Testing Accuracy and Repeatability of UAV Blocks Oriented with GNSS-Supported Aerial Triangulation

Directory of Open Access Journals (Sweden)

Francesco Benassi

2017-02-01

Full Text Available UAV Photogrammetry today already enjoys a largely automated and efficient data processing pipeline. However, the goal of dispensing with Ground Control Points looks closer, as dual-frequency GNSS receivers are put on board. This paper reports on the accuracy in object space obtained by GNSS-supported orientation of four photogrammetric blocks, acquired by a senseFly eBee RTK and all flown according to the same flight plan at 80 m above ground over a test field. Differential corrections were sent to the eBee from a nearby ground station. Block orientation has been performed with three software packages: PhotoScan, Pix4D and MicMac. The influence on the checkpoint errors of the precision given to the projection centers has been studied: in most cases, values in Z are critical. Without GCP, the RTK solution consistently achieves a RMSE of about 2–3 cm on the horizontal coordinates of checkpoints. In elevation, the RMSE varies from flight to flight, from 2 to 10 cm. Using at least one GCP, with all packages and all test flights, the geocoding accuracy of GNSS-supported orientation is almost as good as that of a traditional GCP orientation in XY and only slightly worse in Z.

CompareTests-R package

Science.gov (United States)

CompareTests is an R package to estimate agreement and diagnostic accuracy statistics for two diagnostic tests when one is conducted on only a subsample of specimens. A standard test is observed on all specimens.

Directory of transport packaging test facilities

International Nuclear Information System (INIS)

1983-08-01

Radioactive materials are transported in packagings or containers which have to withstand certain tests depending on whether they are Type A or Type B packagings. In answer to a request by the International Atomic Energy Agency, 13 Member States have provided information on the test facilities and services existing in their country which can be made available for use by other states by arrangement for testing different kinds of packagings. The directory gives the technical information on the facilities, the services, the tests that can be done and in some cases even the financial arrangement is included

lmerTest Package: Tests in Linear Mixed Effects Models

DEFF Research Database (Denmark)

Kuznetsova, Alexandra; Brockhoff, Per B.; Christensen, Rune Haubo Bojesen

2017-01-01

One of the frequent questions by users of the mixed model function lmer of the lme4 package has been: How can I get p values for the F and t tests for objects returned by lmer? The lmerTest package extends the 'lmerMod' class of the lme4 package, by overloading the anova and summary functions...... by providing p values for tests for fixed effects. We have implemented the Satterthwaite's method for approximating degrees of freedom for the t and F tests. We have also implemented the construction of Type I - III ANOVA tables. Furthermore, one may also obtain the summary as well as the anova table using...

Radioactive material package testing capabilities at Sandia National Laboratories

International Nuclear Information System (INIS)

Uncapher, W.L.; Hohnstreiter, G.F.

1995-01-01

Evaluation and certification of radioactive and hazardous material transport packages can be accomplished by subjecting these packages to normal transport and hypothetical accident test conditions. The regulations allow package designers to certify packages using analysis, testing, or a combination of analysis and testing. Testing can be used to substantiate assumptions used in analytical models and to demonstrate package structural and thermal response. Regulatory test conditions include impact, puncture, crush, penetration, water spray, immersion, and thermal environments. Testing facilities are used to simulate the required test conditions and provide measurement response data. Over the past four decades, comprehensive testing facilities have been developed at Sandia National Laboratories to perform a broad range of verification and certification tests on hazardous and radioactive material packages or component sections. Sandia's facilities provide an experience base that has been established during the development and certification of many package designs. These unique facilities, along with innovative instrumentation data collection capabilities and techniques, simulate a broad range of testing environments. In certain package designs, package testing can be an economical alternative to complex analysis to resolve regulatory questions or concerns

49 CFR 173.465 - Type A packaging tests.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Type A packaging tests. 173.465 Section 173.465 Transportation Other Regulations Relating to Transportation PIPELINE AND HAZARDOUS MATERIALS SAFETY... SHIPMENTS AND PACKAGINGS Class 7 (Radioactive) Materials § 173.465 Type A packaging tests. (a) The packaging...

CRRES microelectronics test package (MEP)

International Nuclear Information System (INIS)

Mullen, E.G.; Ray, K.P.

1993-01-01

The Microelectronics Test Package (MEP) flown on board the Combined Release and Radiation Effects Satellite (CRRES) contained over 60 device types and approximately 400 total devices which were tested for both single event upset (SEU) and total dose (parametric degradation and annealing). A description of the experiment, the method of testing devices, and the structure of data acquisition are presented. Sample flight data are shown. These included SEUs from a GaAs 1 K RAM during the March 1991 solar flare, and a comparison between passive shielding and a specially designed spot shielding package

WIPP waste package testing on simulated DHLW: emplacement

International Nuclear Information System (INIS)

Molecke, M.A.

1984-01-01

Several series of simulated (nonradioactive) defense high-level waste (DHLW) package tests have been emplaced in the WIPP, a research and development facility authorized to demonstrate the safe disposal of defense-related wastes. The primary purpose of these 3-to-7 year duration tests is to evaluate the in situ materials performance of waste package barriers (canisters, overpacks, backfills, and nonradioactive DHLW glass waste form) for possible future application to a licensed waste repository in salt. This paper describes all test materials, instrumentation, and emplacement and testing techniques, and discusses progress of the various tests. These tests are intended to provide information on materials behavior (i.e., corrosion, metallurgical and geochemical alterations, waste form durability, surface interactions, etc.), as well as comparison between several waste package designs, fabrications details, and actual costs. These experiments involve 18 full-size simulated DHLW packages (approximately 3.0 m x 0.6 m diameter) emplaced in vertical boreholes in the salt drift floor. Six of the test packages contain internal electrical heaters (470 W/canister), and were emplace under approximately reference DHLW repository conditions. Twelve other simulated DHLW packages were emplaced under accelerated-aging or overtest conditions, including the artificial introduction of brine, and a thermal loading approximately three to four times higher than reference. Eight of these 12 test packages contain 1500 W/canister electrical heaters; the other four are filled with DHLW glass. 9 refs., 1 fig

Recent package testing successes at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Ludwig, S.B.; Singley, P.T.; Michelhaugh, R.D.; Hawk, M.B.; Shappert, L.B.

2004-01-01

Oak Ridge National Laboratory (ORNL)'s history of testing of radioactive material packages dates back to the early 1960s, and includes the testing of hundreds of different packages of all shapes and sizes. This paper provides an overview of ORNL's new Packaging Research Facility (PRF) at the National Transportation Research Center (NTRC), and describes recent package testing successes conducted at the NTRC from September 2002 to September 2003

Fire testing for package approval

International Nuclear Information System (INIS)

Burgess, M.H.; Fry, C.J.

1990-01-01

The IAEA Transport Regulations require packaging systems for radioactive material to survive transport accidents without a significant increase in hazard to members of the public. Tests used to demonstrate this include a fire or 'thermal' test which may be a practical demonstration or based on calculations. Work at Winfrith, involving the development of computer models and pool fire techniques, has given an improved understanding of physical processes. This has been used to improve computer models and pool fire techniques. The paper covers the regulatory requirements for fire testing, the basic physics of fires, practical tests, computer modelling and their applications to package design. We have confidence in our ability to predict temperatures and other conditions in accident situations and can illustrate the important features of fires with experimental evidence. (author)

Destructive testing of transport packaging. Quality assurance applied to transport packaging in the USA

International Nuclear Information System (INIS)

Barker, R.F.

1976-01-01

This paper discusses several aspects of quality assurance as applied to packaging, including such requirements for an adequate quality assurance program as assignment of responsibilities, inspections, and audits. In certain cases, we have determined the margin of safety inherent in specific package designs. Testing of packaging to destruction, by subjecting it to conditions far beyond the present accident criteria, was carried out to establish the levels of impact, puncture, crush, and fire at which present designs would fail. A second area in which the Nuclear Regulatory Commission has applied quality assurance is qualification testing. The standards for testing prototypes require essentially no loss of contents under the specified accident test conditions. Qualifying a design with an acceptable degree of reliability by testing it at the specified stress levels with no measurable effect requires large numbers of samples to be tested. Testing the prototype under conditions well above the criteria is shown to offer one of the most effective means of demonstrating the adequacy of a design. Scenario tests, i.e., staged accidents or full-scale tests in which vehicles with samples of packages on board are crashed under specified conditions, in most cases present singular points on a curve. One-point tests in most cases will disprove a package design if it fails but may not confirm that a design will not fail. At the same time, much information and some public assurances can be obtained from such tests. (author)

Drop testing of the Westinghouse fresh nuclear fuel package

International Nuclear Information System (INIS)

Shappert, L.B.; Sanders, C.F.

1993-01-01

The Westinghouse Columbia Fuel Fabrication Facility has decided to develop and certify a new fresh fuel package design (type A, fissile) that has the capability to transport more highly enriched fuel than was previously possible. A prototype package was tested in support of the Safety Analysis Report of the Packaging (SARP). This paper provides detailed information on the tests and test results. A first prototype test was carried out at the STF, and the design did not give the safety margin that Westinghouse wanted for their containers. The data from the test were used to redesign the connection between the clamping frame and the pressure pad, and the tests were reinitiated. Three packages were then tested at the STF. All packages met the acceptance criteria and acceleration information was obtained that provided an indication of the behavior of the cradle and strongback which holds the fuel assemblies and nuclear poison in place. (J.P.N.)

Nuclear-waste-package materials degradation modes and accelerated testing

International Nuclear Information System (INIS)

1981-09-01

This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

The development of a digital signal processing and plotting package to support testing of hazardous and radioactive material packages

International Nuclear Information System (INIS)

Ludwigsen, J.S.; Uncapher, W.L.; Arviso, M.; Lattier, C.N.; Hankinson, M.; Cannone, D.J.

1995-01-01

Federal regulations allow package designers to use analysis, testing, or a combination of analysis and testing to support certification of packages used to transport hazardous or radioactive materials. In recent years, many certified packages were subjected to a combination of analysis and testing. A major part of evaluating structural or thermal package response is the collection, reduction and presentation of instrumentation measurement data. Sandia National Laboratories, under the sponsorship of the US Department of Energy, has developed a comprehensive analysis and plotting package (known as KAPP) that performs digital signal processing of both transient structural and thermal data integrated with a comprehensive plotting package designed to support radioactive material package testing

Hermeticity testing of MEMS and microelectronic packages

CERN Document Server

Costello, Suzanne

2013-01-01

Packaging of microelectronics has been developing since the invention of the transistor in 1947. With the increasing complexity and decreasing size of the die, packaging requirements have continued to change. A step change in package requirements came with the introduction of the Micro-Electro-Mechanical System (MEMS) whereby interactions with the external environment are, in some cases, required.This resource is a rapid, definitive reference on hermetic packaging for the MEMS and microelectronics industry, giving practical guidance on traditional and newly developed test methods. This book in

Radioactive material package seal tests

International Nuclear Information System (INIS)

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

1990-01-01

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 x 10 -7 std cm 3 /s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab

Radioactive material package test standards and performance requirements - public perception

International Nuclear Information System (INIS)

Pope, R.B.; Shappert, L.B.; Rawl, R.R.

1992-01-01

This paper addresses issues related to the public perception of the regulatory test standards and performance requirements for packaging and transporting radioactive material. Specifically, it addresses the adequacy of the package performance standards and testing for Type B packages, which are those packages designed for transporting the most hazardous quantities and forms of radioactive material. Type B packages are designed to withstand accident conditions in transport. To improve public perception, the public needs to better understand: (a) the regulatory standards and requirements themselves, (b) the extensive history underlying their development, and (c) the soundness of the technical foundation. The public needs to be fully informed on studies, tests, and analyses that have been carried out worldwide and form the basis of the regulatory standards and requirements. This paper provides specific information aimed at improving the public perception of packages test standards

Qualification test of packages for transporting radioactive materials and wastes

International Nuclear Information System (INIS)

Oliveira Santos, P. de; Miaw, S.T.W.

1990-01-01

Since 1979 the Waste Treatment Division of Nuclear Tecnology Development Center has been developed and tested packagings for transporting radioactive materials and wastes. The Division has designed facilities for testing Type A packages in accordance with the adopted regulations. The Division has tested several packages for universities, research centers, industries, INB, FURNAS, etc. (author) [pt

Radioisotope thermoelectric generator licensed hardware package and certification tests

International Nuclear Information System (INIS)

Goldmann, L.H.; Averette, H.S.

1994-01-01

This paper presents the Licensed Hardware package and the Certification Test portions of the Radioisotope Thermoelectric Generator Transportation System. This package has been designed to meet those portions of the Code of Federal Regulations (10 CFR 71) relating to ''Type B'' shipments of radioactive materials. 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 US Department of Energy's Hanford Site near Richland, Washington. The hardware includes independent double containments to prevent the environmental spread of 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 4500 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. These provisions include test ports used in conjunction with helium mass spectrometers to determine seal leakage rates of each containment during the assembly process

Regulatory and extra-regulatory testing to demonstrate radioactive material packaging safety

International Nuclear Information System (INIS)

Ammerman, D.J.

1997-01-01

Packages for the transportation of radioactive material must meet performance criteria to assure safety and environmental protection. The stringency of the performance criteria is based on the degree of hazard of the material being transported. Type B packages are used for transporting large quantities of radioisotopes (in terms of A 2 quantities). These packages have the most stringent performance criteria. Material with less than an A 2 quantity are transported in Type A packages. These packages have less stringent performance criteria. Transportation of LSA and SCO materials must be in open-quotes strong-tightclose quotes packages. The performance requirements for the latter packages are even less stringent. All of these package types provide a high level of safety for the material being transported. In this paper, regulatory tests that are used to demonstrate this safety will be described. The responses of various packages to these tests will be shown. In addition, the response of packages to extra-regulatory tests will be discussed. The results of these tests will be used to demonstrate the high level of safety provided to workers, the public, and the environment by packages used for the transportation of radioactive material

Low-dose irradiation with modified atmosphere packaging for mango against the Oriental Fruit Fly (Diptera: Tephritidae)

Science.gov (United States)

Irradiation and vapor–heating treatments are commonly used to disinfest the Oriental fruit fly, Bactrocera dorsalis (Hendel) (Diptera:Tephritidae), and other pests on mango fruits before export from Thailand to foreign markets. Modified atmosphere packaging (MAP) used during export of mangoes create...

Qualification tests for a type B (U) package

International Nuclear Information System (INIS)

Vieru, G.

2004-01-01

The primary objective for the safety of radioactive materials transport is to protect human health and the environment taking into consideration its potential risks and radiological consequences. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for the safe transport of radioactive materials (RAM) in accordance with the Agency's recommendations as well as other international specialized organizations. The paper will describe the qualification tests performed for a type B (U) package, intended to be used for the transport of the radioactive sources Am-241 and Cs-137. For this kind of package the tests were performed the first time in Romania and include: the water spray test, the 1.2 m free drop test, the stacking test, the penetration test, the 9m free drop test, the thermal test and the submersion under a head of water of at least 15 m. The test facilities used for performing qualification tests for the type B (U) package as well as experience and conclusions will be also presented

The design, construction and testing of packaging

International Nuclear Information System (INIS)

1976-01-01

Essentially uniform regulations, based on the IAEA Regulations for the Safe Transport of Radioactive Materials, have been adopted on a world-wide basis with the aim of ensuring safety in the transport of radioactive and fissile substances by road, rail, sea and air. The application of these regulations over a period of almost 20 years has resulted in practically complete safety in the sense that there has been no evidence of death or injury that could be attributed to the special properties of the material even when consignments were involved in serious accidents. In the regulations, reliance is placed, to the greatest extent possible, on the packaging to provide adequate shielding and containment of the contents under both normal transport and accident conditions. The Agency organized an international seminar in 1971 to consider the performance tests that have to be applied to packaging to demonstrate compliance with the regulatory requirements. The general conclusion was that the testing programme specified in the regulations was adequate for the near future, but that further consideration should be given to assessing the risks presented by the increasing volume of transport. The second international seminar, which is the subject of this report, dealt with all aspects of the design, construction and testing of packaging for the transport both of relatively small quantities of radioactive substances, which are being used to an ever increasing extent for medical and research purposes, and of the much larger quantities arising in various stages of the nuclear fuel cycle. The programme covered the general requirements for packaging; risk assessment for the transport of various radioactive and fissile substances, including plutonium; specific features of the design and construction of packaging; quality assurance; damage simulation tests, including calculational methods and scale-model testing; tests for the retention of shielding and containment after damage; and the

Safety Evaluation of Radioactive Material Transport Package under Stacking Test Condition

International Nuclear Information System (INIS)

Lee, Ju Chan; Seo, Ki Seog; Yoo, Seong Yeon

2012-01-01

Radioactive waste transport package was developed to transport eight drums of low and intermediate level waste(LILW) in accordance with the IAEA and domestic related regulations. The package is classified with industrial package IP-2. IP-2 package is required to undergo a free drop test and a stacking test. After free drop and stacking tests, it should prevent the loss or dispersal of radioactive contents, and loss of shielding integrity which would result in more than 20 % increase in the radiation level at any external surface of the package. The objective of this study is to establish the safety test method and procedure for stacking test and to prove the structural integrities of the IP-2 package. Stacking test and analysis were performed with a compressive load equal to five times the weight of the package for a period of 24 hours using a full scale model. Strains and displacements were measured at the corner fitting of the package during the stacking test. The measured strains and displacements were compared with the analysis results, and there were good agreements. It is very difficult to measure the deflection at the container base, so the maximum deflection of the container base was calculated by the analysis method. The maximum displacement at the corner fitting and deflection at the container base were less than their allowable values. Dimensions of the test model, thickness of shielding material and bolt torque were measured before and after the stacking test. Throughout the stacking test, it was found that there were no loss or dispersal of radioactive contents and no loss of shielding integrity. Thus, the package was shown to comply with the requirements to maintain structural integrity under the stacking condition.

EARLY TESTS OF DRUM TYPE PACKAGINGS - THE LEWALLEN REPORT

Energy Technology Data Exchange (ETDEWEB)

Smith, A.

2010-07-29

The need for robust packagings for radioactive materials (RAM) was recognized from the earliest days of the nuclear industry. The U.S. Department of Energy (DOE) Rocky Flats Plant developed a packaging for shipment of Pu in the early 1960's, which became the U.S. Department of Transportation (DOT) 6M specification package. The design concepts were employed in other early packagings. Extensive tests of these at Savannah River Laboratory (now Savannah River National Laboratory) were performed in 1969 and 1970. The results of these tests were reported in 'Drum and Board-Type Insulation Overpacks of Shipping Packages for Radioactive Materials', by E. E. Lewallen. The Lewallen Report was foundational to design of subsequent drum type RAM packaging. This paper summarizes this important early study of drum type packagings. The Lewallen Report demonstrated the ability packagings employing drum and insulation board overpacks and engineered containment vessels to meet the Type B package requirements. Because of the results of the Lewallen Report, package designers showed high concern for thermal protection of 'Celotex'. Subsequent packages addressed this by following strategies like those recommended by Lewallen and by internal metal shields and supplemental, encapsulated insulation disks, as in 9975. The guidance provide by the Lewallen Report was employed in design of a large number of drum size packagings over the following three decades. With the increased public concern over transportation of radioactive materials and recognition of the need for larger margins of safety, more sophisticated and complex packages have been developed and have replaced the simple packagings developed under the Lewallen Report paradigm.

Is the test of senior friendly/child resistant packaging ethical?

Science.gov (United States)

Bix, Laura; de la Fuente, Javier; Pimple, Kenneth D; Kou, Eric

2009-12-01

Research has documented the drastic reduction of unintentional poisonings of children since the introduction of child resistant (CR) packaging. However, studies also indicate that consumers report difficulty using CR packages, in part because tests which determine the 'senior friendliness' of CR designs that are used throughout the world disallow people with 'overt or obvious' disabilities from being test subjects. Our review of drug package usability suggests that the current tests of CR packaging can and should be revised to correct this problem. We use US legislation, regulation and data to exemplify these points, but the conclusions are applicable to all protocols that include the exclusionary provision.

The CEBAF test package: A symbolic and dynamic test, histogram and parameter package for on- and off-line particle physics data analysis

International Nuclear Information System (INIS)

Wood, S.A.; Abbott, S.

1995-01-01

Nuclear physics data analysis programs often use packages, such as Q, that allow parameter values, test definitions and histogram booking parameters to be controlled at run time through external files or shared memory. Data within a physics analyzer are usually referenced by indices, leading to a high use of equivalence statements and to extra bookkeeping. In the CEBAF Test Package (CTP), parameters, tests and histogram definitions defined in external files all refer to data elements by the same variable names as used in the C or Fortran source code for the analyzer. This is accomplished by requirieng the analyzer developer to open-quotes registerclose quotes each variable and array that is to be accessible by the package. Any registered variable as well as the test and histogram definitions may be dynamically read and modified by tasks that communicate via standard networking calls. As this package is implemented in C and requires only HBOOK and SUN RPC networking, it is highly portable. CTP works with the CEBAF Online Data Acquisition system (CODA), but may be used with other data acquisition systems or stand alone

Analysis of Type A packaging systems based on greater than 400 individual packaging tests

International Nuclear Information System (INIS)

Edling, D.A.

1976-01-01

Type A packagings commonly used within the U.S. were studied to determine their performance with respect to, ''Tests for demonstrating ability to withstand normal conditions of transport,'' (e.g., water spray, free drop (4 ft), penetration, corner drop, and compression). There are several differences in U.S. and IAEA Type A packaging requirements and these are outlined. For purposes of this study, U. S. requirements were used. More than 100 separate packagings (greater than 400 individual tests) were studied and evaluated. Most of these packagings can be divided into four basic groups: steel drums, wooden boxes, fiberboard containers, and steel boxes. The steel drums met all the requirements with a minimum of qualification and restrictions on use. The wooden boxes performed well, with three-way corner construction providing the best results. The Type A performance requirements had a much greater effect on fiberboard packagings (boxes and drums). In most cases penetration of the fiberboard container did occur, but this was dependent on the inner packagings and materials used. Steel boxes offer a wide flexibility in types of construction, materials usable, volumes, and authorized gross weights. Material usage and construction for wooden and fiberboard containers, such as use of plywood in box construction, banding of boxes, and use of ''firm'' cushioning materials within fiberboard containers, are also discussed

A regulator's perspective on physical testing for type B packages

International Nuclear Information System (INIS)

Brach, William E.

2004-01-01

The U.S. Nuclear Regulatory Commission has a great deal of experience certifying Type B transport packages as complying with the regulations in 10 CFR Part 71. With this experience base, supporting risk studies, and with an exceptional historical safety record for transport, we are very confident in both the current regulations and the methods we use to review and certify transportation packages. Nevertheless, we have a responsibility to remain vigilant and review our regulations and implementing practices with a view towards continuous improvement. NRC regulations permit certification through testing, analyses, comparison to similar approved designs, or combinations of these methods. Testing can be further broken into scale models, components, simple models, or full-scale models. NRC does not require full-scale testing for certification of any package; however, many applicants for package certification have conducted a physical testing program to demonstrate that the package design meets the hypothetical accident conditions. The plans for a repository at Yucca Mountain have raised significant interest in the United States of America in transportation of spent fuel, and created a broad stakeholder and public interest in transportation package testing. As an expected large increase in the number of spent fuel transports nears, this interest will likely grow. The technical and regulatory reasons for, or for not, performing tests need to be well understood and communicated to all stakeholders

Leak test method for radioactive material packagings without pressure valve connections

International Nuclear Information System (INIS)

Johnson, S.F.; Stenbaeck, A.

1976-01-01

A leak test method has been developed at Studsvik which provides the possibility of testing Type B packagings unequipped with valves for evacuation or pressurizing. Even large packagings with pressure valve connections can be leak tested by this method. The method is a pressure test method. The test gas comprises a mixture of helium and nitrogen or helium and air. Excess pressure in a valveless packaging is achieved by vaporization of liquid nitrogen. All parts of the packaging or package where leaks might be expected are covered by plastic sheet. Samples of the gas accumulated under the plastic sheets are taken using evacuated glass ampoules which are initially sealed off to a breakable point. The gas samples are measured with a He-mass spectrometer. The sensitivity of this method of leak testing is, in practice, of the order of 10 -7 atmcm 3 s -1 . (author)

16 CFR 1700.20 - Testing procedure for special packaging.

Science.gov (United States)

2010-01-01

... packages shall be tested at room temperature. (2) Child test—(i) Test subjects—(A) Selection criteria. Use... be done in a location that is familiar to the children, for example, their customary nursery school... temperature. 3. Reclosable packages shall be opened and properly resecured one time (or more if appropriate...

ARM Data-Oriented Metrics and Diagnostics Package for Climate Model Evaluation Value-Added Product

Energy Technology Data Exchange (ETDEWEB)

Zhang, Chengzhu [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Xie, Shaocheng [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-10-15

A Python-based metrics and diagnostics package is currently being developed by the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Infrastructure Team at Lawrence Livermore National Laboratory (LLNL) to facilitate the use of long-term, high-frequency measurements from the ARM Facility in evaluating the regional climate simulation of clouds, radiation, and precipitation. This metrics and diagnostics package computes climatological means of targeted climate model simulation and generates tables and plots for comparing the model simulation with ARM observational data. The Coupled Model Intercomparison Project (CMIP) model data sets are also included in the package to enable model intercomparison as demonstrated in Zhang et al. (2017). The mean of the CMIP model can serve as a reference for individual models. Basic performance metrics are computed to measure the accuracy of mean state and variability of climate models. The evaluated physical quantities include cloud fraction, temperature, relative humidity, cloud liquid water path, total column water vapor, precipitation, sensible and latent heat fluxes, and radiative fluxes, with plan to extend to more fields, such as aerosol and microphysics properties. Process-oriented diagnostics focusing on individual cloud- and precipitation-related phenomena are also being developed for the evaluation and development of specific model physical parameterizations. The version 1.0 package is designed based on data collected at ARM’s Southern Great Plains (SGP) Research Facility, with the plan to extend to other ARM sites. The metrics and diagnostics package is currently built upon standard Python libraries and additional Python packages developed by DOE (such as CDMS and CDAT). The ARM metrics and diagnostic package is available publicly with the hope that it can serve as an easy entry point for climate modelers to compare their models with ARM data. In this report, we first present the input data, which

Tests of potential functional barriers for laminated multilayer food packages. Part I: Low molecular weight permeants.

Science.gov (United States)

Simal-Gándara, J; Sarria-Vidal, M; Koorevaar, A; Rijk, R

2000-08-01

The advent of the functional barrier concept in food packaging has brought with it a requirement for fast tests of permeation through potential barrier materials. In such tests it would be convenient for both foodstuffs and materials below the functional barrier (sub-barrier materials) to be represented by standard simulants. By means of inverse gas chromatography, liquid paraffin spiked with appropriate permeants was considered as a potential simulant of sub-barrier materials based on polypropylene (PP) or similar polyolefins. Experiments were performed to characterize the kinetics of the permeation of low molecular weight model permeants (octene, toluene and isopropanol) from liquid paraffin, through a surrogate potential functional barrier (25 microns-thick oriented PP) into the food stimulants olive oil and 3% (w/v) acetic acid. These permeation results were interpreted in terms of three permeation kinetic models regarding the solubility of a particular model permeant in the post-barrier medium (i.e. the food simulant). The results obtained justify the development and evaluation of liquid sub-barrier simulants that would allow flexible yet rigorous testing of new laminated multilayer packaging materials.

Reliability test and failure analysis of high power LED packages

International Nuclear Information System (INIS)

Chen Zhaohui; Zhang Qin; Wang Kai; Luo Xiaobing; Liu Sheng

2011-01-01

A new type application specific light emitting diode (LED) package (ASLP) with freeform polycarbonate lens for street lighting is developed, whose manufacturing processes are compatible with a typical LED packaging process. The reliability test methods and failure criterions from different vendors are reviewed and compared. It is found that test methods and failure criterions are quite different. The rapid reliability assessment standards are urgently needed for the LED industry. 85 0 C/85 RH with 700 mA is used to test our LED modules with three other vendors for 1000 h, showing no visible degradation in optical performance for our modules, with two other vendors showing significant degradation. Some failure analysis methods such as C-SAM, Nano X-ray CT and optical microscope are used for LED packages. Some failure mechanisms such as delaminations and cracks are detected in the LED packages after the accelerated reliability testing. The finite element simulation method is helpful for the failure analysis and design of the reliability of the LED packaging. One example is used to show one currently used module in industry is vulnerable and may not easily pass the harsh thermal cycle testing. (semiconductor devices)

Testing and evaluation of used UF6 shipping packages

International Nuclear Information System (INIS)

Barlow, C.R.; Ziehlke, K.T.; Pryor, W.A.; Housholder, W.R.

1986-01-01

Damage to shipping packages and their components, whether due to normal environmental exposure or because of unforeseen accidents, requires occasional reevaluation and requalification to assure the suitability of the packages for continued service. Pressure tests have been conducted on used 30B cylinders that were involved in a warehouse fire to assess the possible damaging effects of the exposure. Deteriorated and mechanically damaged overpacks which had absorbed large quantities of water in service were subjected to drying tests, foam properties were evaluated, and a rehabilitation procedure was developed to allow return of such packages to service. Protective shipping packages show deterioration with extended service, principally structural damage from rough handling and rust damage from exposure to weather and from storage practices which may promote absorption of water by the insulating foam. The structural and thermal properties of the phenolic foam insulation from used shipping packages were found to be not adversely affected by absorbed water, and they were not degraded by the drying process. In order to slow or avoid continuing rust damage in renovated packages, however, a process was developed for drying the foam in commercial facilities prior to restoration work on used or damaged containers. Two 2-1/2-ton steel transport cylinders, type 30B, were involved in a warehouse fire where portions of the cylinders were estimated to have reached a temperature of 1600 0 F. The cylinders were empty at the time of the fire and thus were not in the protective packages in which full product cylinders are handled while in transit. Hydrostatic burst tests showed that the integrity of the cylinders was not degraded by the fire exposure. They withstood test pressures in excess of 10 times the design pressure, and showed a volume expansion of 30% above the original capacity before rupturing in a completely ductile fashion

The Use of Digital Radiography in the Evaluation of Radioactive Materials. Packaging Performance Testing

International Nuclear Information System (INIS)

May, C; Lawrence Gelder, L; Boyd Howard, B

2007-01-01

New designs of radioactive material shipping packages are required to be evaluated in accordance with 10 CFR Part 71, ''Packaging and Transportation of Radioactive Material''. This paper will discuss the use of digital radiography to evaluate the effects of the tests required by 10 CFR 71.71, Normal Conditions of Transport (NCT), and 10 CFR 71.73, Hypothetical Accident Conditions (HAC). One acceptable means of evaluating packaging performance is to subject packagings to the series of NCT and HAC tests. The evaluation includes a determination of the effect on the packaging by the conditions and tests. That determination has required that packagings be cut and sectioned to learn the actual effects on internal components. Digital radiography permits the examination of internal packaging components without sectioning a package. This allows a single package to be subjected to a series of tests. After each test, the package is digitally radiographed and the effects of particular tests evaluated. Radiography reduces the number of packages required for testing and also reduces labor and materials required to section and evaluate numerous packages. This paper will include a description of the digital radiography equipment used in the testing and evaluation of the 9977 and 9978 packages at SRNL. The equipment is capable of making a single radiograph of a full-sized package in one exposure. Radiographs will be compared to sectioned packages that show actual conditions compared to radiographic images

Test procedure forms for sludge retrieval and packaging

International Nuclear Information System (INIS)

Feigenbutz, L.V.

1994-01-01

This document provides test procedure forms for sludge retrieval and packaging tests in the 305 Cold Test Facility. The completed and approved forms provide all descriptions, criteria and analysis to safely perform sludge equipment tests in the 305 Cold Test Facility

Radioisotope Thermoelectric Generator Transporation System licensed hardware second certification test series and package shock mount system test

International Nuclear Information System (INIS)

Ferrell, P.C.; Moody, D.A.

1995-10-01

This paper presents a summary of two separate drop test a e performed in support of the Radioisotope Thermoelectric Generator (RTG) Transportation System (RTGTS). The first portion of this paper presents the second series of drop testing required to demonstrate that the RTG package design meets the requirements of Title 10, Code of Federal Regulations, ''Part 71'' (10 CFR 71). Results of the first test series, performed in July 1994, demonstrated that some design changes were necessary. The package design was modified to improve test performance and the design changes were incorporated into the Safety Analysis Report for Packaging (SARP). The second full-size certification test article (CTA-2) incorporated the modified design and was tested at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. With the successful completion of the test series, and pending DOE Office of Facility Safety Analysis approval of the SARP, a certificate of compliance will be issued for the RTG package allowing its use. The second portion of this paper presents the design and testing of the RTG Package Mount System. The RTG package mount was designed to protect the RTG from excessive vibration during transport, provide shock protection during on/off loading, and provide a mechanism for moving the RTG package with a forklift. Military Standard (MIL-STD) 810E, Transit Drop Procedure (DOE 1989), was used to verify that the shock limiting system limited accelerations in excess of 15 G's at frequencies below 150 Hz. Results of the package mount drop tests indicate that an impact force of 15 G's was not exceeded in any test from a free drop height of 457 mm (18 in.)

Improving package structure of object-oriented software using multi-objective optimization and weighted class connections

Directory of Open Access Journals (Sweden)

Amarjeet

2017-07-01

Full Text Available The software maintenance activities performed without following the original design decisions about the package structure usually deteriorate the quality of software modularization, leading to decay of the quality of the system. One of the main reasons for such structural deterioration is inappropriate grouping of source code classes in software packages. To improve such grouping/modular-structure, previous researchers formulated the software remodularization problem as an optimization problem and solved it using search-based meta-heuristic techniques. These optimization approaches aimed at improving the quality metrics values of the structure without considering the original package design decisions, often resulting into a totally new software modularization. The entirely changed software modularization becomes costly to realize as well as difficult to understand for the developers/maintainers. To alleviate this issue, we propose a multi-objective optimization approach to improve the modularization quality of an object-oriented system with minimum possible movement of classes between existing packages of original software modularization. The optimization is performed using NSGA-II, a widely-accepted multi-objective evolutionary algorithm. In order to ensure minimum modification of original package structure, a new approach of computing class relations using weighted strengths has been proposed here. The weights of relations among different classes are computed on the basis of the original package structure. A new objective function has been formulated using these weighted class relations. This objective function drives the optimization process toward better modularization quality simultaneously ensuring preservation of original structure. To evaluate the results of the proposed approach, a series of experiments are conducted over four real-worlds and two random software applications. The experimental results clearly indicate the effectiveness

Test anxiety, perfectionism, goal orientation, and academic performance.

Science.gov (United States)

Eum, KoUn; Rice, Kenneth G

2011-03-01

Dimensions of perfectionism and goal orientation have been reported to have differential relationships with test anxiety. However, the degree of inter-relationship between different dimensions of perfectionism, the 2 × 2 model of goal orientations proposed by Elliot and McGregor, cognitive test anxiety, and academic performance indicators is not known. Based on data from 134 university students, we conducted correlation and regression analyses to test associations between adaptive and maladaptive perfectionism, four types of goal orientations, cognitive test anxiety, and two indicators of academic performance: proximal cognitive performance on a word list recall test and distal academic performance in terms of grade point average. Cognitive test anxiety was inversely associated with both performance indicators, and positively associated with maladaptive perfectionism and avoidance goal orientations. Adaptive and maladaptive perfectionism accounted for significant variance in cognitive test anxiety after controlling for approach and avoidance goal orientations. Overall, nearly 50% of the variance in cognitive test anxiety could be attributed to gender, goal orientations, and perfectionism. Results suggested that students who are highly test anxious are likely to be women who endorse avoidance goal orientations and are maladaptively perfectionistic.

44 years of testing radioactive materials packages at ORNL

Energy Technology Data Exchange (ETDEWEB)

Shappert, L.B.; Ludwig, S.B. [Oak Ridge National Lab., Oak Ridge, TN (United States)

2004-07-01

This paper briefly reviews the package testing at the Oak Ridge National Laboratory (ORNL) since 1960 and then examines the trends in the testing activities that occurred during the same period. Radioactive material shipments have been made from ORNL since the 1940s. The first fully operating reactor built at the ORNL site was patterned after the graphite pile constructed by Enrico Fermi under Stagg Field in Chicago. After serving as a test bed for future reactors, it became useful as a producer of radioactive isotopes. The Isotopes Division was established at ORNL to furnish radioactive materials used in the medical community. Often these shipments have been transported by aircraft worldwide due to the short half-lives of many of the materials. This paper touches briefly on the lighter and smaller radioisotope packages that were being shipped from ORNL in large numbers and then deals with the testing of packages designed to handle large radioactive sources, such as spent fuel, and other fissile materials.

44 years of testing radioactive materials packages at ORNL

International Nuclear Information System (INIS)

Shappert, L.B.; Ludwig, S.B.

2004-01-01

This paper briefly reviews the package testing at the Oak Ridge National Laboratory (ORNL) since 1960 and then examines the trends in the testing activities that occurred during the same period. Radioactive material shipments have been made from ORNL since the 1940s. The first fully operating reactor built at the ORNL site was patterned after the graphite pile constructed by Enrico Fermi under Stagg Field in Chicago. After serving as a test bed for future reactors, it became useful as a producer of radioactive isotopes. The Isotopes Division was established at ORNL to furnish radioactive materials used in the medical community. Often these shipments have been transported by aircraft worldwide due to the short half-lives of many of the materials. This paper touches briefly on the lighter and smaller radioisotope packages that were being shipped from ORNL in large numbers and then deals with the testing of packages designed to handle large radioactive sources, such as spent fuel, and other fissile materials

Drop testing of the Westinghouse fresh nuclear fuel package

International Nuclear Information System (INIS)

Shappert, L.B.; Sanders, C.F.

1992-01-01

In recent years, the Westinghouse Columbia Fuel Fabrication Facility has been faced with increasing pressure from utilities that wished to take the fuel in their nuclear power plants to higher burnups. To help accommodate this trend, Westinghouse has determined that it needs the ability to increase the enrichment of the fresh fuel it delivers to its customers. One critical step in this process is to certify a new (Type A, fissile) fresh fuel package design that has the capability to transport fuel with a higher enrichment than was previously available. A prototype package was tested in support of the Safety Analysis Report of the Packaging. This paper provides detailed information on those tests and their results

Demonstration tests for low level radioactive waste packaging safety

International Nuclear Information System (INIS)

Nagano, I.; Shimura, S.; Miki, T.; Tamamura, T.; Kunitomi, K.

1993-01-01

The transport packaging for low level radioactive waste (so-called the LLW packaging) has been developed to be utilized for transportation of LLW in 200 liter-drums from Japanese nuclear power stations to the LLW Disposal Center at Rokkashomura in Aomori Prefecture. Transportation is expected to start from December in 1992. We will explain the brief history of the development, technical features and specifications as well as two kinds of safety demonstration tests, namely one is '1.2 meter free drop test' and the other is 'ISO container standard test'. (J.P.N.)

An ARM data-oriented diagnostics package to evaluate the climate model simulation

Science.gov (United States)

Zhang, C.; Xie, S.

2016-12-01

A set of diagnostics that utilize long-term high frequency measurements from the DOE Atmospheric Radiation Measurement (ARM) program is developed for evaluating the regional simulation of clouds, radiation and precipitation in climate models. The diagnostics results are computed and visualized automatically in a python-based package that aims to serve as an easy entry point for evaluating climate simulations using the ARM data, as well as the CMIP5 multi-model simulations. Basic performance metrics are computed to measure the accuracy of mean state and variability of simulated regional climate. The evaluated physical quantities include vertical profiles of clouds, temperature, relative humidity, cloud liquid water path, total column water vapor, precipitation, sensible and latent heat fluxes, radiative fluxes, aerosol and cloud microphysical properties. Process-oriented diagnostics focusing on individual cloud and precipitation-related phenomena are developed for the evaluation and development of specific model physical parameterizations. Application of the ARM diagnostics package will be presented in the AGU session. This work is performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344, IM release number is: LLNL-ABS-698645.

Crush Testing at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Feldman, Matthew R.

2011-01-01

The dynamic crush test is required in the certification testing of some small Type B transportation packages. International Atomic Energy Agency regulations state that the test article must be 'subjected to a dynamic crush test by positioning the specimen on the target so as to suffer maximum damage.' Oak Ridge National Laboratory (ORNL) Transportation Technologies Group performs testing of Type B transportation packages, including the crush test, at the National Transportation Research Center in Knoxville, Tennessee (United States). This paper documents ORNL's experiences performing crush tests on several different Type B packages. ORNL has crush tested five different drum-type package designs, continuing its 60 year history of RAM package testing. A total of 26 crush tests have been performed in a wide variety of package orientations and crush plate CG alignments. In all cases, the deformation of the outer drum created by the crush test was significantly greater than the deformation damage caused by the 9 m drop test. The crush test is a highly effective means for testing structural soundness of smaller nondense Type B shipping package designs. Further regulatory guidance could alleviate the need to perform the crush test in a wide range of orientations and crush plate CG alignments.

Data package for the Turkey Point material interaction test capsules

International Nuclear Information System (INIS)

Krogness, J.C.; Davis, R.B.

1979-01-01

Objective of the Materials Interaction Test (MIT) is to obtain interaction information on candidate package storage materials and geologies under prototypic temperatures in gamma and low level neutron fields. Compatibility, structural properties, and chemical transformations will be studied. The multiple test samples are contained within test capsules connected end-to-end to form a test train. Only passive instrumentation has been used to monitor temperatures and record neutron fluence. The test train contains seven capsules: three to test compatibility, two for structural tests, and two for chemical transformation studies. The materials tested are potential candidates for the spent fuel package canister and repository geologies

Model 9975 Life Extension Test Package 3 - Interim Report - January 2017

Energy Technology Data Exchange (ETDEWEB)

Daugherty, W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-01-31

Life extension package LE3 (9975-03203) has been instrumented and subjected to an elevated temperature environment for approximately 8 years. During this time, the cane fiberboard has been maintained at a maximum temperature of ~160 - 165 °F, which was established by a combination of internal (19 watts) and external heat sources. Several tests and parameters were used to characterize the package components. Results from these tests generally indicate agreement between this full-scale shipping package and small-scale laboratory tests on fiberboard samples, including the degradation models based on the laboratory tests. These areas of agreement include the rate of change of fiberboard weight, dimensions and density, and change in fiberboard thermal conductivity. Corrosion of the lead shield occurred at a high rate during the first several weeks of aging, but dropped significantly after most of the moisture in the fiberboard migrated away from the lead shield. Dimensional measurements of the lead shield indicate that no significant creep deformation has occurred. This is consistent with literature data that predict a very small creep deformation for the time at temperature experienced by this package. The SCV O-rings were verified to remain leak-tight after ~5 years aging at an average temperature of ~170 °F. This package provides an example of the extent to which moisture within a typical fiberboard assembly can redistribute in the presence of a temperature gradient such as might be created by a 19 watt internal heat load. The majority of water within the fiberboard migrated to the bottom layers of fiberboard, with approximately 2 kg of water (2 liters) eventually escaping from the package. Two conditions have developed that are not consistent with package certification requirements. The axial gap at the top of the package increased to a maximum value of 1.549 inches, exceeding the 1 inch criterion. In addition, staining and/or corrosion have formed in a few spots

Test facilities for radioactive material transport packages (AEA Technology, Winfrith, UK)

International Nuclear Information System (INIS)

Burgess, M.H.

1991-01-01

Transport packages for radioactive materials are tested to demonstrate compliance with national and international regulations. The involvement of AEA Technology is traced from the establishment of the early IAEA Regulations. Transport package design, testing, assessment and approval requires a wide variety of skills and facilities. The comprehensive capability of AEA Technology in these areas is described with references to practical experience in the form of a short bibliography. The facilities described include drop-test cranes and targets (up to 700te); air guns for impacts up to sonic velocities; pool fires, furnaces and rigs for thermal tests including heat dissipation on prototype flasks; shielding facilities and instruments; criticality simulations and leak test instruments. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

The design, construction and testing of packaging[Radioactive materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-07-01

Essentially uniform regulations, based on the IAEA Regulations for the Safe Transport of Radioactive Materials, have been adopted on a world-wide basis with the aim of ensuring safety in the transport of radioactive and fissile substances by road, rail, sea and air. The application of these regulations over a period of almost 20 years has resulted in practically complete safety in the sense that there has been no evidence of death or injury that could be attributed to the special properties of the material even when consignments were involved in serious accidents. In the regulations, reliance is placed, to the greatest extent possible, on the packaging to provide adequate shielding and containment of the contents under both normal transport and accident conditions. The Agency organized an international seminar in 1971 to consider the performance tests that have to be applied to packaging to demonstrate compliance with the regulatory requirements. The general conclusion was that the testing programme specified in the regulations was adequate for the near future, but that further consideration should be given to assessing the risks presented by the increasing volume of transport. The second international seminar, which is the subject of this report, dealt with all aspects of the design, construction and testing of packaging for the transport both of relatively small quantities of radioactive substances, which are being used to an ever increasing extent for medical and research purposes, and of the much larger quantities arising in various stages of the nuclear fuel cycle. The programme covered the general requirements for packaging; risk assessment for the transport of various radioactive and fissile substances, including plutonium; specific features of the design and construction of packaging; quality assurance; damage simulation tests, including calculational methods and scale-model testing; tests for the retention of shielding and containment after damage; and the

DOT-7A packaging test procedure

International Nuclear Information System (INIS)

Kelly, D.L.

1995-01-01

This test procedure documents the steps involved with performance testing of Department of Transportation Specification 7A (DOT-7A) Type A packages. It includes description of the performance tests, the personnel involved, appropriate safety considerations, and the procedures to be followed while performing the tests. Westinghouse Hanford Company (WHC) is conducting the evaluation and testing discussed herein for the Department of Energy-Headquarters, Division of Quality Verification and Transportation Safety (EH-321). Please note that this report is not in WHC format. This report is being submitted through the Engineering Documentation System so that it may be used for reference and information purposes

Certification testing of the MOX Fresh Fuel Package (MFFP)

International Nuclear Information System (INIS)

Nichols, J.C. III; Yapuncich, F.L.

2004-01-01

Packaging Technology, Inc. (PacTec) is designing the MFFP as part of the Duke, COGEMA, Stone and Webster (DCS) consortium. DCS is tasked with providing the Department of Energy (DOE) with domestic MOX fuel fabrication and reactor irradiation services for the purpose of disposing of surplus weapons usable plutonium. This paper will discuss the development of the MFFP certification test program. The MFFP was subjected to a total of eleven free and puncture drops of the course of the certification testing. Because of the plutonium content, the design must be a Type BF, which among other things requires a containment boundary with a tested leakage rate of 1 x 10 -7 cm 3 /s air at 1 atm absolute and 25 C, or less. Both economics (desire for maximized payload) and operational (conveyance mode restricts size and weight) constraints lead to a highly optimized design. The optimized package design led to a significant test program which needed to address the containment boundary stability, puncture resistance of the package and lid end impact limiter, structural performance of the light weight lid structure, and stability of the internal structures. The test program efficiently balanced the test objectives while minimizing the number of costly hardware items used during this destructive testing. This balance achieved by strategic replacement of mock and prototypic payloads, impact limiters, and by careful test order considerations. The paper will conclude with a selected summary of the testing and an assessment of the test programs thoroughness

School food environment: Quality and advertisement frequency of child-oriented packaged products within walking distance of public schools.

Science.gov (United States)

Missbach, Benjamin; Pachschwöll, Caterina; Kuchling, Daniel; König, Jürgen

2017-06-01

Food marketing for children is a major concern for public health nutrition and many schools make efforts to increase healthy eating. Food environments surrounding schools in urban areas may undermine these efforts for healthy nutrition within school programs. Our study aim is to describe the nutrition environment within walking distance of schools in terms of food quality and food marketing and to explore the degree to which elements of the nutrition environment varies by proximity to schools. In a cross-sectional study, we analyzed the surrounding food environments of a convenience sample of 46 target schools within 950m walking distance in 7 different urban districts across Vienna, Austria. In total, we analyzed data from 67 fast food outlets and 54 supermarkets analyzing a total of 43.129 packaged snack food and beverage products, from which 85% were for adults and 15% of the products were child-oriented. Proximity to the schools did not affect the availability of child-oriented products and dedicated food advertisements for children. After applying nutrient profiling using the Nutrient Profiling Model (NPM) on child-oriented products, results showed that 15.8% of the packaged snack food were categorized as "healthy" foods and 84.2% as "less healthy"; for beverages 65.7% were categorized as "healthy" and 34.3% as "less healthy". In conclusion, our results show that child-oriented snacks are not more frequently advertised around schools but substantially lack in nutritional quality with the potential to undermine efforts for promoting healthy eating practices within schools.

School food environment: Quality and advertisement frequency of child-oriented packaged products within walking distance of public schools

Directory of Open Access Journals (Sweden)

Benjamin Missbach

2017-06-01

Full Text Available Food marketing for children is a major concern for public health nutrition and many schools make efforts to increase healthy eating. Food environments surrounding schools in urban areas may undermine these efforts for healthy nutrition within school programs. Our study aim is to describe the nutrition environment within walking distance of schools in terms of food quality and food marketing and to explore the degree to which elements of the nutrition environment varies by proximity to schools. In a cross-sectional study, we analyzed the surrounding food environments of a convenience sample of 46 target schools within 950m walking distance in 7 different urban districts across Vienna, Austria. In total, we analyzed data from 67 fast food outlets and 54 supermarkets analyzing a total of 43.129 packaged snack food and beverage products, from which 85% were for adults and 15% of the products were child-oriented. Proximity to the schools did not affect the availability of child-oriented products and dedicated food advertisements for children. After applying nutrient profiling using the Nutrient Profiling Model (NPM on child-oriented products, results showed that 15.8% of the packaged snack food were categorized as “healthy” foods and 84.2% as “less healthy”; for beverages 65.7% were categorized as “healthy” and 34.3% as “less healthy”. In conclusion, our results show that child-oriented snacks are not more frequently advertised around schools but substantially lack in nutritional quality with the potential to undermine efforts for promoting healthy eating practices within schools.

Waste package materials testing for a salt repository: 1983 status summary report

International Nuclear Information System (INIS)

Moak, D.P.

1986-09-01

The United States plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy is sponsoring research on the designing and testing of waste packages and waste package materials. This fiscal year 1983 status report summarizes recent results of waste package materials testing in a salt environment. The results from these tests will be used by waste package designers and performance assessment experts. Release characteristics data are available on two waste forms (spent fuel and waste-containing glass) that were exposed to leaching tests at various radiation levels, temperatures, pH, glass surface area to solution volume ratios, and brine solutions simulating expected salt repository conditions. Candidate materials tested for corrosion resistance and other properties include iron alloys; TI-CODE 12, the most promising titanium alloy for containment; and nickel alloys. In component interaction testing, synergistic effects have not ruled out any candidate material. 21 refs., 37 figs., 15 tabs

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

Energy Technology Data Exchange (ETDEWEB)

Shull, D.

2012-06-18

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.

STRUCTURAL CALCULATIONS FOR THE LIFTING IN VERTICAL ORIENTATION OF 5-DHLW/DOE SNF SINGLE CRM WASTE PACKAGES

International Nuclear Information System (INIS)

S. Mastilovic

1999-01-01

The purpose of this activity is to determine the structural response of the extension of outer shell (which is referred to as skirt throughout this document) designs of both long and short design concepts of 5-Defense High-Level Waste (DHLW) Department of Energy (DOE) spent nuclear fuel (SNF) single corrosion resistant material (CRM) waste packages (WP), subjected to a gravitational load in the course of lifting in vertical orientation. The scope of this document is limited to reporting the calculation results in terms of stress intensity magnitudes. This activity is associated with the WP design; calculations are performed by the Waste Package Design group. AP-3.124, Revision 0, ICN 0, Calculations, is used to perform the calculation and develop the document

Design and tests of a package for the transport of radioactive sources

International Nuclear Information System (INIS)

Santos, Paulo de Oliveira

2011-01-01

The Type A package was designed for transportation of seven cobalt-60 sources with total activity of 1 GBq. The shield thickness to accomplish the dose rate and the transport index established by the radioactive transport regulation was calculated by the code MCNP (Monte Carlo N-Particle Transport Code Version 5). The sealed cobalt-60 sources were tested for leakages. according to the regulation ISO 9978:1992 (E). The package was tested according to regulation Radioactive Material Transport CNEN. The leakage tests results pf the sources, and the package tests demonstrate that the transport can be safe performed from the CDTN to the steelmaking industries

Mixed waste chemical compatibility: A testing program for plastic packaging components

International Nuclear Information System (INIS)

Nigrey, P.J.

1995-01-01

The purpose of hazardous and radioactive materials packaging is to enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations in the United States have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified by the US Department of Transportation (DOT, 49 CFR 173) and the US Nuclear Regulatory Commission (NRC, 10 CFR 71). The design requirements for both hazardous [49 CFR 173.24 (e)(1)] and radioactive [49 CFR 173.412 (g)] materials packaging specify packaging compatibility, i.e., that the materials of the packaging at sign d any contents be chemically compatible with each other. Furthermore, Type A [49 CFR 173.412 (g)] and Type B (10 CFR 71.43) packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program attempts to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. This program has been described in considerable detail in an internal SNL document, the Chemical Compatibility Test Plan ampersand Procedure Report (Nigrey 1993)

9978 AND 9975 TYPE B PACKAGING INTERNAL DATA COLLECTION FEASIBILITY TESTING

Energy Technology Data Exchange (ETDEWEB)

Fogle, R.

2012-05-07

The objective of this report is to document the findings from a series of proof-of-concept tests performed by Savannah River National Laboratory (SRNL) R and D Engineering, for the DOE Packaging Certification Program to determine if a viable radio link could be established from within the stainless steel confines of several drum-style DOE certified Type B radioactive materials packagings. Two in-hand, off-the-shelf radio systems were tested. The first system was a Wi-Fi Librestream Onsight{trademark} camera with a Fortress ES820 Access Point and the second was the On-Ramp Wireless Ultra-Link Processing{trademark} (ULP) radio system. These radio systems were tested within the Model 9975 and 9978 Type B packagings at the SRNL. This report documents the test methods and results. A path forward will also be recommended.

Mann-Whitney Type Tests for Microarray Experiments: The R Package gMWT

Directory of Open Access Journals (Sweden)

Daniel Fischer

2015-06-01

Full Text Available We present the R package gMWT which is designed for the comparison of several treatments (or groups for a large number of variables. The comparisons are made using certain probabilistic indices (PI. The PIs computed here tell how often pairs or triples of observations coming from different groups appear in a specific order of magnitude. Classical two and several sample rank test statistics such as the Mann-Whitney-Wilcoxon, Kruskal-Wallis, or Jonckheere-Terpstra test statistics are simple functions of these PI. Also new test statistics for directional alternatives are provided. The package gMWT can be used to calculate the variable-wise PI estimates, to illustrate their multivariate distribution and mutual dependence with joint scatterplot matrices, and to construct several classical and new rank tests based on the PIs. The aim of the paper is first to briefly explain the theory that is necessary to understand the behavior of the estimated PIs and the rank tests based on them. Second, the use of the package is described and illustrated with simulated and real data examples. It is stressed that the package provides a new flexible toolbox to analyze large gene or microRNA expression data sets, collected on microarrays or by other high-throughput technologies. The testing procedures can be used in an eQTL analysis, for example, as implemented in the package GeneticTools.

Problem-Oriented Simulation Packages and Computational Infrastructure for Numerical Studies of Powerful Gyrotrons

International Nuclear Information System (INIS)

Damyanova, M; Sabchevski, S; Vasileva, E; Balabanova, E; Zhelyazkov, I; Dankov, P; Malinov, P

2016-01-01

Powerful gyrotrons are necessary as sources of strong microwaves for electron cyclotron resonance heating (ECRH) and electron cyclotron current drive (ECCD) of magnetically confined plasmas in various reactors (most notably ITER) for controlled thermonuclear fusion. Adequate physical models and efficient problem-oriented software packages are essential tools for numerical studies, analysis, optimization and computer-aided design (CAD) of such high-performance gyrotrons operating in a CW mode and delivering output power of the order of 1-2 MW. In this report we present the current status of our simulation tools (physical models, numerical codes, pre- and post-processing programs, etc.) as well as the computational infrastructure on which they are being developed, maintained and executed. (paper)

Non-destructive testing of electronic component packages

International Nuclear Information System (INIS)

Anderle, C.

1975-01-01

A non-destructive method of investigating packaged parts of semiconductor components by X radiation is described and the relevant theoretical relations limiting this technique are derived. The application of the technique is demonstrated in testing several components. The described method is iNsimple and quick. (author)

Interactions between cask components and content of packaging for the transport of radioactive material during drop tests

International Nuclear Information System (INIS)

Quercetti, T.; Ballheimer, V.; Zeisler, P.; Mueller, K.

2003-01-01

This paper describes the analytical, numerical and experimental investigations on the phenomenon of interactions between cask components and content of packages for the transport of radioactive material during drop tests required according to the IAEA Regulations for the Safe Transport of Radioactive Material. Radial and axial gaps between cask components and content are usually necessary for thermal reasons but larger gaps can exist because of the geometrical dimensions of the specified content. Consequently interactions between content and cask components (lid system, cask body, etc.) are possible and can not be excluded during drop tests. Interactions in this context are relative movements between cask and content which are mainly due to elastic spring effects after releasing the cask for the free drop. These relative movements can cause interior collisions between content and cask during the main impact of the package onto the unyielding target. Drop tests with various types of Type A and Type B packages fully instrumented with strain gauges and accelerometers showed that these interactions respectively interior collisions can be considerable relating to high forces acting on cask lids, lid bolts and the content. Of course the real quantitative consequences of the interactions depend upon different conditions, among others the drop orientation, the design characteristics of the impact limiters, the dimensions of the gaps, the material characteristics of the contents, etc. . In order to investigate more precisely the phenomenon of interactions BAM carried out finite element calculations for the named casks using the ABAQUS/ Standard and ABAQUS/ Explicit computer code comparing them with results obtained from experiments. Additionally, tests with a simplified model instrumented with accelerometers were carried out accompanied by finite element calculations and analytical calculations using MATHEMATICA. The investigations on the mentioned phenomena of interaction

Nuclear waste package materials testing report: basaltic and tuffaceous environments

International Nuclear Information System (INIS)

Bradley, D.J.; Coles, D.G.; Hodges, F.N.; McVay, G.L.; Westerman, R.E.

1983-03-01

The disposal of high-level nuclear wastes in underground repositories in the continental United States requires the development of a waste package that will contain radionuclides for a time period commensurate with performance criteria, which may be up to 1000 years. This report addresses materials testing in support of a waste package for a basalt (Hanford, Washington) or a tuff (Nevada Test Site) repository. The materials investigated in this testing effort were: sodium and calcium bentonites and mixtures with sand or basalt as a backfill; iron and titanium-based alloys as structural barriers; and borosilicate waste glass PNL 76-68 as a waste form. The testing also incorporated site-specific rock media and ground waters: Reference Umtanum Entablature-1 basalt and reference basalt ground water, Bullfrog tuff and NTS J-13 well water. The results of the testing are discussed in four major categories: Backfill Materials: emphasizing water migration, radionuclide migration, physical property and long-term stability studies. Structural Barriers: emphasizing uniform corrosion, irradiation-corrosion, and environmental-mechanical testing. Waste Form Release Characteristics: emphasizing ground water, sample surface area/solution volume ratio, and gamma radiolysis effects. Component Compatibility: emphasizing solution/rock, glass/rock, glass/structural barrier, and glass/backfill interaction tests. This area also includes sensitivity testing to determine primary parameters to be studied, and the results of systems tests where more than two waste package components were combined during a single test

Regulatory concerns for leakage testing of packagings with three O-ring closure seals

International Nuclear Information System (INIS)

Oras, J.J.; Towell, R.H.; Wangler, M.E.

1997-01-01

The American National Standard for Radioactive Materials--Leakage Tests on Packages for Shipment (ANSI N14.5) provides guidance for leakage rate testing to show that a particular packaging complies with regulatory requirements and also provides guidance in determining appropriate acceptance criteria. Recent radioactive packagings designs have incorporated three O-ring closure seals, the middle O-ring being the containment seal. These designs have the potential for false positive results of leakage rate tests. The volume between the containment O-ring and the inner O-ring is used for the helium gas required for the leakage rate tests to reduce both the amount of helium used and the time required to conduct the tests. A leak detector samples the evacuated volume between the outer O-ring and the containment O-ring. False positive results can be caused in two ways, a large leakage in the containment seal or leakage in the inner seal. This paper will describe the problem together with possible solutions/areas that need to be addressed in a Safety Analysis Report for Packagings before a particular packaging design can be certified for transport

49 CFR 173.466 - Additional tests for Type A packagings designed for liquids and gases.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Additional tests for Type A packagings designed...) Materials § 173.466 Additional tests for Type A packagings designed for liquids and gases. (a) In addition to the tests prescribed in § 173.465, Type A packagings designed for liquids and gases must be...

Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

International Nuclear Information System (INIS)

Gillard, J.E.

2001-01-01

Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

Energy Technology Data Exchange (ETDEWEB)

Gillard, J.E

2001-07-01

Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

The quality and testing PH-SFT infrastructure for the external LHC software packages deployment

CERN Multimedia

CERN. Geneva; MENDEZ LORENZO, Patricia; MATO VILA, Pere

2015-01-01

The PH-SFT group is responsible for the build, test, and deployment of the set of external software packages used by the LHC experiments. This set includes ca. 170 packages including Grid packages and Montecarlo generators provided for different versions. A complete build structure has been established to guarantee the quality of the packages provided by the group. This structure includes an experimental build and three daily nightly builds, each of them dedicated to a specific ROOT version including v6.02, v6.04, and the master. While the former build is dedicated to the test of new packages, versions and dependencies (basically SFT internal used), the three latter ones are the responsible for the deployment to AFS of the set of stable and well tested packages requested by the LHC experiments so they can apply their own builds on top. In all cases, a c...

Safe transport of radioactive materials - Leakage testing on packages. 1. ed.

International Nuclear Information System (INIS)

1996-01-01

This International Standard describes a method for relating permissible activity release rates of the radioactive contents carried within a containment system to equivalent gas leakage rates under specified test conditions. This approach is called gas leakage test methodology. However, in this International Standard it is recognized that other methodologies might be acceptable. When other methodologies are to be used, it shall be shown that the methodology demonstrates that any release of the radioactive contents will not exceed the regulatory requirements. The use of any alternative methodology shall be by agreement with the competent authority. This International Standard provides both overall and detailed guidance on the complex relationships between an equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent authority during the Type B package certification process. It should be noted that, for a given package, demonstration of compliance is not limited to a single methodology. While this International Standard does not require particular gas leakage test procedures, it does present minimum requirements for any test that is to be used. It is the responsibility of the package designer or consignor to estimate or determine the maximum permissible release rate of radioactivity to the environment and to select appropriate leakage test procedures that have adequate sensitivity. This International Standard pertains specifically to Type B packages for which the regulatory containment requirements are specified explicitly

Normal conditions of transport thermal analysis and testing of a Type B drum package

International Nuclear Information System (INIS)

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

1995-01-01

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. The type B shipping container used in the study is a double containment fiberboard drum package. The package is primarily used to transport uranium and plutonium metals and oxides. A normal condition of transport (NCT) thermal test was performed to benchmark an NCT analysis of the package. A 21 W heater was placed in an instrumented package to simulate the maximum source decay heat. The package reached thermal equilibrium 120 hours after the heater was turned on. Testing took place indoors to minimize ambient temperature fluctuations. The thermal analysis of the package used fiberboard properties reported in the literature and resulted in temperature significantly greater than those measured during the test. Details of the NCT test will be described and transient temperatures at key thermocouple locations within the package will be presented. Analytical results using nominal fiberboard properties will be presented. Explanations of the results and the attempt to benchmark the analysis will be presented. The discovery that fiberboard has an anisotropic thermal conductivity and its effect on thermal performance will also be discussed

UV protective zinc oxide coating for biaxially oriented polypropylene packaging film by atomic layer deposition

Energy Technology Data Exchange (ETDEWEB)

Lahtinen, Kimmo, E-mail: kimmo.lahtinen@lut.fi [ASTRaL, Lappeenranta University of Technology, Sammonkatu 12, FI-50130 Mikkeli (Finland); Kääriäinen, Tommi, E-mail: tommi.kaariainen@colorado.edu [ASTRaL, Lappeenranta University of Technology, Sammonkatu 12, FI-50130 Mikkeli (Finland); Johansson, Petri, E-mail: petri.johansson@tut.fi [Paper Converting and Packaging Technology, Tampere University of Technology, P.O.Box 589, FI-33101 Tampere (Finland); Kotkamo, Sami, E-mail: sami.kotkamo@tut.fi [Paper Converting and Packaging Technology, Tampere University of Technology, P.O.Box 589, FI-33101 Tampere (Finland); Maydannik, Philipp, E-mail: philipp.maydannik@lut.fi [ASTRaL, Lappeenranta University of Technology, Sammonkatu 12, FI-50130 Mikkeli (Finland); Seppänen, Tarja, E-mail: tarja.seppanen@lut.fi [ASTRaL, Lappeenranta University of Technology, Sammonkatu 12, FI-50130 Mikkeli (Finland); Kuusipalo, Jurkka, E-mail: jurkka.kuusipalo@tut.fi [Paper Converting and Packaging Technology, Tampere University of Technology, P.O.Box 589, FI-33101 Tampere (Finland); Cameron, David C., E-mail: david.cameron@miktech.fi [ASTRaL, Lappeenranta University of Technology, Sammonkatu 12, FI-50130 Mikkeli (Finland)

2014-11-03

Biaxially oriented polypropylene (BOPP) packaging film was coated with zinc oxide (ZnO) coatings by atomic layer deposition (ALD) in order to protect the film from UV degradation. The coatings were made at a process temperature of 100 °C using diethylzinc and water as zinc and oxygen precursors, respectively. The UV protective properties of the coatings were tested by using UV–VIS and infrared spectrometry, differential scanning calorimetry (DSC) and a mechanical strength tester, which characterised the tensile and elastic properties of the film. The results obtained with 36 and 67 nm ZnO coatings showed that the ZnO UV protective layer is able to provide a significant decrease in photodegradation of the BOPP film under UV exposure. While the uncoated BOPP film suffered a complete degradation after a 4-week UV exposure, the 67 nm ZnO coated BOPP film was able to preserve half of its original tensile strength and 1/3 of its elongation at break after a 6-week exposure period. The infrared analysis and DSC measurements further proved the UV protection of the ZnO coatings. The results show that a nanometre scale ZnO coating deposited by ALD is a promising option when a transparent UV protection layer is sought for polymer substrates. - Highlights: • Atomic layer deposited zinc oxide coatings were used as UV protection layers. • Biaxially oriented polypropylene (BOPP) film was well protected against UV light. • Formation of UV degradation products in BOPP was significantly reduced. • Mechanical properties of the UV exposed BOPP film were significantly improved.

Non-Destructive Testing for Control of Radioactive Waste Package

Science.gov (United States)

Plumeri, S.; Carrel, F.

2015-10-01

Characterization and control of radioactive waste packages are important issues in the management of a radioactive waste repository. Therefore, Andra performs quality control inspection on radwaste package before disposal to ensure the compliance of the radwast characteristics with Andra waste disposal specifications and to check the consistency between Andra measurements results and producer declared properties. Objectives of this quality control are: assessment and improvement of producer radwaste packages quality mastery, guarantee of the radwaste disposal safety, maintain of the public confidence. To control radiological characteristics of radwaste package, non-destructive passive methods (gamma spectrometry and neutrons counting) are commonly used. These passive methods may not be sufficient, for instance to control the mass of fissile material contained inside radwaste package. This is particularly true for large concrete hull of heterogeneous radwaste containing several actinides mixed with fission products like 137Cs. Non-destructive active methods, like measurement of photofission delayed neutrons, allow to quantify the global mass of actinides and is a promising method to quantify mass of fissile material. Andra has performed different non-destructive measurements on concrete intermediate-level short lived nuclear waste (ILW-SL) package to control its nuclear material content. These tests have allowed Andra to have a first evaluation of the performance of photofission delayed neutron measurement and to identify development needed to have a reliable method, especially for fissile material mass control in intermediate-level long lived waste package.

ProtPOS: a python package for the prediction of protein preferred orientation on a surface.

Science.gov (United States)

Ngai, Jimmy C F; Mak, Pui-In; Siu, Shirley W I

2016-08-15

Atomistic molecular dynamics simulation is a promising technique to investigate the energetics and dynamics in the protein-surface adsorption process which is of high relevance to modern biotechnological applications. To increase the chance of success in simulating the adsorption process, favorable orientations of the protein at the surface must be determined. Here, we present ProtPOS which is a lightweight and easy-to-use python package that can predict low-energy protein orientations on a surface of interest. It combines a fast conformational sampling algorithm with the energy calculation of GROMACS. The advantage of ProtPOS is it allows users to select any force fields suitable for the system at hand and provide structural output readily available for further simulation studies. ProtPOS is freely available for academic and non-profit uses at http://cbbio.cis.umac.mo/software/protpos Supplementary data are available at Bioinformatics online. shirleysiu@umac.mo. © The Author 2016. Published by Oxford University Press.

Westinghouse Hanford Company package testing capabilities

International Nuclear Information System (INIS)

Hummer, J.H.; Mercado, M.S.

1993-07-01

The Department of Energy's Hanford Site is a 1,450-km 2 (560-mi 2 ) installation located in southeastern Washington State. Established in 1943 as a plutonium production facility, Hanford's role has evolved into one of environmental restoration and remediation. Many of these environmental restoration and remediation activities involve transportation of radioactive/hazardous materials. Packagings used for the transportation of radioactive/hazardous materials must be capable of meeting certain normal transport and hypothetical accident performance criteria. Evaluations of performance to these criteria typically involve a combination of analysis and testing. Required tests may include the free drop, puncture, penetration, compression, thermal, heat, cold, vibration, water spray, water immersion, reduced pressure, and increased pressure tests. The purpose of this paper is to outline the Hanford capabilities for performing each of these tests

DiagTest3Grp: An R Package for Analyzing Diagnostic Tests with Three Ordinal Groups

Directory of Open Access Journals (Sweden)

Jingqin Luo

2012-10-01

Full Text Available Medical researchers endeavor to identify potentially useful biomarkers to develop marker-based screening assays for disease diagnosis and prevention. Useful summary measures which properly evaluate the discriminative ability of diagnostic markers are critical for this purpose. Literature and existing software, for example, R packages nicely cover summary measures for diagnostic markers used for the binary case (e.g., healthy vs. diseased. An intermediate population at an early disease stage usually exists between the healthy and the fully diseased population in many disease processes. Supporting utilities for three-group diagnostic tests are highly desired and important for identifying patients at the early disease stage for timely treatments. However, application packages which provide summary measures for three ordinal groups are currently lacking. This paper focuses on two summary measures of diagnostic accuracy—volume under the receiver operating characteristic surface and the extended Youden index, with three diagnostic groups. We provide the R package DiagTest3Grp to estimate, under both parametric and nonparametric assumptions, the two summary measures and the associated variances, as well as the optimal cut-points for disease diagnosis. An omnibus test for multiple markers and a Wald test for two markers, on independent or paired samples, are incorporated to compare diagnostic accuracy across biomarkers. Sample size calculation under the normality assumption can be performed in the R package to design future diagnostic studies. A real world application evaluating the diagnostic accuracy of neuropsychological markers for Alzheimer’s disease is used to guide readers through step-by-step implementation of DiagTest3Grp to demonstrate its utility.

The ZOOM minimization package

International Nuclear Information System (INIS)

Fischler, Mark S.; Sachs, D.

2004-01-01

A new object-oriented Minimization package is available for distribution in the same manner as CLHEP. This package, designed for use in HEP applications, has all the capabilities of Minuit, but is a re-write from scratch, adhering to modern C++ design principles. A primary goal of this package is extensibility in several directions, so that its capabilities can be kept fresh with as little maintenance effort as possible. This package is distinguished by the priority that was assigned to C++ design issues, and the focus on producing an extensible system that will resist becoming obsolete

Digital Radiography of a Drop Tested 9975 Radioactive Materials Packaging

International Nuclear Information System (INIS)

Blanton, P.S.

2001-01-01

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

tscvh R Package: Computational of the two samples test on microarray-sequencing data

Science.gov (United States)

Fajriyah, Rohmatul; Rosadi, Dedi

2017-12-01

We present a new R package, a tscvh (two samples cross-variance homogeneity), as we called it. This package is a software of the cross-variance statistical test which has been proposed and introduced by Fajriyah ([3] and [4]), based on the cross-variance concept. The test can be used as an alternative test for the significance difference between two means when sample size is small, the situation which is usually appeared in the bioinformatics research. Based on its statistical distribution, the p-value can be also provided. The package is built under a homogeneity of variance between samples.

Test facility of transport packagings for radioactive materials in the St. Petersburg region (Russia)

International Nuclear Information System (INIS)

Guskov, V.D.; Korotkov, G.V.; Drozdov, V.P.; Ershov, V.N.; Yanovskaya, N.S.

2001-01-01

The paper describes the test facility located near St. Petersburg (Russia) where test of packagings of mass up to 140 tons are carried out. The results of tests of some new designs of packaging for irradiated nuclear fuel are briefly considered. (author)

Initial waste package interaction tests: status report

International Nuclear Information System (INIS)

Shade, J.W.; Bradley, D.J.

1980-12-01

This report describes the results of some initial investigations of the effects of rock media on the release of simulated fission products from a sngle waste form, PNL reference glass 76-68. All tests assemblies contained a minicanister prepared by pouring molten, U-doped 76-68 glass into a 2-cm-dia stanless steel tube closed at one end. The tubes were cut to 2.5 to 7.5 cm in length to expose a flat glass surface rimmed by the canister wall. A cylindrical, whole rock pellet, cut from one of the rock materials used, was placed on the glass surface then both the canister and rock pellet were packed in the same type of rock media ground to about 75 μm to complete the package. Rock materials used were a quartz monzonite basalt and bedded salt. These packages were run from 4 to 6 weeks in either 125 ml digestion bombs or 850 ml autoclaves capable of direct solution sampling, at either 250 or 150 0 C. Digestion bomb pressures were the vapor pressure of water, 600 psig at 250 0 C, and the autoclaves were pressurized at 2000 psig with an argon overpressure. In general, the solution chemistry of these initial package tests suggests that the rock media is the dominant controlling factor and that rock-water interaction may be similar to that observed in some geothermal areas. In no case was uranium observed in solution above 15 ppB. The observed leach rates of U glass not in contact with potential sinks (rock surfaces and alteration products) have been observed to be considerably higher. Thus the use of leach rates and U concentrations observed from binary leach experiments (waste-form water only) to ascertain long-term environmental consequences appear to be quite conservative compared to actual U release in the waste package experiments. Further evaluation, however, of fission product transport behavior and the role of alteration phases as fission product sinks is required

Full-scale testing of waste package inspection system

International Nuclear Information System (INIS)

Yagi, T.; Kuribayashi, H.; Moriya, Y.; Fujisawa, H.; Takebayashi, N.

1989-01-01

In land disposal of low-level radioactive waste (LLW) in Japan, it is legally required that the waste packages to be disposed of be inspected for conformance to applicable technical regulations prior to shipment from each existing power station. JGC has constructed a fully automatic waste package inspection system for the purpose of obtaining the required design data and proving the performance of the system. This system consists of three inspection units (for visual inspection, surface contamination/dose rate measurement and radioactivity/weight measurement), a labelling unit, a centralized control unit and a drum handling unit. The outstanding features of the system are as follows: The equipment and components are modularized and designed to be of the most compact size and the quality control functions are performed by an advanced centralized control system. The authors discuss how, as a result of the full-scale testing, it has been confirmed that this system satisfies all the performance requirements for the inspection of disposal packages

Concept for waste package environment tests in the Yucca Mountain exploratory shaft

International Nuclear Information System (INIS)

Yow, J.L. Jr.

1985-05-01

The Nevada Nuclear Waste Storage Investigations (NNWSI) project is studying a tuffaceous rock unit located at Yucca Mountain on the western boundary of the Nevada Test Site, Nye County, Nevada. The objective is to evaluate the suitability of the volcanic rocks located above the water table at Yucca Mountain as a potential location for a repository for high level radioactive waste. As part of the NNWSI project, Lawrence Livermore National Laboratory is responsible for the design of the waste package and for determining the expected performance of the waste package in the repository environment. To design an optimal waste package system for the unsaturated emplacement environment, the mechanisms by which liquid water can return to contact the metal canister after peaking of the thermal load must be established. Definition of these flux and flow mechanisms is essential for estimating canister corrosion modes and rates. Therefore, three waste package environment tests are being designed for the in situ phase of exploratory shaft testing. These tests emphasize measurement techniques that offer the possibility of characterizing the movement of water into and through the pores and fractures of the densely welded Topopah Spring Member. Other measurement techniques will be used to examine the interactions between moisture migration and the thermomechanical rock mass behavior. Three reduced-scale heater tests will use electrical resistive heaters in a horizontal configuration. All three tests are designed to investigate moisture conditions in the rock during heating and cooling phases of a thermal cycle so that the effects of these moisture conditions on the performance of the waste package system may be established. 28 refs., 4 figs., 3 tabs

Waste Package and Material Testing for the Proposed Yucca Mountain High Level Waste Repository

International Nuclear Information System (INIS)

Doering, Thomas; Pasupathi, V.

2002-01-01

Over the repository lifetime, the waste package containment barriers will perform various functions that will change with time. During the operational period, the barriers will function as vessels for handling, emplacement, and waste retrieval (if necessary). During the years following repository closure, the containment barriers will be relied upon to provide substantially complete containment, through 10,000 years and beyond. Following the substantially complete containment phase, the barriers and the waste package internal structures help minimize release of radionuclides by aqueous- and gaseous-phase transport. These requirements have lead to a defense-in-depth design philosophy. A multi-barrier design will result in a lower breach rate distributed over a longer period of time, thereby ensuring the regulatory requirements are met. The design of the Engineered Barrier System (EBS) has evolved. The initial waste package design was a thin walled package, 3/8 inch of stainless steel 304, that had very limited capacity, (3 PWR and 4 BWR assemblies) and performance characteristics, 300 to 1,000 years. This design required over 35,000 waste packages compared to today's design of just over 10,000 waste packages. The waste package designs are now based on a defense-in-depth/multi-barrier philosophy and have a capacity similar to the standard storage and rail transported spent nuclear fuel casks. Concurrent with the development of the design of the waste packages, a comprehensive waste package materials testing program has been undertaken to support the selection of containment barrier materials and to develop predictive models for the long-term behavior of these materials under expected repository conditions. The testing program includes both long-term and short-term tests and the results from these tests combination with the data published in the open literature are being used to develop models for predicting performance of the waste packages

MEMS packaging

CERN Document Server

Hsu , Tai-Ran

2004-01-01

MEMS Packaging discusses the prevalent practices and enabling techniques in assembly, packaging and testing of microelectromechanical systems (MEMS). The entire spectrum of assembly, packaging and testing of MEMS and microsystems, from essential enabling technologies to applications in key industries of life sciences, telecommunications and aerospace engineering is covered. Other topics included are bonding and sealing of microcomponents, process flow of MEMS and microsystems packaging, automated microassembly, and testing and design for testing.The Institution of Engineering and Technology is

Testing of package design AWG 668 to the 1985 IAEA Regulations (as amended 1990)

International Nuclear Information System (INIS)

1992-01-01

This report gives details of the tests for Normal Transport (Type A Tests) and Accident Conditions (Type B Tests) carried out on the AWE(A) packaging assembly AWG 668 and demonstrates the ability of the packaging to remain leak tight after the tests with no damage to the contents. Included in the report are a comprehensive quality plan and test certificates for the leak tests. (author)

Western aeronautical test range real-time graphics software package MAGIC

Science.gov (United States)

Malone, Jacqueline C.; Moore, Archie L.

1988-01-01

The master graphics interactive console (MAGIC) software package used on the Western Aeronautical Test Range (WATR) of the NASA Ames Research Center is described. MAGIC is a resident real-time research tool available to flight researchers-scientists in the NASA mission control centers of the WATR at the Dryden Flight Research Facility at Edwards, California. The hardware configuration and capabilities of the real-time software package are also discussed.

Test plan, sludge retrieval, sludge packaging

International Nuclear Information System (INIS)

Feigenbutz, L.V.

1994-01-01

This document provides direction for the cold testing of tools, equipment and systems which will be installed and operated in K-East (KE) Basin in support of the sludge retrieval and packaging project. The technical uncertainties related to the effectiveness of sludge retrieval procedures and equipment require that cold testing be completed before installation in KE Basin to identify and resolve existing problems, and to optimize the efficiency of all equipment and systems used. This plan establishes the responsibilities, test requirements, and documentation requirements necessary to complete cold tests of: (1) equipment with no potential for plant use; (2) prototype equipment and systems which may be upgraded for use in K-Basin; and (3) plant equipment and systems requiring cold acceptance testing prior to plant use. Some equipment and systems may have been subject to a formal design review and safety assessment; the results of which will be included as supporting documents to the operational readiness review (ORR)

"Galveston Orientation and Amnesia Test": tradução e validação "Galveston Orientation and Amnesia Test": traducción y validación "Galveston Orientation and Amnesia Test": translation and validation

Directory of Open Access Journals (Sweden)

Silvia Cristina Fürbringer e Silva

2007-03-01

Full Text Available OBJETIVO: Traduzir e validar o Galveston Orientation and Amnesia Test para uso em nosso meio. MÉTODOS: Esse teste foi traduzido para o português e retro-traduzido para o inglês por diferentes especialistas na língua e por fim, feita a avaliação da equivalência entre o instrumento original e a versão retro-traduzida. Sua aplicação em 73 vítimas de trauma crânio-encefálico contuso e a indicação da gravidade dessa lesão, estabelecida pela Escala de Coma de Glasgow, permitiram verificar as propriedades de medida do instrumento. RESULTADOS: A confiabilidade verificada pelo Alfa de Cronbach resultou em 0,76. Houve indicação de validade convergente e discriminante do instrumento quando os resultados de aplicação do Galveston Orientation and Amnésia Test foram analisados perante a gravidade do trauma crânio-encefálico. CONCLUSÃO: Os resultados observados dão suporte para a aplicação do Galveston Orientation and Amnesia Test em nosso meio como indicador do término da amnésia pós-traumática.OBJETIVO: Traducir y validar el Galveston Orientation and Amnesia Test para su uso en nuestro medio. MÉTODOS: El test fue traducido al portugués retrotraducido al inglés por diferentes especialistas en la lengua y por fin, realizada la evaluación de la equivalencia entre el instrumento original y la versión retrotraducida. Su aplicación en 73 víctimas de traumatismo encéfalo craneano con constusión y la indicación de la gravedad de esa lesión, establecida por la Escala de Coma de Glasgow, permitieron verificar las propiedades de medida del instrumento. RESULTADOS: La confiabilidad verificada por el Alfa de Cronbach fue de 0,76. Hubo indicación de validez convergente y discriminante del instrumento cuando los resultados de aplicación del Galveston Orientation and Amnésia Test fueron analizados frente a la gravedad del traumatismo encéfalo craneano. CONCLUSIÓN: Los resultados observados dan soporte para la aplicación del

Packaging of MEMS/MOEMS and nanodevices: reliability, testing, and characterization aspects

Science.gov (United States)

Tekin, Tolga; Ngo, Ha-Duong; Wittler, Olaf; Bouhlal, Bouchaib; Lang, Klaus-Dieter

2011-02-01

The last decade witnessed an explosive growth in research and development efforts devoted to MEMS devices and packaging. The successfully developed MEMS devices are, for example inkjet, pressure sensors, silicon microphones, accelerometers, gyroscopes, MOEMS, micro fuel cells and emerging MEMS. For the next decade, MEMS/MOEMS and nanodevice based products will penetrate into IT, telecommunications, automotive, defense, life sciences, medical and implantable applications. Forecasts say the MEMS market to be $14 billion by 2012. The packaging cost of MEMS/MOEMS products in general is about 70 percent. Unlike today's electronics IC packaging, their packaging are custom-built and difficult due to the moving structural elements. In order for the moving elements of a MEMS device to move effectively in a well-controlled atmosphere, hermetic sealing of the MEMS device in a cap is necessary. For some MEMS devices, such as resonators and gyroscopes, vacuum packaging is required. Usually, the cap is processed at the wafer level, and thus MEMS packaging is truly a wafer level packaging. In terms of MEMS/MOEMS and nanodevice packaging, there are still many critical issues need to be addressed due to the increasing integration density supported by 3D heterogeneous integration of multi-physic components/layers consisting of photonics, electronics, rf, plasmonics, and wireless. The infrastructure of MEMS/MOEMS and nanodevices and their packaging is not well established yet. Generic packaging platform technologies are not available. Some of critical issues have been studied intensively in the last years. In this paper we will discuss about processes, reliability, testing and characterization of MEMS/MOEMS and nanodevice packaging.

Modeling and simulation for microelectronic packaging assembly manufacturing, reliability and testing

CERN Document Server

Liu, Sheng

2011-01-01

Although there is increasing need for modeling and simulation in the IC package design phase, most assembly processes and various reliability tests are still based on the time consuming ""test and try out"" method to obtain the best solution. Modeling and simulation can easily ensure virtual Design of Experiments (DoE) to achieve the optimal solution. This has greatly reduced the cost and production time, especially for new product development. Using modeling and simulation will become increasingly necessary for future advances in 3D package development.  In this book, Liu and Liu allow people

Technical committee on transport package test standards, Tokyo, Japan, 28 September - 2 October 1981

International Nuclear Information System (INIS)

Ek, P.

The Technical Committee looked into the following tasks: a) the additional 200 m water immersion test for packages designed for irradiated fuel when the activity exceeds 10 6 Ci; b) the proposed addition of a crush test for light weight Type B and fissile materials packages; c) the proposed new text for thermal test

The LCDROOT Analysis Package

International Nuclear Information System (INIS)

Abe, Toshinori

2001-01-01

The North American Linear Collider Detector group has developed simulation and analysis program packages. LCDROOT is one of the packages, and is based on ROOT and the C++ programing language to maximally benefit from object oriented programming techniques. LCDROOT is constantly improved and now has a new topological vertex finder, ZVTOP3. In this proceeding, the features of the LCDROOT simulation are briefly described

Advisory group on transport package test standards. Vienna, 19-23 December 1977

International Nuclear Information System (INIS)

Ek, P.; Taylor, W.R.

1978-03-01

The IAEA convened the Advisory Group to (1) consider any available data on transport accidents and any risk assessments performed in Member States, with a view to making a critical study of the continuing adequacy of the package test requirements included in the current version of the IAEA Regulations for the Safe Transport of Radioactive Materials (Safety Series No.6, 1973 Revised Edition), and (2) make recommendations concerning the future planning and conduct of this study. The reports and recommendations are presented of the four working groups assigned, i.e., Statistical Data on Accidents and ''Near Accidents'', Incidents of Accidents and Risk Assessments, Review Package Testing Requirements, and Review Basis for the Radiation Levels for Packages

The individual-oriented and social-oriented Chinese bicultural self: testing the theory.

Science.gov (United States)

Lu, Luo

2008-06-01

The author proposes a bicultural self theory for contemporary Chinese individuals, encompassing 2 main components: the individual-oriented self and the social-oriented self. The social orientation is rooted in traditional Chinese conceptualization of the self, whereas the individual orientation has evolved and developed under Western influences along with recent societal modernization. The author conducted a series of 5 studies to test the theory and relate the model to important issues in current personality and social psychological research, such as cultural individualism-collectivism, self-construals, motivation, cognition, emotion, and well-being. A total of 977 university students in Taiwan participated. The author found that contrasting self-aspects were differentially associated with the aforementioned constructs, as theoretically predicted. This evidence thus generally supported the bicultural self model.

Qualification testing facility for packages to be used for transport and storage of radioactive materials

International Nuclear Information System (INIS)

Vieru, Gheorghe

2009-01-01

The radioactive materials (RAM) packaging have to comply to all modes and transport condition, routine or in accident conditions possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the ROMANIAN nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- 'Norms for a Safe Transport of Radioactive Material', the IAEA Vienna Recommendation stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing. In addition, a part of the qualification tests for a package (designed and manufactured in INR Pitesti) used for transport and storage of spent fuel LEU elements of a TRIGA nuclear reactor will be described and analyzed. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (author)

Galveston Orientation Amnesia Test (GOAT Galveston Orientation Amnesia Test (GOAT Galveston Orientation Amnesia Test (GOAT

Directory of Open Access Journals (Sweden)

Silvia Cristina Fürbringer e Silva

2009-12-01

Full Text Available O trauma crânio-encefálico contuso (TCEC é freqüentemente seguido pela amnésia pós-traumática (APT, caracterizada como um estado transitório de confusão e desorientação. Sua duração tem sido utilizada para quantificar a gravidade do TCEC e prever distúrbios nas funções cognitivas, assim como para antever as alterações na capacidade funcional das vítimas pós-trauma. O Galveston Orientation Amnesia Test (GOAT é o primeiro instrumento sistematizado criado e o mais amplamente utilizado para avaliar a APT. Este artigo apresenta esse instrumento, as bases conceituais para seu desenvolvimento e a adaptação e validação do GOAT para cultura brasileira. Além disso, descreve sua aplicação e comenta as restrições do seu uso. Resultados de pesquisas realizadas em nosso meio contribuíram para as evidências sobre a validade do GOAT. Também apontaram os indicadores do momento pós-trauma em que o GOAT deve ser aplicado e destacaram as dificuldades no uso desse instrumento.El trauma cráneo-encefálico contuso (TCEC es frecuentemente seguido por la amnesia pos-traumática (APT, caracterizada como un estado transitorio de confusión y desorientación. Su duración ha sido utilizada para cuantificar la severidad del TCEC y prever alteraciones en las funciones cognitivas, tanto como para antever las dificultades en la capacidad funcional de las víctimas pos-trauma. El Galveston Orientation Amnésia Test (GOAT es la primera encuesta sistematizada que fue creada y el mas ampliamente utilizada para evaluar la APT. Esta publicación presenta esta encuesta, las bases conceptuales para su desarrollo y la adaptación y validación del GOAT para la cultura brasileña. Además, describe su aplicación y limitaciones en el uso. Resultados de pesquisas brasileñas contribuyeron para las evidencias sobre la validad del GOAT. También apuntaron los indicadores del momento pos-trauma en que el GOAT debe ser aplicado y destacaron las dificultades

Testing of AWE (A) package design AWG 446Eu4 to IAEA (1985) Regulations Standard

International Nuclear Information System (INIS)

Cohen, L.R.

1990-10-01

This report gives details of the tests for normal transport (Type A tests) and accident conditions (Type B tests) carried out on the AWE(A) packaging assembly AWG 446Eu4 and demonstrates the ability of the packaging to remain leaktight after the tests with no damage to the contents. Included in the report are a comprehensive quality plan and test certificates for the leak tests. (author)

Structural performance of an IP2 package in free drop test conditions: Numerical and experimental evaluations

International Nuclear Information System (INIS)

Lo Frano, Rosa; Pugliese, Giovanni; Nasta, Marco

2014-01-01

Highlights: • Vertical free drop test. • Qualification of an IP2 type Italian packaging. • Numerical and experimental investigation of the package integrity. • Demonstration the Italian packaging meets safety requirements. - Abstract: The casks or packaging systems used for the transportation of nuclear materials, especially spent fuel elements, have to be designed according to rigorous acceptance requirements, like the IAEA ones, in order to provide protection to human beings and environment against radiation exposure and contamination. This study deals with the free drop test of an Italian design packaging system to be used for the transportation of low and intermediate level radioactive wastes. Impact drop experiments were performed in the Lab. Scalbatraio of the DICI – University of Pisa. Dynamic analyses too have been carried out, by refined models of both the cask and target surface to predict the effects of the impact shock (vertical drop) on the package. The experimental tests and numerical analyses are thoroughly compared, presented and discussed. The numerical approach shows to be suitable to reproduce with good reliability the test situations and results

Review of waste package verification tests. Semiannual report, April 1985-September 1985

International Nuclear Information System (INIS)

Soo, P.

1986-01-01

Several studies were completed this period to evaluate experimental and analytical methodologies being used in the DOE waste package program. The first involves a determination of the relevance of the test conditions being used by DOE to characterize waste package component behavior in a salt repository system. Another study focuses on the testing conditions and procedures used to measure radionuclide solubility and colloid formation in repository groundwaters. An attempt was also made to evaluate the adequacy of selected waste package performance codes. However, the latter work was limited by an inability to obtain several codes from DOE. Nevertheless, it was possible to comment briefly on the structures and intents of the codes based on publications in the open literature. The final study involved an experimental program to determine the likelihood of stress-corrosion cracking of austenitic stainless steels and Incoloy 825 in simulated tuff repository environments. Tests for six-month exposure periods in water and air-steam conditions are described. 52 figs., 48 tabs

Over-the-road tests of nuclear materials package response to normal environments

International Nuclear Information System (INIS)

Gwinn, K.W.; Glass, R.E.; Edwards, K.R.

1991-12-01

In support of the development of American National Standards Institute standards for the transport of radioactive materials, Sandia has a program to characterize the normal transport environment. This program includes both analytical modeling of package and trailer responses, and over-the-road tests to measure those responses. This paper presents the results of a series of over-the-road tests performed using Chem-Nuclear equipment in the Barnwell, SC, area. The test events included a variety of road types such as rough concrete, shock events such as railroad grade crossings, and driver responses such as sharp turns. The response of the package and trailer to these events was measured with accelerometers at various locations to determine the inertial loads. Either load cells or strain gages were used to measure tiedown response. These accelerations and loads were measured on systems with flexible and ''rigid'' tiedowns. The results indicated that while significant accelerations occur on the trailer bed, these do not translate into equivalent loads in either the package or the tiedown system. This indicates that trailer-bed response should not be used in determining the load factor for fatigue calculations of the package components or in determining design loads for tiedowns

Computerized Adaptive Testing with R: Recent Updates of the Package catR

Directory of Open Access Journals (Sweden)

David Magis

2017-01-01

Full Text Available The purpose of this paper is to list the recent updates of the R package catR. This package allows for generating response patterns under a computerized adaptive testing (CAT framework with underlying item response theory (IRT models. Among the most important updates, well-known polytomous IRT models are now supported by catR; several item selection rules have been added; and it is now possible to perform post-hoc simulations. Some functions were also rewritten or withdrawn to improve the usefulness and performances of the package.

Molding compound trends in a denser packaging world: Qualification tests and reliability concerns

Science.gov (United States)

Nguyen, L. T.; Lo, R. H. Y.; Chen, A. S.; Belani, J. G.

1993-12-01

Molding compound development has traditionally been driven by the memory market, then subsequent applications filter down to other IC technologies such as logic, analog, and ASIC. However, this strategy has changed lately with the introduction of thin packages such as PQFP & TSOP. Rather than targeting a compound for a family of IC such as DRAM or SRAM, compound development efforts are now focused at specific classes of packages. The configurations of these thin packages impose new functional requirements that need to be revisited to provide the optimized combination of properties. The evolution of qualification tests mirrors the advances in epoxy and compounding technologies. From the first standard novolac-based epoxies of the 1970s to the latest 3(sup rd)-generation ultra-low stress materials, longer test times at increasingly harsher environments were achieved. This paper benchmarks the current reliability tests used by the electronic industry, examines those tests that affect and are affected by the molding compounds, discusses the relevance of accelerated testing, and addresses the major reliability issues facing current molding compound development efforts. Six compound-related reliability concerns were selected: moldability, package stresses, package cracking, halogen-induced intermetallic growth at bond pads, moisture-induced corrosion, and interfacial delamination. Causes of each failure type are surveyed and remedies are recommended. Accelerated tests are designed to apply to a limited quantity of devices, bias, or environmental conditions larger than usual ratings, to intensify failure mechanisms that would occur under normal operating conditions. The observed behavior is then extrapolated from the lot to the entire population. Emphasis is on compressing the time necessary to obtain reliability data. This approach has two main drawbacks. With increasingly complex devices, even accelerated tests are expensive. And with new technologies, it becomes

Development status of the experimental and numerical load analysis of package units CASTOR registered under drop test conditions

International Nuclear Information System (INIS)

Voelzer, Walter; Schaefer, Marc; Rumanus, Erkan; Liedtke, Ralph; Brehmer, Frank

2012-01-01

The mechanical integrity of package units CASTOR registered for a 9-m drop test under accident conditions has to be demonstrated according the requirements of IAEA among others. For reduction of the loads the containers have to be equipped with shock absorbers on the bottom and top sides. The determination of loads under drop test conditions can be performed with experimental or numerical methods. Due to the complexity of the load state and the verification of results both methods are usually used for integrity demonstration. The numerical codes have to model the short-term dynamic behavior of the whole container for different drop orientations and temperatures, local stress states have to be quantifiable for assessment. One of the problems is the modeling of the material behavior of wood that is used in the shock absorbers. The so far used energetic calculation approach will be replaced by a dynamic approach, the numerical models will have to be verified by experimental drop tests.

The ENSDF Java Package

International Nuclear Information System (INIS)

Sonzogni, A.A.

2005-01-01

A package of computer codes has been developed to process and display nuclear structure and decay data stored in the ENSDF (Evaluated Nuclear Structure Data File) library. The codes were written in an object-oriented fashion using the java language. This allows for an easy implementation across multiple platforms as well as deployment on web pages. The structure of the different java classes that make up the package is discussed as well as several different implementations

Data package for the Turkey Point material interaction test capsules

International Nuclear Information System (INIS)

Krogness, J.C.; Davis, R.B.

1980-02-01

Objective of the test is to obtain interaction information on candidate package storage materials and geologies under prototypic temperatures in gamma and low-level neutron fields. This document provides a fabrication record of the experiment

AIR: A batch-oriented web program package for construction of supermatrices ready for phylogenomic analyses

Directory of Open Access Journals (Sweden)

Mevik Bjørn-Helge

2009-10-01

Full Text Available Abstract Background Large multigene sequence alignments have over recent years been increasingly employed for phylogenomic reconstruction of the eukaryote tree of life. Such supermatrices of sequence data are preferred over single gene alignments as they contain vastly more information about ancient sequence characteristics, and are thus more suitable for resolving deeply diverging relationships. However, as alignments are expanded, increasingly numbers of sites with misleading phylogenetic information are also added. Therefore, a major goal in phylogenomic analyses is to maximize the ratio of information to noise; this can be achieved by the reduction of fast evolving sites. Results Here we present a batch-oriented web-based program package, named AIR that allows 1 transformation of several single genes to one multigene alignment, 2 identification of evolutionary rates in multigene alignments and 3 removal of fast evolving sites. These three processes can be done with the programs AIR-Appender, AIR-Identifier, and AIR-Remover (AIR, which can be used independently or in a semi-automated pipeline. AIR produces user-friendly output files with filtered and non-filtered alignments where residues are colored according to their evolutionary rates. Other bioinformatics applications linked to the AIR package are available at the Bioportal http://www.bioportal.uio.no, University of Oslo; together these greatly improve the flexibility, efficiency and quality of phylogenomic analyses. Conclusion The AIR program package allows for efficient creation of multigene alignments and better assessment of evolutionary rates in sequence alignments. Removing fast evolving sites with the AIR programs has been employed in several recent phylogenomic analyses resulting in improved phylogenetic resolution and increased statistical support for branching patterns among the early diverging eukaryotes.

Statistical Disclosure Control for Micro-Data Using the R Package sdcMicro

Directory of Open Access Journals (Sweden)

Matthias Templ

2015-10-01

The R package sdcMicro serves as an easy-to-handle, object-oriented S4 class implementation of SDC methods to evaluate and anonymize confidential micro-data sets. It includes all popular disclosure risk and perturbation methods. The package performs automated recalculation of frequency counts, individual and global risk measures, information loss and data utility statistics after each anonymization step. All methods are highly optimized in terms of computational costs to be able to work with large data sets. Reporting facilities that summarize the anonymization process can also be easily used by practitioners. We describe the package and demonstrate its functionality with a complex household survey test data set that has been distributed by the International Household Survey Network.

The development of an enhanced strain measurement device to support testing of radioactive material packages

International Nuclear Information System (INIS)

Uncapkher, W.L.; Arviso, M.

1995-01-01

Radioactive material package designers use structural testing to verify and demonstrate package performance. A major part of evaluating structural response is the collection of reliable instrumentation measurement data. Over the last four decades, Sandia National Laboratories (SNL) has been actively involved in the development, testing, and evaluation of measurement devices for a broad range of applications, resulting in the commercialization of several measurement devices commonly used today. SNL maintains an ongoing program sponsored by the US Department of Energy (DOE) to develop and evaluate measurement devices to support testing of packages used to transport radioactive or hazardous materials. The development of the enhanced strain measurement device is part of this program

Feature test report for the Small Debris Collection and Packaging System

International Nuclear Information System (INIS)

Brisbin, S.A.

1995-01-01

The Spent Nuclear Fuel Equipment Engineering group performed feature testing of the Small Debris Collection and Packaging System (SDCPS) in the 305 Cold Test Facility from January 30, 1995, to February 1, 1995. Feature testing of the Small Debris Collection and Packaging System (SDCPS) was performed for the following reasons: To assess the feasibility of using ''drop-out'' vessels to collect small debris (<2.5 cm) in MK-II fuel canisters while transferring sludge to the Weasel Pit. To evaluate system performance under conditions similar to those in the K-Basins (e.g. submerged under 4.9 meters of water and operated with long handled tools) while using a surrogate sludge mixed with debris. To determine if canister weight could be used to predict the volume of sludge and/or debris contained within the canisters during system operation

The Ettention software package

International Nuclear Information System (INIS)

Dahmen, Tim; Marsalek, Lukas; Marniok, Nico; Turoňová, Beata; Bogachev, Sviatoslav; Trampert, Patrick; Nickels, Stefan; Slusallek, Philipp

2016-01-01

We present a novel software package for the problem “reconstruction from projections” in electron microscopy. The Ettention framework consists of a set of modular building-blocks for tomographic reconstruction algorithms. The well-known block iterative reconstruction method based on Kaczmarz algorithm is implemented using these building-blocks, including adaptations specific to electron tomography. Ettention simultaneously features (1) a modular, object-oriented software design, (2) optimized access to high-performance computing (HPC) platforms such as graphic processing units (GPU) or many-core architectures like Xeon Phi, and (3) accessibility to microscopy end-users via integration in the IMOD package and eTomo user interface. We also provide developers with a clean and well-structured application programming interface (API) that allows for extending the software easily and thus makes it an ideal platform for algorithmic research while hiding most of the technical details of high-performance computing. - Highlights: • Novel software package for “reconstruction from projections” in electron microscopy. • Support for high-resolution reconstructions on iterative reconstruction algorithms. • Support for CPU, GPU and Xeon Phi. • Integration in the IMOD software. • Platform for algorithm researchers: object oriented, modular design.

The Ettention software package

Energy Technology Data Exchange (ETDEWEB)

Dahmen, Tim, E-mail: Tim.Dahmen@dfki.de [German Research Center for Artificial Intelligence GmbH (DFKI), 66123 Saarbrücken (Germany); Saarland University, 66123 Saarbrücken (Germany); Marsalek, Lukas [Eyen SE, Na Nivách 1043/16, 141 00 Praha 4 (Czech Republic); Saarland University, 66123 Saarbrücken (Germany); Marniok, Nico [Saarland University, 66123 Saarbrücken (Germany); Turoňová, Beata [Saarland University, 66123 Saarbrücken (Germany); IMPRS-CS, Max-Planck Institute for Informatics, Campus E 1.4, 66123 Saarbrücken (Germany); Bogachev, Sviatoslav [Saarland University, 66123 Saarbrücken (Germany); Trampert, Patrick; Nickels, Stefan [German Research Center for Artificial Intelligence GmbH (DFKI), 66123 Saarbrücken (Germany); Slusallek, Philipp [German Research Center for Artificial Intelligence GmbH (DFKI), 66123 Saarbrücken (Germany); Saarland University, 66123 Saarbrücken (Germany)

2016-02-15

We present a novel software package for the problem “reconstruction from projections” in electron microscopy. The Ettention framework consists of a set of modular building-blocks for tomographic reconstruction algorithms. The well-known block iterative reconstruction method based on Kaczmarz algorithm is implemented using these building-blocks, including adaptations specific to electron tomography. Ettention simultaneously features (1) a modular, object-oriented software design, (2) optimized access to high-performance computing (HPC) platforms such as graphic processing units (GPU) or many-core architectures like Xeon Phi, and (3) accessibility to microscopy end-users via integration in the IMOD package and eTomo user interface. We also provide developers with a clean and well-structured application programming interface (API) that allows for extending the software easily and thus makes it an ideal platform for algorithmic research while hiding most of the technical details of high-performance computing. - Highlights: • Novel software package for “reconstruction from projections” in electron microscopy. • Support for high-resolution reconstructions on iterative reconstruction algorithms. • Support for CPU, GPU and Xeon Phi. • Integration in the IMOD software. • Platform for algorithm researchers: object oriented, modular design.

Implementing and Testing the LINTAB, HEATER and PLOTTAB code package

International Nuclear Information System (INIS)

Cullen, D.E.; Smith, J.J.

1987-07-01

Enclosed is a description of the magnetic tape or floppy diskette containing the LINTAB, HEATER and PLOTTAB code package. In addition detailed information is provided on implementation and testing of these codes. These codes are documented in IAEA-NDS-84. (author)

Model-Based Software Testing for Object-Oriented Software

Science.gov (United States)

Biju, Soly Mathew

2008-01-01

Model-based testing is one of the best solutions for testing object-oriented software. It has a better test coverage than other testing styles. Model-based testing takes into consideration behavioural aspects of a class, which are usually unchecked in other testing methods. An increase in the complexity of software has forced the software industry…

Inspection, testing, and operating requiremens for the packaging and shipping of uranium trioxide in 55-gallon Department of Transportation (DOT) Specification 6M shipping packagings

International Nuclear Information System (INIS)

Toomer, D.V.

1991-06-01

This document identifies the inspection, testing and operating requirements for the packaging, loading, and shipping of uranium trioxide (UO 3 ) in 55-gallon DOT Specification 6M shipping packagings from the Idaho Chemical Processing Plant (ICPP). Compliance with this document assures established controls for the purchasing, packaging, loading, and shipping of DOT Specification 6M shipping packagings are maintained in strict accordance with applicable Code of Federal Regulations (CFRs) and Department of Energy (DOE) Orders. 7 refs., 3 figs., 1 tab

Simulation tests of plastic-packaged commercial SRAM

International Nuclear Information System (INIS)

Kalashnikov, O.A.; Nikiforov, A.Y.

1999-01-01

Laser and X-ray simulation test technique is developed adopted to plastic-packaged ICs. Dose rate and total dose test results are presented for two types of commercial RAMS. Dose rate and total dose test results were obtained for two types of commercial RAMS: AS7C256-20 256 K (32 K x 8) and MT5C1008W - 1 M (128 K x 8). The latch-up of AS7C256-20 was detected at dose rate 1.510 9 rad(Si)/s and of MT5C1008W - at dose rate 5.7-10 8 rad(Si)/s. The total dose failure thresholds were in the ranges of 55 to 90 krad(Si) for AS7C25620 and 40 to 328 krad for MT5C1008W depending on RAM operational mode under irradiation. The obtained simulation test results are in a good agreement with previously published for radiation installations. (authors)

Overview of hydrothermal testing of waste-package barrier materials at the Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1982-01-01

The current Waste Package Department (WPD) hydrothermal testing program for the Basalt Waste Isolation Project (BWIP) has followed a systematic approach for the testing of waste-barrier-basalt interactions based on sequential penetration of barriers by intruding groundwaters. Present test activities in the WPD program have focused on determining radionuclide solubility limits (or steady-state conditions) of simulated waste forms and the long-term stability of waste package barriers under site-specific hydrothermal conditions. The resulting data on solution compositions and solid alteration products have been used to evaluate waste form degradation under conditions specific to a nuclear waste repository located in basalt (NWRB). Isothermal, time-invariant compositional data on sampled solutions have been coupled with realistic hydrologic flow data for near-field and far-field modeling for the calculation of meaningful radionuclide release rates. Radionuclides that are not strongly sorbed or precipitated from solution and that, therefore, may require special attention to ensure their isolation within the waste package have been identified. Taken together, these hydrothermal test data have been used to establish design requirements for waste packages located in basalt

LDR: A Package for Likelihood-Based Sufficient Dimension Reduction

Directory of Open Access Journals (Sweden)

R. Dennis Cook

2011-03-01

Full Text Available We introduce a new mlab software package that implements several recently proposed likelihood-based methods for sufficient dimension reduction. Current capabilities include estimation of reduced subspaces with a fixed dimension d, as well as estimation of d by use of likelihood-ratio testing, permutation testing and information criteria. The methods are suitable for preprocessing data for both regression and classification. Implementations of related estimators are also available. Although the software is more oriented to command-line operation, a graphical user interface is also provided for prototype computations.

Design and testing of Spec 7A containers for packaging radioactive wastes

International Nuclear Information System (INIS)

Roberts, R.S.; Perkins, C.L.

1982-01-01

For a variety of reasons, the containers that have or currently are being used for packaging radioactive waste have drawbacks which has motivated LLNL to investigate, design and destructively test different Type A containers. The result of this work is manifested in the TX-4, which is comparatively lightweight, increases the net payload, and the simplicity of the design and ease in handling have proved to be timesaving. The TX-4 is readily available, relatively inexpensive and practical to use. It easily meets Type A packaging specifications with a gross payload of 7000 pounds. Although no tests were performed at a higher weight, we feel that the TX-4 could pass the tests at higher gross weights if the need arises. 20 figures

Next-generation avionics packaging and cooling 'test results from a prototype system'

Science.gov (United States)

Seals, J. D.

The author reports on the design, material characteristics, and test results obtained under the US Air Force's advanced aircraft avionics packaging technologies (AAAPT) program, whose charter is to investigate new designs and technologies for reliable packaging, interconnection, and thermal management. Under this program, AT&T Bell Laboratories has completed the preliminary testing of and is evaluating a number of promising materials and technologies, including conformal encapsulation, liquid flow-through cooling, and a cyanate ester backplane. A fifty-two module system incorporating these and and other technologies has undergone preliminary cooling efficiency, shock, sine and random vibration, and maintenance testing. One of the primary objectives was to evaluate the interaction compatibility of new materials and designs with other components in the system.

Destructive Examination of Shipping Package 9975-02019

Energy Technology Data Exchange (ETDEWEB)

Daugherty, W. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-06-13

Destructive and non-destructive examinations have been performed on the components of shipping package 9975-02019 as part of a comprehensive SRS surveillance program for plutonium material stored in the K-Area Complex (KAC). During the field surveillance inspection of this package in KAC, two non-conforming conditions were noted: the axial gap of 1.577 inch exceeded the 1 inch maximum criterion, and two areas of dried glue residue were noted on the upper fiberboard subassembly. This package was subsequently transferred to SRNL for more detailed inspection and destructive examination. In addition to the conditions noted in KAC, the following conditions were noted: - Numerous small spots of corrosion were observed along the bottom edge of the drum. - In addition to the smeared glue residue on the upper fiberboard subassembly, there was also a small dark stain. - Mold was present on the side and bottom of the lower fiberboard subassembly. Dark stains from elevated moisture content were also present in these areas. - A dark spot with possible light corrosion was observed on the primary containment vessel flange, and corresponding rub marks were observed on the secondary containment vessel ID. - The fiberboard thermal conductivity in the radial orientation was above the specified range. When the test was repeated with slightly lower moisture content, the result was acceptable. The moisture content for both tests was within a range typical of other packages in storage. The observed conditions must be fully evaluated by KAC to ensure the safety function of the package is being maintained. Several factors can contribute to the concentration of moisture in the fiberboard, including higher than average initial moisture content, higher internal temperature (due to internal heat load and placement within the array of packages), and the creation of additional moisture as the fiberboard begins to degrade.

Leaktightness definitions for and leakage tests on packages for the transport of radioactive materials

International Nuclear Information System (INIS)

Tanguy, L.

1989-07-01

In 1986, the International Organization for Standardization asked a group of experts representing some fifteen countries to draft a standard for the leaktightness of packagings used for the transport of radioactive materials. Progress of work and test before shipping of packages are reviewed

Testing Object-Oriented Software

DEFF Research Database (Denmark)

Caspersen, Michael Edelgaard; Madsen, Ole Lehrmann; Skov, Stefan H.

The report is a result of an activity within the project Centre for Object Technology (COT), case 2. In case 2 a number of pilot projects have been carried out to test the feasibility of using object technology within embedded software. Some of the pilot projects have resulted in proto-types that......The report is a result of an activity within the project Centre for Object Technology (COT), case 2. In case 2 a number of pilot projects have been carried out to test the feasibility of using object technology within embedded software. Some of the pilot projects have resulted in proto......-types that are currently being developed into production versions. To assure a high quality in the product it was decided to carry out an activ-ity regarding issues in testing OO software. The purpose of this report is to discuss the issues of testing object-oriented software. It is often claimed that testing of OO...... software is radically different form testing traditional software developed using imperative/procedural programming. Other authors claim that there is no difference. In this report we will attempt to give an answer to these questions (or at least initiate a discussion)....

Thermal testing transport packages for radioactive materials: Reality vs regulation

International Nuclear Information System (INIS)

Hovingh, J.; Carlson, R.W.

1994-03-01

The principle objective of this paper is to provide information that will help describe the physical thermal tests performed to demonstrate compliance with the hypothetical accident conditions specified in 10 CFR 71.73. Physical testing should be applied to packages that cannot be modeled by analysis to adequately predict their response to hypothetical accident conditions. These tests should be used when chemical decomposition or material changes occur during an accident that would be difficult to analytically predict or model

RF and microwave integrated circuit development technology, packaging and testing

CERN Document Server

Gamand, Patrice; Kelma, Christophe

2018-01-01

RF and Microwave Integrated Circuit Development bridges the gap between existing literature, which focus mainly on the 'front-end' part of a product development (system, architecture, design techniques), by providing the reader with an insight into the 'back-end' part of product development. In addition, the authors provide practical answers and solutions regarding the choice of technology, the packaging solutions and the effects on the performance on the circuit and to the industrial testing strategy. It will also discuss future trends and challenges and includes case studies to illustrate examples. * Offers an overview of the challenges in RF/microwave product design * Provides practical answers to packaging issues and evaluates its effect on the performance of the circuit * Includes industrial testing strategies * Examines relevant RF MIC technologies and the factors which affect the choice of technology for a particular application, e.g. technical performance and cost * Discusses future trends and challen...

Lessons learned from the fire test of Westinghouse's new type AF package, the traveller: (nothing like the real thing)

International Nuclear Information System (INIS)

Malloy, J.; Hempy, B.; Utlak, R.; Kent, N.

2004-01-01

Satisfying the thermal test requirements is a significant part of licensing a Type AF package. Regulations allow the thermal test requirements to be satisfied by several means including thermal analysis, thermal test inside a furnace, pool fire test, test using a scale model of the package, test using a segment or portion of a package, or test using a full-scale package. It was decided that a pool fire test using a full-scale package was the only way to adequately test the many features of the Traveller. Items crucial to criticality safety are more subject to damage during the thermal test. The Traveller design includes a substantial amount of neutron moderating material built into the packaging. This is so that criticality safety would not be dependent on moderation by HAC immersion. A full-scale fire test proved to be the only method to verify that the moderator survives. The Traveller also features a unique impact limiter system inside the packaging that is designed to lessen the impact of the contents in an end drop. It was determined that the full-scale fire test would be the only way to verify that the limiters would not ignite and burn inside the package. Actual pool fire temperatures are more severe than the 800 C minimum required in the regulations. Also it is impossible to model distortions and stresses caused by an actual fire, and these have a significant impact on any thermal analysis. This paper describes the many exploratory and scoping tests that preceded the final fire tes t. The lessons learned, though perhaps not new to those regularly employed in the fire testing profession, proved to be valuable to the licensee in completing the Traveller design

The use of an object oriented technique for fault diagnosis in nuclear reactors

International Nuclear Information System (INIS)

Jalel, N.A.; Nicholson, H.

1990-11-01

In recent years there has been an increased growth of interest in object oriented programming which is a new approach to software construction having wide application. The possibility of using object oriented programming to build a software package that will assist the nuclear reactor operator in diagnosing any faults or alarms in the Loss Of Fluid Test (LOFT), a small scale pressurised water reactor, reactor is investigated in this work. (author)

Simulation of the target-oriented driving of an autonomous vehicle in a labyrinthic environment by means of the KISMET software package

International Nuclear Information System (INIS)

Knueppel, H.; Kuehnapfel, U.; Smidt, D.

1991-10-01

By using the special capabilities of the KISMET software-package and hardware for geometric operations and graphical presentation, an algorithm for the collision-free target-oriented driving of an autonomous vehicle was developed, implemented and linked to KISMET. The algorithm employs a simple global route-planner. It creates the global path neglecting the finite vehicle dimensions as input to the sensor-based local route-planner. The local planner for each time step transforms the sensor pattern, received by a number of ultrasonic sensors, to the movement-pattern. The target oriented global information influences the local operations. Some examples and a video demonstrate, the target will be reached collision free and close to the shortest path even in a labyrinthic environment. (orig.) [de

10 CFR 431.86 - Uniform test method for the measurement of energy efficiency of commercial packaged boilers.

Science.gov (United States)

2010-01-01

... efficiency of commercial packaged boilers. 431.86 Section 431.86 Energy DEPARTMENT OF ENERGY ENERGY... Boilers Test Procedures § 431.86 Uniform test method for the measurement of energy efficiency of... packaged boiler equipment classes. (B) On or after March 2, 2012, conduct the thermal efficiency test as...

Technical committee on transport package test standards (for radioactive materials transport). Vienna, 6-10 August 1979

International Nuclear Information System (INIS)

White, M.C.

1979-11-01

The report of a meeting of the technical committee on transport package test standards is presented. The committee assigned high priority to work on Low Level Solid material and Low Specific Activity material, on the justification for and requirements of a Crush Test and on leakage from packages

Dual-task results and the lateralization of spatial orientation: artifact of test selection?

Science.gov (United States)

Bowers, C A; Milham, L M; Price, C

1998-01-01

An investigation was conducted to identify the degree to which results regarding the lateralization of spatial orientation among men and women are artifacts of test selection. A dual-task design was used to study possible lateralization differences, providing baseline and dual-task measures of spatial-orientation performance, right- and left-hand tapping, and vocalization of "cat, dog, horse." The Guilford-Zimmerman Test (Guilford & Zimmerman, 1953), the Eliot-Price Test (Eliot & Price, 1976), and the Stumpf-Fay Cube Perspectives Test (Stumpf & Fay, 1983) were the three spatial-orientation tests used to investigate possible artifacts of test selection. Twenty-eight right-handed male and 39 right-handed female undergraduates completed random baseline and dual-task sessions. Analyses indicated no significant sex-related differences in spatial-orientation ability for all three tests. Furthermore, there was no evidence of differential lateralization of spatial orientation between the sexes.

Performance-oriented packaging: A guide to identifying, procuring, and using. Procurement and use of packaging using HM-181 regulations

International Nuclear Information System (INIS)

1994-09-01

This document addresses procurement of nonbulk packaging used for nonradioactive, hazardous materials that are transported by highway. The basic procedure is the same when making shipments by other modes. However, other sections of the regulations may affect the packaging requirements when shipping by other modes. The variation in requirements is extensive when air transportation is selected. A packaging engineer or transportation specialist should be contacted for guidance wen transport is by a mode other than highway

Enabling More than Moore: Accelerated Reliability Testing and Risk Analysis for Advanced Electronics Packaging

Science.gov (United States)

Ghaffarian, Reza; Evans, John W.

2014-01-01

For five decades, the semiconductor industry has distinguished itself by the rapid pace of improvement in miniaturization of electronics products-Moore's Law. Now, scaling hits a brick wall, a paradigm shift. The industry roadmaps recognized the scaling limitation and project that packaging technologies will meet further miniaturization needs or ak.a "More than Moore". This paper presents packaging technology trends and accelerated reliability testing methods currently being practiced. Then, it presents industry status on key advanced electronic packages, factors affecting accelerated solder joint reliability of area array packages, and IPC/JEDEC/Mil specifications for characterizations of assemblies under accelerated thermal and mechanical loading. Finally, it presents an examples demonstrating how Accelerated Testing and Analysis have been effectively employed in the development of complex spacecraft thereby reducing risk. Quantitative assessments necessarily involve the mathematics of probability and statistics. In addition, accelerated tests need to be designed which consider the desired risk posture and schedule for particular project. Such assessments relieve risks without imposing additional costs. and constraints that are not value added for a particular mission. Furthermore, in the course of development of complex systems, variances and defects will inevitably present themselves and require a decision concerning their disposition, necessitating quantitative assessments. In summary, this paper presents a comprehensive view point, from technology to systems, including the benefits and impact of accelerated testing in offsetting risk.

Design and tests of a package for the transport of radioactive sources; Projeto e testes de uma embalagem para o transporte de fontes radioativas

Energy Technology Data Exchange (ETDEWEB)

Santos, Paulo de Oliveira, E-mail: pos@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-10-26

The Type A package was designed for transportation of seven cobalt-60 sources with total activity of 1 GBq. The shield thickness to accomplish the dose rate and the transport index established by the radioactive transport regulation was calculated by the code MCNP (Monte Carlo N-Particle Transport Code Version 5). The sealed cobalt-60 sources were tested for leakages. according to the regulation ISO 9978:1992 (E). The package was tested according to regulation Radioactive Material Transport CNEN. The leakage tests results pf the sources, and the package tests demonstrate that the transport can be safe performed from the CDTN to the steelmaking industries

Certification of packagings: compliance with DOT specification 7A packaging requirements

International Nuclear Information System (INIS)

Edling, D.A.

1976-01-01

A study was conducted to determine which of the packagings currently listed in CFR 49 Section 173.395 a.1-5, meet the Specification 7A requirements (CFR 49 Section 173.350). According to DOT HM-111 the present listing of various authorized DOT specifications in Section 173.394 and Section 173.395 (Type A containers) of ICC Tariff No. 27 would be deleted with complete reliance being placed on the use of DOT 7A, Type A general packaging specification. Each user of a Specification 7A package would be required to document and maintain on file for one year a written record of his determination of compliance with the DOT Specification 7A performance requirements. All the specification packagings listed in CFR 49 Section 173.395a.1-5 were tested and shown to meet the Specification 7A criteria; however, in many cases qualifications were placed on their use. Forty-nine specification packagings were tested and shown to meet the DOT Specification 7A performance requirements and since there were several styles of some specific packagings, this amounts to greater than 80 packagings. The extensive testing generally indicated a high degree of containment integrity in the packagings tested and the documentation discussed is a valuable tool for shippers of Type A quantities of radioactive materials

Quality assurance requirements in the testing of packages to be used for safe transportation of RAM

International Nuclear Information System (INIS)

Vieru, Gheorghe; Nistor, Viorica; Mihaiu, Ramona

2010-01-01

The quality of the Type A, B or C packages used for transport and storage of Radioactive Material (RAM) has to be proved by performing qualification tests in accordance with the Transport Regulations, within the Reliability and Testing Laboratory, Institute for Nuclear Research (INR) Pitesti, where has designed and developed a new Romanian Testing Facility. The qualifications testing are performed under a strict quality assurance programme based on the specific procedures prior approved by the Romanian Nuclear Regulatory Body CNCAN (National Commission for Nuclear Activity Control). This paper describe the quality assurance programme in accordance with the quality management system developed in order to meet the requirements provided by the national regulations as well as to the requirements of the IAEA's safety standard TS-R-1 related to testing of packages to be used for transport of RAM and also provides an overview of the new Romanian Testing Facilities for RAM Packages, developed by the INR's Reliability and Testing Laboratory within an Excellence Scientific Contract. (authors)

Safety Analysis Report - Packages, 9965, 9968, 9972-9975 Packages

International Nuclear Information System (INIS)

Blanton, P.

2000-01-01

This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on four type B Packages: the 9972, 9973, 9974, and 9975 packages. Because all four packages have similar designs with very similar performance characteristics, all of them are presented in a single SARP. The performance evaluation presented in this SARP documents the compliance of the 9975 package with the regulatory safety requirements. Evaluations of the 9972, 9973, and 9974 packages support that of the 9975. To avoid confusion arising from the inclusion of four packages in a single document, the text segregates the data for each package in such a way that the reader interested in only one package can progress from Chapter 1 through Chapter 9. The directory at the beginning of each chapter identifies each section that should be read for a given package. Sections marked ''all'' are generic to all packages

Wavelet analysis to decompose a vibration simulation signal to improve pre-distribution testing of packaging

Science.gov (United States)

Griffiths, K. R.; Hicks, B. J.; Keogh, P. S.; Shires, D.

2016-08-01

In general, vehicle vibration is non-stationary and has a non-Gaussian probability distribution; yet existing testing methods for packaging design employ Gaussian distributions to represent vibration induced by road profiles. This frequently results in over-testing and/or over-design of the packaging to meet a specification and correspondingly leads to wasteful packaging and product waste, which represent 15bn per year in the USA and €3bn per year in the EU. The purpose of the paper is to enable a measured non-stationary acceleration signal to be replaced by a constructed signal that includes as far as possible any non-stationary characteristics from the original signal. The constructed signal consists of a concatenation of decomposed shorter duration signals, each having its own kurtosis level. Wavelet analysis is used for the decomposition process into inner and outlier signal components. The constructed signal has a similar PSD to the original signal, without incurring excessive acceleration levels. This allows an improved and more representative simulated input signal to be generated that can be used on the current generation of shaker tables. The wavelet decomposition method is also demonstrated experimentally through two correlation studies. It is shown that significant improvements over current international standards for packaging testing are achievable; hence the potential for more efficient packaging system design is possible.

Testing of Type A and B packages in accordance with IAEA transport regulations

International Nuclear Information System (INIS)

Nitsche, F.; Runge, K.; Birkigt, W.; Mueller, E.

1984-01-01

Revised and extended version of a paper presented during the Interregional Training Course on the Safe Transport of Radioactive Materials, organized by the IAEA, Harwell, May 1982, dealing with the test conditions for Type A and Type B packages as well as possible test methods, the performance of testing, and the assessmnt of test results

Test report dot7A type A liquid packaging

Energy Technology Data Exchange (ETDEWEB)

Ketusky, E. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Brandjes, C. [Ameriphysics LLC, Knoxville, TN (United States); Benoit, T. J. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-19

This section presents a general description of the DOT Specification 7A Type A liquid content packaging (HVYTAL), the liquid content evaluated as its payload, acceptable payload shipping configurations and features special to its use. This test report documents compliance with the regulatory safety requirements of 49 CFR Parts 173.24, 173.24a, 173.27, 173.410, 173.412, 173.461 – 173.466 and 178.350.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-30

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.

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

International Nuclear Information System (INIS)

1996-01-01

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

Development of a test and flight engineering oriented language, phase 3

Science.gov (United States)

Kamsler, W. F.; Case, C. W.; Kinney, E. L.; Gyure, J.

1970-01-01

Based on an analysis of previously developed test oriented languages and a study of test language requirements, a high order language was designed to enable test and flight engineers to checkout and operate the proposed space shuttle and other NASA vehicles and experiments. The language is called ALOFT (a language oriented to flight engineering and testing). The language is described, its terminology is compared to similar terms in other test languages, and its features and utilization are discussed. The appendix provides the specifications for ALOFT.

Java Test Driver Generation from Object-Oriented Interaction Traces

NARCIS (Netherlands)

M.M. Bonsangue (Marcello); F.S. de Boer (Frank); A. Gruener; M. Steffen

2009-01-01

htmlabstractIn the context of test-driven development for object-oriented programs, mock objects are increasingly used for unit testing. Several Java mock object frameworks exist, which all have in common that mock objects, realizing the test environment, are directly specied at the Java program

Packaged die heater

Science.gov (United States)

Spielberger, Richard; Ohme, Bruce Walker; Jensen, Ronald J.

2011-06-21

A heater for heating packaged die for burn-in and heat testing is described. The heater may be a ceramic-type heater with a metal filament. The heater may be incorporated into the integrated circuit package as an additional ceramic layer of the package, or may be an external heater placed in contact with the package to heat the die. Many different types of integrated circuit packages may be accommodated. The method provides increased energy efficiency for heating the die while reducing temperature stresses on testing equipment. The method allows the use of multiple heaters to heat die to different temperatures. Faulty die may be heated to weaken die attach material to facilitate removal of the die. The heater filament or a separate temperature thermistor located in the package may be used to accurately measure die temperature.

Development and evaluation of measurement devices used to support testing of radioactive material transportation packages

International Nuclear Information System (INIS)

Uncapher, W.L.; Ammerman, D.J.; Stenberg, D.R.; Bronowski, D.R.; Arviso, M.

1992-01-01

Radioactive material package designers use structural testing to verify and demonstrate package performance. A major part of evaluating structural response is the collection of instrumentation measurement data. Sandia National Laboratories (SNL) has an ongoing program to develop and evaluate measurement devices to support testing of radioactive material packages. Measurement devices developed in support of this activity include evaluation channels, ruggedly constructed linear variable differential transformers, and piezoresistive accelerometers with enhanced measurement capabilities. In addition to developing measurement devices, a method has been derived to evaluate accelerometers and strain gages for measurement repeatability, ruggedness, and manufacturers' calibration data under both laboratory and field conditions. The developed measurement devices and evaluation technique will be discussed and the results of the evaluation will be presented

GOOSE Version 1.4: A powerful object-oriented simulation environment for developing reactor models

International Nuclear Information System (INIS)

Nypaver, D.J.; March-Leuba, C.; Abdalla, M.A.; Guimaraes, L.

1992-01-01

A prototype software package for a fully interactive Generalized Object-Oriented Simulation Environment (GOOSE) is being developed at Oak Ridge National Laboratory. Dynamic models are easily constructed and tested; fully interactive capabilities allow the user to alter model parameters and complexity without recompilation. This environment provides assess to powerful tools such as numerical integration packages, graphical displays, and online help. In GOOSE, portability has been achieved by creating the environment in Objective-C 1 , which is supported by a variety of platforms including UNIX and DOS. GOOSE Version 1.4 introduces new enhancements like the capability of creating ''initial,'' ''dynamic,'' and ''digital'' methods. The object-oriented approach to simulation used in GOOSE combines the concept of modularity with the additional features of allowing precompilation, optimization, testing, and validation of individual modules. Once a library of classes has been defined and compiled, models can be built and modified without recompilation. GOOSE Version 1.4 is primarily command-line driven

Role-Oriented Enterprise Systems

DEFF Research Database (Denmark)

Holst, Philip; Beringer, Joerg; Winther, Jacob

This paper examines the concept of role-­oriented enterprise systems by investigating motivations for and approaches to constructing and reflecting predefined organizational roles in user interfaces of packaged enterprise systems. The research is conducted as case studies of Microsoft and SAP......, constructed from interviews, documents, and examples of role-­‐oriented enterprise system packages from both vendors. The research indicates that the primary motivation of the vendors for including predefined roles is to complement a function-­‐centric approach with a user-­‐centric approach to the design...... of user interfaces of enterprise systems. The research furthermore identifies strategies of an embedded and an independent approach to modeling the role concept and a unified and a componentized approach to reflecting role aggregation in user interfaces....

76 FR 30551 - Specifications for Packagings

Science.gov (United States)

2011-05-26

... design qualification test and each periodic retest on a packaging, a test report must be prepared. The... where the design qualification tests are conducted, for as long as the packaging is produced and for at... report; (5) Manufacturer of the packaging; (6) Description of the packaging design type (e.g. dimensions...

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

International Nuclear Information System (INIS)

KELLY, D.L.

2003-01-01

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

Predicting neuropsychological test performance on the basis of temporal orientation.

Science.gov (United States)

Ryan, Joseph J; Glass, Laura A; Bartels, Jared M; Bergner, CariAnn M; Paolo, Anthony M

2009-05-01

Temporal orientation is often disrupted in the context of psychiatric or neurological disease; tests assessing this function are included in most mental status examinations. The present study examined the relationship between scores on the Temporal Orientation Scale (TOS) and performance on a battery of tests that assess memory, language, and cognitive functioning in a sample of patients with Alzheimer's disease (N = 55). Pearson-product moment correlations showed that, in all but two instances, the TOS was significantly correlated with each neuropsychological measure, p values < or = .05. Also, severely disoriented (i.e., TOS score < or = -8) patients were consistently 'impaired' on memory tests but not on tests of language and general cognitive functioning.

Analysis of the qualification test standards for small radioactive material shipping packages

International Nuclear Information System (INIS)

McClure, J.D.

1978-01-01

The study compares the severity of the existing regulatory standards which are used to license radioactive material (RAM) shipping packages with the severity of transportation accidents. The basic findings of the study indicate that the present regulatory standards provide significantly higher levels of protection for surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It was also determined that crush can occur in all of the transport modes and is not presently included in existing regulations for accident conditions. Test proposals are included for the surface transport mode (truck, rail) and the air transport mode

An object-oriented simulation package for power plants

International Nuclear Information System (INIS)

Robinson, J.T.; Otaduy, P.J.

1987-01-01

This paper describes the application of object-oriented programming to the simulation of continuous/discrete processes such as nuclear power plants. Systems are modeled using this technique as a collection of objects that communicate by passing messages, which invoke methods that describe the state and dynamic behavior of objects. The objects themselves generally correspond to actual plant components, thus minimizing the representational mismatch between actual and modeled systems and facilitating their validation. Several concepts of object-oriented programming, in particular classes, inheritance, and message passing, have proved to be very useful for simulation. The use of these features are discussed and illustrated with examples

Marketing foods to children through product packaging: prolific, unhealthy and misleading.

Science.gov (United States)

Mehta, Kaye; Phillips, Clare; Ward, Paul; Coveney, John; Handsley, Elizabeth; Carter, Patricia

2012-09-01

To investigate marketing techniques used on the packaging of child-oriented products sold through supermarkets. Food and beverage products which met criteria for 'marketed to children' were recorded as child-oriented. The products were analysed for food categories, nutritional value, and type and extent of marketing techniques used. A major supermarket chain in Adelaide, South Australia. Child-oriented food and beverage products. One hundred and fifty-seven discrete products were marketed to children via product packaging; most (75·2 %) represented non-core foods, being high in fat or sugar. Many marketing techniques (more than sixteen unique marketing techniques) were used to promote child-oriented food products. Claims about health and nutrition were found on 55·5 % of non-core foods. A median of 6·43 marketing techniques per product was found. The high volume and power of marketing non-core foods to children via product packaging in supermarkets should be of concern to policy makers wanting to improve children's diet for their health and to tackle childhood obesity. Claims about health or nutrition on non-core foods deserve urgent attention owing to their potential to mislead and confuse child and adult consumers.

Practical Implementation of Defect-Oriented Testing for a Mixed-Signal Class-D Amplifier

NARCIS (Netherlands)

Beurze, R.H.; Xing, Y; Xing, Y.; van Kleef, R.; Tangelder, R.J.W.T.; Engin, N.

1999-01-01

This paper describes the flow of defect-oriented testing from beginning to end, based on the industrial test development for a commercial mixed-signal class-D amplifier. A software tool called DOTSS (Defect-Oriented Test Simulation System) was used to perform the fault simulations. The greatest

A Test Set for stiff Initial Value Problem Solvers in the open source software R: Package deTestSet

NARCIS (Netherlands)

Mazzia, F.; Cash, J.R.; Soetaert, K.

2012-01-01

In this paper we present the R package deTestSet that includes challenging test problems written as ordinary differential equations (ODEs), differential algebraic equations (DAEs) of index up to 3 and implicit differential equations (IDES). In addition it includes 6 new codes to solve initial value

Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask

Energy Technology Data Exchange (ETDEWEB)

Romano, T.

1997-09-29

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.

Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask

International Nuclear Information System (INIS)

Romano, T.

1997-01-01

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

Testing Automation of Context-Oriented Programs Using Separation Logic

Directory of Open Access Journals (Sweden)

Mohamed A. El-Zawawy

2014-01-01

Full Text Available A new approach for programming that enables switching among contexts of commands during program execution is context-oriented programming (COP. This technique is more structured and modular than object-oriented and aspect-oriented programming and hence more flexible. For context-oriented programming, as implemented in COP languages such as ContextJ* and ContextL, this paper introduces accurate operational semantics. The language model of this paper uses Java concepts and is equipped with layer techniques for activation/deactivation of layer contexts. This paper also presents a logical system for COP programs. This logic is necessary for the automation of testing, developing, and validating of partial correctness specifications for COP programs and is an extension of separation logic. A mathematical soundness proof for the logical system against the proposed operational semantics is presented in the paper.

Thermomechanical scoping calculations for the waste package environment tests

International Nuclear Information System (INIS)

Butkovich, T.R.; Yow, J.L. Jr.

1986-03-01

During the site characterization phase of the Nevada Nuclear Waste Storage Investigation Project, tests are planned to provide field information on the hydrological and thermomechanical environment. These results are needed for assessing performance of stored waste packages emplaced at depth in excavations in a rock mass. Scoping calculations were performed to provide information on displacements and stress levels attained around excavations in the rock mass from imposing a thermal load designed to simulate the heat produced by radioactive decay. In this way, approximate levels of stresses and displacements are available for choosing instrumentation type and sensitivity as well as providing indications for optimizing instrument emplacement during the test. 7 refs., 9 figs., 1 tab

General Mechanical Repair. Minor Automotive Maintenance, Small Engine [Repair, and] Welding: Competency Test Package.

Science.gov (United States)

Hamlin, Larry

This document contains the competency test package for three sections of a general mechanical repair course: minor automotive maintenance, small engine mechanics, and welding. Following a list of the common essential elements for trade and industrial education, competency tests for the three sections are provided. Each test includes unit name,…

Prototype heater test of the environment around a simulated waste package

International Nuclear Information System (INIS)

Ramirez, A.L.; Buscheck, T.A.; Carlson, R.; Daily, W.; Latorre, V.R.; Lee, K; Lin, Wunan; Mao, Nai-hsien; Towse, D.; Ueng, Tzou-Shin; Watwood, D.

1991-01-01

This paper presents selected results obtained during the 301 day duration of the Prototype Engineered Barrier System Field Test (PEBSFT) performed in G-Tunnel within the Nevada Test Site. The test described is a precursor to the Engineered Barrier Systems Field Tests (EBSFT) planned for the Exploratory Shaft Facility in Yucca Mountain. The EBSFT will consist of in situ tests of the geohydrologic and geochemical environment in the near field (within a few meters) of heaters emplaced in welded tuff to simulate the thermal effects of waste packages. The paper discusses the evolution of hydrothermal behavior during the prototype test, including rock temperatures, changes in rock moisture content, air permeability of fractures and gas-phase humidity in the heater borehole

Computerized adaptive and multistage testing with R using packages catR and mstR

CERN Document Server

Magis, David; von Davier, Alina A

2017-01-01

The goal of this guide and manual is to provide a practical and brief overview of the theory on computerized adaptive testing (CAT) and multistage testing (MST) and to illustrate the methodologies and applications using R open source language and several data examples.  Implementation relies on the R packages catR and mstR that have been already or are being developed by the first author (with the team) and that include some of the newest research algorithms on the topic. The book covers many topics along with the R-code: the basics of R, theoretical overview of CAT and MST, CAT designs, CAT assembly methodologies, CAT simulations, catR package, CAT applications, MST designs, IRT-based MST methodologies, tree-based MST methodologies, mstR package, and MST applications.  CAT has been used in many large-scale assessments over recent decades, and MST has become very popular in recent years.  R open source language also has become one of the most useful tools for applications in almost all fields, including b...

Thermal testing of packages for transport of radioactive wastes

International Nuclear Information System (INIS)

Koski, J.A.

1994-01-01

Shipping containers for radioactive materials must be shown capable of surviving tests specified by regulations such as Title 10, Code of Federal Regulations, Part 71 (called 10CFR71 in this paper) within the United States. Equivalent regulations hold for other countries such as Safety Series 6 issued by the International Atomic Energy Agency. The containers must be shown to be capable of surviving, in order, drop tests, puncture tests, and thermal tests. Immersion testing in water is also required, but must be demonstrated for undamaged packages. The thermal test is intended to simulate a 30 minute exposure to a fully engulfing pool fire that could occur if a transport accident involved the spill of large quantities of hydrocarbon fuels. Various qualification methods ranging from pure analysis to actual pool fire tests have been used to prove regulatory compliance. The purpose of this paper is to consider the alternatives for thermal testing, point out the strengths and weaknesses of each approach, and to provide the designer with the information necessary to make informed decisions on the proper test program for the particular shipping container under consideration. While thermal analysis is an alternative to physical testing, actual testing is often emphasized by regulators, and this report concentrates on these testing alternatives

Full scale tests on remote handled FFTF fuel assembly waste handling and packaging

International Nuclear Information System (INIS)

Allen, C.R.; Cash, R.J.; Dawson, S.A.; Strode, J.N.

1986-01-01

Handling and packaging of remote handled, high activity solid waste fuel assembly hardware components from spent FFTF reactor fuel assemblies have been evaluated using full scale components. The demonstration was performed using FFTF fuel assembly components and simulated components which were handled remotely using electromechanical manipulators, shielding walls, master slave manipulators, specially designed grapples, and remote TV viewing. The testing and evaluation included handling, packaging for current and conceptual shipping containers, and the effects of volume reduction on packing efficiency and shielding requirements. Effects of waste segregation into transuranic (TRU) and non-transuranic fractions also are discussed

Guidelines for conducting impact tests on shipping packages for radioactive material

International Nuclear Information System (INIS)

Mok, G.C.; Carlson, R.W.; Lu, S.C.; Fischer, L.E.

1995-09-01

Federal regulation (10 CFR Part 71) specifies a number of impact conditions (free-drop, penetration, and puncture), under which a package for the transport of radioactive materials must be tested or evaluated to demonstrate compliance with the regulation. This report is a comprehensive guide to the planning and execution of these impact tests. The report identifies the required considerations for both the design, pre-, and post-test inspections of the test model and the measurement, recording, analysis, and reporting of the test data. The report also presents reasons for the requirements, identifies the major difficulties in meeting these requirements, and suggests possible methods to overcome the difficulties. Discussed in substantial detail is the use of scale models and instrumented measurements

PSF blind test SSC, SPVC, and SVBC physics-dosimetry-metallurgy data packages

International Nuclear Information System (INIS)

1984-01-01

Information is presented concerning the final PSF radiometric data; calculated spectral fluences and dosimeter activities for the metallurgical blind test irradiations at the ORR-PSF; fabrication data package for HEDL dosimetry in the ORNL Poolside Facility LWR pressure vessel mock-up irradiation; SSC-1; NUREG-CR-3457; and NUREG-CR-3295

Food Preparation: An Instructional Package with Adaptations for Visually Impaired Individuals.

Science.gov (United States)

Crawford, Glinda B.; And Others

This instructional package, developed for the home economics teacher of mainstreamed visually impaired students, provides food preparation lesson plans appropriate for the junior high level. First, teacher guidelines are given, including characteristics of the visually impaired, orienting such students to the classroom, orienting class members to…

Testing nano-silver food packaging to evaluate silver migration and food spoilage bacteria on chicken meat.

Science.gov (United States)

Gallocchio, Federica; Cibin, Veronica; Biancotto, Giancarlo; Roccato, Anna; Muzzolon, Orietta; Carmen, Losasso; Simone, Belluco; Manodori, Laura; Fabrizi, Alberto; Patuzzi, Ilaria; Ricci, Antonia

2016-06-01

Migration of nanomaterials from food containers into food is a matter of concern because of the potential risk for exposed consumers. The aims of this study were to evaluate silver migration from a commercially available food packaging containing silver nanoparticles into a real food matrix (chicken meat) under plausible domestic storage conditions and to test the contribution of such packaging to limit food spoilage bacteria proliferation. Chemical analysis revealed the absence of silver in chicken meatballs under the experimental conditions in compliance with current European Union legislation, which establishes a maximum level of 0.010 mg kg(-1) for the migration of non-authorised substances through a functional barrier (Commission Regulation (EU) No. 10/2011). On the other hand, microbiological tests (total microbial count, Pseudomonas spp. and Enterobacteriaceae) showed no relevant difference in the tested bacteria levels between meatballs stored in silver-nanoparticle plastic bags or control bags. This study shows the importance of testing food packaging not only to verify potential silver migration as an indicator of potential nanoparticle migration, but also to evaluate the benefits in terms of food preservation so as to avoid unjustified usage of silver nanoparticles and possible negative impacts on the environment.

Validation of an impact limiter crush prediction model with test data: the case of the HI-STAR 100 package

International Nuclear Information System (INIS)

Singh, K.P.; Soler, A.I.; Bullard, C.W.

2004-01-01

An impact limiter is an essential appurtenance in a Part 71 transport package. The impact limiter serves to protect the cask contents from excessive deceleration in the event of a mechanical accident. 10CFR71.73 (as do the IAEA regulations) specifies a drop height of 9 meters (30 feet) onto an essentially rigid surface as the design requirement for the impact limiter. The orientation of the cask relative to the ''target'' at the instance of the impact, however, is not specified in the regulations. Therefore, the impact limiter must be capable of limiting the cask's deceleration to a prescribed limit regardless of the cask's orientation at impact. In addition to the indeterminacy with respect to the orientation at impact, the impact limiter must be capable of performing its intended function under a wide range of ambient conditions, ranging from -20 F to 100 F, and relative humidity from zero to 100%

Investigating Consumer Preferences towards Sustainability in Product Packaging

OpenAIRE

Petit, Lisa

2017-01-01

This research-oriented thesis investigates to which extent German consumers consider the sustainability aspect of a product package as their main factor in preferring a product. The research was conducted based on a comparison between two specific smoothies from the Company A and Company B brands. Company A smoothies are packed in glass bottles, whereas Company B smoothies are sold in plastic bottles. For the scope of the thesis, sustainable product packaging was defined regarding its contrib...

Object-oriented design of medical imaging software.

Science.gov (United States)

Ligier, Y; Ratib, O; Logean, M; Girard, C; Perrier, R; Scherrer, J R

1994-01-01

A special software package for interactive display and manipulation of medical images was developed at the University Hospital of Geneva, as part of a hospital wide Picture Archiving and Communication System (PACS). This software package, called Osiris, was especially designed to be easily usable and adaptable to the needs of noncomputer-oriented physicians. The Osiris software has been developed to allow the visualization of medical images obtained from any imaging modality. It provides generic manipulation tools, processing tools, and analysis tools more specific to clinical applications. This software, based on an object-oriented paradigm, is portable and extensible. Osiris is available on two different operating systems: the Unix X-11/OSF-Motif based workstations, and the Macintosh family.

Safety Evaluation for Packaging for onsite Transfer of plutonium recycle test reactor ion exchange columns

International Nuclear Information System (INIS)

Smith, R.J.

1995-01-01

The purpose of this Safety Evaluation for Packaging (SEP) is to authorize the use of three U.S. Department of Transportation (DOT) 7A, Type A metal boxes (Capital Industries Part No. S 0600-0600-1080- 0104) to package 12 Plutonium Recycle Test Reactor (PRTR) ion exchange columns as low-level waste (LLW). The packages will be transferred from the 309 Building in the 300 Area to low level waste burial in the 200 West Area. Revision 1 of WHC-SD-TP-SEP-035 (per ECN No. 621467) documents that the boxes containing ion exchange columns and grout will maintain the payload under normal conditions of transport if transferred without the box lids

Certification test for safety of new fuel transportation package

International Nuclear Information System (INIS)

Aritomi, Masanori; Sugawa, Osami; Suga, Masao.

1993-01-01

The objective of this certification test is to prove the safety of new fuel transportation package against a fire of actual size caused by traffic accidents. After the fire test, the fuel assemblies were covered with coal-tar like material vaporized from anti-shock material used in the container. Surface color of BWR-type fuel assembly was dark grey that is supposed to be the color of oxide of Zircaloy. As for PWR-type fuel assembly, the condition encountered during fire test caused no change to the outlook of the rod element. Both the BWR and PWR type fuel rod elements showed no deformation and were completely sound. Therefore it may be concluded that the container protected the mimic fuel assemblies against fire of 30 minutes duration and caused no damage. This report is the result of the above experiments and examinations, and we appreciate the cooperation of those who are concerned. (J.P.N.)

Design aspects of plutonium air-transportable packages

International Nuclear Information System (INIS)

Allen, G.C.; Moya, J.L.; Pierce, J.D.; Attaway, S.W.

1989-01-01

Recent worldwide interest in transporting plutonium powders by air has created a need for expanding the packaging technology base as well as improving their understanding of how plutonium air transport (PAT) packagings perform during severe accident tests. Historically it has not been possible to establish design rules for individual package components because of the complex way parts interacted in forming a successful whole unit. Also, computer analyses were only considered valid for very limited portions of the design effort because of large deformations, localized tearing occurring in the package during accident testing, and extensive use of orthotropic materials. Consequently, iterative design and experimentation has historically been used to develop plutonium air-transportable packages. Full-scale prototypes have been tested since scaling of packages utilizing wood as an energy absorber and thermal insulator has not proven to be very successful. This is because the wood grain and dynamic performance of the wood during crush do not always scale. The high cost of full-scale testing of large packages has certainly hindered obtaining additional data and development new designs. The testing criteria for PAT packages, as described in the US Nuclear Regulatory Commission's Qualification Criteria to Certify a Package for Air Transport of Plutonium, NUREG-0360, 1978, are summarized. Computer modeling techniques have greatly improved over the last ten years, and there are some areas of opportunity for future applications to plutonium air-transportable package design problems. Having developed a better understanding of the performance of current packages, they have the opportunity to make major improvements in new packaging concepts. Each of these areas is explored in further depth to establish their impact on design practices for air-transportable packages

Sexual Orientation Differences in HIV Testing Motivation among College Men

Science.gov (United States)

Kort, Daniel N.; Samsa, Gregory P.; McKellar, Mehri S.

2017-01-01

Objective: To investigate sexual orientation differences in college men's motivations for HIV testing. Participants: 665 male college students in the Southeastern United States from 2006 to 2014. Methods: Students completed a survey on HIV risk factors and testing motivations. Logistic regressions were conducted to determine the differences…

Test Plan for Lockheed Idaho Technologies Company (LITCO), ARROW-PAK Packaging, Docket 95-40-7A, Type A Container

International Nuclear Information System (INIS)

Kelly, D.L.

1995-01-01

This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance testing to be followed for qualification of the Lockheed Idaho Technologies Company, ARROW-PAK, for use as a Type A Packaging. The packaging configuration being tested is intended for transportation of radioactive solids, Form No. 1, Form No. 2, and Form No. 3

Proton Exchange Membrane Fuel Cell Engineering Model Powerplant. Test Report: Benchmark Tests in Three Spatial Orientations

Science.gov (United States)

Loyselle, Patricia; Prokopius, Kevin

2011-01-01

Proton exchange membrane (PEM) fuel cell technology is the leading candidate to replace the aging alkaline fuel cell technology, currently used on the Shuttle, for future space missions. This test effort marks the final phase of a 5-yr development program that began under the Second Generation Reusable Launch Vehicle (RLV) Program, transitioned into the Next Generation Launch Technologies (NGLT) Program, and continued under Constellation Systems in the Exploration Technology Development Program. Initially, the engineering model (EM) powerplant was evaluated with respect to its performance as compared to acceptance tests carried out at the manufacturer. This was to determine the sensitivity of the powerplant performance to changes in test environment. In addition, a series of tests were performed with the powerplant in the original standard orientation. This report details the continuing EM benchmark test results in three spatial orientations as well as extended duration testing in the mission profile test. The results from these tests verify the applicability of PEM fuel cells for future NASA missions. The specifics of these different tests are described in the following sections.

Drop Weight Device Fabrication and Tests for a Dynamic Material Property of Shock-Absorbing Material and Structure in Transportation Package

International Nuclear Information System (INIS)

Choi, Woo Seok; Jeon, Jea Eon; Han, Sang Hyeok; Lee, Sang Hoon; Seo, Ki Seok

2009-01-01

A radioactive material transportation package consists of canister and impact limiters. IAEA Safety Standard Series No. TS-R-1 recommends a drop test to evaluate the structural integrity of a transportation package under a hypothetical accident condition. The free drop test of a transportation package from 9 m height simulates one of accident conditions. The transportation package has a potential energy corresponding to 9 m drop height, and this energy changes to a kinetic energy when it impacts on the target. The energy is absorbed by a deformation of shock-absorbing material so that the minimum energy is transferred to canister. Accordingly, the shock-absorbing material is a very important part in transportation package design. Since the data for shock-absorbing material characteristics is acquired by a static test in general, it is quite different to that of dynamic characteristics. And the dynamic characteristics data is hardly found in literature. In this study, a drop weight facility was designed and fabricated which produces an impact speed like that of free drop of 9 m height. Several materials considered for an impact limiter and impact limiter structures were tested by a drop weight facility to acquire a dynamic material characteristics data

Drop Weight Device Fabrication and Tests for a Dynamic Material Property of Shock-Absorbing Material and Structure in Transportation Package

Energy Technology Data Exchange (ETDEWEB)

Choi, Woo Seok; Jeon, Jea Eon; Han, Sang Hyeok; Lee, Sang Hoon; Seo, Ki Seok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-05-15

A radioactive material transportation package consists of canister and impact limiters. IAEA Safety Standard Series No. TS-R-1 recommends a drop test to evaluate the structural integrity of a transportation package under a hypothetical accident condition. The free drop test of a transportation package from 9 m height simulates one of accident conditions. The transportation package has a potential energy corresponding to 9 m drop height, and this energy changes to a kinetic energy when it impacts on the target. The energy is absorbed by a deformation of shock-absorbing material so that the minimum energy is transferred to canister. Accordingly, the shock-absorbing material is a very important part in transportation package design. Since the data for shock-absorbing material characteristics is acquired by a static test in general, it is quite different to that of dynamic characteristics. And the dynamic characteristics data is hardly found in literature. In this study, a drop weight facility was designed and fabricated which produces an impact speed like that of free drop of 9 m height. Several materials considered for an impact limiter and impact limiter structures were tested by a drop weight facility to acquire a dynamic material characteristics data.

Safety analysis report: packages. Argonne National Laboratory SLSF test train shipping container, P-1 shipment. Fissile material. Final report

International Nuclear Information System (INIS)

Meyer, C.A.

1975-06-01

The package is used to ship an instrumented test fuel bundle (test train) containing fissile material. The package assembly is Argonne National Laboratory (ANL) Model R1010-0032. The shipment is fissile class III. The packaging consists of an outer carbon steel container into which an inner container is placed; the inner container is separated from the outer container by urethane foam cushioning material. The test train is supported in the inner container by a series of transverse supports spaced along the length of the test train. Both the inner and outer containers are closed with bolted covers. The covers do not seal the containers in a leaktight manner. The gross weight of the shipment is about 8350 lb. The unirradiated fissile material content is less than 3 kg of UO 2 of up to 93.2 percent enrichment. This is a Type A quantity (transport group III and less than 3 curies) of radioactive material which does not require shielding, cooling or heating, or neutron absorption or moderation functions in its packaging. The maximum exterior dimensions of the container are 37 ft 11 in. long, 24 1 / 2 in. wide, and 19 3 / 4 in. high

Consumer response to packaging design

NARCIS (Netherlands)

Steenis, Nigel D.; Herpen, van Erica; Lans, van der Ivo A.; Ligthart, Tom N.; Trijp, van Hans C.M.

2017-01-01

Building on theories of cue utilization, this paper investigates whether and how packaging sustainability influences consumer perceptions, inferences and attitudes towards packaged products. A framework is tested in an empirical study among 249 students using soup products varying in packaging

Field Tested Service Oriented Robotic Architecture: Case Study

Science.gov (United States)

Flueckiger, Lorenzo; Utz, Hanz

2012-01-01

This paper presents the lessons learned from six years of experiments with planetary rover prototypes running the Service Oriented Robotic Architecture (SORA) developed by the Intelligent Robotics Group (IRG) at NASA Ames Research Center. SORA relies on proven software methods and technologies applied to the robotic world. Based on a Service Oriented Architecture and robust middleware, SORA extends its reach beyond the on-board robot controller and supports the full suite of software tools used during mission scenarios from ground control to remote robotic sites. SORA has been field tested in numerous scenarios of robotic lunar and planetary exploration. The results of these high fidelity experiments are illustrated through concrete examples that have shown the benefits of using SORA as well as its limitations.

Barriers to increased market-oriented activity

DEFF Research Database (Denmark)

Bisp, Søren

1999-01-01

and related activities still seem to attract relatively few resources is not answered by supplying another checklist or package of facilitators. Based on published conceptual writings and empirical studies this article makes an account of what the intra-organizational barriers may be to increased market......Most research on market orientation has dealt with assessing how market orientation behaviour is related to business performance. This work has established an intense market-oriented activity as significantly and positively related to business performance under most circumstances. In a maturing......-oriented activity. A framework of six generic domains is suggested: Organizational structure, human resource management, market-oriented activity competence, psychological climate, managers' personality characteristics, and individually held beliefs. A model is suggested inter-relating the domains....

10 CFR 60.143 - Monitoring and testing waste packages.

Science.gov (United States)

2010-01-01

....143 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN... repository operations area, the environment of the waste packages selected for the waste package monitoring program shall be representative of the environment in which the wastes are to be emplaced. (c) The waste...

10 CFR 63.134 - Monitoring and testing waste packages.

Science.gov (United States)

2010-01-01

....134 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A... geologic repository operations area, the environment of the waste packages selected for the waste package monitoring program must be representative of the environment in which the wastes are to be emplaced. (c) The...

Food packages for Space Shuttle

Science.gov (United States)

Fohey, M. F.; Sauer, R. L.; Westover, J. B.; Rockafeller, E. F.

1978-01-01

The paper reviews food packaging techniques used in space flight missions and describes the system developed for the Space Shuttle. Attention is directed to bite-size food cubes used in Gemini, Gemini rehydratable food packages, Apollo spoon-bowl rehydratable packages, thermostabilized flex pouch for Apollo, tear-top commercial food cans used in Skylab, polyethylene beverage containers, Skylab rehydratable food package, Space Shuttle food package configuration, duck-bill septum rehydration device, and a drinking/dispensing nozzle for Space Shuttle liquids. Constraints and testing of packaging is considered, a comparison of food package materials is presented, and typical Shuttle foods and beverages are listed.

Packages for radiactive waste disposal

International Nuclear Information System (INIS)

Oliveira, R. de.

1983-01-01

The development of multi-stage type package for sea disposal of compactable nuclear wastes, is presented. The basic requirements for the project followed the NEA and IAEA recommendations and observations of the solutions adopted by others countries. The packages of preliminary design was analysed, by computer, under several conditions arising out of its nature, as well as their conditions descent, dumping and durability in the deep of sea. The designed pressure equalization mechanic and the effect compacting on the package, by prototypes and specific tests, were studied. These prototypes were also submitted to the transport tests of the 'Regulament for the Safe Transport of Radioactive Materials'. Based on results of the testes and the re-evaluation of the preliminary design, final indications and specifications for excuting the package design, are presented. (M.C.K.) [pt

Development of waste packages for tuff

International Nuclear Information System (INIS)

Rothman, A.J.

1982-01-01

The objective of this program is to develop nuclear waste packages that meet the Nuclear Regulatory Commission's requirements for a licensed repository in tuff at the Nevada Test Site. Selected accomplishments for FY82 are: (1) Selection, collection of rock, and characterization of suitable outcrops (for lab experiments); (2) Rock-water interactions (Bullfrog Tuff); (3) Corrosion tests of ferrous metals; (4) Thermal modeling of waste package in host rock; (5) Preliminary fabrication tests of alternate backfills (crushed tuff); (6) Reviewed Westinghouse conceptual waste package designs for tuff and began modification for unsaturated zone; and (7) Waste Package Codes (BARIER and WAPPA) now running on our computer. Brief discussions are presented for rock-water interactions, corrosion tests of ferrous metals, and thermal and radionuclide migration modelling

Status of the object-oriented EGS interface project

International Nuclear Information System (INIS)

Yacout, A.M.; Dunn, W.L.; Nelson, W.R.; Lui, P.; Bielajew, A.F.; Hirayama, H.; Namito, Y.

2000-01-01

The object-oriented EGS interface project seeks to simplify - using modern object-oriented and visual user interface techniques - the geometry and scoring aspects of the process of running the EGS code. The project will create an extremely user-friendly EGS package that retains and exploits the well documented physics advantages of EGS but removes the requirement that the user write HOWFAR and AUSGAB subroutines to define the geometry and scoring aspects of each new problem. In addition, several physics enhancements will be incorporated in EGS5. Although EGS5 will be able to be used in the traditional way - in a stand-alone fashion with users writing their own geometry and scoring subroutines - it is designed to be used in a completely new way - linked to a user interface through which users can manage all aspects of problem specification and code operation. This paper concentrates on the object-oriented user interface, which will dramatically simplify defining problem-specific detail for EGS. The 'EGS5 + VUI1' package will allow users to solve independent problems by run-time linking of the EGS5 code with class libraries that encapsulate the geometry and scoring aspects of each problem. Some simple example problems are considered in order to illustrate features of the EGS5 + VUI1 package. (author)

CH Packaging Program Guidance

International Nuclear Information System (INIS)

2008-01-01

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 pplication.' 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 U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M and 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. In accordance with 10 CFR Part 71, 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 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

CH Packaging Program Guidance

International Nuclear Information System (INIS)

2009-01-01

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 U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M and 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. In accordance with 10 CFR Part 71, 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 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

RH Packaging Program Guidance

International Nuclear Information System (INIS)

2008-01-01

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 and 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

RH Packaging Program Guidance

International Nuclear Information System (INIS)

2006-01-01

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 and 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) 1.8, '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

CH Packaging Program Guidance

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2003-01-01

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 and 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

CH Packaging Program Guidance

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2002-01-01

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 and 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

EVIO - A lightweight object-oriented I/O package

International Nuclear Information System (INIS)

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

2008-01-01

The EVIO package implements I/O between disk and an in-memory hierarchical object tree. Tree nodes are either container nodes, holding other nodes, or leaf nodes, containing any amount of data of a single type (int64 t ,..., int8 t , float, double, and string). Trees can easily be constructed using factory methods and stream operators; queried using STL-like algorithms, function object, etc; or modified using tree or node methods. The tree logically maps to XML, and utilities exist to transform between binary and ASCII XML formats. The binary representation is compact, I/O is simple and efficient, and endian conversions are handled automatically. EVIO will be used by the next generation of experiments at Jefferson Lab.

MCViNE – An object oriented Monte Carlo neutron ray tracing simulation package

Energy Technology Data Exchange (ETDEWEB)

Lin, Jiao Y.Y., E-mail: linjiao@ornl.gov [Caltech Center for Advanced Computing Research, California Institute of Technology (United States); Department of Applied Physics and Materials Science, California Institute of Technology (United States); Neutron Data Analysis and Visualization Division, Oak Ridge National Laboratory (United States); Smith, Hillary L. [Department of Applied Physics and Materials Science, California Institute of Technology (United States); Granroth, Garrett E., E-mail: granrothge@ornl.gov [Neutron Data Analysis and Visualization Division, Oak Ridge National Laboratory (United States); Abernathy, Douglas L.; Lumsden, Mark D.; Winn, Barry; Aczel, Adam A. [Quantum Condensed Matter Division, Oak Ridge National Laboratory (United States); Aivazis, Michael [Caltech Center for Advanced Computing Research, California Institute of Technology (United States); Fultz, Brent, E-mail: btf@caltech.edu [Department of Applied Physics and Materials Science, California Institute of Technology (United States)

2016-02-21

MCViNE (Monte-Carlo VIrtual Neutron Experiment) is an open-source Monte Carlo (MC) neutron ray-tracing software for performing computer modeling and simulations that mirror real neutron scattering experiments. We exploited the close similarity between how instrument components are designed and operated and how such components can be modeled in software. For example we used object oriented programming concepts for representing neutron scatterers and detector systems, and recursive algorithms for implementing multiple scattering. Combining these features together in MCViNE allows one to handle sophisticated neutron scattering problems in modern instruments, including, for example, neutron detection by complex detector systems, and single and multiple scattering events in a variety of samples and sample environments. In addition, MCViNE can use simulation components from linear-chain-based MC ray tracing packages which facilitates porting instrument models from those codes. Furthermore it allows for components written solely in Python, which expedites prototyping of new components. These developments have enabled detailed simulations of neutron scattering experiments, with non-trivial samples, for time-of-flight inelastic instruments at the Spallation Neutron Source. Examples of such simulations for powder and single-crystal samples with various scattering kernels, including kernels for phonon and magnon scattering, are presented. With simulations that closely reproduce experimental results, scattering mechanisms can be turned on and off to determine how they contribute to the measured scattering intensities, improving our understanding of the underlying physics.

Standard test method for determining the orientation of a metal crystal

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This test method covers the back-reflection Laue procedure for determining the orientation of a metal crystal. The back-reflection Laue method for determining crystal orientation (1, 2) may be applied to macrograins (3) (0.5-mm diameter or larger) within polycrystalline aggregates, as well as to single crystals of any size. The method is described with reference to cubic crystals; it can be applied equally well to hexagonal, tetragonal, or orthorhombic crystals. 1.2 Most natural crystals have well developed external faces, and the orientation of such crystals can usually be determined from inspection. The orientation of a crystal having poorly developed faces, or no faces at all (for example, a metal crystal prepared in the laboratory) must be determined by more elaborate methods. The most convenient and accurate of these involves the use of X-ray diffraction. The “orientation of a metal crystal” is known when the positions in space of the crystallographic axes of the unit cell have been located with...

49 CFR 178.503 - Marking of packagings.

Science.gov (United States)

2010-10-01

...) A letter identifying the performance standard under which the packaging design type has been... tests; (4) A designation of the specific gravity or mass for which the packaging design type has been... of the hydrostatic pressure test that the packaging design type has successfully passed; (ii) For...

Qualification testing facility for type A, B and C packages to be used for transport and storage of radioactive materials

International Nuclear Information System (INIS)

Vieru, G.; Nistor, V.; Vasile, A.; Cojocaru, V.

2009-01-01

In accordance with the Economic Commission for Europe-Committee on inland transport (ADR- European Agreement-concerning the international carriage of dangerous goods by road, 2007 Edition) the Safety and Security of the dangerous goods class No. 7 - Radioactive Materials during transport in all different modes - by road, by rail, by sea, by inland rivers or by air - have to be ensured at a very high level. The radioactive materials (RAM) packaging have to comply to all transport conditions, routine or in accident conditions, possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the Romanian nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- N orms for a Safe Transport of Radioactive Material , the IAEA Vienna Recommendation (1, 2) stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (authors)

CH Packaging Program Guidance

International Nuclear Information System (INIS)

2006-01-01

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 U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant| (WIPP) management and operating (M and 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.In accordance with 10 CFR Part 71, 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 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

CH Packaging Program Guidance

International Nuclear Information System (INIS)

2007-01-01

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 U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M and 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.In accordance with 10 CFR Part 71, 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 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

Development of fresh fuel packaging for ATR demonstration reactor

International Nuclear Information System (INIS)

Kurakami, J.; Kurita, I.

1993-01-01

Related to development of the demonstration advanced thermal reactor, it is necessary and important to develop transport packaging which is used for transporting fresh fuel assemblies. Therefore, the packaging is now being developed in Power Reactor and Nuclear Fuel Development Corporation (PNC). Currently, PNC is fabricating two prototype packagings based on the final design, and land cruising and vibration tests, handling performance tests and prototype packaging tests will be executed with prototype packagings in order to experimentally confirm the soundness of packaging and its contents and the propriety of design technique. This paper describes the summary of general specifications and structures of this packaging and the summary of preliminary safety analysis of package. (J.P.N.)

The influence of food packaging on children's snack food ...

International Development Research Centre (IDRC) Digital Library (Canada)

especially in the advertisement and packaging of high- calorie snack foods. ... marketing is one of the policy strategies proposed to address obesity in children. In order to ... explore the views of school-aged children toward child- oriented food ...

Comparative Packaging Study

Science.gov (United States)

Perchonok, Michele H.; Oziomek, Thomas V.

2009-01-01

Future long duration manned space flights beyond low earth orbit will require the food system to remain safe, acceptable and nutritious. Development of high barrier food packaging will enable this requirement by preventing the ingress and egress of gases and moisture. New high barrier food packaging materials have been identified through a trade study. Practical application of this packaging material within a shelf life test will allow for better determination of whether this material will allow the food system to meet given requirements after the package has undergone processing. The reason to conduct shelf life testing, using a variety of packaging materials, stems from the need to preserve food used for mission durations of several years. Chemical reactions that take place during longer durations may decrease food quality to a point where crew physical or psychological well-being is compromised. This can result in a reduction or loss of mission success. The rate of chemical reactions, including oxidative rancidity and staling, can be controlled by limiting the reactants, reducing the amount of energy available to drive the reaction, and minimizing the amount of water available. Water not only acts as a media for microbial growth, but also as a reactant and means by which two reactants may come into contact with each other. The objective of this study is to evaluate three packaging materials for potential use in long duration space exploration missions.

A comparison of paper-and-pencil and computerized forms of Line Orientation and Enhanced Cued Recall Tests.

Science.gov (United States)

Aşkar, Petek; Altun, Arif; Cangöz, Banu; Cevik, Vildan; Kaya, Galip; Türksoy, Hasan

2012-04-01

The purpose of this study was to assess whether a computerized battery of neuropsychological tests could produce similar results as the conventional forms. Comparisons on 77 volunteer undergraduates were carried out with two neuropsychological tests: Line Orientation Test and Enhanced Cued Recall Test. Firstly, students were assigned randomly across the test medium (paper-and-pencil versus computerized). Secondly, the groups were given the same test in the other medium after a 30-day interval between tests. Results showed that the Enhanced Cued Recall Test-Computer-based did not correlate with the Enhanced Cued Recall Test-Paper-and-pencil results. Line Orientation Test-Computer-based scores, on the other hand, did correlate significantly with the Line Orientation Test-Paper-and-pencil version. In both tests, scores were higher on paper-and-pencil tests compared to computer-based tests. Total score difference between modalities was statistically significant for both Enhanced Cued Recall Tests and for the Line Orientation Test. In both computer-based tests, it took less time for participants to complete the tests.

Safety analysis report: packages. LP-12 tritium package (packaging of fissile and other radioactive materials). Final report

International Nuclear Information System (INIS)

Gates, A.A.; McCarthy, P.G.; Edl, J.W.

1975-05-01

Elemental tritium is shipped at low pressure in a stainless steel container (LP-12) within an aluminum vessel and surrounded by 3.9 in.-thick Celotex insulation in a steel drum. Information is presented on the packaging design, evaluation of the structural, thermal, containment, shielding, and criticality characteristics of the package, procedures for loading, unloading, transporting, and testing the LP-12, and quality assurance requirements. (U.S.)

JGromacs: a Java package for analyzing protein simulations.

Science.gov (United States)

Münz, Márton; Biggin, Philip C

2012-01-23

In this paper, we introduce JGromacs, a Java API (Application Programming Interface) that facilitates the development of cross-platform data analysis applications for Molecular Dynamics (MD) simulations. The API supports parsing and writing file formats applied by GROMACS (GROningen MAchine for Chemical Simulations), one of the most widely used MD simulation packages. JGromacs builds on the strengths of object-oriented programming in Java by providing a multilevel object-oriented representation of simulation data to integrate and interconvert sequence, structure, and dynamics information. The easy-to-learn, easy-to-use, and easy-to-extend framework is intended to simplify and accelerate the implementation and development of complex data analysis algorithms. Furthermore, a basic analysis toolkit is included in the package. The programmer is also provided with simple tools (e.g., XML-based configuration) to create applications with a user interface resembling the command-line interface of GROMACS applications. JGromacs and detailed documentation is freely available from http://sbcb.bioch.ox.ac.uk/jgromacs under a GPLv3 license .

Report on geotechnical tests with model structures Work Package - Deliverable number: WP 7.2 – D72.2

DEFF Research Database (Denmark)

Gintautas, Tomas; Sørensen, John Dalsgaard

2017-01-01

This report aims to give a comprehensive summary of the geotechnical tests with model structures that have been performed in work package 7.2 task 7.2.2 within the IRPWIND project. The large-scale tests are intended to determine soil-structure interaction effects in order to support probabilistic...... calculations of the reliability of offshore wind turbine support structures. These calculations are mainly performed in work package 7.4 of the IRPWIND project. However, this report already includes the development of a probabilistic model for the axial bearing capacity / resistance that is obtained using...

Experimental study on the properties of drum-packed, cement solidified waste package of pre and after sea dumping test of sea depth 30m and 100m

International Nuclear Information System (INIS)

Maki, Yasuro; Abe, Hirotoshi; Hattori, Seiichi

1976-01-01

Japan Marine Science and Technology Center has been tackling with the development of the monitoring system to confirm the soundness of drum-packed, cement-solidified low level radioactive waste (the package) during falling and after reaching at sea bed when it is dumped into sea. The test was carried out at Sagami Bay of 30 m and 100 m sea depth using non-radioactive packages. The observation of the falling behaviour of packages in sea was carried out by taking photographs of the motion of packages with an underwater 16 mm movie camera and an underwater industrial TV (ITV), and the observation of the soundness and the area of packages scattered on sea bed was carried out with an underwater ITV and an underwater 70 mm snap camera which were set up on the frame. The proportion of cement-solidified waste was decided so that the uni-axial compressive strength of the cement-solidified waste satisfies the condition of ''The tentative guideline''. Prior to tests at sea, hydrostatic pressure test of packages are carried out on land. After that, core specimens were sampled to obtain the uniaxial compressive strength from packages and were tested. After sea dumping tests, 6 packages were recovered from sea bed, and the soundness were tested. As the results, the deformation and damage of drums and cement solidified waste packages did not occur at all. (Kako, I.)

Characterization of the crystal orientation in mono-oriented films of HDPE/LLDPE blends by IR dichroism

Energy Technology Data Exchange (ETDEWEB)

Canevarolo, Sebastião V., E-mail: caneva@ufscar.br; Ravazzi, Camila; Silva, Jorge, E-mail: jorge.silva@ufscar.br [Departamento de Engenharia de Materiais, Universidade Federal de São Carlos Rod. Washington Luiz Km 235, 13565-905, SãoCarlos, SP - Brazil (Brazil); Elias, Marcelo [Motechfilm Produtos Plásticos, Estrada Municipal do Bonfim, 100, Pinhal, Cabreúva, SP - Brazil (Brazil)

2016-03-09

Polyethylene films are a common packaging material. The level and type of chain orientation in these films are a very important property which is of great care and concern of the converter personnel during the conformation process. Usually bi-orientation is the conventional procedure but when easy tear in one direction is needed mono-orientation is sought. This paper deal with the characterization of the crystalline orientation in films of polyethylene blends (HDPE/LLDPE) which have being oriented in two steps: initially the polymer was bi-oriented via extrusion-blown, cooled, and then in a second process hot stretched along the machine direction in order to produce mono-oriented films. In order to evaluate the orientation of the film, the polarization of the FT-IR beam was rotated 360° in steps of 5° by rotating the polarizer. In each step the absorbance spectrum was recorded and the corresponding dichroic ratio (DR) calculated after subtracting the baseline. With differential scanning calorimetry (DSC) was possible to infer about the changes in the morphology caused by the stretching.

Testing Object-Oriented Programs using Dynamic Aspects and Non-Determinism

DEFF Research Database (Denmark)

Achenbach, Michael; Ostermann, Klaus

2010-01-01

decisions exposing private data. We present an approach that both improves the expressiveness of test cases using non-deterministic choice and reduces design modifications using dynamic aspect-oriented programming techniques. Non-deterministic choice facilitates local definitions of multiple executions...... without parameterization or generation of tests. It also eases modelling naturally non-deterministic program features like IO or multi-threading in integration tests. Dynamic AOP facilitates powerful design adaptations without exposing test features, keeping the scope of these adaptations local to each...... test. We also combine non-determinism and dynamic aspects in a new approach to testing multi-threaded programs using co-routines....

PRIDE Surveillance Projects Data Packaging Project, Information Package Specification Version 1.0

Energy Technology Data Exchange (ETDEWEB)

Kelleher, D.M.; Shipp, R. L.; Mason, J. D.

2009-09-28

This document contains a specification for a standard XML document format called an information package that can be used to store information and the context required to understand and use that information in information management systems and other types of information archives. An information package consists of packaged information, a set of information metadata that describes the packaged information, and an XML signature that protects the packaged information. The information package described in this specification was designed to be used to store Department of Energy (DOE) and National Nuclear Security Administration (NNSA) information and includes the metadata required for that information: a unique package identifier, information marking that conforms to DOE and NNSA requirements, and access control metadata. Information package metadata can also include information search terms, package history, and notes. Packaged information can be text content, binary content, and the contents of files and other containers. A single information package can contain multiple types of information. All content not in a text form compatible with XML must be in a text encoding such as base64. Package information is protected by a digital XML signature that can be used to determine whether the information has changed since it was signed and to identify the source of the information. This specification has been tested but has not been used to create production information packages. The authors expect that gaps and unclear requirements in this specification will be identified as this specification is used to create information packages and as information stored in information packages is used. The authors expect to issue revised versions of this specification as needed to address these issues.

Documentation package for the RFID temperature monitoring system (Model 9977 packages at NTS)

International Nuclear Information System (INIS)

Chen, K.; Tsai, H.

2009-01-01

The technical basis for extending the Model 9977 shipping package periodic maintenance beyond the one-year interval to a maximum of five years is based on the performance of the O-ring seals and the environmental conditions. The DOE Packaging Certification Program (PCP) has tasked Argonne National Laboratory to develop a Radio-Frequency Identification (RFID) temperature monitoring system for use by the facility personnel at DAF/NTS. The RFID temperature monitoring system, depicted in the figure below, consists of the Mk-1 RFId tags, a reader, and a control computer mounted on a mobile platform that can operate as a stand-alone system, or it can be connected to the local IT network. As part of the Conditions of Approval of the CoC, the user must complete the prescribed training to become qualified and be certified for operation of the RFID temperature monitoring system. The training course will be administered by Argonne National Laboratory on behalf of the Headquarters Certifying Official. This is a complete documentation package for the RFID temperature monitoring system of the Model 9977 packagings at NTS. The documentation package will be used for training and certification. The table of contents are: Acceptance Testing Procedure of MK-1 RFID Tags for DOE/EM Nuclear Materials Management Applications; Acceptance Testing Result of MK-1 RFID Tags for DOE/EM Nuclear Materials Management Applications; Performance Test of the Single Bolt Seal Sensor for the Model 9977 Packaging; Calibration of Built-in Thermistors in RFID Tags for Nevada Test Site; Results of Calibration of Built-in Thermistors in RFID Tags; Results of Thermal Calibration of Second Batch of MK-I RFID Tags; Procedure for Installing and Removing MK-1 RFID Tag on Model 9977 Drum; User Guide for RFID Reader and Software for Temperature Monitoring of Model 9977 Drums at NTS; Software Quality Assurance Plan (SQAP) for the ARG-US System; Quality Category for the RFID Temperature Monitoring System; The

Packaging Technologies for High Temperature Electronics and Sensors

Science.gov (United States)

Chen, Liangyu; Hunter, Gary W.; Neudeck, Philip G.; Beheim, Glenn M.; Spry, David J.; Meredith, Roger D.

2013-01-01

This paper reviews ceramic substrates and thick-film metallization based packaging technologies in development for 500degC silicon carbide (SiC) electronics and sensors. Prototype high temperature ceramic chip-level packages and printed circuit boards (PCBs) based on ceramic substrates of aluminum oxide (Al2O3) and aluminum nitride (AlN) have been designed and fabricated. These ceramic substrate-based chiplevel packages with gold (Au) thick-film metallization have been electrically characterized at temperatures up to 550degC. A 96% alumina based edge connector for a PCB level subsystem interconnection has also been demonstrated recently. The 96% alumina packaging system composed of chip-level packages and PCBs has been tested with high temperature SiC devices at 500degC for over 10,000 hours. In addition to tests in a laboratory environment, a SiC JFET with a packaging system composed of a 96% alumina chip-level package and an alumina printed circuit board mounted on a data acquisition circuit board was launched as a part of the MISSE-7 suite to the International Space Station via a Shuttle mission. This packaged SiC transistor was successfully tested in orbit for eighteen months. A spark-plug type sensor package designed for high temperature SiC capacitive pressure sensors was developed. This sensor package combines the high temperature interconnection system with a commercial high temperature high pressure stainless steel seal gland (electrical feed-through). Test results of a packaged high temperature capacitive pressure sensor at 500degC are also discussed. In addition to the pressure sensor package, efforts for packaging high temperature SiC diode-based gas chemical sensors are in process.

Impact of female-oriented cigarette packaging in the United States.

Science.gov (United States)

Hammond, David; Doxey, Juliana; Daniel, Samantha; Bansal-Travers, Maansi

2011-07-01

Cigarette packaging is among the most prominent forms of tobacco marketing. This study examined the impact of cigarette pack design among young women in the United States. A national sample of 18- to 19-year-old females in the United States completed an online survey in February 2010. Participants were randomized to view eight cigarette packs designed according to one of four experimental conditions: fully branded female packs, same packs without descriptors (e.g., "slims"), same packs without brand imagery or descriptors ("plain" packs), and branded non-female brands. Participants rated packs on measures of appeal and health risk and completed a behavioral pack selection task. Fully branded female packs were rated significantly more appealing than the same packs without descriptors, "plain" packs, and non-female-branded packs. Female-branded packs were associated with a greater number of positive attributes including glamour, slimness, and attractiveness and were more likely to be perceived as less harmful. Approximately 40% of smokers and nonsmokers requested a pack at the end of the study; female-branded packs were 3 times more likely to be selected than plain packs. Plain packaging and removing descriptors such as "slims" from cigarette packs may reduce smoking susceptibility among young women.

Impact of Female-Oriented Cigarette Packaging in the United States

Science.gov (United States)

Doxey, Juliana; Daniel, Samantha; Bansal-Travers, Maansi

2011-01-01

Introduction: Cigarette packaging is among the most prominent forms of tobacco marketing. This study examined the impact of cigarette pack design among young women in the United States. Method: A national sample of 18- to 19-year-old females in the United States completed an online survey in February 2010. Participants were randomized to view eight cigarette packs designed according to one of four experimental conditions: fully branded female packs, same packs without descriptors (e.g., “slims”), same packs without brand imagery or descriptors (“plain” packs), and branded non-female brands. Participants rated packs on measures of appeal and health risk and completed a behavioral pack selection task. Results: Fully branded female packs were rated significantly more appealing than the same packs without descriptors, “plain” packs, and non–female-branded packs. Female-branded packs were associated with a greater number of positive attributes including glamour, slimness, and attractiveness and were more likely to be perceived as less harmful. Approximately 40% of smokers and nonsmokers requested a pack at the end of the study; female-branded packs were 3 times more likely to be selected than plain packs. Conclusion: Plain packaging and removing descriptors such as “slims” from cigarette packs may reduce smoking susceptibility among young women. PMID:21486994

equateIRT: An R Package for IRT Test Equating

Directory of Open Access Journals (Sweden)

Michela Battauz

2015-12-01

Full Text Available The R package equateIRT implements item response theory (IRT methods for equating different forms composed of dichotomous items. In particular, the IRT models included are the three-parameter logistic model, the two-parameter logistic model, the one-parameter logistic model and the Rasch model. Forms can be equated when they present common items (direct equating or when they can be linked through a chain of forms that present common items in pairs (indirect or chain equating. When two forms can be equated through different paths, a single conversion can be obtained by averaging the equating coefficients. The package calculates direct and chain equating coefficients. The averaging of direct and chain coefficients that link the same two forms is performed through the bisector method. Furthermore, the package provides analytic standard errors of direct, chain and average equating coefficients.

Experimental and theoretical analyses of package-on-package structure under three-point bending loading

International Nuclear Information System (INIS)

Jia Su; Wang Xi-Shu; Ren Huai-Hui

2012-01-01

High density packaging is developing toward miniaturization and integration, which causes many difficulties in designing, manufacturing, and reliability testing. Package-on-Package (PoP) is a promising three-dimensional high-density packaging method that integrates a chip scale package (CSP) in the top package and a fine-pitch ball grid array (FBGA) in the bottom package. In this paper, in-situ scanning electron microscopy (SEM) observation is carried out to detect the deformation and damage of the PoP structure under three-point bending loading. The results indicate that the cracks occur in the die of the top package, then cause the crack deflection and bridging in the die attaching layer. Furthermore, the mechanical principles are used to analyse the cracking process of the PoP structure based on the multi-layer laminating hypothesis and the theoretical analysis results are found to be in good agreement with the experimental results. (condensed matter: structural, mechanical, and thermal properties)

Safety analysis report for packaging: the ORNL DOT specification 6M - special form package

Energy Technology Data Exchange (ETDEWEB)

Schaich, R.W.

1982-07-01

The ORNL DOT Specification 6M - Special Form Package was fabricated at the Oak Ridge Nation al Laboratory (ORNL) for the transport of Type B solid non-fissile radioactive materials in special form. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities in special form of non-fissile radioactive materials.

Safety analysis report for packaging: the ORNL DOT specification 6M - special form package

International Nuclear Information System (INIS)

Schaich, R.W.

1982-07-01

The ORNL DOT Specification 6M - Special Form Package was fabricated at the Oak Ridge Nation al Laboratory (ORNL) for the transport of Type B solid non-fissile radioactive materials in special form. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities in special form of non-fissile radioactive materials

Safety analysis report for packaging: the ORNL DOT specification 6M - tritium trap package

International Nuclear Information System (INIS)

DeVore, J.R.

1984-04-01

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

Safety analysis report: packages. LP-50 tritium package (packaging of fissile and other radioactive materials). Final report

International Nuclear Information System (INIS)

Gates, A.A.; McCarthy, P.G.; Edl, J.W.

1975-04-01

Elemental tritium is shipped at low pressure in a stainless steel container (LP-50) sealed within an aluminum vessel and surrounded by a minimum of 4-in. thick Celotex insulation in a steel drum. The structural, thermal, containment, shielding, and criticality safety aspects of this package are evaluated. Procedures for loading and unloading, empty cask transport, acceptance testing and maintenance, and quality assurance requirements for the LP-50 package are described in detail. (U.S.)

Safety analysis report; packages LP-50 tritium package. (Packaging of fissile and other radioactive materials). Final report

International Nuclear Information System (INIS)

Gates, A.A.; McCarthy, P.G.; Edl, J.W.; Chalfant, G.G.

1975-05-01

Elemental tritium is shipped at low pressure in a stainless steel container (LP-50) surrounded by an aluminum vessel and Celotex insulation at least 4 in. thick in a steel drum. The total weight of the package is 260 lbs maximum. The various components that constitute the package are described and are shown in 7 figures. The safety analysis includes: structural evaluations; thermal evaluations; containment; operating procedures; acceptance tests and maintenance program; and design review

Radiation sterilization of plastic packing materials and aseptic packaging

International Nuclear Information System (INIS)

Tokuoka, Keiko

1986-01-01

In the present day of 'satiation', quality, not quantity, is emphasized for foods, the consumers being oriented toward raw and healthy foodstuff. Aseptic Packaging is excellent means of conservation. While conventionally chemicals have been used for sterilization of packing materials for aseptic packaging, the sterilization by radiation is used in part recently. The following are described : history of aseptic packaging and its features, sterilization by radiation, γ-ray sterilization of large-sized containers, the development of an aseptic packaging system using electron rays, the occurrence of offensive odors from packing materials (comparison of odors from various materials, volatile substances occurring in irradiated polyethylene, influence of film grade upon the formation of carboxylic acid, influence of the irradiation conditions upon the occurrences of volatile substances, volatile substances occurring in the irradiation of bag-in-box packing materials), changes in properties of the packing materials. (Mori, K.)

Safety Analysis Report for the KRI-ASM Transport Package

Energy Technology Data Exchange (ETDEWEB)

Bang, K. S.; Lee, J. C.; Kim, D. H.; Park, H. Y.; Kim, J. B.; Kim, H. J.; Seo, K. S

2005-11-15

Safety evaluation for the KRI-ASM transport package to transport safely I-131, which is produced at HANARO research reactor in KAERI, was carried out. In the safety analyses results for the KRI-ASM transport package, all the maximum stresses as well as the maximum temperature of the surface are lower than their allowable limits. The safety tests were performed by using the test model of the KRI-ASM transport package. Leak Test was performed after drop test and penetration test, the measured leakage rate was lower than allowable leakage rate. It is revealed that the containment integrity of the KRI-ASM transport package is maintained. Therefore, it shows that the integrity of the KRI-ASM transport package is well maintained.

Safety analysis report for packaging: the ORNL DOT Specification 20WC-5 - special form packaging

International Nuclear Information System (INIS)

Schaich, R.W.

1982-10-01

The ORNL DOT Specification 20WC-5 - Special Form Package was fabricated for the transport of large quantities of solid nonfissile radioactive materials in special form. The package was evaluated on the basis of tests performed at Sandia National Laboratories, Albuquerque, New Mexico on an identical fire and impact shield and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of large quantities of nonfissile radioactive materials in special form

Test Preparation in the Accountability Era: Toward a Learning-Oriented Approach

Science.gov (United States)

Gebril, Atta

2018-01-01

The article introduces a learning-oriented approach to test preparation that could help in easing the tension between learning and assessment. The first part of the article discusses the different concepts that are usually used in the context of test preparation. The second section reports on the literature pertaining to the effects of test…

The Ettention software package.

Science.gov (United States)

Dahmen, Tim; Marsalek, Lukas; Marniok, Nico; Turoňová, Beata; Bogachev, Sviatoslav; Trampert, Patrick; Nickels, Stefan; Slusallek, Philipp

2016-02-01

We present a novel software package for the problem "reconstruction from projections" in electron microscopy. The Ettention framework consists of a set of modular building-blocks for tomographic reconstruction algorithms. The well-known block iterative reconstruction method based on Kaczmarz algorithm is implemented using these building-blocks, including adaptations specific to electron tomography. Ettention simultaneously features (1) a modular, object-oriented software design, (2) optimized access to high-performance computing (HPC) platforms such as graphic processing units (GPU) or many-core architectures like Xeon Phi, and (3) accessibility to microscopy end-users via integration in the IMOD package and eTomo user interface. We also provide developers with a clean and well-structured application programming interface (API) that allows for extending the software easily and thus makes it an ideal platform for algorithmic research while hiding most of the technical details of high-performance computing. Copyright © 2015 Elsevier B.V. All rights reserved.

Japan's electronic packaging technologies

Science.gov (United States)

Tummala, Rao R.; Pecht, Michael

1995-02-01

The JTEC panel found Japan to have significant leadership over the United States in the strategic area of electronic packaging. Many technologies and products once considered the 'heart and soul' of U.S. industry have been lost over the past decades to Japan and other Asian countries. The loss of consumer electronics technologies and products is the most notable of these losses, because electronics is the United States' largest employment sector and is critical for growth businesses in consumer products, computers, automobiles, aerospace, and telecommunications. In the past there was a distinction between consumer and industrial product technologies. While Japan concentrated on the consumer market, the United States dominated the industrial sector. No such distinction is anticipated in the future; the consumer-oriented technologies Japan has dominated are expected to characterize both domains. The future of U.S. competitiveness will, therefore, depend on the ability of the United States to rebuild its technological capabilities in the area of portable electronic packaging.

Package performance evaluation: our latest 30-year experience

International Nuclear Information System (INIS)

Malesys, Pierre; Gagner, Laurent

2006-01-01

Packages for the transport of radioactive material have to comply with national and / or international regulations. These regulations are widely based on the requirements set forth by the International Atomic Energy Agency (IAEA) in the 'Regulations for the Safe Transport of Radioactive Material'. The packages designed to transport the most demanding contents are submitted to tests for demonstrating their ability to withstand accident conditions of transport. These tests are typically: - a nine-meter drop onto a flat and unyielding surface, - a one-meter drop onto a punch, - a 800 deg. C / 30 minutes fire, and an immersion under a head of water of either 0.9 m, or 15 m or 200 m (depending of the criteria to be considered). During the last 20 years, on several of its package designs, COGEMA LOGISTICS has performed tests and analyses to simulate extremely severe accidents. These tests and analysis include: 1. long duration fire test and deep immersion test on a package designed to transport plutonium oxide powder; - 2. deep immersion tests on scale model of packages designed to transport spent fuel, high level vitrified waste and fresh MOX (uranium and plutonium mixed oxide) fuel; - 3. burial in a soft ground of packages designed to transport spent fuel; - 4. numerical study of the thermal behaviour of packages designed to transport spent fuel and high level vitrified waste; - 5. aircraft crash test on scale models of dual-purpose packages for the transport and storage of spent fuel. The paper will: - review the tests and analysis which were performed; - show that our designs are able to withstand extremely severe conditions; - demonstrate that there is no cliff effect: should a failure occurs, it appears gradually and there is no sudden collapse of the package; - explain how compliance with all the regulatory requirements lead to high performances regarding each of them (for instance, in many cases, the need to meet radiation exposure criteria induces a mechanical

Which future energetic package?; Quel bouquet energetique futur

Energy Technology Data Exchange (ETDEWEB)

Chevallier, B.

2011-01-15

In this plenary session presided over by Olivier Appert (President of the IFP new Energies), are considered hypotheses, evolutions or constraints which will orient the making of this package while satisfying the need of people mobility and flashing a searchlight on the conditions and problems raised by the gas development. (O.M.)

CH Packaging Program Guidance

International Nuclear Information System (INIS)

2005-01-01

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 and 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.

Safety Analysis Report for the KRI-ALM Transport Package

Energy Technology Data Exchange (ETDEWEB)

Bang, K. S.; Lee, J. C.; Kim, D. H.; Park, H. Y.; Kim, J. B.; Kim, H. J.; Seo, K. S

2005-11-15

Safety evaluation for the KRI-ALM transport package to transport safely I-123, which is produced at Cyclotron in KIRAMS, was carried out. In the safety analyses results for the KRI-ALM transport package, all the maximum stresses as well as the maximum temperature of the surface are lower than their allowable limits. The safety tests were performed by using the test model of the KRI-ALM transport package. Leak Test was performed after drop test, the measured leakage rate was lower than allowable leakage rate. It is revealed that the containment integrity of the KRI-ALM transport package is maintained. Therefore, it shows that the integrity of the KRI-ALM transport package is well maintained.

Consumer response to packaging design: The role of packaging materials and graphics in sustainability perceptions and product evaluations

NARCIS (Netherlands)

Steenis, N.D.; Herpen, E. van; Lans, I.A. van der; Ligthart, T.N.; Trijp, H.C.M. van

2017-01-01

Building on theories of cue utilization, this paper investigates whether and how packaging sustainability influences consumer perceptions, inferences and attitudes towards packaged products. A framework is tested in an empirical study among 249 students using soup products varying in packaging

Thermal analysis of NNWSI conceptual waste package designs

International Nuclear Information System (INIS)

Stein, W.; Hockman, J.N.; O'Neal, W.C.

1984-04-01

Lawrence Livermore National Laboratory is involved in the design and testing of high-level nuclear waste packages. Many of the aspects of waste package design and testing (e.g., corrosion and leaching) depend in part on the temperature history of the emplaced packages. This report discusses thermal modeling and analysis of various emplaced waste package conceptual designs including the models used, the assumptions and approximations made, and the results obtained. 16 references

A Thermodynamics Course Package in Onenote

Science.gov (United States)

Falconer, John L.; Nicodemus, Garret D.; Medlin, J. Will; deGrazia, Janet; McDanel, Katherine P.

2014-01-01

A ready-to-use package of active-learning materials for a semester-long chemical engineering thermodynamics course was prepared for instructors, and similar materials are being prepared for a material and energy balance course. The course package includes ConcepTests, explanations of the ConcepTests for instructors, links to screencasts, chapter…

Safety Analysis Report - Packages, 9965, 9968, 9972-9975 Packages

International Nuclear Information System (INIS)

Van Alstine, M.N.

1999-01-01

This Safety Analysis Report for Packaging (SARP) documents the performance of the 9965 B, 9968 B, 9972 B(U), 9973 B(U), 9974 B(U), and 9975 B(U) packages in satisfying the regulatory safety requirements of the Code of Federal Regulations (CFR) 711 and the International Atomic Energy Agency (IAEA) Safety Series No. 6, Regulations for the Safe Transport of Radioactive Material, 1985 edition2. Results of the analysis and testing performed on the 9965 B, 9968 B, 9972 B(U), 9973 B(U), 9974 B(U), and 9975 B(U) packages are presented in this SARP, which was prepared in accordance with U.S. Department of energy (DOE) Order 5480.33 and in the format specified in the Nuclear Regulatory Commission (NRC) Regulatory Guides 7.94 and 7.10.5

Safety analysis report - packages 9965, 9968, 9972-9975 packages

International Nuclear Information System (INIS)

Van Alstine, M.N.

1997-10-01

This Safety Analysis Report for Packaging (SARP) documents the performance of the 9965 B( ), 9968 B( ), 9972 B(U), 9973 B(U), 9974 B(U), and 9975 B(U) packages in satisfying the regulatory safety requirements of the Code of Federal Regulations (CFR) 10 CFR 71 and the International Atomic Energy Agency (IAEA) Safety Series No. 6, Regulations for the Safe Transport of Radioactive Material, 1985 edition. Results of the analysis and testing performed on the 9965 B(), 9968 B(), 9972 B(U), 9973 B(U), and 9975 B(U) packages are presented in this SARP, which was prepared in accordance with U.S. Department of Energy (DOE) Order 5480.3 and in the format specified in the Nuclear Regulatory Commission (NRC) Regulatory Guides 7.9 and 7.10

Review of waste package verification tests. Semiannual report, October 1984-March 1985

International Nuclear Information System (INIS)

Soo, P.

1985-07-01

The potential of WAPPA, a second-generation waste package system code, to meet the needs of the regulatory community is analyzed. The analysis includes an indepth review of WAPPA's individual process models and a review of WAPPA's operation. It is concluded that the code is of limited use to the NRC in the present form. Recommendations for future improvement, usage, and implementation of the code are given. This report also describes the results of a testing program undertaken to determine the chemical environment that will be present near a high-level waste package emplaced in a basalt repository. For this purpose, low carbon 1020 steel (a current BWIP reference container material), synthetic basaltic groundwater and a mixture of bentonite and basalt were exposed, in an autoclave, to expected conditions some period after repository sealing (150 0 C, approx. =10.4 MPa). Parameters measured include changes in gas pressure with time and gas composition, variation in dissolved oxygen (DO), pH and certain ionic concentrations of water in the packing material across an imposed thermal gradient, mineralogic alteration of the basalt/bentonite mixture, and carbon steel corrosion behavior. A second testing program was also initiated to check the likelihood of stress corrosion cracking of austenitic stainless steels and Incoloy 825 which are being considered for use as waste container materials in the tuff repository program. 82 refs., 70 figs., 27 tabs

[Action-oriented versus state-oriented reactions to experimenter-induced failures].

Science.gov (United States)

Brunstein, J C

1989-01-01

The present study assessed different effects of action-oriented versus state-oriented styles of coping with failure on achievement-related performance and cognition. In a learned helplessness experiment, students were exposed to an academic failure situation and were then tested on a series of problem-solving tasks, either immediately after the pretreatment or after a delay of 24 hours. Performance and cognitive concomitants were measured during both experimental periods. Results demonstrated that action orientation was associated with self-immunizing cognitions during helplessness training. Action-oriented participants improved their performance level even after repeated failure feedbacks. Moreover, action-oriented students assigned to the delayed test condition responded with increased striving for success and showed performance increments, even in comparison with control subjects. In contrast, state-oriented participants developed symptoms of helplessness and showed impaired performance during failure inductions. In later tests on problem-solving tasks, state-oriented groups responded with increased fear of failure. Independent of immediate or delayed test conditions, they soon lapsed into new performance decrements.

Developing a Standard Method of Test for Packaged, Solid-Desiccant Based Dehumidification Systems

International Nuclear Information System (INIS)

Sand, J.R.

2001-01-01

A draft Method of Test (MOT) has been proposed for packaged, air-to-air, desiccant-based dehumidifier systems that incorporate a thermally-regenerated desiccant material for dehumidification. This MOT is intended to function as the ''system'' testing and rating compliment to the desiccant ''component'' (desiccant wheels and/or cassettes) MOT (ASHRAE 1998) and rating standard (ARI 1998) already adopted by industry. This draft standard applies to ''packaged systems'' that: Use desiccants for dehumidification of conditioned air for buildings; Use heated air for regeneration of the desiccant material; Include fans for moving process and regeneration air; May include other system components for filtering, pre-cooling, post-cooling, or heating conditioned air; and May include other components for humidification of conditioned air. The proposed draft applies to four different system operating modes depending on whether outdoor or indoor air is used for process air and regeneration air streams . Only the ''ventilation'' mode which uses outdoor air for both process and regeneration inlets is evaluated in this paper. Performance of the dehumidification system is presented in terms that would be most familiar and useful to designers of building HVAC systems to facilitate integration of desiccant equipment with more conventional hardware. Parametric performance results from a modified, commercial desiccant dehumidifier undergoing laboratory testing were used as data input to evaluate the draft standard. Performance results calculated from this experimental input, results from an error-checking/heat-balance verification test built into the standard, and estimated comparisons between desiccant and similarly performing conventional dehumidification equipment are calculated and presented. Some variations in test procedures are suggested to aid in analytical assessment of individual component performance

The relation between knee muscle strength and performance tests in orienteering athletes.

Science.gov (United States)

Çinar-Medeni, Özge; Colakoglu, Fatma F; Yüce, Koray; Ipekoğlu, Gökhan; Baltaci, Gul

2016-11-01

The aim of this study was to analyze the effect of knee muscle strength on performance tests in orienteers. Thirty-seven orienteers were voluntarily included in this study. Isokinetic knee flexor and extensor muscles' strength was assessed at 120°/s velocity for both "dominant leg" (DL) and "non-dominant leg" (NDL). "Single-legged hop test" (SLHT), "flamingo balance test" (FBT), "star excursion balance test" (SEBT), vertical jump-and-reach test (for anaerobic power), T-drill test and 20-meter shuttle run test (for aerobic power) were carried out. Correlation and regression analyses were performed on the data. VO2max levels showed moderate correlations with DL's "flexor peak torque" (FPT) and NDL's "extensor peak torque" (EPT) and FPT values respectively (r=0.49, r=0.38, r=0.58). FPT of NDL was a predictor of VO2max level (R2=0.33). Anaerobic power has a relationship with EPT of NDL (r=0.43) and T-drill test with EPT and FPT values of both DL and NDL respectively (r=-0.35, r=-0.63, r=-0.53, r=-0.58). EPT of NDL was a predictor for anaerobic power (R2=0.19) and FPT of DL for agility (R2=0.40). Nonparametric linear regression results showed that EPT is a predictor in DL (median slope=-0.71, P=0.01), and FPT in NDL (median slope=-0.90, P=0.006) for FBT. FPT was a predictor of SEBT scores for both legs (0.13orienteering performance.

Optimization of an impact limiter for radioactive waste packaging

International Nuclear Information System (INIS)

Mourao, Rogerio Pimenta; Mattar Neto, Miguel

1999-01-01

A certain class of packages for the transportation of radioactive wastes - type B packages in the transport jargon - is supposed to resist to a series of postulated tests, the most severe for the majority of the packages being the 9 m height drop test. To improve the performance of the packages under this test, impact limiters are added to them, normally as a removable overpack, with the primary goal of reducing the deceleration loads transmitted to the packages and their contents. The first impact limiter concept, developed during the '70s, used a shell-type impact limiter attached to both ends of the package. Later on, wood was tested as impact limiter filling, which improved the package's mechanical performance, but not its thermal resistance. The popularization of the polymeric materials and their growing use in engineer applications have led to the use of these materials in impact limiters, with the extra advantage of the polymers good thermal properties. This paper proposes a methodology for the optimization of an impact limiter for a package for the conditioning of spent sealed sources. Two simplified methods for the design of impact limiters are presented. Finally, a brief discussion is presented on the methodology usually employed in the design of accident-resisting packages. (author)

Safety analysis report for packaging (onsite) doorstop samplecarrier system

Energy Technology Data Exchange (ETDEWEB)

Obrien, J.H.

1997-02-24

The Doorstop Sample Carrier System consists of a Type B certified N-55 overpack, U.S. Department of Transportation (DOT) specification or performance-oriented 208-L (55-gal) drum (DOT 208-L drum), and Doorstop containers. The purpose of the Doorstop Sample Carrier System is to transport samples onsite for characterization. This safety analysis report for packaging (SARP) provides the analyses and evaluation necessary to demonstrate that the Doorstop Sample Carrier System meets the requirements and acceptance criteria for both Hanford Site normal transport conditions and accident condition events for a Type B package. This SARP also establishes operational, acceptance, maintenance, and quality assurance (QA) guidelines to ensure that the method of transport for the Doorstop Sample Carrier System is performed safely in accordance with WHC-CM-2-14, Hazardous Material Packaging and Shipping.

In-Package Chemistry Abstraction

Energy Technology Data Exchange (ETDEWEB)

P.S. Domski

2003-07-21

The work associated with the development of this model report was performed in accordance with the requirements established in ''Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA'' (BSC 2002a). The in-package chemistry model and in-package chemistry model abstraction are developed to predict the bulk chemistry inside of a failed waste package and to provide simplified expressions of that chemistry. The purpose of this work is to provide the abstraction model to the Performance Assessment Project and the Waste Form Department for development of geochemical models of the waste package interior. The scope of this model report is to describe the development and validation of the in-package chemistry model and in-package chemistry model abstraction. The in-package chemistry model will consider chemical interactions of water with the waste package materials and the waste form for commercial spent nuclear fuel (CSNF) and codisposed high-level waste glass (HLWG) and N Reactor spent fuel (CDNR). The in-package chemistry model includes two sub-models, the first a water vapor condensation (WVC) model, where water enters a waste package as vapor and forms a film on the waste package components with subsequent film reactions with the waste package materials and waste form--this is a no-flow model, the reacted fluids do not exit the waste package via advection. The second sub-model of the in-package chemistry model is the seepage dripping model (SDM), where water, water that may have seeped into the repository from the surrounding rock, enters a failed waste package and reacts with the waste package components and waste form, and then exits the waste package with no accumulation of reacted water in the waste package. Both of the submodels of the in-package chemistry model are film models in contrast to past in-package chemistry models where all of the waste package pore space was filled with water. The

In-Package Chemistry Abstraction

International Nuclear Information System (INIS)

P.S. Domski

2003-01-01

The work associated with the development of this model report was performed in accordance with the requirements established in ''Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA'' (BSC 2002a). The in-package chemistry model and in-package chemistry model abstraction are developed to predict the bulk chemistry inside of a failed waste package and to provide simplified expressions of that chemistry. The purpose of this work is to provide the abstraction model to the Performance Assessment Project and the Waste Form Department for development of geochemical models of the waste package interior. The scope of this model report is to describe the development and validation of the in-package chemistry model and in-package chemistry model abstraction. The in-package chemistry model will consider chemical interactions of water with the waste package materials and the waste form for commercial spent nuclear fuel (CSNF) and codisposed high-level waste glass (HLWG) and N Reactor spent fuel (CDNR). The in-package chemistry model includes two sub-models, the first a water vapor condensation (WVC) model, where water enters a waste package as vapor and forms a film on the waste package components with subsequent film reactions with the waste package materials and waste form--this is a no-flow model, the reacted fluids do not exit the waste package via advection. The second sub-model of the in-package chemistry model is the seepage dripping model (SDM), where water, water that may have seeped into the repository from the surrounding rock, enters a failed waste package and reacts with the waste package components and waste form, and then exits the waste package with no accumulation of reacted water in the waste package. Both of the submodels of the in-package chemistry model are film models in contrast to past in-package chemistry models where all of the waste package pore space was filled with water. The current in-package

The taxlist package: managing plant taxonomic lists in R

Directory of Open Access Journals (Sweden)

Miguel Alvarez

2018-05-01

Full Text Available Taxonomic lists are crucial elements of vegetation-plot databases and provide the links between original entries, reference taxon views and different taxon concepts. We introduce the R package taxlist in the context of object-oriented modelling for taxonomic lists. This package provides a data structure based on species lists in Turboveg, which is a software broadly used for the storage of vegetation-plot databases and implements functions for importing and handling them prior to statistical analysis. We also present a schema for relational databases, compatible with taxlist objects and recommend its use for handling diversity records.

The particle tracking package Kassiopeia

Energy Technology Data Exchange (ETDEWEB)

Groh, Stefan [Karlsruhe Institute of Technology (Germany); Collaboration: KATRIN-Collaboration

2016-07-01

The Kassiopeia particle tracking framework is an object-oriented software package utilizing modern C++ techniques, written originally to meet the needs of the Katrin collaboration. Kassiopeia's target consists of simulating particle trajectories governed by arbitrarily complex differential equations of motion, continuous physics processes that may in part be modeled as terms perturbing that equation of motion, stochastic processes that occur in flight such as bulk scattering and decay, and potentially stochastic surface processes occurring at interfaces, including transmission and reflection effects. This entire set of computations takes place against the backdrop of a fully-featured geometry package which serves a variety of roles, including initialization of electromagnetic field simulations, gas flow simulations, and the support of state-dependent algorithm-swapping and behavioral changes. Kassiopeia has been well validated and widely used within the Katrin collaboration, playing a primary role in many theses and refereed publications.

WIPP/SRL in-situ tests: MIIT program--The effects of metal package components

International Nuclear Information System (INIS)

Covington, J.A.; Wicks, G.G.; Molecke, M.A.

1991-01-01

The Materials Interface Interactions Tests or MIIT is the largest in-situ testing program in progress, involving burial of many simulated nuclear waste systems and accompanying package components. In MIIT, waste glass samples were fabricated into the shape of 'pineapple slices', polished on one side. Proposed package components were also made into a similar configuration and the various glasses, metals, and geologic samples were than stacked onto heater elements within Teflon assemblies. This produced interactions of interest by creating glass/glass, glass/salt, and glass/metal interfaces. Since the outer diameter of the metal was smaller than the outer diameter of the glass, a lip was created which was also produced a glass/liquid interface, which was also studied. Overall, a total of 50 stacks or assemblies of pineapple slices were created in seven different stacking arrangements. Each individual assembly was then installed in an instrumented borehole at WIPP. Brine was then added to most of boreholes and the assemblies heated and maintained at 90 degrees C. This was achieved by energizing the central heating and rod that traversed through the middle opening of each of the pineapple slices in each assembly. Due to the design of these units, glass, metal and geologic samples could be removed at time intervals of 6 mos., 1 year, 2 years, and 5 years. Currently, all but the 5 year samples have been removed from test and are being evaluated in laboratories of MIIT participants

Alternate Materials In Design Of Radioactive Material Packages

International Nuclear Information System (INIS)

Blanton, P.; Eberl, K.

2010-01-01

This paper presents a summary of design and testing of material and composites for use in radioactive material packages. These materials provide thermal protection and provide structural integrity and energy absorption to the package during normal and hypothetical accident condition events as required by Title 10 Part 71 of the Code of Federal Regulations. Testing of packages comprising these materials is summarized.

Intercomparison of PIXE spectrometry software packages

International Nuclear Information System (INIS)

2003-02-01

During the year 2000, an exercise was organized to make a intercomparison of widely available software packages for analysis of particle induced X ray emission (PIXE) spectra. This TECDOC describes the method used in this intercomparison exercise and presents the results obtained. It also gives a general overview of the participating software packages. This includes basic information on their user interface, graphical presentation capabilities, physical phenomena taken in account, way of presenting results, etc. No recommendation for a particular software package or method for spectrum analysis is given. It is intended that the readers reach their own conclusions and make their own choices, according to their specific needs. This TECDOC will be useful to anyone involved in PIXE spectrum analysis. This TECDOC includes a companion CD with the complete set of test spectra used for intercomparison. The test spectra on this CD can be used to test any PIXE spectral analysis software package

Manager personality, manager service quality orientation, and service climate: test of a model.

Science.gov (United States)

Salvaggio, Amy Nicole; Schneider, Benjamin; Nishii, Lisa H; Mayer, David M; Ramesh, Anuradha; Lyon, Julie S

2007-11-01

This article conceptually and empirically explores the relationships among manager personality, manager service quality orientation, and climate for customer service. Data were collected from 1,486 employees and 145 managers in grocery store departments (N = 145) to test the authors' theoretical model. Largely consistent with hypotheses, results revealed that core self-evaluations were positively related to managers' service quality orientation, even after dimensions of the Big Five model of personality were controlled, and that service quality orientation fully mediated the relationship between personality and global service climate. Implications for personality and organizational climate research are discussed. (c) 2007 APA

Test and evaluation report for Lockheed Idaho Technologies Company, arrow-pak packaging, docket 95-40-7A, type A container

International Nuclear Information System (INIS)

Kelly, D.L.

1996-01-01

This report incorporates the U.S. Department of Energy, Office of Facility Safety Analysis (DOE/EH-32) approval letter for packaging use. This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance test results of the Arrow-Pak packaging. The Arrow-Pak packaging system consists of Marlex M-8000 Driscopipe, manufactured by Phillips-Driscopipe, Inc., and is sealed with two dome-shaped end caps manufactured from the same materials. The patented sealing process involves the use of electrical energy to heat opposing faces of the pipe and end caps, and hydraulic rams to press the heated surfaces together. This fusion process produces a homogeneous bonding of the end cap to the pipe. The packaging may be used with or without the two internal plywood spacers. This packaging configuration described in this report is designed to ship Type A quantities of solid radioactive materials

Power cycling test of a 650 V discrete GaN-on-Si power device with a laminated packaging embedding technology

DEFF Research Database (Denmark)

Song, Sungyoung; Munk-Nielsen, Stig; Uhrenfeldt, Christian

2017-01-01

A GaN-on-Si power device is a strong candidate to replace power components based on silicon in high-end market for low-voltage applications, thanks to its electrical characteristics. To maximize opportunities of the GaN device in field applications, a package technology plays an important role...... in a discrete GaN power device. A few specialized package technologies having very lower stray inductance and higher thermal conductivity have been proposed for discrete GaN-on-Si power devices. Despite their superior performance, there has been little discussion of their reliability. The paper presents a power...... cycling test of a discrete GaN power device employing a laminated embedded packaging technology subjected to 125 degrees Celsius junction temperature swing. Failure modes are described with collected electrical characteristics and measured temperature data under the test. In conclusion, physical...

Leak testing United States Nuclear Regulatory Commission type b packaging

International Nuclear Information System (INIS)

Lacy, K.A.

1995-01-01

The Waste Isolation Pilot Plant (WTPP) is a one of its kind research and development facility operated by the Department of Energy, Carlsbad Area Office. Located in southeastern New Mexico, the WTPP is designed to demonstrate the safe, permanent disposal of transuranic (TRU) radioactive nuclear waste, accumulated from 40 years of nuclear weapons production. Before the waste can be disposed of, it must first be safely transported from generator storage sites to the WIPP. To accomplish this, the TRUPACT-II was designed and fabricated. This double containment, non-vented waste packaging successfully completed a rigorous testing program, and in 1989 received a Certificate of Compliance (C of C) from the Nuclear Regulatory Commission (NRC). Currently, the TRUPACT-II is in use at Idaho National Engineering Laboratory to transport waste on site for characterization. The DOE/CAO is responsible for maintaining the TRUPACT-II C of C. The C of C requires performance of nondestructive examination (NDE), e.g., visual testing (VT), dimensional inspections, Liquid Dye Penetrant testing (PT), and Helium Leak Detection (HLD). The Waste Isolation Division (WID) uses HLD for verification of the containment integrity. The following HLD tests are performed on annual basis or when required, i.e. repairs or component replacement: (1) fabrication verification leak tests on both the outer containment vessel (OCV) and the inner containment vessel (ICV); (2) assembly verification leak tests on the OCV and ICV upper main o-rings; and (3) assembly verification leak tests on the OCV and the ICV vent port plugs. These tests are addressed in detail as part of this presentation

Wafer-level micro-optics: trends in manufacturing, testing, packaging, and applications

Science.gov (United States)

Voelkel, Reinhard; Gong, Li; Rieck, Juergen; Zheng, Alan

2012-11-01

Micro-optics is an indispensable key enabling technology (KET) for many products and applications today. Probably the most prestigious examples are the diffractive light shaping elements used in high-end DUV lithography steppers. Highly efficient refractive and diffractive micro-optical elements are used for precise beam and pupil shaping. Micro-optics had a major impact on the reduction of aberrations and diffraction effects in projection lithography, allowing a resolution enhancement from 250 nm to 45 nm within the last decade. Micro-optics also plays a decisive role in medical devices (endoscopes, ophthalmology), in all laser-based devices and fiber communication networks (supercomputer, ROADM), bringing high-speed internet to our homes (FTTH). Even our modern smart phones contain a variety of micro-optical elements. For example, LED flashlight shaping elements, the secondary camera, and ambient light and proximity sensors. Wherever light is involved, micro-optics offers the chance to further miniaturize a device, to improve its performance, or to reduce manufacturing and packaging costs. Wafer-scale micro-optics fabrication is based on technology established by semiconductor industry. Thousands of components are fabricated in parallel on a wafer. We report on the state of the art in wafer-based manufacturing, testing, packaging and present examples and applications for micro-optical components and systems.

Investigating the effect of aesthetic aspect of packaging and its dimensions on purchase intention through packaging preference

OpenAIRE

Abolghasem Ebrahimi; Sayed Moslem Alavi; Mehdi Najafi Seyahroodi

2015-01-01

Companies in the era of quality convergence of products are bound to differentiation. As a differentiating tool, Packaging can be a troubleshooter in this field. One of the ways of differentiation is to consider aesthetic aspect of packaging. According to this fact, current survey has studied the impact of aesthetic aspect of packaging on purchase intention of goods through packaging preference. A sample consisted of 384 customers of the big food stores in Shiraz is selected. To test the vali...

Simplified analytical solutions for free drops during NCT for radioactive material packagings

International Nuclear Information System (INIS)

Gupta, N.K.

1997-01-01

To ensure structural integrity during normal conditions of transport (NCT), Federal regulations in 10CFR71.71 require that the nuclear material package designs be evaluated for the effects of free drops. The vessel stress acceptance criteria for these drops are given in Regulatory Guide 7.6 and ASME Section III Code. During initial phases of the package design, the effects of the NCT free drops can be evaluated by simplified analytical solutions which will ensure that the safety margins specified in R. G. 7.6 are met. These safety margins can be verified during the final stages of the package design with dynamic analyses using finite element methods. This paper calculates the maximum impact open-quotes gclose quotes loading on the vessels using single degree of freedom models for different drop orientations. Only end, bottom, and corner drops are analyzed for cylindrical packages or packages with cylindrical ends

High-voltage leak detection of a parenteral proteinaceous solution product packaged in form-fill-seal plastic laminate bags. Part 1. Method development and validation.

Science.gov (United States)

Damgaard, Rasmus; Rasmussen, Mats; Buus, Peter; Mulhall, Brian; Guazzo, Dana Morton

2013-01-01

In Part 1 of this three-part research series, a leak test performed using high-voltage leak detection (HVLD) technology, also referred to as an electrical conductivity and capacitance leak test, was developed and validated for container-closure integrity verification of a small-volume laminate plastic bag containing an aqueous solution for injection. The sterile parenteral product is the rapid-acting insulin analogue, insulin aspart (NovoRapid®/NovoLog®, by Novo Nordisk A/S, Bagsværd, Denmark). The aseptically filled and sealed package is designed to preserve product sterility through expiry. Method development and validation work incorporated positive control packages with a single hole laser-drilled through the laminate film of each bag. A unique HVLD method characterized by specific high-voltage and potentiometer set points was established for testing bags positioned in each of three possible orientations as they are conveyed through the instrument's test zone in each of two possible directions-resulting in a total of six different test method options. Validation study results successfully demonstrated the ability of all six methods to accurately and reliably detect those packages with laser-drilled holes from 2.5-11.2 μm in nominal diameter. Part 2 of this series will further explore HVLD test results as a function of package seal and product storage variables. The final Part 3 will report the impact of HVLD exposure on product physico-chemical stability. In this Part 1 of a three-part research series, a leak test method based on electrical conductivity and capacitance, called high voltage leak detection (HVLD), was used to find leaks in small plastic bags filled with an insulin pharmaceutical solution for human injection by Novo Nordisk A/S (Bagsværd, Denmark). To perform the test, the package is electrically grounded while being conveyed past an electrode linked to a high-voltage, low-amperage transformer. The instrument measures the current that passes

RH Packaging Operations Manual

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2003-01-01

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 at wipp.ws for approval

DOT-7A Type A packaging design guide

International Nuclear Information System (INIS)

Kelly, D.L.

1995-01-01

The purpose of this Design Guide is to provide instruction for designing a U.S. Department of Transportation Specification 7A (DOT-7A) Type A packaging. Another purpose for this Design Guide is to support the evaluation and testing activities that are performed on new designs by a U.S. Department of Energy (DOE) test facility. This evaluation and testing program is called the DOT-7A Program. When an applicant has determined that a DOT-7A packaging is needed and not commercially available, a design may be created according to this document. The design should include a packaging drawing, specifications, analysis report, operating instructions, and a Packaging Qualification Checklist; all of which should be forwarded to a DOE/HQ approved test facility for evaluation and testing. This report is being submitted through the Engineering Documentation System so that it may be used for reference and information purposes

Testing all six person-oriented principles in dynamic factor analysis.

Science.gov (United States)

Molenaar, Peter C M

2010-05-01

All six person-oriented principles identified by Sterba and Bauer's Keynote Article can be tested by means of dynamic factor analysis in its current form. In particular, it is shown how complex interactions and interindividual differences/intraindividual change can be tested in this way. In addition, the necessity to use single-subject methods in the analysis of developmental processes is emphasized, and attention is drawn to the possibility to optimally treat developmental psychopathology by means of new computational techniques that can be integrated with dynamic factor analysis.

A Generalized Correlation Plot Package for the CEBAF Control System

International Nuclear Information System (INIS)

D. Wu; W. Akers; S. Schaffner; H. Shoaee; W. A. Watson; D. Wetherholt

1996-01-01

The Correlation Package is a general facility for data acquisition and analysis serving as an online environment for performing a wide variety of machine physics experiments and engineering diagnostics. Typical correlation experiments consist of an initial set of actions followed by stepping one or two accelerator parameters while measuring up to several hundred control system parameters. The package utilizes the CDEV [1] device API to access accelerator systems. A variety of analysis and graphics tools are included through integration with the Matlab math modeling package. A post- acquisition script capability is available to automate the data reduction process. A callable interface allows this facility to serve as the data acquisition and analysis engine for high level applications. A planned interface to archived accelerator data will allow the same analysis and graphics tools to be used for viewing and correlating history data. The object oriented design and C++ implementation details as well as the current status of the Correlation Package will be presented

Thermal analysis of transportation packaging for nuclear spent fuel

International Nuclear Information System (INIS)

Akamatsu, Hiroshi; Taniuchi, Hiroaki

1989-01-01

Safety analysis of transportation packaging for nuclear spent fuel comprises structural, thermal, containment, shielding and criticality factors, and the safety of a packaging is verified by these analyses. In thermal analysis, the temperature of each part of the packaging is calculated under normal and accident test conditions. As an example of thermal analysis, the temperature distribution of a packaging being subjected to a normal test was calculated by the TRUMP code and compared with measured data. (author)

Feasibility study using hypothesis testing to demonstrate containment of radionuclides within waste packages

International Nuclear Information System (INIS)

Thomas, R.E.

1986-04-01

The purpose of this report is to apply methods of statistical hypothesis testing to demonstrate the performance of containers of radioactive waste. The approach involves modeling the failure times of waste containers using Weibull distributions, making strong assumptions about the parameters. A specific objective is to apply methods of statistical hypothesis testing to determine the number of container tests that must be performed in order to control the probability of arriving at the wrong conclusions. An algorithm to determine the required number of containers to be tested with the acceptable number of failures is derived as a function of the distribution parameters, stated probabilities, and the desired waste containment life. Using a set of reference values for the input parameters, sample sizes of containers to be tested are calculated for demonstration purposes. These sample sizes are found to be excessively large, indicating that this hypothesis-testing framework does not provide a feasible approach for demonstrating satisfactory performance of waste packages for exceptionally long time periods

Web based aphasia test using service oriented architecture (SOA)

International Nuclear Information System (INIS)

Voos, J A; Vigliecca, N S; Gonzalez, E A

2007-01-01

Based on an aphasia test for Spanish speakers which analyze the patient's basic resources of verbal communication, a web-enabled software was developed to automate its execution. A clinical database was designed as a complement, in order to evaluate the antecedents (risk factors, pharmacological and medical backgrounds, neurological or psychiatric symptoms, brain injury -anatomical and physiological characteristics, etc) which are necessary to carry out a multi-factor statistical analysis in different samples of patients. The automated test was developed following service oriented architecture and implemented in a web site which contains a tests suite, which would allow both integrating the aphasia test with other neuropsychological instruments and increasing the available site information for scientific research. The test design, the database and the study of its psychometric properties (validity, reliability and objectivity) were made in conjunction with neuropsychological researchers, who participate actively in the software design, based on the patients or other subjects of investigation feedback

Web based aphasia test using service oriented architecture (SOA)

Energy Technology Data Exchange (ETDEWEB)

Voos, J A [Clinical Engineering R and D Center, Universidad Tecnologica Nacional, Facultad Regional Cordoba, Cordoba (Argentina); Vigliecca, N S [Consejo Nacional de Investigaciones Cientificas y Tecnicas, CONICET, Cordoba (Argentina); Gonzalez, E A [Clinical Engineering R and D Center, Universidad Tecnologica Nacional, Facultad Regional Cordoba, Cordoba (Argentina)

2007-11-15

Based on an aphasia test for Spanish speakers which analyze the patient's basic resources of verbal communication, a web-enabled software was developed to automate its execution. A clinical database was designed as a complement, in order to evaluate the antecedents (risk factors, pharmacological and medical backgrounds, neurological or psychiatric symptoms, brain injury -anatomical and physiological characteristics, etc) which are necessary to carry out a multi-factor statistical analysis in different samples of patients. The automated test was developed following service oriented architecture and implemented in a web site which contains a tests suite, which would allow both integrating the aphasia test with other neuropsychological instruments and increasing the available site information for scientific research. The test design, the database and the study of its psychometric properties (validity, reliability and objectivity) were made in conjunction with neuropsychological researchers, who participate actively in the software design, based on the patients or other subjects of investigation feedback.

Cigarette package design: opportunities for disease prevention.

Science.gov (United States)

Difranza, J R; Clark, D M; Pollay, R W

2002-06-15

To learn how cigarette packages are designed and to determine to what extent cigarette packages are designed to target children. A computer search was made of all Internet websites that post tobacco industry documents using the search terms: packaging, package design, package study, box design, logo, trademark and design study. All documents were retrieved electronically and analyzed by the first author for recurrent themes. Cigarette manufacturers devote a great deal of attention and expense to package design because it is central to their efforts to create brand images. Colors, graphic elements, proportioning, texture, materials and typography are tested and used in various combinations to create the desired product and user images. Designs help to create the perceived product attributes and project a personality image of the user with the intent of fulfilling the psychological needs of the targeted type of smoker. The communication of these images and attributes is conducted through conscious and subliminal processes. Extensive testing is conducted using a variety of qualitative and quantitative research techniques. The promotion of tobacco products through appealing imagery cannot be stopped without regulating the package design. The same marketing research techniques used by the tobacco companies can be used to design generic packaging and more effective warning labels targeted at specific consumers.

Drop Tests Results Of Revised Closure Bolt Configuration Of The Standard Waste Box, Standard Large Box 2, And Ten Drum Overpack Packagings

International Nuclear Information System (INIS)

May, C.; Opperman, E.; Mckeel, C.

2010-01-01

The Transuranic (TRU) Disposition Project at Savannah River Site will require numerous transfers of radioactive materials within the site boundaries for sorting and repackaging. The three DOT Type A shipping packagings planned for this work have numerous bolts for securing the lids to the body of the packagings. In an effort to reduce operator time to open and close the packages during onsite transfers, thus reducing personnel exposure and costs, an evaluation was performed to analyze the effects of reducing the number of bolts required to secure the lid to the packaging body. The evaluation showed the reduction to one-third of the original number of bolts had no effect on the packagings capability to sustain vibratory loads, shipping loads, internal pressure loads, and the loads resulting from a 4-ft drop. However, the loads caused by the 4-ft drop are difficult to estimate and the study recommended each of the packages be dropped to show the actual effects on the package closure. Even with reduced bolting, the packagings were still required to meet the 49 CFR 178.350 performance criteria for Type A packaging. This paper discusses the effects and results of the drop testing of the three packagings.

Warpage of QFN Package in Post Mold Cure Process of integrated circuit packaging

Science.gov (United States)

Sriwithoon, Nattha; Ugsornrat, Kessararat; Srisuwitthanon, Warayoot; Thonglor, Panakamon

2017-09-01

This research studied about warpage of QFN package in post mold cure process of integrated circuit (IC) packages using pre-plated (PPF) leadframe. For IC package, epoxy molding compound (EMC) are molded by cross linking of compound stiffness but incomplete crosslinked network and leading the fully cured thermoset by post mold cure (PMC) process. The cure temperature of PMC can change microstructure of EMC in term of stress inside the package and effect to warpage of the package due to coefficient of thermal expansion (CTE) between EMC and leadframe. In experiment, cure temperatures were varied to check the effect of internal stress due to different cure temperature after completed post mold cure for TDFN 2×3 8L. The cure temperature were varied with 180 °C, 170 °C, 160 °C, and 150°C with cure time 4 and 6 hours, respectively. For analysis, the TDFN 2×3 8L packages were analyzed the warpage by thickness gauge and scanning acoustic microscope (SAM) after take the test samples out from the oven cure. The results confirmed that effect of different CTE between EMC and leadframe due to different cure temperature resulting to warpage of the TDFN 2×3 8L packages.

The Importance of Take-Out Food Packaging Attributes: Conjoint Analysis and Quality Function Deployment Approach

Science.gov (United States)

Lestari Widaningrum, Dyah

2014-03-01

This research aims to investigate the importance of take-out food packaging attributes, using conjoint analysis and QFD approach among consumers of take-out food products in Jakarta, Indonesia. The conjoint results indicate that perception about packaging material (such as paper, plastic, and polystyrene foam) plays the most important role overall in consumer perception. The clustering results that there is strong segmentation in which take-out food packaging material consumer consider most important. Some consumers are mostly oriented toward the colour of packaging, while another segment of customers concerns on packaging shape and packaging information. Segmentation variables based on packaging response can provide very useful information to maximize image of products through the package's impact. The results of House of Quality development described that Conjoint Analysis - QFD is a useful combination of the two methodologies in product development, market segmentation, and the trade off between customers' requirements in the early stages of HOQ process

GillesPy: A Python Package for Stochastic Model Building and Simulation.

Science.gov (United States)

Abel, John H; Drawert, Brian; Hellander, Andreas; Petzold, Linda R

2016-09-01

GillesPy is an open-source Python package for model construction and simulation of stochastic biochemical systems. GillesPy consists of a Python framework for model building and an interface to the StochKit2 suite of efficient simulation algorithms based on the Gillespie stochastic simulation algorithms (SSA). To enable intuitive model construction and seamless integration into the scientific Python stack, we present an easy to understand, action-oriented programming interface. Here, we describe the components of this package and provide a detailed example relevant to the computational biology community.

The corrosion rate of copper in a bentonite test package measured with electric resistance sensors

Energy Technology Data Exchange (ETDEWEB)

Rosborg, Bo [Division of Surface and Corrosion Science, KTH, Stockholm (Sweden); Kosec, Tadeja; Kranjc, Andrej; Kuhar, Viljem; Legat, Andraz [Slovenian National Building and Civil Engineering Institute, Ljubljana (Slovenia)

2012-12-15

LOT1 test parcel A2 was exposed for six years in the Aespoe Hard Rock Laboratory, which offers a realistic environment for the conditions that will prevail in a deep repository for high-level radioactive waste disposal in Sweden. The test parcel contained copper electrodes for real-time corrosion monitoring in bentonite ring 36, where the temperature was 24 deg C, and copper coupons in bentonite rings 22 and 30, where the temperature was higher. After retrieval of the test parcel in January 2006, a bentonite test package consisting of bentonite rings 35 - 37 was placed in a container and sealed with a thick layer of paraffin. Later the same year new copper electrodes were installed in the test package. In January 2007 electric resistance (ER) sensors of pure copper with a thickness of 35 {mu}m were also installed in the test package mainly to facilitate the interpretation of the results from the real-time corrosion monitoring with electrochemical techniques. The ER measurements have shown that the corrosion rate of pure copper exposed in an oxic bentonite/ saline groundwater environment at room temperate decreases slowly with time to low but measurable values. The corrosion rates estimated from the regularly performed EIS measurements replicate the ER data. Thus, for this oxic environment in which copper acquires corrosion potentials of the order of 200 mV (SHE) or higher, electrochemical measurements provide believable data. Comparing the recorded ER data with an estimate of the average corrosion rate based on comparing cross-sections from exposed and protected sensor elements, it is obvious that the former overestimates the actual corrosion rate, which is understandable. It seems as if electrochemical measurements can provide a better estimate of the corrosion rate; however, this is quite dependent on the use of proper measuring frequencies and evaluation methods. In this respect ER measurements are more reliable. It has been shown that real-time corrosion

The corrosion rate of copper in a bentonite test package measured with electric resistance sensors

International Nuclear Information System (INIS)

Rosborg, Bo; Kosec, Tadeja; Kranjc, Andrej; Kuhar, Viljem; Legat, Andraz

2012-12-01

LOT1 test parcel A2 was exposed for six years in the Aespoe Hard Rock Laboratory, which offers a realistic environment for the conditions that will prevail in a deep repository for high-level radioactive waste disposal in Sweden. The test parcel contained copper electrodes for real-time corrosion monitoring in bentonite ring 36, where the temperature was 24 deg C, and copper coupons in bentonite rings 22 and 30, where the temperature was higher. After retrieval of the test parcel in January 2006, a bentonite test package consisting of bentonite rings 35 - 37 was placed in a container and sealed with a thick layer of paraffin. Later the same year new copper electrodes were installed in the test package. In January 2007 electric resistance (ER) sensors of pure copper with a thickness of 35 μm were also installed in the test package mainly to facilitate the interpretation of the results from the real-time corrosion monitoring with electrochemical techniques. The ER measurements have shown that the corrosion rate of pure copper exposed in an oxic bentonite/ saline groundwater environment at room temperate decreases slowly with time to low but measurable values. The corrosion rates estimated from the regularly performed EIS measurements replicate the ER data. Thus, for this oxic environment in which copper acquires corrosion potentials of the order of 200 mV (SHE) or higher, electrochemical measurements provide believable data. Comparing the recorded ER data with an estimate of the average corrosion rate based on comparing cross-sections from exposed and protected sensor elements, it is obvious that the former overestimates the actual corrosion rate, which is understandable. It seems as if electrochemical measurements can provide a better estimate of the corrosion rate; however, this is quite dependent on the use of proper measuring frequencies and evaluation methods. In this respect ER measurements are more reliable. It has been shown that real-time corrosion

Monte Carlo and detector simulation in OOP [Object-Oriented Programming

International Nuclear Information System (INIS)

Atwood, W.B.; Blankenbecler, R.; Kunz, P.; Burnett, T.; Storr, K.M.

1990-10-01

Object-Oriented Programming techniques are explored with an eye toward applications in High Energy Physics codes. Two prototype examples are given: McOOP (a particle Monte Carlo generator) and GISMO (a detector simulation/analysis package)

Long-Term Waste Package Degradation Studies at the Yucca Mountain Potential High-Level Nuclear Waste Repository

International Nuclear Information System (INIS)

Mon, K. G.; Bullard, B. E.; Longsine, D. E.; Mehta, S.; Lee, J. H.; Monib, A. M.

2002-01-01

The Site Recommendation (SR) process for the potential repository for spent nuclear fuel (SNF) and high-level nuclear waste (HLW) at Yucca Mountain, Nevada is underway. Fulfillment of the requirements for substantially complete containment of the radioactive waste emplaced in the potential repository and subsequent slow release of radionuclides from the Engineered Barrier System (EBS) into the geosphere will rely on a robust waste container design, among other EBS components. Part of the SR process involves sensitivity studies aimed at elucidating which model parameters contribute most to the drip shield and waste package degradation characteristics. The model parameters identified included (a) general corrosion rate model parameters (temperature-dependence and uncertainty treatment), and (b) stress corrosion cracking (SCC) model parameters (uncertainty treatment of stress and stress intensity factor profiles in the Alloy 22 waste package outer barrier closure weld regions, the SCC initiation stress threshold, and the fraction of manufacturing flaws oriented favorably for through-wall penetration by SCC). These model parameters were reevaluated and new distributions were generated. Also, early waste package failures due to improper heat treatment were added to the waste package degradation model. The results of these investigations indicate that the waste package failure profiles are governed by the manufacturing flaw orientation model parameters and models used

Testing of the permissible inventories in radioactive waste packages

International Nuclear Information System (INIS)

Stegmaier, W.

1988-01-01

The inventories of radionuclides in waste packages which are to be stored in repositories are determined in the Waste Acceptance Requirements of the repository and in the Act on Transport of Dangerous Goods. In this report limiting values of relevant radionuclides are given in such a way that it is possible to use them in a standardized manner. The limiting values apply to single radionuclides, for handling mixtures of nuclides it is necessary to use the sum formula. The minimized number of waste packages which must be produced from a given quantity of raw waste and an inventory of radionuclides keeping all parameters can be calculated with the help of the shown calculating sheet. (orig.) [de

Piloting an email-based resource package for job seekers with multiple sclerosis.

Science.gov (United States)

Dorstyn, Diana; Roberts, Rachel; Murphy, Gregory; Kneebone, Ian; Migliorini, Christine; Craig, Ashley; Hutchinson, Claire; Field, Deborah

2017-05-01

Media-based rehabilitation provides a powerful opportunity to examine vocational behaviors in the disability sector. However, this research is preliminary at best. This paper reports pilot data. Eighteen adults with multiple sclerosis (MS) accessed an email-delivered, resource-based package, Work and MS. Pre- and post-access vocational self-efficacy and identity (Job-Procurement Self Efficacy Scale, My Vocational Situation Scale- primary outcomes), life orientation and depressed mood (Life Orientation Test - revised and Patient Health Questionnaire-9 - secondary outcomes) were assessed. Pre- and post-change scores were examined with Wilcoxon signed ranks tests and Hedges g effect sizes with associated 95% confidence intervals. Reliable change analyses were additionally calculated to determine the clinical significance of individual change scores. Significant and positive effects were reported for vocational self-efficacy, identity, and optimism. Reliable change scores in one or more of these key outcomes were reported by 30% of the sample. Satisfaction with the content and delivery of the email-based intervention was also noted. Preliminary evidence suggests that Work and MS can help to promote vocational goals, interests and strengths among job seekers with a disability by providing a set of tools, information and linkages relating to vocational pursuits and career development. Replication with a randomized control design is indicated. Implications for Rehabilitation Research indicates a high unemployment rate among working-age adults with MS. A combination of disease-specific, psychological, programmatic and societal variables contribute to employment instability in this group. This pilot study demonstrates that an e-mail-based resource package, Work and MS, provides an innovative and feasible option for promoting consumer engagement with vocational services and, potentially, improving vocational outcomes. Work and MS has potential applicability to other

Package Design Affects Accuracy Recognition for Medications.

Science.gov (United States)

Endestad, Tor; Wortinger, Laura A; Madsen, Steinar; Hortemo, Sigurd

2016-12-01

Our aim was to test if highlighting and placement of substance name on medication package have the potential to reduce patient errors. An unintentional overdose of medication is a large health issue that might be linked to medication package design. In two experiments, placement, background color, and the active ingredient of generic medication packages were manipulated according to best human factors guidelines to reduce causes of labeling-related patient errors. In two experiments, we compared the original packaging with packages where we varied placement of the name, dose, and background of the active ingredient. Age-relevant differences and the effect of color on medication recognition error were tested. In Experiment 1, 59 volunteers (30 elderly and 29 young students), participated. In Experiment 2, 25 volunteers participated. The most common error was the inability to identify that two different packages contained the same active ingredient (young, 41%, and elderly, 68%). This kind of error decreased with the redesigned packages (young, 8%, and elderly, 16%). Confusion errors related to color design were reduced by two thirds in the redesigned packages compared with original generic medications. Prominent placement of substance name and dose with a band of high-contrast color support recognition of the active substance in medications. A simple modification including highlighting and placing the name of the active ingredient in the upper right-hand corner of the package helps users realize that two different packages can contain the same active substance, thus reducing the risk of inadvertent medication overdose. © 2016, Human Factors and Ergonomics Society.

Catalogue of facilities in Member States of the European Community for testing the packaging of radioactive materials

International Nuclear Information System (INIS)

Marchal, A.; Swindell, G.E.

1983-01-01

A group of experts convened by the Commission of the European Communities in Brussels on 2 July 1980 to suggest possible actions in connection with the safe transport of radioactive materials, recommended, among other things, that the Commission should collect and distribute information on packaging test facilities in Member States. In response to that recommendation a letter of enquiry was sent informally, on behalf of the Commission, to the competent authorities of the Member States. The purpose of the enquiry is to assist in the effective implementation of the internationally accepted Regulations for the Safe Transport of Radioactive Materials through the dissemination of information on test facilities and on the terms and conditions under which the services of these facilities could be made available for the testing of packaging designed in other countries. As an aid to the presentation of the material in a harmonized format, it was suggested that the information provided should cover relevant topics. The information received by the Commission has been assembled for each installation according to this format

An evaluation of department of transportation specification packages

International Nuclear Information System (INIS)

Ratledge, J.E.; Rawl, R.R.

1993-01-01

Specification packages are broad families of package designs developed and authorized by the U.S. Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC) for transport of certain Type B and fissile radioactive materials, with each specification containing a number of designs of various sizes. The specification package designs have remained essentially unchanged in a changing regulatory environment. Changes to package designs or authorized contents under the DOT system can be accomplished by rule making action, but there has been little updating of the designs over the years. Many of the individual package designs are no longer supported by reasonably current safety analyses. Since the publication of these specifications, there have been changes in regulatory requirements and improvements in methods of testing and analysis. Additionally, contemplated revisions to the DOT and NRC regulations to bring design requirements into accord with IAEA Safety Series No. 6, 1985 Edition would eliminate fissile classes and require resistance to a crush test for small Type B packages meeting certain criteria. The NRC has requested that the Oak Ridge National Laboratory (ORNL) staff review the safety documentation of the specification packages to determine the possible need for further testing and analysis, modifications to the designs, and, perhaps, elimination of any designs for which there is insufficient demonstration of compliance with current and proposed requirements. This paper will present a summary of the technical data and information concerning the use of the packages that has been received to date. (author)

Food Packaging Materials

Science.gov (United States)

1978-01-01

The photos show a few of the food products packaged in Alure, a metallized plastic material developed and manufactured by St. Regis Paper Company's Flexible Packaging Division, Dallas, Texas. The material incorporates a metallized film originally developed for space applications. Among the suppliers of the film to St. Regis is King-Seeley Thermos Company, Winchester, Ma'ssachusetts. Initially used by NASA as a signal-bouncing reflective coating for the Echo 1 communications satellite, the film was developed by a company later absorbed by King-Seeley. The metallized film was also used as insulating material for components of a number of other spacecraft. St. Regis developed Alure to meet a multiple packaging material need: good eye appeal, product protection for long periods and the ability to be used successfully on a wide variety of food packaging equipment. When the cost of aluminum foil skyrocketed, packagers sought substitute metallized materials but experiments with a number of them uncovered problems; some were too expensive, some did not adequately protect the product, some were difficult for the machinery to handle. Alure offers a solution. St. Regis created Alure by sandwiching the metallized film between layers of plastics. The resulting laminated metallized material has the superior eye appeal of foil but is less expensive and more easily machined. Alure effectively blocks out light, moisture and oxygen and therefore gives the packaged food long shelf life. A major packaging firm conducted its own tests of the material and confirmed the advantages of machinability and shelf life, adding that it runs faster on machines than materials used in the past and it decreases product waste; the net effect is increased productivity.

Cigarette package design: opportunities for disease prevention

Directory of Open Access Journals (Sweden)

Pollay RW

2003-01-01

Full Text Available Abstract Objective To learn how cigarette packages are designed and to determine to what extent cigarette packages are designed to target children. Methods A computer search was made of all Internet websites that post tobacco industry documents using the search terms: packaging, package design, package study, box design, logo, trademark and design study. All documents were retrieved electronically and analyzed by the first author for recurrent themes. Data Synthesis Cigarette manufacturers devote a great deal of attention and expense to package design because it is central to their efforts to create brand images. Colors, graphic elements, proportioning, texture, materials and typography are tested and used in various combinations to create the desired product and user images. Designs help to create the perceived product attributes and project a personality image of the user with the intent of fulfilling the psychological needs of the targeted type of smoker. The communication of these images and attributes is conducted through conscious and subliminal processes. Extensive testing is conducted using a variety of qualitative and quantitative research techniques. Conclusion The promotion of tobacco products through appealing imagery cannot be stopped without regulating the package design. The same marketing research techniques used by the tobacco companies can be used to design generic packaging and more effective warning labels targeted at specific consumers.

lawstat: An R Package for Law, Public Policy and Biostatistics

Directory of Open Access Journals (Sweden)

Wallace Hui

2008-01-01

Full Text Available We present a new R software package lawstat that contains statistical tests and procedures that are utilized in various litigations on securities law, antitrust law, equal employment and discrimination as well as in public policy and biostatistics. Along with the well known tests such as the Bartels test, runs test, tests of homogeneity of several sample proportions, the Brunner-Munzel tests, the Lorenz curve, the Cochran-Mantel-Haenszel test and others, the package contains new distribution-free robust tests for symmetry, robust tests for normality that are more sensitive to heavy-tailed departures, measures of relative variability, Levene-type tests against trends in variances etc. All implemented tests and methods are illustrated by simulations and real-life examples from legal cases, economics and biostatistics. Although the package is called lawstat, it presents implementation and discussion of statistical procedures and tests that are also employed in a variety of other applications, e.g., biostatistics, environmental studies, social sciences and others, in other words, all applications utilizing statistical data analysis. Hence, name of the package should not be considered as a restriction to legal statistics. The package will be useful to applied statisticians and "quantitatively alert practitioners" of other subjects as well as an asset in teaching statistical courses.

CH Packaging Maintenance Manual

International Nuclear Information System (INIS)

Washington TRU Solutions

2002-01-01

This procedure provides instructions for performing inner containment vessel (ICV) and outer containment vessel (OCV) maintenance and periodic leakage rate testing on the following packaging seals and corresponding seal surfaces using a nondestructive helium (He) leak test. In addition, this procedure provides instructions for performing ICV and OCV structural pressure tests

On user-friendly interface construction for CACSD packages

DEFF Research Database (Denmark)

Ravn, Ole

1989-01-01

Some ideas that are used in the development of user-friendly interface for a computer-aided control system design (CACSD) package are presented. The concepts presented are integration and extensibility through the use of object-oriented programming, man-machine interface and user support using...... direct manipulation, and multiple views and multiple actions on objects in different domains. The use of multiple views and actions in combination with graphics enhances the user's ability to get an overview of the system to be designed. Good support for iteration is provided, and the short time between...... action and presentation allows the user to evaluate actions quickly. Object-oriented programming has been used to provide modularity and encapsulation...

Waste package emplacement borehole option study

International Nuclear Information System (INIS)

Streeter, W.S.

1992-03-01

This study evaluates the cost and thermal effects of various waste package emplacement configurations that differ in emplacement orientation, number of containers per borehole, and standoff distance at the potential Yucca Mountain nuclear waste repository. In this study, eight additional alternatives to the vertical and horizontal orientation options presented in the Site Characterization Plan Conceptual Design Report are considered. Typical panel layout configurations based on thermal analysis of the waste and cost estimates for design and construction, operations, and closure and decommissioning were made for each emplacement option. For the thermal analysis average waste 10 years out of reactor and the SIM code were used to determine whether the various configurations temperatures would exceed the design criteria for temperature. This study does not make a recommendation for emplacement configuration, but does provide information for comparison of alternatives

ZLIB++: Object-oriented numerical library for differential algebra

International Nuclear Information System (INIS)

Malitsky, N.; Reshetov, A.; Yan, Y.

1994-01-01

New software engineering tools and object-oriented design have a great impact on the software development process. But in high energy physics all major packages were implemented in FORTRAN and porting of these codes to another language is rather complicated, primarily because of their huge size and heavy use of FORTRAN mathematical libraries. But some intrinsic accelerator concepts, such as nested structure of modern accelerators, look very pretty when implemented with the object-oriented approach. In this paper we present the object-oriented version of ZLIB, numerical library for differential algebra and show how the modern approaches can simplify the development and support of accelerator codes, decrease code size, and allow description of complex mathematical transformations by simple language

A New Test Device for Characterization of Mechanical Stress Caused by Packaging Processes

International Nuclear Information System (INIS)

Hirsch, Soeren; Doerner, Steffen; Hauptmann, Peter; Schmidt, Bertram

2006-01-01

This paper reports on a new method for estimation and minimization of mechanical stress on MEMS sensor and actuator structures due to packaging processes based on flip chip technology. For studying mechanical stress a test chip with silicon membranes was fabricated. A network of piezo-resistive solid state resistors created by diffusion was used to measure the surface tension pattern between adjacent membranes. Finite element method simulation was used to calculate the stress profile and to determine the optimum positions for placing the resistive network

CYPROS - Cybernetic Program Packages

Directory of Open Access Journals (Sweden)

Arne Tyssø

1980-10-01

Full Text Available CYPROS is an interactive program system consisting of a number of special purpose packages for simulation, identification, parameter estimation and control system design. The programming language is standard FORTRAN IV and the system is implemented on a medium size computer system (Nord-10. The system is interactive and program control is obtained by the use of numeric terminals. Output is rapidly examined by extensive use of video colour graphics. The subroutines included in the packages are designed and documented according to standardization rules given by the SCL (Scandinavian Control Library organization. This simplifies the exchange of subroutines throughout the SCL system. Also, this makes the packages attractive for implementation by industrial users. In the simulation package, different integration methods are available and it can be easily used for off-line, as well as real time, simulation problems. The identification package consists of programs for single-input/single-output and multivariablc problems. Both transfer function models and state space models can be handled. Optimal test signals can be designed. The control package consists of programs based on multivariable time domain and frequency domain methods for analysis and design. In addition, there is a package for matrix and time series manipulation. CYPROS has been applied successfully to industrial problems of various kinds, and parts of the system have already been implemented on different computers in industry. This paper will, in some detail, describe the use and the contents of the packages and some examples of application will be discussed.

Packaging Concerns and Techniques for Large Devices: Challenges for Complex Electronics

Science.gov (United States)

LaBel, Kenneth A.; Sampson, Michael J.

2010-01-01

NASA is going to have to accept the use of non-hermetic packages for complex devices. There are a large number of packaging options available. Space application subjects the packages to stresses that they were probably not designed for (vacuum for instance). NASA has to find a way of having assurance in the integrity of the packages. There are manufacturers interested in qualifying non-hermetic packages to MIL-PRF-38535 Class V. Government space users are agreed that Class V should be for hermetic packages only. NASA is working on a new Class for non-hermetic packages for M38535 Appendix B, "Class Y". Testing for package integrity will be required but can be package specific as described by a Package Integrity Test Plan. The plan is developed by the manufacturer and approved by DSCC and government space.

Hanford Immobilized LAW Product Acceptance: Tanks Focus Area Testing Data Package II

International Nuclear Information System (INIS)

Schulz, Rebecca L.; Lorier, Troy H.; Peeler, David K.; Brown, Kevin G.; Reamer, Irene A.; Vienna, John D.; Jiricka, Antonin; Jorgensen, Benaiah M.; Smith, Donald E.

2001-01-01

This report is a continuation of the Hanford Immobilized Low Activity Waste (LAW) Product Acceptance (HLP): Initial Tanks Focus Area Testing Data Package (Vienna (and others) 2000). In addition to new 5000-h product consistency test (PCT), vapor hydration test (VHT), and alteration products data, some previously reported data together with relevant background information are included for an easily accessible source of reference when comparing the response of the various glasses to different test conditions. A matrix of 55 glasses was developed and tested to identify the impact of glass composition on long-term corrosion behavior and to develop an acceptable composition region for Hanford LAW glasses. Of the 55 glasses, 45 were designed to systematically vary the glass composition, and 10 were selected because large and growing databases on their corrosion characteristics had accumulated. The targeted and measured compositions of these glasses are found in the Appendix A. All glasses were fabricated according to standard procedures and heat treated to simulate the slow cooling that will occur in a portion of the waste glass after vitrification in the planned treatment facility at Hanford

Effects of mixed waste simulants on transportation packaging plastic components

International Nuclear Information System (INIS)

Nigrey, P.J.; Dickens, T.G.

1994-01-01

The purpose of hazardous and radioactive materials packaging is to, enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified. The design requirements for both hazardous and radioactive materials packaging specify packaging compatibility, i.e., that the materials of the packaging and any contents be chemically compatible with each other. Furthermore, Type A and Type B packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program, supported by the US Department of Energy's (DOE) Transportation Management Division, EM-261 provides the means to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. In this paper, we describe the general elements of the testing program and the experimental results of the screening tests. The implications of the results of this testing are discussed in the general context of packaging development. Additionally, we present the results of the first phase of this experimental program. This phase involved the screening of five candidate liner and six seal materials against four simulant mixed wastes

Model 9975 Life Extension Package 1 - Final Report

International Nuclear Information System (INIS)

Daugherty, W.

2011-01-01

Life extension package LE1 (9975-03382) was instrumented and subjected to a temperature/humidity environment that bounds KAMS package storage conditions for 92 weeks. During this time, the maximum fiberboard temperature was ∼180 F, and was established by a combination of internal heat (12 watts) and external heat (∼142 F). The relative humidity external to the package was maintained at 80 %RH. This package was removed from test in November 2010 after several degraded conditions were observed during a periodic examination. These conditions included degraded fiberboard (easily broken, bottom layer stuck to the drum), corrosion of the drum, and separation of the air shield from the upper fiberboard assembly. Several tests and parameters were used to characterize the package components. Results from these tests generally indicate agreement between this full-scale shipping package and small-scale laboratory tests on fiberboard and O-ring samples. These areas of agreement include the rate of fiberboard weight loss, change in fiberboard thermal conductivity, fiberboard compression strength, and O-ring compression set. In addition, this package provides an example of the extent to which moisture within the fiberboard can redistribute in the presence of a temperature gradient such as might be created by a 12 watt internal heat load. Much of the moisture near the fiberboard ID surface migrated towards the OD surface, but there was not a significant axial moisture gradient during most of the test duration. Only during the last inspection period (i.e. after 92 weeks exposure during the second phase) did enough moisture migrate to the bottom fiberboard layers to cause saturation. A side effect of moisture migration is the leaching of soluble compounds from the fiberboard. In particular, the corrosion observed on the drum appears related primarily to the leaching and concentration of chlorides. In most locations, this attack appears to be general corrosion, with shallow

Service Oriented Robotic Architecture for Space Robotics: Design, Testing, and Lessons Learned

Science.gov (United States)

Fluckiger, Lorenzo Jean Marc E; Utz, Hans Heinrich

2013-01-01

This paper presents the lessons learned from six years of experiments with planetary rover prototypes running the Service Oriented Robotic Architecture (SORA) developed by the Intelligent Robotics Group (IRG) at the NASA Ames Research Center. SORA relies on proven software engineering methods and technologies applied to space robotics. Based on a Service Oriented Architecture and robust middleware, SORA encompasses on-board robot control and a full suite of software tools necessary for remotely operated exploration missions. SORA has been eld tested in numerous scenarios of robotic lunar and planetary exploration. The experiments conducted by IRG with SORA exercise a large set of the constraints encountered in space applications: remote robotic assets, ight relevant science instruments, distributed operations, high network latencies and unreliable or intermittent communication links. In this paper, we present the results of these eld tests in regard to the developed architecture, and discuss its bene ts and limitations.

Extended testing of a modified 18B plutonium nitrate shipping container

International Nuclear Information System (INIS)

Yoshimura, H.R.; Pope, R.B.; Leisher, W.B.; Joseph, B.J.; Schulz-Forberg, B.; Hubner, H.W.

1980-01-01

The container damage observed as the result of the high-speed pulldown impact test was more severe than that of either the 185-m free-fall drop of a prototype container onto a semirigid surface or the crush environment produced by a 9-m drop of a 2-tonne block onto a modified container resting on an unyielding surface. In comparison to the extended tests, the 9-m regulatory drop test onto an unyielding surface of the prototype packaging in its most damaging orientation produced the least amount of damage. Very little deformation in the overpack was observed, and there was no influence on the fire resistivity and leaktightness of the containment vessel. The 128 m/s impact test produced a leak in the container. It appears that the 18B packaging, designed to withstand the environments specified in IAEA Safety Series No. 6, can withstand extended environments including longer duration fires and higher velocity impacts on yielding targets. When modified with ring stiffeners, the packaging withstood a dynamic crush test, but did not survive the high speed impact onto an unyielding surface as specified in NUREG 0360

What should ''damaged'' mean in air transport of fissile packages

International Nuclear Information System (INIS)

Luna, R.E.; Falci, F.P.; Blackman, D.

1995-01-01

It is likely that the ongoing process to produce the 1996 version of the IAEA Regulation for the Safe Transport of Radioactive Materials, IAEA Safety Series 6(SS 6) will result in a more stringent package qualification standard for air transport of large quantities of radioactive materials (RAM) than is included in the 1990 version. During the process to define the scope of the new requirements there was extensive discussion of their impact on, and application to, fissile material package qualification criteria. Since fissile materials are shipped in a variety of packagings ranging from exempt to Type B, each packaging of each type must be evaluated for its ability to maintain subcriticality both alone and in arrays and in both damaged and undamaged condition. In the 1990 version of SS 6 ''damaged'' means the condition of a package after it had undergone the ''tests for demonstrating the ability to withstand accident conditions in transport,'' i.e., Type B qualification tests. These tests conditions are typical of severe accidents in surface modes, but are less severe than air mode qualification test environments to be applied to Type C packages. As a result, questions arose about the need for a corresponding change in the 1996 SS 6 to define ''damaged'' to include the Type C test regime for criticality evaluations of fissile packages in air transport

Engineered barrier systems and canister orientation studies for the Yucca Mountain Project, Nevada

International Nuclear Information System (INIS)

Wilder, D.G.

1990-07-01

Emplacement borehole orientation directly impacts many aspects of the Engineered Barrier System (EBS) and interactions with the near field environment. This paper considers the impacts of orientation on the hydrologic portion of the environment and its interactions with the EBS. The hydrologic environments is considered from a conceptual standpoint, the numerical analyses are left for subsequent work. As reported in this paper, several aspects of the hydrological environment are more favorable for long term performance of vertically oriented rather than horizontally oriented Waste Packages. 19 refs., 15 figs

Safety analysis report for packages: packaging of fissile and other radioactive materials. Final report

International Nuclear Information System (INIS)

Chalfant, G.G.

1984-01-01

The 9965, 9966, 9967, and 9968 packages are designed for surface shipment of fissile and other radioactive materials where a high degree of containment (either single or double) is required. Provisions are made to add shielding material to the packaging as required. The package was physically tested to demonstrate that it meets the criteria specified in USDOE Order No. 5480.1, chapter III, dated 5/1/81, which invokes Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packing and Transportation of Radioactive Material, and Title 49, Code of Federal Regulations, Part 100-179, Transportation. By restricting the maximum normal operating pressure of the packages to less than 7 kg/cm 2 (gauge) (99 to 54 psig), the packages will comply with Type B(U) regulations of the International Atomic Energy Agency (IAEA) in its Regulations for the Safe Transport of Radioactive Materials, Safety Series No. 6, 1973 Revised Edition, and may be used for export and import shipments. These packages have been assessed for transport of up to 14.5 kilograms of uranium, excluding uranium-233, or 4.4 kilograms of plutonium metal, oxides, or scrap having a maximum radioactive decay energy of 30 watts. Specific maximum package contents are given. This quantity and the configuration of uranium or plutonium metal cannot be made critical by any combination of hydrogeneous reflection and moderation regardless of the condition of the package. For a uranium-233 shipment, a separate criticality evaluation for the specific package is required

Packaging of control system software

International Nuclear Information System (INIS)

Zagar, K.; Kobal, M.; Saje, N.; Zagar, A.; Sabjan, R.; Di Maio, F.; Stepanov, D.

2012-01-01

Control system software consists of several parts - the core of the control system, drivers for integration of devices, configuration for user interfaces, alarm system, etc. Once the software is developed and configured, it must be installed to computers where it runs. Usually, it is installed on an operating system whose services it needs, and also in some cases dynamically links with the libraries it provides. Operating system can be quite complex itself - for example, a typical Linux distribution consists of several thousand packages. To manage this complexity, we have decided to rely on Red Hat Package Management system (RPM) to package control system software, and also ensure it is properly installed (i.e., that dependencies are also installed, and that scripts are run after installation if any additional actions need to be performed). As dozens of RPM packages need to be prepared, we are reducing the amount of effort and improving consistency between packages through a Maven-based infrastructure that assists in packaging (e.g., automated generation of RPM SPEC files, including automated identification of dependencies). So far, we have used it to package EPICS, Control System Studio (CSS) and several device drivers. We perform extensive testing on Red Hat Enterprise Linux 5.5, but we have also verified that packaging works on CentOS and Scientific Linux. In this article, we describe in greater detail the systematic system of packaging we are using, and its particular application for the ITER CODAC Core System. (authors)

Development of Transportation Package for Medical and Industrial Radioisotope

Energy Technology Data Exchange (ETDEWEB)

Seo, K. S.; Lee, J. C.; Bang, K. S. (and others)

2007-06-15

The objective of this project is development of RI transport package and establishment of transportation system. This report describes the objective of project, necessaries, state of related technology, scope and results, proposal for application etc. The scope of the project consist of establishment of performance test system for type-A package for medical use, development of type-B package for industrial use and development of casting technology for DU shield and evaluation of shielding efficiency. The research results obtained from this project are expected to be utilized as a basic data for design, analysis, test and license of transport package.

Entrepreneurial orientation, market orientation, and competitive environment

DEFF Research Database (Denmark)

Sørensen, Hans Eibe; Cadogan, John W.

This study sheds light on the role that the competitive environment plays in determining how elements of market orientation and elements of entrepreneurial orientation interact to influence business success. We develop a model in which we postulate that market orientation, entrepreneurial...... orientation, and competitive environment shape business performance via a three-way interaction. We test the model using primary data from the CEOs of 270 CEO of manufacturing firms, together with secondary data on these firms' profit performance. An assessment of the results indicates that customer...... orientation moderates the positive relationships between the competitiveness element of entrepreneurial orientation and market share and return on assets (ROA): the positive relationships between competitiveness and market share and competitiveness and ROA become stronger the greater the firms' customer...

Non-shielded transport package impact response to unyielding and semi-yielding surfaces

International Nuclear Information System (INIS)

Gablin, K.A.; Jefferson, R.M.; Pope, R.B.; Vigil, M.G.; Joseph, B.J.; Yoshimura, H.R.

1983-01-01

The Super Tiger, licensed under US NRC Permit No. 6400, is a box 2.44 m wide by 2.44 m high by 6.1 long constructed of steel encased urethane foam. It is designed to carry fissile and other large-quantity hazardous materials. The Super Tiger weighs about 7.4 metric-tons and can carry a 13 metric-ton payload. The inner cavity of the super Tiger is 1.93 m wide by 1.93 m high by 5.1 m long. The end-wall cross section consists of an outer wall of 17.5-mm-thick carbon steel. Two full-scale Super Tiger Type B nonshielded packages have been dropped in a center-of-gravity over corner orientation onto unyielding (rigid) and semi-yielding (semi-rigid) surface in separate tests. The recent drop testing of the Super Tiger at ORNL damaged the packaging more than did the earlier 1970 prototype testing. This conclusion is based upon the extensive weld failures (tearing), greater deformation of the impacted corner, interior cavity deformation, and shattering of the ISO corner attachment in the recently tested Super Tiger. A review of both target structures indicates significant differences in construction; the earlier target structure may have been much softer. Although the target used to test the prototype appeared rigid, the 1982 test demonstrated that it was probably not a perfectly rigid target. To obtain a perfectly rigid target, a very large amount of mass and a very rigid material are necessary so that essentially all the energy goes into container deformation. In either case, the containers did not lose their contents. In conclusion, some thought should be given by the industry to the developing standards for similar testing severity, in order to eliminate variables of this nature. The use of government-owned testing facilities by private industry may be a useful goal to pursue

Influence of packaging materials on Kashkaval quality

OpenAIRE

Talevski, Goce; Srbinovska, Sonja; Santa, Dushica; Mateva, Natasha

2017-01-01

This study focused on investigating the influence of 4 different packaging materials (A - the control, B - polymer emulsion, C - wax and D - polymer foil) on the quality of Kashkaval cheese. The lowest pH value had the sample protected by wax, which is most probably related to the retention of the formed organic acids and gases from the packaging material. A significant influence of the tested packaging materials (p

Effect on moisture permeability of typewriting on unit dose package surfaces.

Science.gov (United States)

Rackson, J T; Zellhofer, M J; Birmingham, P H

1984-10-01

The effects of typewriting on labels of two unit dose packages with respect to moisture permeability were examined. Using an electric typewriter, a standard label format was imprinted on two different types of class A unit dose packages: (1) a heat-sealed paper-backed foil and cellofilm strip pouch, and (2) a copolyester and polyethylene multiple-cup blister with a heat-sealed paper-backed foil and cellofilm cover. The labels were typed at various typing-element impact settings. The official USP test for water permeation was then performed on typed packages and untyped control packages. The original untyped packages were confirmed to be USP class A quality. The packages for which successively harder impact settings were used showed a corresponding increase in moisture permeability. This resulted in a lowering of USP package ratings from class A to class B and D, some of which would be unsuitable for use in any unit dose system under current FDA repackaging standards. Typing directly onto the label of a unit dose package before it is sealed will most likely damage the package and possibly make it unfit for use. Pharmacists who must type labels for the unit dose packages studied should use the lowest possible typewriter impact setting and test for damage using the USP moisture-permeation test.

FLEXIBLE FOOD PACKAGING LABORATORY

Data.gov (United States)

Federal Laboratory Consortium — This laboratory contains equipment to fabricate and test prototype packages of many types and sizes (e.g., bags, pouches, trays, cartons, etc.). This equipment can...

ZLIB++: Object Oriented Numerical Library for Differential Algebra

International Nuclear Information System (INIS)

Yan, Yiton T

2003-01-01

New software engineering tools and object-oriented design have a great impact on the software development process. but in high energy physics all major packages were implemented in FORTRAN and porting of these codes to another language is rather complicated, primarily because of their huge size and heavy use of FORTRAN mathematical libraries. But some intrinsic accelerator concepts, such as nested structure of modern accelerators, look very pretty when implemented with the object-oriented approach. In this paper the authors present the object-oriented version of ZLIB, numerical library for differential algebra, and show how the modern approaches can simplify the development and support of accelerator codes, decrease code size, and allow description of complex mathematical transformations by simple language

Packaging Technologies for 500C SiC Electronics and Sensors

Science.gov (United States)

Chen, Liang-Yu

2013-01-01

Various SiC electronics and sensors are currently under development for applications in 500C high temperature environments such as hot sections of aerospace engines and the surface of Venus. In order to conduct long-term test and eventually commercialize these SiC devices, compatible packaging technologies for the SiC electronics and sensors are required. This presentation reviews packaging technologies developed for 500C SiC electronics and sensors to address both component and subsystem level packaging needs for high temperature environments. The packaging system for high temperature SiC electronics includes ceramic chip-level packages, ceramic printed circuit boards (PCBs), and edge-connectors. High temperature durable die-attach and precious metal wire-bonding are used in the chip-level packaging process. A high temperature sensor package is specifically designed to address high temperature micro-fabricated capacitive pressure sensors for high differential pressure environments. This presentation describes development of these electronics and sensor packaging technologies, including some testing results of SiC electronics and capacitive pressure sensors using these packaging technologies.

Quick Prototyping of Educational Software: An Object-Oriented Approach.

Science.gov (United States)

Wong, Simon C-H

1994-01-01

Introduces and demonstrates a quick-prototyping model for educational software development that can be used by teachers developing their own courseware using an object-oriented programming system. Development of a courseware package called "The Match-Maker" is explained as an example that uses HyperCard for quick prototyping. (Contains…

Toddler foods, children's foods: assessing sodium in packaged supermarket foods targeted at children.

Science.gov (United States)

Elliott, Charlene D; Conlon, Martin J

2011-03-01

To critically examine child-oriented packaged food products sold in Canada for their sodium content, and to assess them light of intake recommendations, the current policy context and suggested targets. Baby/toddler foods (n 186) and child-oriented packaged foods (n 354) were coded for various attributes (including sodium). Summary statistics were created for sodium, then the children's food products were compared with the UK Food Standards Agency (FSA) 'targets' for sodium in packaged foods. Also assessed were the products' per-serving sodium levels were assessed in light of the US Institute of Medicine's dietary reference intakes and Canada's Food Guide. Calgary, Alberta, Canada. None. Twenty per cent of products could be classified as having high sodium levels. Certain sub-categories of food (i.e. toddler entrées, children's packaged lunches, soups and canned pastas) were problematic. Significantly, when scaled in according to Schedule M or viewed in light of the serving sizes on the Nutrition Facts table, the sodium level in various dry goods products generally fell within, and below, the Adequate Intake (AI)/Tolerable Upper Intake Level (UL) band for sodium. When scaled in accordance with the UK FSA targets, however, none of the (same) products met the targets. In light of AI/UL thresholds based on age and per-serving cut-offs, packaged foodstuffs for youngsters fare relatively well, with the exception of some problematic areas. 'Stealth sodium' and 'subtle sodium' are important considerations; so is use of the FSA's scaling method to evaluate sodium content, because it is highly sensitive to the difference between the reference amount and the actual real-world serving size for the product being considered.

The GENIE Universal, Object-Oriented Neutrino Generator

International Nuclear Information System (INIS)

Andreopoulos, C.

2006-01-01

A Universal Object-Oriented/C++ Neutrino Monte Carlo Generator (GENIE) is briefly described. The purpose of this large scale software system is to become the 'canonical' Monte Carlo for Neutrino Interaction Physics whose validity will extend to all neutrino types and nuclear targets in the energy range from few MeV to few hundred GeV. GENIE attempts to unify the Monte Carlo generation approaches used by a host of different, smaller procedural systems in a modern object-oriented software design. It is already a mature software system that currently consists of ∼100,000 lines of C++ code (∼350 classes organised in ∼40 packages)

Safety analysis report: packages. DOT specification 7A - Type A container Mark 15 sludge shipping package

International Nuclear Information System (INIS)

Zeh, C.W.

1985-03-01

Sludge or filter cake containing 1.1 wt % 235 U enriched uranium from Mark 15 fabrication will be packaged in 55-gallon containers and shipped from SRP to NLO, Fernald, Ohio for recovery of product. About 7 Metric Tons (MT) of filter cake will be produced from fabricating Mark 15 slugs each reactor charge. Packaged shipments of this material, consigned as exclusive use, will be shipped to NLO in Department of Transportation (DOT) Specification 7A - Type A packages under a DOE Certificate of Compliance for Fissile Class III shipments. ''Type A packaging'' is designed to retain containment and shielding integrity under normal conditions of transport. This report documents compliance of the package design, construction methods, material and test performance with DOT Specification 7A. This DOT 7A Type A package contains a carbon steel outer container which is a 0.060-in.-thick 55-gal, galvanized drum equipped with a gasketed closure. The outer container encloses a 0.090-in.-thick, open head, polyethylene liner with lid

TRU waste transportation package development

International Nuclear Information System (INIS)

Eakes, R.G.; Lamoreaux, G.H.; Romesberg, L.E.; Sutherland, S.H.; Duffey, T.A.

1980-01-01

Inventories of the transuranic wastes buried or stored at various US DOE sites are tabulated. The leading conceptual design of Type-B packaging for contact-handled transuranic waste is the Transuranic Package Transporter (TRUPACT), a large metal container comprising inner and outer tubular steel frameworks which are separated by rigid polyurethane foam and sheathed with steel plate. Testing of TRUPACT is reported. The schedule for its development is given. 6 figures

Application of Green Environmentally Friendly Materials in Food Packaging

OpenAIRE

Jixia Li

2017-01-01

With social development, requirements on the spiritual and material life have increased. However, some environmental issues appear, for example, in food packaging. Application of environment-friendly materials in food packaging has been more and more attractive. This study analyses the characteristics of degradable food packaging material and the existing problems, proposes the manufacturing of food packaging with poly(lactic acid)/nanocrystalline cellulose composite material, tests its therm...

Thermal modeling of nuclear waste package designs for disposal in tuff

International Nuclear Information System (INIS)

Hockman, J.N.; O'Neal, W.C.

1983-09-01

Lawrence Livermore National Laboratory is involved in the design and testing of high-level nuclear waste packages. Many of the aspects of waste package design and testing (e.g., corrosion and leaching) depend in part on the temperature history of the emplaced packages. This paper discusses thermal modeling and analysis of various emplaced waste package conceptual designs including the models used, the assumptions and approximations made, and the results obtained. 6 references, 6 figures, 3 tables

Thermal modeling of nuclear waste package designs for disposal in tuff

International Nuclear Information System (INIS)

Hockman, J.N.; O'Neal, W.C.

1984-02-01

Lawrence Livermore National Laboratory is involved in the design and testing of high-level nuclear waste packages. Many of the aspects of waste package design and testing (e.g., corrosion and leaching) depend in part on the temperature history of the emplaced packages. This paper discusses thermal modeling and analysis of various emplaced waste package conceptual designs including the models used, the assumptions and approximations made, and the results obtained. 6 references, 6 figures, 4 tables

Type B package for the transport of large medical and industrial sources

International Nuclear Information System (INIS)

Brown, Darrell Dwaine; Noss, Philip W.

2010-01-01

AREVA Federal Services LLC, under contract to the Los Alamos National Laboratory's Offsite Source Recovery Project, is developing a new Type B(U)-96 package for the transport of unwanted or abandoned high activity gamma and neutron radioactive sealed sources (sources). The sources were used primarily in medical or industrial devices, and are of domestic (USA) or foreign origin. To promote public safety and mitigate the possibility of loss or misuse, the Offsite Source Recovery Project is recovering and managing sources worldwide. The package, denoted the LANL-B, is designed to accommodate the sources within an internal gamma shield. The sources are located either in the IAEA's Long Term Storage Shield (LTSS), or within intact medical or industrial irradiation devices. As the sources are already shielded separately, the package does not include any shielding of its own. A particular challenge in the design of the LANL-B has been weight. Since the LTSS shield weighs approximately 5,000 lb (2,270 kg), and the total package gross weight must be limited to 10,000 lb (4,540 kg), the net weight of the package was limited to 5,000 lb, for an efficiency of 50% (i.e., the payload weight is 50% of the gross weight of the package). This required implementation of a light-weight bell-jar concept, in which the containment takes the form of a vertical bell which is bolted to a base. A single impact limiter is used on the bottom, to protect the elastomer seals and bolted joint. A top-end impact is mitigated by the deformation of a tori spherically-shaped head. Impacts in various orientations on the bottom end are mitigated by a cylindrical, polyurethane foam-filled impact limiter. Internally, energy is absorbed using honeycomb blocks at each end, which fill the torispherical head volumes. As many of the sources are considered to be in normal form, the LANL-B package offers leak-tight containment using an elastomer seal at the joint between the bell and the base, as well as on the

NWTS waste package program plan. Volume II. Program logic networks

International Nuclear Information System (INIS)

1981-10-01

This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced

Poly(hydroxyalkanoates for Food Packaging: Application and Attempts towards Implementation

Directory of Open Access Journals (Sweden)

M. Koller

2014-09-01

Full Text Available Plastics are well-established for convenient and safe packaging and distribution of food and feed goods. At present, this special sector of the plastic market displays remarkably increasing quantities of its annual production. Caused by the ongoing limitation and strongly fluctuating prices of fossil feedstocks, classically used for plastic production, there is an evident trend to switch towards so-called “bio-plastics”. Especially for bulk applications such as food packaging, a broad implementation of “bio-plastics” constitutes a future-oriented strategy to restrict the dependence of global industry on fossil feedstocks, and to diminish current problematic environmental issues arising from plastic disposal. However, food packaging demands a great deal of the utilized packaging material. This encompasses tailored mechanical properties such as low brittleness and adequate tensile strength, a sufficient barrier for oxygen, CO2, and aromatic flavors, high UV-resistance, and high water retention-capacity to block the food´s moisture content, or to prevent humidity, respectively. Due to their hydrophobic character and the broad flexibility of their mechanical features, prokaryotic poly(hydroxyalkanoates (PHAs are considered as promising materials to compete with petro-plastics on the food-packaging market. Nevertheless, short-comings in particular aspects of their material performance and economics of their biosynthesis and purification constitute stumbling blocks on the long way towards broad implementation of PHAs for food packaging. This article discusses advantages and drawbacks of PHAs as food packaging materials, and demonstrates how desired properties can be improved by the designing of novel composite materials, and also encompassing techniques by applying nanoparticles.

Radiation treatment for sterilization of packaging materials

International Nuclear Information System (INIS)

Haji-Saeid, Mohammad; Sampa, Maria Helena O.; Chmielewski, Andrzej G.

2007-01-01

Treatment with gamma and electron radiation is becoming a common process for the sterilization of packages, mostly made of natural or synthetic plastics, used in the aseptic processing of foods and pharmaceuticals. The effect of irradiation on these materials is crucial for packaging engineering to understand the effects of these new treatments. Packaging material may be irradiated either prior to or after filling. The irradiation prior to filling is usually chosen for dairy products, processed food, beverages, pharmaceutical, and medical device industries in the United States, Europe, and Canada. Radiation effects on packaging material properties still need further investigation. This paper summarizes the work done by different groups and discusses recent developments in regulations and testing procedures in the field of packaging technology

pROC: an open-source package for R and S+ to analyze and compare ROC curves.

Science.gov (United States)

Robin, Xavier; Turck, Natacha; Hainard, Alexandre; Tiberti, Natalia; Lisacek, Frédérique; Sanchez, Jean-Charles; Müller, Markus

2011-03-17

Receiver operating characteristic (ROC) curves are useful tools to evaluate classifiers in biomedical and bioinformatics applications. However, conclusions are often reached through inconsistent use or insufficient statistical analysis. To support researchers in their ROC curves analysis we developed pROC, a package for R and S+ that contains a set of tools displaying, analyzing, smoothing and comparing ROC curves in a user-friendly, object-oriented and flexible interface. With data previously imported into the R or S+ environment, the pROC package builds ROC curves and includes functions for computing confidence intervals, statistical tests for comparing total or partial area under the curve or the operating points of different classifiers, and methods for smoothing ROC curves. Intermediary and final results are visualised in user-friendly interfaces. A case study based on published clinical and biomarker data shows how to perform a typical ROC analysis with pROC. pROC is a package for R and S+ specifically dedicated to ROC analysis. It proposes multiple statistical tests to compare ROC curves, and in particular partial areas under the curve, allowing proper ROC interpretation. pROC is available in two versions: in the R programming language or with a graphical user interface in the S+ statistical software. It is accessible at http://expasy.org/tools/pROC/ under the GNU General Public License. It is also distributed through the CRAN and CSAN public repositories, facilitating its installation.

Destructive and non-destructive tests for radioactive waste packages Task 3 Characterization of radioactive waste forms. A series of final reports (1985-89) No 43

International Nuclear Information System (INIS)

Odoj, R.

1991-01-01

On the basis of preliminary waste acceptance requirements quality control of radioactive waste has to be performed prior to interim storage or final disposal. The quality control can either be achieved by random tests on conditioned radioactive waste packages or by process qualification of the conditioning processes. One of the most important criteria is the activity of the radioactive waste product or packages. To get some first information on the waste package γ-spectrometric measurement is performed as non-destructive test. Besides the γ-emitting nuclides the α and β-emitting nuclides can be estimated by calculation if the waste was generated in nuclear power plants and the nuclide relations are known. If the non-destructive determination of nuclides is not sufficient or the non-radioactive content of the waste packages has to be identified sampling from the waste packages has to be performed. This can best be done by core drilling. To avoid the need of water for cooling the drill head, air cooled core drilling is investigated. As mixed wastes is not allowed for final disposal the determination of possible organic toxic materials like PCB, dioxin and furane-compounds in cemented wastes is conducted by GC-MS-investigations. For getting more knowledge in the field of process qualification concerning super compaction, instrumentation of the super compaction process is investigated and tested

SPHINX experimenters information package

International Nuclear Information System (INIS)

Zarick, T.A.

1996-08-01

This information package was prepared for both new and experienced users of the SPHINX (Short Pulse High Intensity Nanosecond X-radiator) flash X-Ray facility. It was compiled to help facilitate experiment design and preparation for both the experimenter(s) and the SPHINX operational staff. The major areas covered include: Recording Systems Capabilities,Recording System Cable Plant, Physical Dimensions of SPHINX and the SPHINX Test cell, SPHINX Operating Parameters and Modes, Dose Rate Map, Experiment Safety Approval Form, and a Feedback Questionnaire. This package will be updated as the SPHINX facilities and capabilities are enhanced

RH Packaging Program Guidance

International Nuclear Information System (INIS)

Washington TRU Solutions, LLC

2003-01-01

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 and 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

Shelf-life extension of dried shrimps by irradiation and packaging techniques

International Nuclear Information System (INIS)

Warunee Varanyanond; Hirata, Takashi; Ishitani, Takasuke

2000-01-01

Dried shrimps were air-packaged or N2-packaged in the flexible pouch of oriented polypropylene (OPP), polyvinylidene chloride coated polypropylene (KOP) and ethylene vinyl alcohol copolymer (EVOH). The packages were irradiated with gamma ray from cobalt 60 at 3 and 8 kGy. Non-irradiated dried shrimps were used as a control. The samples were stored at 30 deg C and 70+-5 percent RH for 4 months. Non-enzymatic browning induced the discoloration of dried shrimps, and oxidation of astaxanthin proceeded after irradiation and during storage. The hunter color difference, delta E, of all the samples was increased, especially in the non-irradiated air-packages samples. The decrease in astaxanthin content was found in both air - and N2-packaged samples during storage. The number of microorganisms was reduced by irradiation dose of 3 and 8 kGy from 6.5 to 4.2 and 2.7 log CFU/g, respectively. The decreased concentration of O2 in the package also reduced the number of microorganisms. The air packaged dried shrimps in the OPP pouch deteriorated during storage. Shrinkage of the pouches and growth of halophilic bacteria on the surface of dried shrimps were found at a sub(w) of 0.75. The discoloration of dried shrimps in the OPP pouch was more significant than that in other pouches. Irradiation at 3 and 8 kGy in combination with packaging in KOP and EVOH pouches containing N2 atmosphere was one of the promising methods for prolonging shelf-life of dried shrimps at room temperature

Development status of the experimental and numerical load analysis of package units CASTOR {sup registered} under drop test conditions; Entwicklungsstand in der experimentellen und numerischen Beanspruchungsanalyse von Versandstuecken der Bauart CASTOR {sup registered} unter Fallpruefbedingungen

Energy Technology Data Exchange (ETDEWEB)

Voelzer, Walter; Schaefer, Marc; Rumanus, Erkan; Liedtke, Ralph [Gesellschaft fuer Nuklear-Service mbH (Germany); Brehmer, Frank [ITB GmbH (Germany)

2012-11-01

The mechanical integrity of package units CASTOR {sup registered} for a 9-m drop test under accident conditions has to be demonstrated according the requirements of IAEA among others. For reduction of the loads the containers have to be equipped with shock absorbers on the bottom and top sides. The determination of loads under drop test conditions can be performed with experimental or numerical methods. Due to the complexity of the load state and the verification of results both methods are usually used for integrity demonstration. The numerical codes have to model the short-term dynamic behavior of the whole container for different drop orientations and temperatures, local stress states have to be quantifiable for assessment. One of the problems is the modeling of the material behavior of wood that is used in the shock absorbers. The so far used energetic calculation approach will be replaced by a dynamic approach, the numerical models will have to be verified by experimental drop tests.

Structural safety test and analysis of type IP-2 transport packages with bolted lid type and thick steel plate for radioactive waste drums in a NPP

International Nuclear Information System (INIS)

Kim, Dong Hak; Seo, Ki Seog; Lee, Sang Jin; Lee, Kyung Ho; Kim, Jeong Mook

2007-01-01

If a type IP-2 transport package were to be subjected to a free drop test and a penetration test under the normal conditions of transport, it should prevent a loss or dispersal of the radioactive contents and a more than 20% increase in the maximum radiation level at any external surface of the package. In this paper, we suggested the analytic method to evaluate the structural safety of a type IP-2 transport package using a thick steel plate for a structure part and a bolt for tying a bolt. Using an analysis a loss or disposal of the radioactive contents and a loss of shielding integrity were confirmed for two kinds of type IP-2 transport packages to transport radioactive waste drums from a waste facility to a temporary storage site in a nuclear power plant. Under the free drop condition the maximum average stress at the bolts and the maximum opening displacement of a lid were compared with the tensile stress of a bolt and the steps in a lid, which were made to avoid a streaming radiation in the shielding path, to evaluate a loss or dispersal of radioactive waste contents. Also a loss of shielding integrity was evaluated using the maximum decrease in a shielding thickness. To verify the impact dynamic analysis for free drop test condition and evaluate experimentally the safety of two kinds of type IP-2 transport packages, free drop tests were conducted with various drop directions

CH Packaging Operations for High Wattage Waste at LANL

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2002-01-01

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal

CH Packaging Operations for High Wattage Waste at LANL

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2002-01-01

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal

CH Packaging Operations for High Wattage Waste at LANL

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2003-01-01

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal

Application of Green Environmentally Friendly Materials in Food Packaging

Directory of Open Access Journals (Sweden)

Jixia Li

2017-11-01

Full Text Available With social development, requirements on the spiritual and material life have increased. However, some environmental issues appear, for example, in food packaging. Application of environment-friendly materials in food packaging has been more and more attractive. This study analyses the characteristics of degradable food packaging material and the existing problems, proposes the manufacturing of food packaging with poly(lactic acid/nanocrystalline cellulose composite material, tests its thermal and mechanical properties, and applies it to the design of food packaging. The results demonstrate that the thermal and mechanical properties of the material could satisfy the requirements of food packaging and that the material is applicable to the design of food packaging in the future. This work provides a reference for the application of green, environment-friendly materials in the design of food packaging.

Packaging and transport case of test fuel assembly irradiated in the Creys-Malville reactor

International Nuclear Information System (INIS)

Geffroy, J.; Vivien, J.; Pouard, M.; Dujardin, G.N.; Veron, B.; Michoux, H.

1986-06-01

Some irradiated fuel assemblies from the fast neutron Creys Malville reactor will be sent to hot laboratories to follow fuel behavior. These test assemblies will be examined after a limited cooling time and transport is realized at high residual power (about 10kW) and cladding temperature should not rise over 500deg C. The fuel assemblies are not dismantled and transported into sodium. The assembly is placed into a case containing sodium plugged and put into a packaging. Dimensioning, thermal behavior, radiation protection and containment are examined [fr

Second Generation Waste Package Design Study

International Nuclear Information System (INIS)

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

2007-01-01

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 test environments 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

Packaging Solutions : Delivering customer value through Logistical Packaging: A Case Study at Stora Enso Packaging

OpenAIRE

Shan, Kun; Julius, Joezer

2015-01-01

AbstractBackground;Despite of the significant role of packaging within logistics and supply chain management, packaging is infrequently studied as focal point in supply chain. Most of the previous logistics research studies tend to explain the integration between packaging and logistics through logistical packaging. In very rare cases, the studies mentioned about customer value. Therefore the major disadvantage of these studies is that, they didn’t consider logistical packaging and customer v...

An analysis of the qualification criteria for small radioactive material shipping packages

International Nuclear Information System (INIS)

McClure, J.D.

1983-05-01

The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described

An analysis of the qualification criteria for small radioactive material shipping packages

Energy Technology Data Exchange (ETDEWEB)

McClure, J.D.

1983-05-01

The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

ORIENTEERING SITUATION TESTS IN THE FUNCTION OF PREDICTING SUCCESS OF POLICE OFFICERS IN TOPOGRAPHY FIELD TRAINING

Directory of Open Access Journals (Sweden)

Boban Milojković

2006-06-01

Full Text Available The sample of 45 students (15 students of the I year of Police Academy – the members of orienteering section – Group 1, 15 students of the I year of Police Academy – Group 2 and 15 students of Advanced School of Interior Affairs – Group 3 has been chosen to test the degree of success in topography field training through several stages, and orienteering situation tests were used in one of these stages. The research was carried out following the completed theoretical and practical training in topography by the same teacher but according to various models. During the research, three batteries of tests were used, the tests of capability of fast and accurate reading of topographic maps in the form of perforated sections (T-1, T-2 and T-3. With regard to measuring success in solving orienteering situation tests of three tested groups based on which the educational efficiency of police members in topography field training should have been evaluated, the obtained results have shown that at a general level there were statistically important differences of total variance of the observed set of variables of tested groups at the level p = 0.000 (Willks Lambda, 0.056, F = 225.598. The results have shown that there were statistically important differences between the success in test solving with reference to groups at the level p = 0.002 and p = 0.000, respectively. Thedifferences between groups in the function of an individual test were as follows: T-1, there was a cross difference between all three groups; T-2, there was no difference between the first and second groups, but the third group differed in relation to the first and second ones; T-3, there was a cross difference between all three groups. The results of tested population by means of the stated instruments describe the level of competency of police members in topography respectively in order to individualize training, but primarily prove statistically considerable difference of the level

Design, construction, test and field support of a containerless payload package for rocket flight. [electromagnetic heating and confinement

Science.gov (United States)

1977-01-01

The performance of a device for electromagnetically heating and positioning containerless melts during space processing was evaluated during a 360 second 0-g suborbital sounding rocket flight. Components of the electromagnetic containerless processing package (ECPP), its operation, and interface with the rocket are described along with flight and qualification tests results.

Research and Development Program for transportation packagings at Sandia National Laboratories

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Sorenson, K.B.

1995-01-01

This document contains information about the research and development programs dealing with waste transport at Sandia National Laboratories. This paper discusses topics such as: Why new packaging is needed; analytical methodologies and design codes;evaluation of packaging components; materials characterization; creative packaging concepts; packaging engineering and analysis; testing; and certification support

The role of assessment packages for diagnostic consultations

DEFF Research Database (Denmark)

Rossen, Camilla B; Buus, Niels; Stenager, Egon

2015-01-01

and content. Assessment packages are widely used in an increasing number of medical specialities; however, there is a lack of knowledge about how packaged assessment influences the interaction between doctor and patient. In this study, we investigate the final consultation in assessment packages, which...... whose goal was to leave the consultation with clarification in the form of a definite diagnosis, but who were not offered such clarification. These patients negotiated the outcome of the consultation by applying implicit and explicit pressure, which induced the doctors to disregard the boundaries...... of the package and offer the patient more tests. The study highlights some of the problems related to introducing narrow, specialized package assessment....

Packaging fluency

DEFF Research Database (Denmark)

Mocanu, Ana; Chrysochou, Polymeros; Bogomolova, Svetlana

2011-01-01

Research on packaging stresses the need for packaging design to read easily, presuming fast and accurate processing of product-related information. In this paper we define this property of packaging as “packaging fluency”. Based on the existing marketing and cognitive psychology literature on pac...

Thermal Testing and Quality Assurance of BGA LCC & QFN Electronic Packages

Energy Technology Data Exchange (ETDEWEB)

Kuper, Cameron Mathias [Univ. of New Mexico, Albuquerque, NM (United States)

2015-12-10

The purpose of this project is to experimentally validate the thermal fatigue life of solder interconnects for a variety of surface mount electronic packages. Over the years, there has been a significant amount of research and analysis in the fracture of solder joints on printed circuit boards. Solder is important in the mechanical and electronic functionality of the component. It is important throughout the life of the product that the solder remains crack and fracture free. The specific type of solder used in this experiment is a 63Sn37Pb eutectic alloy. Each package was surrounded conformal coating or underfill material.

Effect of gamma irradiation on physico-mechanical properties of spice packaging films

Energy Technology Data Exchange (ETDEWEB)

Mizani, Maryam [Department of Food Science and Technology, Science and Research Branch, Islamic Azad University, P.O. Box 14155-4933, Tehran (Iran, Islamic Republic of)], E-mail: mizani1_2000@yahoo.com; Sheikh, Nasrin [Nuclear Science and Technology Research Institute, Radiation Application Research School, P.O. Box 11365-3486, Tehran (Iran, Islamic Republic of); Ebrahimi, Samad N. [Department of Phytochemistry, Medicinal Plants and Drugs Research Institute, Shahid Beheshti University, P.O. Box 19835-389, Tehran (Iran, Islamic Republic of); Gerami, Abas [School of Mathematics, Statistics and Computer Science, University of Tehran, P.O. Box 14155-6455, Tehran (Iran, Islamic Republic of); Tavakoli, Farnaz A. [Department of Food Science and Technology, Science and Research Branch, Islamic Azad University, P.O. Box 14155-4933, Tehran (Iran, Islamic Republic of)

2009-09-15

Physico-mechanical properties of two types of laminated films, commercially used for spice packaging, are investigated after gamma irradiation at 8, 10 and 15 kGy. Data showed that polyethylene terephthalate/polyethylene terephthalate/linear low density polyethylene (PET/PET/LLDPE) was more resistant to radiation compared to biaxially oriented polypropylene/cast polypropylene (BOPP/CPP) and its barrier properties slightly improved up to 15 kGy. Oxygen transmission rate of BOPP/CPP was increased by 25%, and the melting peak temperature was decreased by 3.9% at 15 kGy, which may lead to oxidation of packaged spices and loss of their aroma/flavour, respectively.

Effect of gamma irradiation on physico-mechanical properties of spice packaging films

International Nuclear Information System (INIS)

Mizani, Maryam; Sheikh, Nasrin; Ebrahimi, Samad N.; Gerami, Abas; Tavakoli, Farnaz A.

2009-01-01

Physico-mechanical properties of two types of laminated films, commercially used for spice packaging, are investigated after gamma irradiation at 8, 10 and 15 kGy. Data showed that polyethylene terephthalate/polyethylene terephthalate/linear low density polyethylene (PET/PET/LLDPE) was more resistant to radiation compared to biaxially oriented polypropylene/cast polypropylene (BOPP/CPP) and its barrier properties slightly improved up to 15 kGy. Oxygen transmission rate of BOPP/CPP was increased by 25%, and the melting peak temperature was decreased by 3.9% at 15 kGy, which may lead to oxidation of packaged spices and loss of their aroma/flavour, respectively.

A program to develop packages for long-lived ILW

International Nuclear Information System (INIS)

Sakamoto, H.; Kobayashi, S.; Tanabe, H.; Kataoka, S.; Yoshida, T.; Takei, A.; Nakamori, Y.; Sugimoto, M.; Kanno, T.

2001-01-01

TRU waste packages development has been conducted from 1998 by RWMC and industries in Japan to establish configuration which comply with the TRU waste disposal concept. 5 waste package concepts were selected through comparison study among over 20 proposals. Those 5 packages are two concrete container types and three metal container types. They were chosen from the view points of engineering feasibility and prospected advantages for repository performance. In this paper, overview of the development plan is introduced, and the design concepts of those 5 waste packages and the results of functional tests for some packages are shown. (author)

An R package "VariABEL" for genome-wide searching of potentially interacting loci by testing genotypic variance heterogeneity

Directory of Open Access Journals (Sweden)

Struchalin Maksim V

2012-01-01

Full Text Available Abstract Background Hundreds of new loci have been discovered by genome-wide association studies of human traits. These studies mostly focused on associations between single locus and a trait. Interactions between genes and between genes and environmental factors are of interest as they can improve our understanding of the genetic background underlying complex traits. Genome-wide testing of complex genetic models is a computationally demanding task. Moreover, testing of such models leads to multiple comparison problems that reduce the probability of new findings. Assuming that the genetic model underlying a complex trait can include hundreds of genes and environmental factors, testing of these models in genome-wide association studies represent substantial difficulties. We and Pare with colleagues (2010 developed a method allowing to overcome such difficulties. The method is based on the fact that loci which are involved in interactions can show genotypic variance heterogeneity of a trait. Genome-wide testing of such heterogeneity can be a fast scanning approach which can point to the interacting genetic variants. Results In this work we present a new method, SVLM, allowing for variance heterogeneity analysis of imputed genetic variation. Type I error and power of this test are investigated and contracted with these of the Levene's test. We also present an R package, VariABEL, implementing existing and newly developed tests. Conclusions Variance heterogeneity analysis is a promising method for detection of potentially interacting loci. New method and software package developed in this work will facilitate such analysis in genome-wide context.

Licensing experiences, risk assessment, demonstration test on nuclear fuel packages and design criteria for sea going vessel carrying spent fuel in Japan

International Nuclear Information System (INIS)

Aoki, S.; Ikeda, K.

1978-01-01

In Japan spent fuels from nuclear power plants shall be shipped to reprocessing plants by sea-going vessels. Atomic Energy Committee has initiated a board of experts to implement the assessment of environmental safety for sea transport. As a part of the assessment a study has been conducted by Central Research Institute of Electric Power Industry under sponsorship of Nuclear Safety Bureau, which is intended to guarantee the safety of sea transport. Nuclear Safety Bureau also has a program to carry out a long term demonstration test on spent fuel package using full scale package models. The test consists of drop, heat transfer, fire, collapse under high external pressure, immersion, shielding and subcritical test. The purpose of this test is to obtain the public acceptance and also to verify the adequacy of the safety analysis for nuclear fuel packages. In order to secure the safety of sea transport, the Ministry of Transportation has provided for the design criteria for sea-going vessel in the case of full load shipping, which aims to make minimum the probability of sinking at collision, grounding and other unforeseen accidents on the sea and also to retain the radiation exposure to crews as low as possible. The design criteria consists of the following items: (1) structural strength of vessel, (2) collision protective structure, (3) arrangement of holds, (4) stability after damage, (5) grounding protective structure, (6) cooling system, (7) tie-down equipment, (8) radiation inspection apparatus, (9) decontamination facilities, (10) emergency water flooding equipment for ship fire, (11) emergency electric sources, etc. Based on the design criteria a sea-going vessel names HINOURA-MARU has been reconstructed to transport spent fuel packages from nuclear power stations to the reprocessing plant

Microelectronic packaging

CERN Document Server

Datta, M; Schultze, J Walter

2004-01-01

Microelectronic Packaging analyzes the massive impact of electrochemical technologies on various levels of microelectronic packaging. Traditionally, interconnections within a chip were considered outside the realm of packaging technologies, but this book emphasizes the importance of chip wiring as a key aspect of microelectronic packaging, and focuses on electrochemical processing as an enabler of advanced chip metallization.Divided into five parts, the book begins by outlining the basics of electrochemical processing, defining the microelectronic packaging hierarchy, and emphasizing the impac

PAC++: Object-oriented platform for accelerator codes

International Nuclear Information System (INIS)

Malitsky, N.; Reshetov, A.; Bourianoff, G.

1994-06-01

Software packages in accelerator physics have relatively long life cycles. They had been developed and used for a wide range of accelerators in the past as well as for the current projects. For example, the basic algorithms written in the first accelerator Program TRANSPORT are actual for design of most magnet systems. Most of these packages had been implemented on Fortran. But this language is rather inconvenient as a basic language for large integrated projects that possibly could include real-time data acquisition, data base access, graphic riser interface modules (GUI), arid other features. Some later accelerator programs had been based on object-oriented tools (primarily, C++ language). These range from systems for advanced theoretical studies to control system software. For the new generations of accelerators it would be desirable to have an integrated platform in which all simulation and control tasks will be considered with one point of view. In this report the basic principles of an object-oriented platform for accelerator research software (PAC++) are suggested and analyzed. Primary objectives of this work are to enable efficient self-explaining realization of the accelerator concepts and to provide an integrated environment for the updating and the developing of the code

Influence of Hormonal Contraceptive Use and Health Beliefs on Sexual Orientation Disparities in Papanicolaou Test Use

Science.gov (United States)

Corliss, Heather L.; Missmer, Stacey A.; Frazier, A. Lindsay; Rosario, Margaret; Kahn, Jessica A.; Austin, S. Bryn

2014-01-01

Objectives. Reproductive health screenings are a necessary part of quality health care. However, sexual minorities underutilize Papanicolaou (Pap) tests more than heterosexuals do, and the reasons are not known. Our objective was to examine if less hormonal contraceptive use or less positive health beliefs about Pap tests explain sexual orientation disparities in Pap test intention and utilization. Methods. We used multivariable regression with prospective data gathered from 3821 females aged 18 to 25 years in the Growing Up Today Study (GUTS). Results. Among lesbians, less hormonal contraceptive use explained 8.6% of the disparities in Pap test intention and 36.1% of the disparities in Pap test utilization. Less positive health beliefs associated with Pap testing explained 19.1% of the disparities in Pap test intention. Together, less hormonal contraceptive use and less positive health beliefs explained 29.3% of the disparities in Pap test intention and 42.2% of the disparities in Pap test utilization. Conclusions. Hormonal contraceptive use and health beliefs, to a lesser extent, help to explain sexual orientation disparities in intention and receipt of a Pap test, especially among lesbians. PMID:23763393

Understanding voter orientation in the context of political market orientation

DEFF Research Database (Denmark)

Ormrod, Robert P.; Henneberg, Stephan C.

2010-01-01

This article develops a conceptual framework and measurement model of political market orientation. The relationships between different behavioural aspects of political market orientation and the attitudinal influences of such behaviour are analysed, and the study includes structural equation...... modelling to test several hypotheses. While the results show that political parties focus on several different aspects of market-oriented behaviour, especially using an internal and societal orientation as cultural antecedents, a more surprising result is the inconclusive effect of a voter orientation...... on political market orientation. This lends support to the argument of 'looking beyond the customer' in political marketing research and practice. The article discusses the findings in the context of the existing literature on political marketing and commercial market orientation....

Development of $Mathematica$ Package 'StandardPhysicalConstants'

CERN Document Server

Ezhela, Vladimir V

2003-01-01

Here we report on the further development of the 'StandardPhysicalConstants' package which was presented for the first time at the last IMS 2001 conference. We would like to dwell on the following issues: the package structure; current status of the physical constant database; data sourses, current data collection and data structure; the main modules of data management system; the first version of "error propagator"; usage examples of one in calculations for high precision tests of physics theories. The outlook of the future development of the package is also given.

Stowing of radioactive materials package during land transport. Third phase

International Nuclear Information System (INIS)

Gilles, P.; Chevalier, G.; Pouard, M.; Jolys, J.C.; Draulans, J.; Lafontaine, I.

1984-01-01

Phase 3 of this study is mainly experimental. The study is based on the work performed during 2 former studies: phase 1: definition and analysis of reference accidental conditions, and phase 2: selection of some reference accidents and computation of the deceleration forces. The main goal of the study is to draw up a reference document, giving some guidances for the stowing of packages on conveyances for land transportation. The third phase includes four frontal impact tests. The reference package used is a French IL-37 container weighing about 1.3 t. The first test was performed using a truck, loaded with two IL-37 containers and launched at a speed of 50 km/h against a fixed obstacle. The deceleration curve the behaviour of each package and the behaviour of stowing systems are compared with the theoretical results. Various measurements were made during the test: vehicle impact speed; vehicle deceleration, measured at different points on the frame, package deceleration, displacement of attachment points. The impact was filmed from different angles. The second test was performed in the same impact conditions but with a waggon instead of a truck, and loaded with one container. The front of the waggon was equipped with special shock absorbers to obtain the same deceleration as recorded during the truck impact (first test). In the third test the stowing systems were reinforced by a nylon one in order to obtain information of stowing systems of that type and to increase the energy absorption capacity. In the fourth test in addition to being stowed the package was also chocked. The results obtained have shown that it is possible to maintain a package on a truck platform even during a severe frontal impact

Hydrothermal waste package interactions with methane-containing basalt groundwater

International Nuclear Information System (INIS)

McGrail, B.P.

1984-11-01

Hydrothermal waste package interaction tests with methane-containing synthetic basalt groundwater have shown that in the absence of gamma radiolysis, methane has little influence on the glass dissolution rate. Gamma radiolysis tests at fluxes of 5.5 x 10 5 and 4.4 x 10 4 R/hr showed that methane-saturated groundwater was more reducing than identical experiments where Ar was substituted for CH 4 . Dissolved methane, therefore, may be beneficial to the waste package in limiting the solubility of redox sensitive radionuclides such a 99 Tc. Hydrocarbon polymers known to form under the irradiation conditions of these tests were not produced. The presence of the waste package constituents apparently inhibited the formation of the polymers, however, the mechanism which prevented their formation was not determined

Effects of ionizing radiation on food packaging materials and quality

International Nuclear Information System (INIS)

Welle, F.; Franz, R.

1999-01-01

Tests have shown that ionizing radiation induces a characteristic smell in the packaging laminates which also affects the simulated foods used, which however were relatively neutral in flavour, so that the tests represent the worst case. The paper explains that due to the various additives used in the production of the plastic packaging materials, the same types of polymers may react differently to the ionizing radiation, so that the results obtained from the tests are not suitable for general application. It is recommended to very carefully select the suitable packaging material for given foods and intended irradiation processes. Aspects of particular importance are discusses. (orig./CB) [de

The Packaging Handbook -- A guide to package design

International Nuclear Information System (INIS)

Shappert, L.B.

1995-01-01

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

An evaluation of a supplementary road safety package.

Science.gov (United States)

Guria, Jagadish; Leung, Joanne

2004-09-01

A Supplementary Road Safety Package (SRSP) was developed in New Zealand in 1995/1996 to supplement the compulsory breath test (CBT) and speed camera programmes introduced in 1993. A major feature of the package was the use of emotion and shock advertising campaigns not only to affect high risk driving attitudes and behaviours towards speeding and drink-driving but also to encourage the use of safety belts. Furthermore, the SRSP also emphasised targeting enforcement to these three areas. This package continued for 5 years. This paper estimates the effect of the package on road trauma. The analysis shows that the Package made substantial impact on road safety and saved over 285 lives over the 5-year period. Copyright 2003 Elsevier Ltd.

A Confirmatory Factor Analysis of the Life Orientation Test-Revised with Competitive Athletes

Science.gov (United States)

Appaneal, Renee N.

2012-01-01

Current reviews outside of sport indicate that the Life Orientation Test-Revised (LOT-R) items load on two separate factors (optimism and pessimism) and, therefore, should be treated as independent constructs. However, researchers in the sport sciences continue to use the single composite score reflecting a unidimensional definition of optimism.…

High-performance packaging for monolithic microwave and millimeter-wave integrated circuits

Science.gov (United States)

Shalkhauser, K. A.; Li, K.; Shih, Y. C.

1992-01-01

Packaging schemes are developed that provide low-loss, hermetic enclosure for enhanced monolithic microwave and millimeter-wave integrated circuits. These package schemes are based on a fused quartz substrate material offering improved RF performance through 44 GHz. The small size and weight of the packages make them useful for a number of applications, including phased array antenna systems. As part of the packaging effort, a test fixture was developed to interface the single chip packages to conventional laboratory instrumentation for characterization of the packaged devices.

CONSUL code package application for LMFR core calculations

Energy Technology Data Exchange (ETDEWEB)

Chibinyaev, A.V.; Teplov, P.S.; Frolova, M.V. [RNC ' Kurchatovskiy institute' , Kurchatov sq.1, Moscow (Russian Federation)

2008-07-01

CONSUL code package designed for the calculation of reactor core characteristics has been developed at the beginning of 90's. The calculation of nuclear reactor core characteristics is carried out on the basis of correlated neutron, isotope and temperature distributions. The code package has been generally used for LWR core characteristics calculations. At present CONSUL code package was adapted to calculate liquid metal fast reactors (LMFR). The comparisons with IAEA computational test 'Evaluation of benchmark calculations on a fast power reactor core with near zero sodium void effect' and BN-1800 testing calculations are presented in the paper. The IAEA benchmark core is based on the innovative core concept with sodium plenum above the core BN-800. BN-1800 core is the next development step which is foreseen for the Russian fast reactor concept. The comparison of the operational parameters has shown good agreement and confirms the possibility of CONSUL code package application for LMFR core calculation. (authors)

Watermarking spot colors in packaging

Science.gov (United States)

Reed, Alastair; Filler, TomáÅ.¡; Falkenstern, Kristyn; Bai, Yang

2015-03-01

In January 2014, Digimarc announced Digimarc® Barcode for the packaging industry to improve the check-out efficiency and customer experience for retailers. Digimarc Barcode is a machine readable code that carries the same information as a traditional Universal Product Code (UPC) and is introduced by adding a robust digital watermark to the package design. It is imperceptible to the human eye but can be read by a modern barcode scanner at the Point of Sale (POS) station. Compared to a traditional linear barcode, Digimarc Barcode covers the whole package with minimal impact on the graphic design. This significantly improves the Items per Minute (IPM) metric, which retailers use to track the checkout efficiency since it closely relates to their profitability. Increasing IPM by a few percent could lead to potential savings of millions of dollars for retailers, giving them a strong incentive to add the Digimarc Barcode to their packages. Testing performed by Digimarc showed increases in IPM of at least 33% using the Digimarc Barcode, compared to using a traditional barcode. A method of watermarking print ready image data used in the commercial packaging industry is described. A significant proportion of packages are printed using spot colors, therefore spot colors needs to be supported by an embedder for Digimarc Barcode. Digimarc Barcode supports the PANTONE spot color system, which is commonly used in the packaging industry. The Digimarc Barcode embedder allows a user to insert the UPC code in an image while minimizing perceptibility to the Human Visual System (HVS). The Digimarc Barcode is inserted in the printing ink domain, using an Adobe Photoshop plug-in as the last step before printing. Since Photoshop is an industry standard widely used by pre-press shops in the packaging industry, a Digimarc Barcode can be easily inserted and proofed.

Design and Certification of Targets for Drop Tests at the NTRC Packaging Research Facility

International Nuclear Information System (INIS)

Ludwig, S.B.

2003-01-01

This report provides documentation of the design and certification of drop pad (targets) at the National Transportation Research Center (NTRC) Packaging Research Facility(PRF). Based on the evaluation performed, it has been demonstrated that the small (interior) drop pad (target) meets the regulatory definition of a flat, essentially unyielding, horizontal surface for packages weighing up to 3,150 lb (1,432 kg). The large (exterior) drop pad (target) meets the regulatory definition of a flat, essentially unyielding, horizontal surface for packages weighing up to 28,184 lb (12,811 kg)

Packaging and testing of multi-wavelength DFB laser array using REC technology

Science.gov (United States)

Ni, Yi; Kong, Xuan; Gu, Xiaofeng; Chen, Xiangfei; Zheng, Guanghui; Luan, Jia

2014-02-01

Packaging of distributed feedback (DFB) laser array based on reconstruction-equivalent-chirp (REC) technology is a bridge from chip to system, and influences the practical process of REC chip. In this paper, DFB laser arrays of 4-channel @1310 nm and 8-channel @1550 nm are packaged. Our experimental results show that both these laser arrays have uniform wavelength spacing and larger than 35 dB average Side Mode Suppression Ratio (SMSR). When I=35 mA, we obtain the total output power of 1 mW for 4-channel @1310 nm, and 227 μw for 8-channel @1550 nm respectively. The high frequency characteristics of the packaged chips are also obtained, and the requirements for 4×10 G or even 8×10 G systems can be reached. Our results demonstrate the practical and low cost performance of REC technology and indicate its potential in the future fiber-to-the-home (FTTH) application.

Feature Selection with the Boruta Package

OpenAIRE

Kursa, Miron B.; Rudnicki, Witold R.

2010-01-01

This article describes a R package Boruta, implementing a novel feature selection algorithm for finding emph{all relevant variables}. The algorithm is designed as a wrapper around a Random Forest classification algorithm. It iteratively removes the features which are proved by a statistical test to be less relevant than random probes. The Boruta package provides a convenient interface to the algorithm. The short description of the algorithm and examples of its application are presented.

Characterization of shock-absorbing material for packages

International Nuclear Information System (INIS)

Mourao, Rogerio Pimenta

2007-01-01

Since 2001 Brazil has been participating in a regional effort with other Latin American countries which operate research reactors to improve its capability in the management of spent fuel elements from these reactors. One of the options considered is the long-term dry storage of the spent fuel in a dual purpose cask, i.e., a package for the transport and storage of radioactive material. In the scope of an IAEA-sponsored project, a cask was designed and a half-scale model for test was built. The cask consists of a sturdy cylindrical body provided with internal cavity to accommodate a basket holding the spent fuel elements, a double lid system, and external impact limiters. The cask is provided with top and bottom impact limiters, which are structures made of an external stainless steel skin and an energy-absorbing filling material. The filling material chosen was the wood composite denominated Oriented Strand Board (OSB), which is an engineered, mat-formed panel product made of strands, flakes or wafers sliced from small diameter, round wood logs and bonded with a binder under heat and pressure. The characterization of this material was carried in the scope of the cask project at the CDTN's laboratories. The tests conducted were the quasi-static compression, impact, shear-bending and edgewise shear tests. The compression, shear-bending and edgewise shear tests were carried out in a standard compression test machine and the impact test at a drop test tower equipped with a sturdy base and a drop weight. The main parameters of the material, like the Young and shear moduli, as well as the static and dynamic stress-strain curves and the specific energy absorbed, were determined during the test campaign. (author)

Characterization of shock-absorbing material for packages

Energy Technology Data Exchange (ETDEWEB)

Mourao, Rogerio Pimenta [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mail: mouraor@cdtn.br

2007-07-01

Since 2001 Brazil has been participating in a regional effort with other Latin American countries which operate research reactors to improve its capability in the management of spent fuel elements from these reactors. One of the options considered is the long-term dry storage of the spent fuel in a dual purpose cask, i.e., a package for the transport and storage of radioactive material. In the scope of an IAEA-sponsored project, a cask was designed and a half-scale model for test was built. The cask consists of a sturdy cylindrical body provided with internal cavity to accommodate a basket holding the spent fuel elements, a double lid system, and external impact limiters. The cask is provided with top and bottom impact limiters, which are structures made of an external stainless steel skin and an energy-absorbing filling material. The filling material chosen was the wood composite denominated Oriented Strand Board (OSB), which is an engineered, mat-formed panel product made of strands, flakes or wafers sliced from small diameter, round wood logs and bonded with a binder under heat and pressure. The characterization of this material was carried in the scope of the cask project at the CDTN's laboratories. The tests conducted were the quasi-static compression, impact, shear-bending and edgewise shear tests. The compression, shear-bending and edgewise shear tests were carried out in a standard compression test machine and the impact test at a drop test tower equipped with a sturdy base and a drop weight. The main parameters of the material, like the Young and shear moduli, as well as the static and dynamic stress-strain curves and the specific energy absorbed, were determined during the test campaign. (author)

The 2030 EU Climate and Energy Package: why and how?

International Nuclear Information System (INIS)

Spencer, Thomas; Colombier, Michel; Ribera, Teresa

2013-01-01

It is not surprising that in difficult economic times a long-term issue like climate policy has slipped down the agenda. However, Europe still has fundamental challenges to face in this regard. The IPCC's 5. assessment report underscored again the urgency of action on climate change. Europe will need to prepare its position for the crucial 2015 climate change negotiations hosted by France. Moreover, Europe's energy sector is in dire need of long-term orientations. Europe's fuel bill is a significant weight on its economy; the weight of evidence suggests that Europe will not replicate the US shale gas revolution. It is also important not to exaggerate the importance of the US shale revolution for competitiveness and economic performance. Europe will need to develop its own collective, competitive solutions. In comparison with 2008, there is significant divergence in Member States' vision for the 2030 climate and energy package. Some want renewables targets, others don't. Neither the Commission nor Member States are yet ready to address energy efficiency in the new package. And so on. This article conducts three thought experiments, thinking through three radically different designs for the 2030 package. These are a CO 2 only package, an innovation package, or a subsidiarity package. These reflections lead to the conclusion that a combination of elements is needed. Firstly, carbon pricing via the EU ETS should remain a central pillar, and be reinforced. Secondly, technology deployment objectives remain necessary: the key question should be what kind of targets and how to negotiate them, not whether. Finally, there is a need to build flexibility into the new package, in order to take into account the diversity of Member States' circumstances and preferences. (authors)

Advanced functional network analysis in the geosciences: The pyunicorn package

Science.gov (United States)

Donges, Jonathan F.; Heitzig, Jobst; Runge, Jakob; Schultz, Hanna C. H.; Wiedermann, Marc; Zech, Alraune; Feldhoff, Jan; Rheinwalt, Aljoscha; Kutza, Hannes; Radebach, Alexander; Marwan, Norbert; Kurths, Jürgen

2013-04-01

Functional networks are a powerful tool for analyzing large geoscientific datasets such as global fields of climate time series originating from observations or model simulations. pyunicorn (pythonic unified complex network and recurrence analysis toolbox) is an open-source, fully object-oriented and easily parallelizable package written in the language Python. It allows for constructing functional networks (aka climate networks) representing the structure of statistical interrelationships in large datasets and, subsequently, investigating this structure using advanced methods of complex network theory such as measures for networks of interacting networks, node-weighted statistics or network surrogates. Additionally, pyunicorn allows to study the complex dynamics of geoscientific systems as recorded by time series by means of recurrence networks and visibility graphs. The range of possible applications of the package is outlined drawing on several examples from climatology.

Packagings in the silicon era

International Nuclear Information System (INIS)

Beone, G.; Mione, A.; Orsini, A.; Forasassi, G.

1993-01-01

ENEA is studying, with the collaboration of the DCMN of the Pisa University, a new packaging to collect wastes in various facilities while proceeding to find a final disposal. Following a survey on the wastes that could be transported in the future, it was agreed to design a packaging able to contain an industrial drum, with a maximum capacity of 220 litres and a total weight less than 4000 N, previously filled with solid wastes in bulk or in a solid binding material. The packaging, to be approved as a Type B in agreement with the IAEA Regulations, will be useful to transport not only radioactive wastes but any kind of dangerous goods and also those not in agreement with the UNO Regulations. The 1/2 scale model of the packaging is formed by two concentric vessels of mild steel obtained by welding commercial shells to cylindrical walls and joined through a flange. The new packaging under development presents features that seem to be proper for its envisaged waste collection main use such as construction simplicity, relatively low cost, time and use endurance, low maintenance requirements. The design analysis and testing program ongoing at present allowed for the preliminary definition of the packaging geometry and confirmed the necessity of further investigations in some key areas as the determination of actual behaviour of the silicon foam, used as energy absorbing/thermal insulating material, in the specific conditions of interest. (J.P.N.)

Hydrothermal waste package interactions with methane-containing basalt groundwater

International Nuclear Information System (INIS)

McGrail, B.P.

1984-01-01

Hydrothermal waste package interaction tests were conducted with a mixture of crushed glass, basalt, and steel in methane-containing synthetic basalt groundwater. In the absence of gamma radiolysis, methane was found to have little influence on the corrosion behavior of the waste package constituents. Under gamma radiolysis, methane was found to significantly lower the solution oxidation potential when compared to identical tests without methane. In addition, colloidal hydrocarbon polymers that have been produced under the irradiation conditions of these experiments were not formed. The presence of the waste package constituents apparently inhibited the formation of the polymers. However, the mechanism which prevented their formation was not determined

Computer Package for Graphite Total Cross-Section Calculations

International Nuclear Information System (INIS)

Adib, M.; Fathalla, M.

2008-01-01

An additive formula is given which allows calculating the contribution of the total neut.>neutron transmission through crystalline graphite. The formula takes into account the graphite form of poly or pyrolytic crystals and its parameters. Computer package Graphite has been designed in order to provide the required calculations in the neutron energy range from 0.1 MeV to 10 eV. The package includes three codes: PCG (Polycrystalline Graphite), PG (Pyrolytic Graphite) and HOPG (Highly Oriented Pyrolytic Graphite) for calculating neutron transmission through fine graphite powder (polycrystalline), neutron transmission and removal coefficient of PG crystal in terms of its mosaic spread for neutrons incident along its c-axis and the transmission of neutrons incident on HOPG crystal at different angles, respectively. For comparison of the experimental neutron transmission data with the calculated values, the program takes into consideration the effect of both wavelength and neutron beam divergence in either 2 constant wavelength spread mode (δλ=constant) or constant wavelength resolution mode (δλ/λ=constant). In order to check the validity for application of computer package Graphite in cross-section calculations, a comparison between calculated values with the available experimental data were carried out. An overall agreement is indicated with an accuracy sufficient for determine the neutron transmission characteristics

FFTF railroad tank car Safety Evaluation for Packaging

International Nuclear Information System (INIS)

Carlstrom, R.F.

1995-01-01

This Safety Evaluation for Packaging (SEP) provides evaluations considered necessary to approve transfer of the 8,000 gallon Liquid Waste Tank Car (LWTC) from Fast Flux Test Facility (FFTF) to the 200 Areas. This SEP will demonstrate that the transfer of the LWTC will provide an equivalent degree of safety as would be provided by packages meeting U.S. Department of Transportation (DOT) requirements. This fulfills onsite transportation requirements implemented in the Hazardous Material Packaging and Shipping, WHC-CM-2-14

The effects of irradiation on physicochemical characteristics of PET packaging film

International Nuclear Information System (INIS)

Jeon, D.H.; Lee, K.H.; Park, H.J.

2004-01-01

The effects of γ-irradiation on physicochemical characteristics of biaxially stretched poly(ethylene terephthalate) (PET) packaging film were investigated in the range of 0-200 kGy. The diethylene glycol (DEG) contents in PET chains were increased at the low doses, 5 and 10 kGy, while these values were decreased at high doses, in the range of 30-200 kGy. Molecular weights, intrinsic viscosity and carboxy end group contents decreased slightly after 60 kGy dose. Permeability, thermal properties, color, haze and surface resistivity on γ-irradiation of oriented PET films were not significantly affected. Although some of the effects were measurable, they have no significance with respect to the use of PET for packaging of foods or medical devices to be irradiated

Leveraging Available Data to Support Extension of Transportation Packages Service Life

Energy Technology Data Exchange (ETDEWEB)

Dunn, K.; Abramczyk, G.; Bellamy, S.; Daugherty, W.; Hackney, B.; Hoffman, E.; Skidmore, E.; Stefek, T.

2012-06-12

Data obtained from testing shipping package materials have been leveraged to support extending the service life of select shipping packages while in nuclear materials transportation. Increasingly, nuclear material inventories are being transferred to an interim storage location where they will reside for extended periods of time. Use of a shipping package to store nuclear materials in an interim storage location has become more attractive for a variety of reasons. Shipping packages are robust and have a qualified pedigree for their performance in normal operation and accident conditions within the approved shipment period and storing nuclear material within a shipping package results in reduced operations for the storage facility. However, the shipping package materials of construction must maintain a level of integrity as specified by the safety basis of the storage facility through the duration of the storage period, which is typically well beyond the one year transportation window. Test programs have been established to obtain aging data on materials of construction that are the most sensitive/susceptible to aging in certain shipping package designs. The collective data are being used to support extending the service life of shipping packages in both transportation and storage.

Leveraging Available Data to Support Extension of Transportation Packages Service Life

International Nuclear Information System (INIS)

Dunn, K.; Abramczyk, G.; Bellamy, S.; Daugherty, W.; Hackney, B.; Hoffman, E.; Skidmore, E.; Stefek, T.

2012-01-01

Data obtained from testing shipping package materials have been leveraged to support extending the service life of select shipping packages while in nuclear materials transportation. Increasingly, nuclear material inventories are being transferred to an interim storage location where they will reside for extended periods of time. Use of a shipping package to store nuclear materials in an interim storage location has become more attractive for a variety of reasons. Shipping packages are robust and have a qualified pedigree for their performance in normal operation and accident conditions within the approved shipment period and storing nuclear material within a shipping package results in reduced operations for the storage facility. However, the shipping package materials of construction must maintain a level of integrity as specified by the safety basis of the storage facility through the duration of the storage period, which is typically well beyond the one year transportation window. Test programs have been established to obtain aging data on materials of construction that are the most sensitive/susceptible to aging in certain shipping package designs. The collective data are being used to support extending the service life of shipping packages in both transportation and storage.

Testing Comprehensive Models of Disclosure of Sexual Orientation in HIV-Positive Latino Men Who Have Sex with Men (MSM)

Science.gov (United States)

Lechuga, Julia; Zea, María Cecilia

2012-01-01

Individuals who disclose their sexual orientation are more likely to also disclose their HIV status. Disclosure of HIV-serostatus is associated with better health outcomes. The goal of this study was to build and test comprehensive models of sexual orientation that included 8 theory-informed predictors of disclosure to mothers, fathers, and closest friends in a sample of HIV-positive Latino gay and bisexual men. US acculturation, gender non-conformity to hegemonic masculinity in self-presentation, comfort with sexual orientation, gay community involvement, satisfaction with social support, sexual orientation and gender of the closest friend emerged as significant predictors of disclosure of sexual orientation. PMID:22690708

Development and experimental testing of the new safety-criticality Cristal package

International Nuclear Information System (INIS)

Mattera, Ch.

1998-01-01

This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA93) and the newest accurate codes (APOLLO2, MORET4, TRIPOLI4). The cristal system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route.) To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OCDE working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author)