through experiments. Pressurized unsaturated flow and vapor hydration experiments were used for accelerated weathering or aging of the glasses. The majority of the thermodynamic data were extracted from the thermodynamic database package shipped with the geochemical code EQ3/6. However, several secondary reaction products identified from laboratory tests with prototypical LAW glasses were not included in this database, nor are the thermodynamic data available in the open literature. One of these phases, herschelite, was determined to have a potentially significant impact on the release calculations and so a solubility product was estimated using a polymer structure model developed for zeolites. Although this data package is relatively complete, final selection of ILAW glass compositions has not been done by the waste treatment plant contractor. Consequently, revisions to this data package to address new ILAW glass formulations are to be regularly expected.

McGrail, B. Peter; Icenhower, Jonathan P.; Martin, Paul F.; Schaef, Herbert T.; O'Hara, Matthew J.; Rodriguez, Eugenio; Steele, Jackie L.

2001-02-01T23:59:59.000Z

451

ISSUANCE: 2014-11-13 Energy Conservation Standards for Commercial Packaged Boilers: Public Meeting and Availability of the Preliminary Technical Support Document  

Broader source: Energy.gov [DOE]

Energy Conservation Standards for Commercial Packaged Boilers: Public Meeting and Availability of the Preliminary Technical Support Document

452

Using Single-Camera 3-D Imaging to Guide Material Handling Robots in a Nuclear Waste Package Closure System  

SciTech Connect (OSTI)

Nuclear reactors for generating energy and conducting research have been in operation for more than 50 years, and spent nuclear fuel and associated high-level waste have accumulated in temporary storage. Preparing this spent fuel and nuclear waste for safe and permanent storage in a geological repository involves developing a robotic packaging system—a system that can accommodate waste packages of various sizes and high levels of nuclear radiation. During repository operation, commercial and government-owned spent nuclear fuel and high-level waste will be loaded into casks and shipped to the repository, where these materials will be transferred from the casks into a waste package, sealed, and placed into an underground facility. The waste packages range from 12 to 20 feet in height and four and a half to seven feet in diameter. Closure operations include sealing the waste package and all its associated functions, such as welding lids onto the container, filling the inner container with an inert gas, performing nondestructive examinations on welds, and conducting stress mitigation. The Idaho National Laboratory is designing and constructing a prototype Waste Package Closure System (WPCS). Control of the automated material handling is an important part of the overall design. Waste package lids, welding equipment, and other tools must be moved in and around the closure cell during the closure process. These objects are typically moved from tool racks to a specific position on the waste package to perform a specific function. Periodically, these objects are moved from a tool rack or the waste package to the adjacent glovebox for repair or maintenance. Locating and attaching to these objects with the remote handling system, a gantry robot, in a loosely fixtured environment is necessary for the operation of the closure cell. Reliably directing the remote handling system to pick and place the closure cell equipment within the cell is the major challenge.

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

453

Complete 90.1 Prototype Building Model package | Building Energy Codes  

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

Complete 90.1 Prototype Building Model package Complete 90.1 Prototype Building Model package The ASHRAE Standard 90.1 prototype building models were developed by Pacific Northwest National Laboratory in support of the U.S. Department of Energy's (DOE's) Building Energy Codes Program. These prototype buildings were derived from DOE's Commercial Reference Building Models. This suite of ASHRAE Standard 90.1 prototype buildings covers all the Reference Building types except supermarket, and also adds a new building prototype representing high-rise apartment buildings.The prototype models include 16 building types in 17 climate locations for ASHRAE Standards 90.1-2004, 90.1-2007 and 90.1-2010. This combination leads to a set of 816 building models (in EnergyPlus Version 6.0). Also included is a scorecard for each

454

Technical Approach for the Development of DOE Building America Builders Challenge Technology Information Packages (Revised)  

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

4687 4687 Revised August 2009 Technical Approach for the Development of DOE Building America Builders Challenge Technology Information Packages D.R. Roberts and R. Anderson National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy Operated by the Alliance for Sustainable Energy, LLC Contract No. DE-AC36-08-GO28308 Technical Report NREL/TP-550-44687 Revised August 2009 Technical Approach for the Development of DOE Building America Builders Challenge Technology Information Packages D.R. Roberts and R. Anderson Prepared under Task No. BET88001 The addition of Appendix D is the only revision to the January 2009

455

Packaging Strategies for Criticality Safety for "Other" DOE Fuels in a Repository  

SciTech Connect (OSTI)

Since 1998, there has been an ongoing effort to gain acceptance of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in the national repository. To accomplish this goal, the fuel matrix was used as a discriminating feature to segregate fuels into nine distinct groups. From each of those groups, a characteristic fuel was selected and analyzed for criticality safety based on a proposed packaging strategy. This report identifies and quantifies the important criticality parameters for the canisterized fuels within each criticality group to: (1) demonstrate how the “other” fuels in the group are bounded by the baseline calculations or (2) allow identification of individual type fuels that might require special analysis and packaging.

Larry L Taylor

2004-06-01T23:59:59.000Z

456

DEGRADATION OF FIBERBOARD IN MODEL 9975 PACKAGE FOLLOWING ENVIRONMENTAL CONDITIONING FIRST INTERIM REPORT  

SciTech Connect (OSTI)

Fiberboard material, used in the 9975 shipping package, has been tested for thermal, mechanical and physical properties following environmental conditioning for periods up to 64 weeks. The environments are either representative or bounding of KAMS storage conditions, in order to provide prediction of long-term performance of the 9975 package in KAMS. This report summarizes the data and analysis performed to date. These data show degradation of some properties in some of the environments, but samples have not degraded beyond identified minimum KAMS requirements. Statistical analysis of the data collected to date support the development of a model to predict a service life in KAMS. Further model development and lifetime predictions will be made following additional conditioning and testing in accordance with the task technical plan.

Daugherty, W; Stephen Harris, S

2007-06-13T23:59:59.000Z

457

Evaluation of Type B shipping packages used to transport potentially flammable gas mixtures  

SciTech Connect (OSTI)

Using Type B shipping packages to transport radioactive materials within a potentially flammable gas mixture is a bold proposal. The Nuclear Regulatory Commission (NRC) has essentially prohibited such shipments. Furthermore, the NRC requires extensive modeling and/or testing of selective contents (e.g., Transuranic Waste) which are prone to generate hydrogen gas to demonstrate that, in general, a flammable mixture inside the containment vessel will not occur during shipment. Contrary to the NRC position, this paper proposes a rigorous containment vessel evaluation methodology to justify shipment of Type B quantities of radioactive materials in the presence of potentially flammable gas mixtures. The Department of Energy (DOE) is currently reviewing the methodology as applied to the 9975 package for shipment of plutonium oxide which may generate significant quantities of hydrogen gas.

Hensel, S.J.

2000-04-26T23:59:59.000Z

458

Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask  

SciTech Connect (OSTI)

This safety evaluation for packaging (SEP) provides the evaluation necessary to demonstrate that the Plutonium Recycle Test Reactor (PRTR) Graphite Cask meets the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B, fissile, non-highway route controlled quantities of radioactive material within the 300 Area of the Hanford Site. The scope of this SEP includes risk, shieldling, criticality, and.tiedown analyses to demonstrate that onsite transportation safety requirements are satisfied. This SEP also establishes operational and maintenance guidelines to ensure that transport of the PRTR Graphite Cask is performed safely in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.

Romano, T.

1997-09-29T23:59:59.000Z

459

MATERIALS COMPATIBILITY OF SNAP FUEL COMPONENTS DURING SHIPMENT IN 9975 PACKAGING  

SciTech Connect (OSTI)

Materials Science and Technology has evaluated materials compatibility for the SNAP (Systems for Nuclear Auxiliary Power) fuel for containment within a 9975 packaging assembly for a shipping period of one year. The evaluation included consideration for potential for water within the convenience can, corrosion from water, galvanic corrosion, tape degradation, and thermal expansion risk. Based on a review of existing literature and assumed conditions, corrosion and/or degradation of the 304 stainless steel (SS) Primary Containment Vessel (PCV) and the 304 stainless steel convenience cans containing the SNAP fuel is not significant to cause failure during the 1 year time shipping period in the 9975 packaging assembly. However, storage beyond the 1 year shipping period has not been validated.

Vormelker, P

2006-11-14T23:59:59.000Z

460

March 10, 2005, Board letter forwarding Recommendation 2005-1, Nuclear Material Packaging  

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

FACLLTIlEs FACLLTIlEs SAFETYBOARD John T. Conway, Chairman A.J. Eggenberger, Vice Chairman Joseph F. Bader John E. Mansfield R. Bruce Matthews 625 Indiana Avenue, NW, Suite 700, Wa5hington. D.C. 20004-2901 (202) 694-7000 March 10, 2005 The Honorable Samuel W. Bodman Secretary of Energy 1000 Independence Avenue, SW Washington, DC 20585-1000 Dear Secretary Bodman: On March 10,2005, the Defense Nuclear Facilities Safety Board (Board), in accordance with 42 U.S.C. 9 2286a(a)(5), unanimously approved Recommendation 2005- 1, Nuclear Material Packaging, which is enclosed for your consideration. This recommendation addresses issuance of a requirement that nuclear material packaging meet technically justified criteria for safe storage and handling outside of engineered contamination barriers.

Note: This page contains sample records for the topic "reheat packaged single-zone" 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

Identification and evaluation of volatile compounds associated with vacuum and modified atmosphere packaged fresh red meats  

E-Print Network [OSTI]

with Lacrobacillus planrarum or Leuconostoc mesenteroides and stored for 28 days at 3'C included acetone, toluene, acetic acid, ethyl acetate, a hydrocarbon and CHCls. The profile of volatiles in packaged sterile loin tissue stored for 28 days was very similar.... , 1979, 1983; Vanderzant et al. , 1986). ~Although many studies have reported these off-odors, very little published information exists relative to the nature of the volatile aroma compounds which result from microbial or enzymatic activity during...

Jackson, Timothy Court

1989-01-01T23:59:59.000Z

462

www.sea.co.uk a Cohort plc company L-DAP Lunar Dust Analysis Package  

E-Print Network [OSTI]

www.sea.co.uk a Cohort plc company L-DAP Lunar Dust Analysis Package Study Overview ESTEC Contract.sea.co.uk a Cohort plc company Dust Problems.. · "I think probably the most aggravating, restricting facets of lunar #12;www.sea.co.uk a Cohort plc company Lunar South Pole ... L-DAP Overview 28th Oct 2011 · South Pole

Anand, Mahesh

463

Safety evaluation for packaging (onsite) for the Pacific Northwest National Laboratory HEPA filter box  

SciTech Connect (OSTI)

This safety evaluation for packaging (SEP) evaluates and documents the safe onsite transport of eight high-efficiency particulate air (HEPA) filters in the Pacific Northwest National Laboratory HEPA Filter Box from the 300 Area of the Hanford Site to the Central Waste Complex and on to burial in the 200 West Area. Use of this SEP is authorized for 1 year from the date of release.

McCoy, J.C.

1998-07-15T23:59:59.000Z

464

Improving the Operating Efficiency of Packaged Air Conditioners and Heat Pumps  

SciTech Connect (OSTI)

This article discusses several control strategies that can significantly reduce energy consumption associated with packaged rooftop units RTUs). Although all of the considered strategies are widely used in built-up air-handing units, they are not commonly used in existing RTUs. Both simulation and field evaluations show that adding these control strategies to existing RTUs can reduce their energy consumption by between 30% and 60%.

Katipamula, Srinivas; Wang, Weimin; Vowles, Mira

2014-03-10T23:59:59.000Z

465

Stress-induced Effects Caused by 3D IC TSV Packaging in Advanced Semiconductor Device Performance  

SciTech Connect (OSTI)

Potential challenges with managing mechanical stress and the consequent effects on device performance for advanced 3D through-silicon-via (TSV) based technologies are outlined. The paper addresses the growing need in a simulation-based design verification flow capable to analyze a design of 3D IC stacks and to determine across-die out-of-spec variations in device electrical characteristics caused by the layout and through-silicon-via (TSV)/package-induced mechanical stress. The limited characterization/measurement capabilities for 3D IC stacks and a strict ''good die'' requirement make this type of analysis critical for the achievement of an acceptable level of functional and parametric yield and reliability. The paper focuses on the development of a design-for-manufacturability (DFM) type of methodology for managing mechanical stresses during a sequence of designs of 3D TSV-based dies, stacks and packages. A set of physics-based compact models for a multi-scale simulation to assess the mechanical stress across the device layers in silicon chips stacked and packaged with the 3D TSV technology is proposed. A calibration technique based on fitting to measured stress components and electrical characteristics of the test-chip devices is presented. A strategy for generation of a simulation feeding data and respective materials characterization approach are proposed, with the goal to generate a database for multi-scale material parameters of wafer-level and package-level structures. For model validation, high-resolution strain measurements in Si channels of the test-chip devices are needed. At the nanoscale, the transmission electron microscopy (TEM) is the only technique available for sub-10 nm strain measurements so far.

Sukharev, V.; Kteyan, A.; Choy, J.-H.; Hovsepyan, H.; Markosian, A. [Mentor Graphics Corporation, 46871 Bayside Parkway, Fremont, CA 94538 (United States); Zschech, E.; Huebner, R. [Fraunhofer Institute for Non-Destructive Testing, Maria-Reiche-Strasse 2, 01109 Dresden (Germany)

2011-11-10T23:59:59.000Z

466

Uranium hexafluoride packaging tiedown systems overview at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio. Revision 1  

SciTech Connect (OSTI)

The Portsmouth Gaseous Diffusion Plant (PORTS) in Piketon, Ohio, is operated by Martin Marietta Energy Systems, Inc., through the US Department of Energy-Oak Ridge Operations Office (DOE-ORO) for the US Department of Energy-Headquarters, Office of Nuclear Energy. The PORTS conducts those operations that are necessary for the production, packaging, and shipment of uranium hexafluoride (UF{sub 6}). Uranium hexafluoride enriched uranium than 1.0 wt percent {sup 235}U shall be packaged in accordance with the US Department of Transportation (DOT) regulations of Title 49 CFR Parts 173 (Reference 1) and 178 (Reference 2), or in US Nuclear Regulatory Commission (NRC) or US Department of Energy (DOE) certified package designs. Concerns have been expressed regarding the various tiedown methods and condition of the trailers being used by some shippers/carriers for international transport of the UF{sub 6} cylinders/overpacks. Because of the concerns about international shipments, the US Department of Energy-Headquarters (DOE-HQ) Office of Nuclear Energy, through DOE-HQ Transportation Management Division, requested Westinghouse Hanford Company (Westinghouse Hanford) to review UF{sub 6} packaging tiedown and shipping practices used by PORTS, and where possible and appropriate, provide recommendations for enhancing these practices. Consequently, a team of two individuals from Westinghouse Hanford visited PORTS on March 5 and 6, 1990, for the purpose of conducting this review. The paper provides a brief discussion of the review activities and a summary of the resulting findings and recommendations. A detailed reporting of the is documented in Reference 4.

Becker, D.L.; Green, D.J.; Lindquist, M.R.

1993-07-01T23:59:59.000Z

467

Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations.

Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

1980-01-01T23:59:59.000Z

468

Safety analysis report for packaging, onsite, long-length contaminated equipment transport system  

SciTech Connect (OSTI)

This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks.

McCormick, W.A.

1997-05-09T23:59:59.000Z

469

INFO-F-309 Administration des Systmes TP1: Installation de Linux et gestion des packages  

E-Print Network [OSTI]

virtuelle avant de la lancer pour mon- ter l'image .iso disponible dans le répertoire /serveur/logicielles/tpINFO-F-309 ­ Administration des Systèmes TP1: Installation de Linux et gestion des packages trouverez l(es) image(s) du TP dans le répertoire : /serveur/logicielles/tp-adminsys/partie1 Ce répertoire

Collette. SĂ©bastien

470

Packaging and Transportation for Offsite Shipment of Materials of National Security Interest  

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

The purpose of this Order is to make clear that the packaging and transportation of all offsite shipments of materials of national security interest for DOE must be conducted in accordance with DOT and Nuclear Regulatory Commission (NRC) regulations that would be applicable to comparable commercial shipments, except where an alternative course of action is identified in this Order. Cancels DOE O 461.1A.

2010-12-20T23:59:59.000Z

471

THERMAL PROPERTIES OF FIBERBOARD OVERPACK MATERIALS IN THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The 9975 shipping package incorporates a cane fiberboard overpack for thermal insulation and impact resistance. Thermal properties (thermal conductivity and specific heat capacity) have been measured on cane fiberboard and a similar wood fiber-based product at several temperatures representing potential storage conditions. While the two products exhibit similar behavior, the measured specific heat capacity varies significantly from prior data. The current data are being developed as the basis to verify that this material remains acceptable over the extended storage time period.

VORMELKER, PHILLIP; DAUGHERTY, W. L.

2005-06-10T23:59:59.000Z

472

PROPERTIES OF FIBERBOARD OVERPACK MATERIAL IN THE 9975 SHIPPING PACKAGE FOLLOWING THERMAL AGING  

SciTech Connect (OSTI)

Many radioactive material shipping packages incorporate cane fiberboard overpacks for thermal insulation and impact resistance. Mechanical, thermal and physical properties have been measured on cane fiberboard following thermal aging in several temperature/humidity environments. Several of the measured properties change significantly over time in the more severe environments, while other properties are relatively constant. These properties continue to be tracked, with the goal of developing a model for predicting a service life under long-term storage conditions.

Daugherty, W

2007-01-10T23:59:59.000Z

473

FINAL REPORT FOR MOISTURE EFFECTS ON COMPACTION OF FIBERBOARD IN A 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Compaction of lower layers in the fiberboard assembly has been observed in 9975 packages that contain elevated moisture. Lab testing has resulted in a better understanding of the relationship between the fiberboard moisture level and compaction of the lower fiberboard assembly, and the behavior of the fiberboard during transport. In laboratory tests of cane fiberboard, higher moisture content has been shown to correspond to higher total compaction, greater rate of compaction, and continued compaction over a longer period of time. In addition, laboratory tests have shown that the application of a dynamic load results in higher fiberboard compaction compared to a static load. The test conditions and sample geometric/loading configurations were chosen to simulate the regulatory requirements for 9975 package input dynamic loading. Dynamic testing was conducted to acquire immediate and cumulative changes in geometric data for various moisture levels. Two sample sets have undergone a complete dynamic test regimen, one set for 27 weeks, and the second set for 47 weeks. The dynamic input, data acquisition, test effects on sample dynamic parameters, and results from this test program are summarized and compared to regulatory specifications for dynamic loading. Compaction of the bottom fiberboard layers due to the accumulation of moisture is one possible cause of an increase in the axial gap at the top of the package. The net compaction of the bottom layers will directly add to the axial gap. The moisture which caused this compaction migrated from the middle region of the fiberboard assembly (which is typically the hottest). This will cause the middle region to shrink axially, which will also contribute directly to the axial gap. Measurement of the axial gap provides a screening tool for identifying significant change in the fiberboard condition. The data in this report provide a basis to evaluate the impact of moisture and fiberboard compaction on 9975 package performance during storage at the Savannah River Site (SRS).

Stefek, T.; Daugherty, W.; Estochen, E.

2013-09-17T23:59:59.000Z

474

The package HarmonicSums: Computer Algebra and Analytic aspects of Nested Sums  

E-Print Network [OSTI]

This paper summarizes the essential functionality of the computer algebra package HarmonicSums. On the one hand HarmonicSums can work with nested sums such as harmonic sums and their generalizations and on the other hand it can treat iterated integrals of the Poincare and Chen-type, such as harmonic polylogarithms and their generalizations. The interplay of these representations and the analytic aspects are illustrated by concrete examples.

Jakob Ablinger

2014-07-23T23:59:59.000Z

475

APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS  

SciTech Connect (OSTI)

This paper reports on the development and testing performed to demonstrate the use of flow forming as an alternate method of manufacturing containment vessels for use in radioactive material shipping packaging designs. Additionally, ASME Boiler and Pressure Vessel Code, Section III, Subsection NB compliance along with the benefits compared to typical welding of containment vessels will be discussed. SRNL has completed fabrication development and the testing on flow formed containment vessels to demonstrate the use of flow forming as an alternate method of manufacturing a welded 6-inch diameter containment vessel currently used in the 9975 and 9977 radioactive material shipping packaging. Material testing and nondestructive evaluation of the flow formed parts demonstrate compliance to the minimum material requirements specified in applicable parts of ASME Boiler and Pressure Vessel Code, Section II. Destructive burst testing shows comparable results to that of a welded design. The benefits of flow forming as compared to typical welding of containment vessels are significant: dimensional control is improved due to no weld distortion; less final machining; weld fit-up issues associated with pipes and pipe caps are eliminated; post-weld non-destructive testing (i.e., radiography and die penetrant tests) is not necessary; and less fabrication steps are required. Results presented in this paper indicate some of the benefits in adapting flow forming to design of future radioactive material shipping packages containment vessels.

Blanton, P.; Eberl, K.; Abramczyk, G.

2012-07-11T23:59:59.000Z

476

Dynamic Simulation of Shipping Package Subjected to Torque Load and Sequential Impacts  

SciTech Connect (OSTI)

A numerical technique has been developed to simulate the structural responses of radioactive material packaging components requiring closure-tightening torque to the scenarios of the hypothetical accident conditions (HAC) defined in the Code of Federal Regulations Title 10 part 71 (10CFR 71). A rigorous solution to this type of problem poses a considerable mathematical challenge. Conventional methods for evaluating the residue stresses due to the torque load are either inaccurate or not applicable to dynamic analyses. In addition, the HAC events occur sequentially and the cumulative damage to the package needs to be evaluated. Commonly, individual HAC events are analyzed separately and the cumulative damage is not addressed. As a result, strict compliance of the package with the requirements specified in 10CFR 71 is usually demonstrated by physical testing. The proposed technique utilizes the combination of kinematic constraints, rigid-body motions and structural deformations to overcome some of the difficulties encountered in modeling the effect of cumulative damage in numerical solutions. The analyses demonstrating use of this technique were performed to determine the cumulative damage of torque preload, a 30-foot drop, a 30-foot dynamic crush and a 40-inch free fall onto a mild steel pipe.

Wu, T

2006-04-17T23:59:59.000Z

477

A COMPARISON OF TWO THERMAL INSULATION AND STRUCTURAL MATERIALS FOR USE IN TYPE B PACKAGINGS  

SciTech Connect (OSTI)

This paper presents the summary of design features and test results of two Type B Shipping Package prototype configurations comprising different insulating materials developed by the Savannah River National Laboratory (SRNL) for the Department of Energy. The materials evaluated, a closed-cell polyurethane foam and a vacuformed ceramic fiber material, were selected to provide adequate structural protection to the package containment vessel during Normal Conditions of Transport (NCT) and Hypothetical Accident Condition (HAC) events and to provide thermal protection during the HAC fire. Polyurethane foam has been used in shipping package designs for many years because of the stiffness it provides to the structure and because of the thermal protection it provides during fire scenarios. This comparison describes how ceramic fiber material offers an alternative to the polyurethane foam in a specific overpack design. Because of the high operating temperature ({approx}2,300 F) of the ceramic material, it allows for contents with higher heat loads to be shipped than is possible with polyurethane foam. Methods of manufacturing and design considerations using the two materials will be addressed.

Blanton, P.; Eberl, K.

2010-07-16T23:59:59.000Z

478

STATUS REPORT FOR MOISTURE EFFECTS ON COMPACTION OF FIBERBOARD IN A 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Compaction of lower layers in the fiberboard overpack has been observed in 9975 packages that contain elevated moisture. Lab testing has resulted in a better understanding of the relationship between the fiberboard moisture level and compaction of the lower fiberboard assembly, and the behavior of the fiberboard during transport. In laboratory tests, higher moisture content has been shown to correspond to higher total compaction of fiberboard material, greater rate of compaction, and continued compaction over a longer period of time. In addition, laboratory tests have shown that the application of a dynamic load results in higher fiberboard compaction. The test conditions and sample geometric/loading configurations were chosen to simulate the regulatory requirements for 9975 package input dynamic loading. Dynamic testing was conducted over a period of six months to acquire immediate and cumulative changes in geometric data for various moisture levels. Currently, one sample set has undergone a complete dynamic test regimen, while testing of another set is still in-progress. The dynamic input, data acquisition, test effects on sample dynamic parameters, and interim results from this test program are summarized and compared to regulatory specifications for dynamic loading. This will provide a basis from which to evaluate the impact of moisture and fiberboard compaction on the safety basis for transportation (Safety Analysis Report for Packaging) and storage (facility Documented Safety Analysis) at the Savannah River Site (SRS).

Stefek, T.; Daugherty, W.; Estochen, E.

2011-06-23T23:59:59.000Z

479

WHITE PAPER: DEMONSTRATION OF EQUIVALENCY OF CANE AND SOFTWOOD BASED CELOTEX FOR 9975 PACKAGING  

SciTech Connect (OSTI)

Cane-based Celotex{trademark} has been used extensively in various DOE packages as a thermal insulator and impact absorber. Cane-based Celotex{trademark} for the 9975 was manufactured by Knight-Celotex Fiberboard at their Marrero Plant in Louisiana. However, Knight-Celotex Fiberboard shut down their Marrero Plant in early 2007 due to impacts from hurricane Katrina and other economic factors. Therefore, cane-based Celotex{trademark} is no longer available for use in the manufacture of new 9975 packages. Knight-Celotex Fiberboard has Celotex{trademark} manufacturing plants in Danville, VA and Sunbury, PA that use softwood and hardwood, respectively, as a raw material in the manufacturing of Celotex{trademark}. The purpose of this White Paper is to demonstrate that softwood-based Celotex{trademark} from the Knight-Celotex Danville Plant has performance equivalent to cane-based Celotex{trademark} from the Knight-Celotex Marrero Plant for transportation in a 9975 package.

Varble, J

2007-11-20T23:59:59.000Z

480

HI's Web-based Standards "packages" will provide you with all of the Stand  

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

HI's Web-based Standards "packages" will provide you with all of the Standards appropriate for HI's Web-based Standards "packages" will provide you with all of the Standards appropriate for a specific pump technology. Select the package that is right for your business and the number of simultaneous users ("seats") you desire, and the state of the art, solution-oriented content you require will be at your fingertips. Your "Standards by Subscription" are full version Standards, authoritative and comprehensive. Content is concise, easy to read, searchable, and always up to date. Importantly, your HI subscription will enable company-wide access to your Standards package for one or more simultaneous users. Your selections will be available 24/7 on the Web, or downloadable for local viewing or printing, from anywhere in the

Note: This page contains sample records for the topic "reheat packaged single-zone" 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.