bluuebunny/crossref_metadata_2025 huggingface dataset:
The “Failure” Of Radical Nationalism and the “Silence” Of Liberal Thought in the Arab World
Authors: Schumann Christoph
Published: December 2008

In the intellectual history of the Arab world, there is a remarkable dearth of literature on liberal thought. In comparison, nationalism and Islamism have attracted much more attention and molded our image of the Middle East. This essay takes a new look at liberal thought by arguing that scholars should not confine themselves to searching for an Arab “liberalism” in the form of intellectuals or organizations that describe themselves as “liberals.” It would be more fruitful to investigate the rise and decline of liberal ideas within the framework of ideologies that seem at first glance not to be liberal. Here, liberal ideas rarely develop by adopting Western liberal traditions but, rather, are the result of political struggles and experiences. Hence, liberal thought emerges from the criticism of authoritarian rule, even though some intellectuals may have advocated authoritarianism at an earlier stage. In the empirical part of this essay, I analyze four autobiographies of former radical nationalist activists from Lebanon, Syria, and Jordan. Although the authors still identify themselves as nationalists, they derived a more liberal outlook by reviewing their concrete political experiences.
Design and Protocol for Monitoring Indoor Air Quality
Authors: Nagda NL , Harper JP
Published: December 2008

Description

Case studies and technical papers describe indoor air investigations in residential and commercial buildings, test protocol, and monitoring techniques. Pollutants such as radon, formaldehyde, and volatile organic compounds are discussed.
Improvement of LWR Pressure Vessel Steel Embrittlement Surveillance: 1984–1986 Progress Report on Belgian Activities in Cooperation with USNRC and Other R&D Programs
Authors: Fabry A , Debrue J , Abderrahim HA , Raedt CD , D'hondt P , Leenders L , Minsart G , Menil R , Leeuw-Gierts GD , Leeuw SD , Pachur D , Kam FBK , Stallmann FW , McGarry ED , Gold R , Roberts JH , McElroy WN
Published: December 2008

As a follow-up to two previous presentations in this series of ASTM-Euratom symposia, this progress report highlights selected new accomplishments pertinent to three specific lines of activities encompassed by the considered cooperative program: 1. Recent progress at the VENUS engineering mock-up is reviewed. This includes final conclusions for the uranium-fuelled core representative of beginning-of-life PWR configurations as well as preliminary results for a new mixed-oxide uranium-plutonium low leakage core. 2. The program of in-vessel and ex-vessel neutron dosimetry performed at the DOEL power plants is outlined, and the trends of theory-versus-experiment comparisons are summarized in light of the overall reactor physics surveillance benchmarking effort. 3. Addressed finally are the development and critical evaluation of metallurgical embrittlement trend curves, an effort born out of the need to understand better the mechanical properties of BR3 reactor beltline materials subsequent to a March 1984 pressure vessel annealing.
U.S. Utility's Experience with Surveillance Dosimetry
Authors: Grant SP
Published: December 2008

Carolina Power & Light Company (CP&L) has completed a series of calculations and measurements for benchmarking the neutron flux in and outside the reactor vessel wall of the H. B. Robinson, Unit No. 2 (HBR2) reactor vessel. Transport calculations have been performed over the height of the core region and correlated with reactor cavity and internal surveillance capsule measurements. Corrections in the calculational approaches were found necessary. An additional improvement on determinations has been provided by ORNL's application of LEPRICON to the HBR2 dosimetry and vessel.

Having found cavity dosimetry measurements superior to those from internal dosimetry capsules at HBR2, CP &L has added the former in the cavities of its BWRs and is contemplating its use at the new Shearon Harris PWR.
Surveillance Neutron Dosimetry at the Hungarian Nuclear Power Plant
Authors: Zsolnay ÉM , Divós F
Published: December 2008

Three reactor blocks of WWER-440 type have been put into operation at the Paks Hungary, nuclear power plant (NPP) from 1983. In the frame of the reactor vessel surveillance program accelerated capsules (LF > 10) have been used. Three surveillance sequences with the first reactor block and two sequences with the second have been evaluated to date.

Surveillance neutron dosimetry analysis and the results of related investigations (ex-vessel dosimetry, additional capsule irradiation) performed in order to improve the life-time assessment of the reactor pressure vessel are presented. Very good agreement between the dpa and fast neutron flux (E > 0.5 MeV) lead factors (LF) was found for the spectrum of interest. The results obtained to date show that the reactor can be safely operated until the end of its designed service life (40 years).
Experimental and Theoretical Neutron Flux Estimations at the Surveillance Chain, at the Pressure Vessel Inner Surface, and in the Cavity of a WER-440 PWR
Authors: Bäars LB , Serén TO , Wasastjerna F
Published: December 2008

Neutron flux measurements and calculations have been performed for VVER 440 reactors at the Loviisa nuclear power plant (NPP) at several locations and for three core configurations.The neutron fluxes within the specimens and the mean axial distributions were measured by using the irradiated steel specimens themselves in the surveillance chains (SC) as dosimeters. The neutron spectra (SC, cavity) were checked and adjusted based on dosimeter sets with Fe(nat), 54Fe, Ni, Ti, Cu, Nb. 238U, Co, and Ag (232Th, 237Np).

The quality of the neutron dose estimates could be significantly improved by using reactor structure materials and especially scraped samples (Fe, Ni, Nb) from the inner and outer surfaces of the reactor pressure vessel (PV) as dosimeters, by applying standardized and relative (PV/SC) methods, which cancel or strongly suppress the influence of systematic (correlated) errors in the cross sections and in other quantities, by developing and using the Nb technique, and by applying a dosimeter rack in the cavity outside the PV.

Accurate flux ratios (lead factors PV/SC) were derived from these measurements.

Nb was separated and purified by chemical methods.

The computed estimates agree well with the measurements even at the distant radial positions at the PV. The calculations were performed using the REPVICS program system (mainly SN method, BUGLE-80 cross-section library). Three-dimensional flux distributions were synthesized from one-dimensional ANISN and two-dimensional DOT 3.5-E calculations ((r,θ) and (r,z)) with additional verification using Monte Carlo calculations.

Together with the material embrittlement measurements of irradiated SC specimens the obtained unique set of measured and calculated flux estimates provide an improved basis for the prediction of pressure vessel embrittlement.

A summary of the neutron flux estimations is presented.
Pressure Vessel Neutron Dosimetry at Three Pressurized Water Reactor Plants Using Niobium Monitors
Authors: Cogburn CO , Hodgson LM , Williams JG
Published: December 2008

Commercially available niobium foil material was irradiated in three PWR vessel cavities concurrently with sets of conventional foil materials. Analysis of the 93Nb(n, n′) 93mNb reaction was compared with reactions from the other foils.

Analysis of the irradiated niobium was carried out by preparing thin deposits from solutions of the dissolved foils. Some difficulty was experienced in preparing uniform, low-mass deposits of sufficient mass accuracy for X-ray spectrometry. However, after several trials satisfactory counting samples were prepared.

Results obtained from the analysis of niobium in the form of thin deposits compared well with neutron transport calculations and with results from the other radiometric monitors.
Neutron Exposure of Gundremmingen-A Pressure Vessel Trepans
Authors: Prillinger G
Published: December 2008

After decommissioning of the nuclear power plant Gundremmingen-A (KRB-A) several trepans have been taken from the pressure vessel for a validation program of sur-veillance test practice. To define neutron exposure after more than ten years' operation a complete analysis of the reactor power time history and of the three-dimensional burnup distributions at the beginning and end of each reactor cycle had to be performed. Neutron exposure parameters such as fast fluence (E > 1.0 and E > 0.1 MeV) and dpa have been calculated using the DOT 4.2 code. The attenuation of neutron exposure within the KRB-A vessel wall is discussed in context with the formulae proposed in Regulaton Guide 1.99, Revisions 1 and 2. To confirm the results of the transport calculations, calculated and measured Mn-54 activities of the trepans have been compared. Additionally dosimetry results from surveillance capsules have been analyzed.
Transport Calculation of the Gamma Field in the Ex-Core Region of the KrŠko Pressure Water Reactor
Authors: Kodeli I , Glumac B , Najžer M
Published: December 2008

Results are presented of the coupled neutron-gamma transport calculation of the KrŠko 632 MWe pressure water reactor (PWR). The DOT 4.2 transport code was used. The variation of gamma flux with fuel burnup was considered, and gamma flux was found to be nearly 50% higher at end of life (EOL) than at beginning of life (BOL) in the regions of interest. For Np and U dosimeters in the surveillance capsules the corrections to the measured neutron exposure due to the gamma reactions were determined. The effect of gamma heating on the temperature of the surveillance capsule and pressure vessel was calculated. The importance of gamma heating in the determination of the heatup and cooldown p-T curves for the plant was evaluated.
Remote Gamma-Ray Mapping: Nuclear Installation Remote Activity Location Device
Authors: Simonet G
Published: December 2008

The mapping of gamma source radiation emission in a nuclear plant is an important safety factor required in a variety of circumstances: 1. Search for radioactive sources. 2. Surveillance of stored radioactive materials. 3. Monitoring of radioactive waste circuits and nuclear fuel reprocessing. 4. Preparation for work and cost assessment in a nuclear plant. 5. Definition of decontamination, dismantling, and decommissioning of a nuclear plant. 6. Initial strategy in the event of incident or accident.

A remote gamma ray mapping process has been developed by SPS/CEA/SACLAY. It uses the "pinhole camera" principle, a precursor of photography. It consists essentially of a radiation-proof box, with a small orifice, placed opposite sensitive emulsions.

An initial conventional photographic-type emulsion photographs the area. A second photographic emulsion shows up the gamma radiations. The superimposition of the two shots gives immediate information concerning the precise location of each source of radiation in the area observed.

To facilitate presentation and to improve the accuracy of the results of radiation level mapping, the films are processed digitally. The processing assigns a color scale to the various levels of observed radiation. Taking into account physical data and standard parameters, it enables estimation of the dose rate.

The device is portable. Its compactness and fully independent nature make it suitable for use anywhere. It can be adapted to a remote automatic handling system, robot, or the like so as to avoid all operator exposure when the local dose rate is too high.
High Absorbed Dose (104 to 108 Gy) Gamma Dosimeters Based on Organic Conductors:Tests Performed in the Irradiation Plant of Reactor Osiris
Authors: Balian P , Ardonceau J , Zuppiroli L , Simonet G
Published: December 2008

Organic conductors are promising candidates for gamma dosimetry in the range of 104 to 108 Gy. Their electrical resistance increases with the absorbed dose, and this variation can be predicted theoretically over a large dose range. One of these conductors called (TMTSF)(DMTCNQ) has been tested in the industrial gamma irradiator of reactor Osiris at a temperature of 50°C. The resolution of this absorbed-dose integrator was shown to be better than 104 Gy for a maximum integrated dose of several 107 Gy. The measurement of this dosimeter in situ during irradiation permits accurate monitoring and control of the industrial irradiation plant for a period of several months.
Intramedullary Rods: Clinical Performance and Related Laboratory Testing
Authors: Harvey JP , Daniels AU , Games RF
Published: December 2008

Description

Intramedullary nails are used to stabilize long bone fractures. STP 1008 contains detailed studies of mechanical tests on these implanted rods, comparisons of different nail designs, failure analysis, and orthopedic surgery techniques.
Measurement of 93mNb for Fast Neutron Metrology
Authors: McCrohon R , Plested ME , Fudge AJ
Published: December 2008

Considerable experience has been gained in the use of a filter-paper source technique for X-ray counting of 93mNb from dissolved niobium dosimeters irradiated in steel irradiation rigs. An alternative method of activity measurement has been investigated using liquid scintillation spectrometry. This more sensitive technique has been assessed and compared with the X-ray counting technique for aspects such as detector calibration, interferences, and overall ease of operation.
Light-Water Reactor Radial Shield Benchmark Studies of the NESTOR Shielding and Dosimetry Improvement Programme (NESDIP)
Authors: Carter MD , Curl IJ , Miller PC , Packwood A
Published: December 2008

The 12/13 configuration of the ORNL PCA was replicated in the ASPIS facility at AEE Winfrith in 1983 in order to utilize the accurately characterized fission plate source of ASPIS. The restricted lateral dimensions of the PCA and REPLICA configurations (68.5by 68.5 cm) are not well suited to solution using one- and two-dimensional codes. Accordingly further studies have been performed in which the lateral extent of the radial shield components has been increased to 183 by 191 cm. The fission plate of the REPLICA studies had a cross section of 40.2 by 63.5 cm. which was identical to the projection of the core source onto the first shield member of the PCA. For the new configuration, measurements have been made using both the fission plate of the REPLICA studies and a fission plate of 56 cm radius.Measurements in all configurations have been performed using activation foils. An analysis of the measurements is presented.
Status of Cf-252 Neutron Spectrum as a Standard
Authors: Mannhart W
Published: December 2008

In reactor metrology, the neutron spectrum of the spontaneous fission of Cf-252 has been used as a standard for many years. Nevertheless, the shape of this spectrum has not yet been unambiguously established. Only recently, the situation changed completely. Based on experimental data, a systematic evaluation of the spectrum was made. The result defines the spectrum with a precision never before attained and comprises a complete uncertainty covariance matrix.

First, a short review of the past status of the definition of this spectrum and the associated problems is given. The reason that recent measurements of the Cf-252 neutron spectrum produced more reliable results is discussed. The experimental data base and the steps of the evaluation procedure are discussed. The result obtained is compared with attempts to describe the Cf-252 neutron spectrum on a theoretical basis. The result of the evaluation is presented, and the progress in defining these data as an internationally accepted standard is reviewed. Finally, the impact of the improved knowledge of the Cf-252 neutron spectrum on past and future reactor dosimetry data is discussed.
Calibration Problems in the Direct Measurement of Radiation Absorbed Dose
Authors: Mason JA , Bainbridge N , Heffer PJH
Published: December 2008

Radiation absorbed dose calorimetry is a direct method for measuring radiation energy deposition in a nuclear reactor environment. It is superior to indirect dosimetry methods, although the validity of the calorimetry technique is crucially dependent on the calibration procedures that are employed.

In this paper calorimeter calibration methods and measurement procedures are critically examined. Calibration problems are considered in the context of three aspects of calorimetry measurements. The first is concerned with the compatibility of the dosimeter with the radiation field. Radiation disequilibrium can lead to significant measurement errors. Errors of instrumentation are then considered, and the problems of temperature stability and electronic noise are emphasized. The bulk of the paper is devoted to an examination of heat transfer aspects of the calibration problem. This area, which has sometimes been ignored, is considered in terms of heat transfer mechanisms and conditions that may lead to significant measurement errors. Calorimeter calibration problems are illustrated with examples from practical calorimetry measurements.
A Contribution to the Theory of Reactor Pressure Vessel Dosimetry
Authors: Shalitin D , Wagschal JJ , Yeivin Y
Published: December 2008

Two topics related to the prediction of neutron fluences (or fluxes) in reactor pressure vessels are discussed. The first is a much simpler derivation of the "adjustment" prescription. The second topic is a proposal of a data rejection technique, based on mutual consistency of the parameter and response data considerations.
Unfolding and Radiation Damage Prediction with and without a priori Information
Authors: Matzke M
Published: December 2008

A brief review is given of the problems connected with the methods of radiation damage prediction by means of reaction rate measurement. The least-squares adjustment with singular covariance matrices of the pre-information group fluence values is discussed. An alternative method of unfolding is proposed. This method is based on the principle of maximum entropy and includes the possibility of assigning confidence intervals at a certain confidence level to integral parameters. The results obtained for the235 U fission spectrum have been compared with least-squares results of the STAY'SL program.
The U.S. Fusion Materials Program: Status and Directions
Authors: Doran DG
Published: December 2008

Fusion materials development is one of four key technical issues identified in the U.S. Magnetic Fusion Program Plan. A long-range program has been formulated recently to provide the scientific and technological basis for assessing the economic and environmental viability of fusion power. An increasingly important element is international participation. The major emphasis is currently on the development of low activation structural materials. The program must also be prepared to meet the near-term needs of the Compact Ignition Tokamak and the proposed International Thermonuclear Experimental Reactor. To do so, the effort on non-structural materials is expected to increase.
Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume)
Authors: Steele LE
Published: December 2008

Description

Topics include: Overview of National Programs; Surveillance Program Results; Research to Support Vessel Integrity Assurance; and Fundamental Damage Mechanisms.
Measurement of Long-Lived Radionuclides in Fusion Materials
Authors: Greenwood LR , Bowers DL
Published: December 2008

Neutron cross section measurements are reported for the production of long-lived radionuclides in fusion reactor materials. Samples were irradiated at 14.5 to 14.8 MeV at the RTNSII facility. Long-lived reaction products were detected using gamma and X-ray spectroscopy, liquid scintillation spectrometry, and accelerator mass spectrometry. Radio-chemical separations were performed for many samples prior to analysis. Results are summarized for reactions leading to 26A1 (720 000 y), 53Mn (3 700 000 y), 55Fe (2.73 y), 63Ni (100y), 59Ni (76 000 y), 91Nb (700 y), and 94Nb (20 300 y).
Helium Production in Mixed-Spectrum Fission Reactors
Authors: Kneff DW , Greenwood LR , Oliver BM , Skowronski RP
Published: December 2008

Total helium production measurements in mixed-spectrum reactors are being used to test the helium production cross-section evaluations used for fusion reactor materials calculations, and to provide dosimetry input for reactor neutron spectrum characterization. Direct comparisons between helium measurements and helium predictions based on crosssection evaluations plus spectral adjustment procedures have pointed out discrepancies in ENDF/B-V cross sections, and have uncovered multiple-step reaction processes that produce enhanced helium in copper and iron at high neutron fluences. Significant variations have been observed in the ratios of helium generation measurements to predictions from reactor to reactor and from experiment to experiment in a given reactor. Based on these observed variations, the helium measurements are now being used as dosimetry input to examine differences in the calculated reactor neutron spectra using spectral adjustment procedures.
Determination of Damage Functions for Polyatomic Materials Irradiated in Research Reactors
Authors: Alberman A , Lesueur D
Published: December 2008

The evaluation of the irradiation parameters of polyatomic materials is extremely important for controlled fusion technology programs. Ceramics, especially for the breeding blanket, are currently the focus of research programs in European research reactors.

The authors present the COMPOSI code for calculating the number of displacements ofj sub-lattice atoms by an i sub-lattice atom, either by direct collision or by an indirect process (intermediate shocked atom). This computation, based on the Lindhard equations, is resolved by an iterative method.

The effective displacement cross sections of j atoms, according to the neutron energy, are determined by convolution with the energy spectra of i-type primaries. The COMPOSI code also serves to calculate the displacements created by the recoil of charged particles directly, such as alpha + triton created by capture on lithium 6 in LiAlO2. The sensitivity of the damage functions is tested in different neutron spectra.
Preparation of Ultra High Purity Niobium for Monitoring Neutron Fluence
Authors: Nishizawa K , Sudo H , Akiyama T , Sugimori M
Published: December 2008

TOSOH has developed a productive and unique producing process for high purity niobium with only several ppm tantalum and less than 1 ppm impurity metals. Our high purity Nb is produced by thermal decomposition of niobiumiodide (Nbl5). which especially includes the heat treatment process for removing Ta in Nb. These high purity metals can be fabricated in the form of sheet, wire, and globules for Nb.
Comparison of Effects of Ventilation, Filtration, and Outdoor Air on Indoor Air at Telephone Office Buildings: A Case Study
Authors: Weschler CJ , Shields HC , Kelty SP , Psota-Kelty LA , Sinclair JD
Published: December 2008

Environmental contaminants can cause failures in telephone switching systems, computers, and other sophisticated electronic equipment. Unfortunately, energy conservation measures frequently increase the indoor concentrations of such contaminants. For almost six years we have been conducting detailed air sampling programs at telephone offices across the United States. This paper outlines the design and procedures used to monitor indoor air quality at these sites. The goal has been to assess the effects of ventilation, filtration, outdoor sources, and indoor sources on the composition of indoor air at representative telephone office buildings. These studies provide direction so that energy conservation measures can be implemented in such a way as to minimize resulting environmentally related failures, and, thereby, the labor and parts needed to correct such failures.
Workshop: Instrumentation and Methods for Measurement of Indoor Air Quality and Related Factors
Authors: Lewis RG , Wallace L
Published: December 2008

Methods and instruments for measuring indoor air quality are described. The major pollutants or classes of pollutants covered are carbon monoxide, nitrogen dioxide, respirable particles, formaldehyde, volatile organic chemicals, pesticides, polynuclear aromatic hydrocarbons, and radon. A brief discussion of a new method for collecting house dust is also included.

In most cases, the methods described have been developed specifically for measuring either indoor air or personal exposure; they are not simply existing methods adapted from ambient (outdoor) use. Generally such existing outdoor air methods are unsuitable on grounds of bulk, noise, excessive air flows, and other problems.

The authors conclude that a complete set of methods allowing both short-term peaks and long-term averages to be measured presently exists for very few, if any, of the major pollutant groups. Thus it will be necessary to have vigorous methods development programs in the public and private sectors if we are to make progress in understanding the magnitude of the indoor air quality problem.
A Tracer Gas Decay System for Monitoring Air Infiltration and Air Movement in Large Single Cell Buildings
Authors: WatersJohn R , Lawrance GV , Jones N
Published: December 2008

A six channel, computer controlled, tracer gas monitoring system has been designed and constructed. It has been used to obtain over 50 sets of tracer decay curves in five buildings, ranging in volume from approximately 4000 to 32 000 m3.In all cases, six air sampling points were distributed evenly, where layout permitted, throughout each building.

The systems design, calibration procedure, and operating strategy are described and discussed. In addition, the method of obtaining infiltration rates and interzonal flows, based on multizone model theory, from the decay curves is outlined and discussed. Five examples of measured interzone flow rates and infiltration rates are given, one for each of the five buildings.
A Multiple Tracer System for Real-Time Measurement of Interzonal Airflows in Residences
Authors: Fortmann RC , Rector HE , Nagda NL
Published: December 2008

Airflows between different parts or zones of a residential dwelling may vary substantially over short time periods due to changes in meteorological conditions. HVAC operation, and occupant activity. The ability to measure interzonal airflows on a "real-time" basis can provide a realistic input for either predicting air pollutant concentrations at various locations within the dwelling or for modeling energy use.

An automated multiple tracer system that employs halocarbons and sulfur hexafluoride (SF6) as the tracers was tested in a bilevel, single-family research house. The system employs a constant injection system for halocarbon release in two zones. An automated system samples each zone in the house four times each hour. Halocarbons and SF6 are quantitated with a gas Chromatograph with an electron capture detector.

Airflow rates between the upstairs and downstairs of the research house ranged from 33 to 610 m3/h. The magnitude of the airflow rate was related to the percent of time that the furnace fan operated. Measurements of average interzonal airflow rates with PFTs were substantially lower than measurements with the halocarbon tracer system. Whole house air exchange rates calculated from the PFT and SF6 decay measurements were nearly identical. For periods with concurrent halocarbon measurements and SF6 decay measurements, whole house air exchange rates calculated with the halocarbons were lower than those calculated with the SF6, decay method.
Fracture Mechanics: Perspectives and Directions (Twentieth Symposium)
Authors: Wei RP , Gangloff RP
Published: December 2008

Description

Provides overviews of the major developments in fracture mechanics and associated applications over the past 20 years, and highlights directions for future developments and applications. 6 major sections include:

• Analytical Fracture Mechanics

• Nonlinear and Time Dependent Fracture Mechanics

• Microstructure and Micro mechanical Modeling

• Fatigue Crack Propagation

• Environmentally Assisted Cracking

• Fracture Mechanics of Nonmetals and New Frontiers.
Turbine Oil Monitoring
Authors: Young WC , Roberton RS
Published: December 2008

Description

Six papers review the behavior of petroleum based and phosphate ester type lubricants in turbine service, particularly in power generation. Emphasizes monitoring practices and the control of lubricant quality to protect equipment and ensure long oil service life.
Zirconium in the Nuclear Industry: Eighth International Symposium
Authors: Eucken CM , Van Swam LFP
Published: December 2008

Description

Topics include:

• Behavior of Pressure Tubes

• Corrosion

• Nodular Corrosion

• Basic Metallurgy

• Mechanical Behavior, Stress Corrosion, and Fatigue

• Creep and Growth

Corrosion behavior is given special emphasis.
Nondestructive Testing of Pavements and Backcalculation of Moduli
Authors: Baladi GY , Bush AJ
Published: December 2008

Description

Topics include:

• Backcalculation of Layer Moduli State of the Art

• Nondestructive Testing Deflection, Radar, and Surface Wave Testing

• Backcalculations of Layer Moduli from Deflection Data

• Procedures for Analysis of Nondestructive Testing Data.
Testing of Intramedullary Nails Using Physiological Loading
Authors: Bear LL , Hamilton JJ , Sukere AA , Lynch G , Davidson JA
Published: December 2008

The increased interest in using intramedullary nails for fixation of long bone fractures has created a need for more in-depth laboratory testing of these devices. Until recently, most testing has addressed bending strength, bending rigidity, and torsional strength as separate properties. In actuality, bending and torsion are applied simultaneously to an implanted intramedullary nail. This study presents a technique for mimicking physiological loading incurred by a intramedullary nail during walking gait and the results of tests performed using this method.
Chemical Protective Clothing Performance in Chemical Emergency Response
Authors: Stull JO , Perkins JL
Published: December 2008

Description

Provides a review of the problems, new technologies, and uses of protective clothing related specifically to chemical emergency response. 21 papers on the following topics:

• Overview/Chemical Protective Clothing

• Chemical Protective Clothing Suit Testing

• Chemical Permeation Research

• Special Applications in Emergency Response

• Polices, Procedures, and Philosophies Affecting Emergency Response.
Biomechanical Variables Affecting Stability and Stresses in the Fractured Femur During Intramedullary Nailing
Authors: Sherman MC , Tencer AF , Johnson KD
Published: December 2008

Closed intramedullary nailing is an accepted method of treatment for femoral shaft fractures. Technical complications of this procedure include fracture instability, which may result in nail migration and malrotation, and femoral bursting during nail insertion. These complications were investigated in terms of geometric and mechanical parameters of the bone-implant system. Mechanical test results indicate that nails of the same nominal size from different manufacturers possess more than a twofold difference in flexural rigidity and a threefold difference in torsional modulus. These differences are due to variations on the cross-sectional shape and wall thickness. Measurements in insertion force and hoop stress in cadaver femora were significantly different for most of the nails tested due to differences in mechanical and geometric properties. Insertion forces in the distal fracture component were consistently lower than those in the proximal fracture component and decreased linearly with component length. Increasing the reamed diameter in the distal component 1 mm over the nail size decreased the insertion forces significantly. The most significant variable affecting femoral bursting was found to be the placement of the starting hole. Anterior offset from the neutral axis of the canal by more than 6.0 mm consistently resulted in excessive hoop stresses and femoral bursting. Case reports are presented to illustrate these biomechanical principles clinically.
Intramedullary Nailing for Treatment of Diaphysial Nonunions of the Femur
Authors: Gualtieri G , Gualtieri I , Gagliardi S , Hendriks M
Published: December 2008

Küntscher nailing was performed on 55 noninfected pseudoarthroses of the femur. Of these, 16 had previously been submitted to conservative treatment while 39 had undergone surgery. Closed intramedullary nailing was used in 24 cases, a half-closed technique in 23 cases, and open intramedullary nailing in 8 cases. The union rate was 100%. The average time from surgery to radiographic consolidation was three months. Complications included two infections.
Ender Nail Fixation in Fractures of the Proximal Femur
Authors: Schaumburg EW , Jeffries GE , Weissfeld SC
Published: December 2008

Between 1980 and 1984, a study to assess the usefulness of Ender nail fixation in the treatment of fractures of the proximal femur was conducted at the University of Tennessee Memorial Hospital. Data were recorded regarding shortening, malunion, knee pain, loss of reduction, nonunion, and pin problems. Assessment of operative time, blood loss, length of hospital stay, auxiliary fixation, and other parameters was made. This study, the first to utilize data from a large (225 cases), consecutive series of flexible nailings done by a small number of surgeons (the three authors), clearly demonstrated the advantages of Ender nailing in peritrochanteric fractures: fracture stability, decreased operative trauma, very low infection rate, and very low nonunion rate. The complication rate decreased significantly as the surgeons gained more expertise, emphasizing the importance of precision and experience in placing the Ender nails.
Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel
Authors: Taboada A , Randall PN , Serpan CZ
Published: December 2008

This paper is in several parts: the first presents an overview of research activities sponsored by the U.S. Nuclear Regulatory Commission (NRC) on neutron irradiation embrittlement of pressure vessel steels. A series of irradiation experiments have evaluated effects of chemistry on the fracture toughness properties of submerged arc welds representing current nuclear vessel fabrication practices and provide data to validate ASME Code practices. A correlation between Charpy energy and fracture toughness is being studied as is a program on radiation sensitivity to define the role of dose rate and to study the effects of postirradiation heat treatment (annealing). The development of a comprehensive data base for radiation embrittlement data has been initiated and is being applied in a correlation of reactor surveillance data with test reactor data. A comprehensive dosimetry effort has produced validated standard methods for calculating and measuring neutron flux and fluence parameters and the correlation of these parameters to embrittlement of pressure vessel steels in light water reactors. Our knowledge of radiation damage to reactor vessels has also been greatly increased in recent years by the accumulation of power reactor surveillance data and by better models and better analysis techniques applied to that data. Unfortunately, the results show that radiation damage is often more than previously predicted, using Revision 1 of NRC Regulatory Guide 1.99, and will result in more restrictive pressure temperature limits. The second part of this paper describes some of the system and operational impacts produced, which in turn lead to challenges to long-established safety margins. Finally, a number of outstanding issues which require further research are discussed, many of which will require better understanding of radiation damage mechanisms.
Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels
Authors: Davies LM , Squires RL
Published: December 2008

This paper describes recent work on irradiation embrittlement of pressurized water reactor (PWR) pressure vessel (PV) steels in the United Kingdom (U.K.). It also describes current relevant developments, namely, the Sizewell ‘B’ PWR, the recent Light Water Reactor Study Group (LWRSG) report on PWR PV integrity, and the presentation of a design for a 300-MW(e) PWR by Rolls-Royce.

The paper goes on to describe the U.K. involvement in two major international programs on irradiation embrittlement, the International Atomic Energy Agency (IAEA), Coordinated Research Programme and the Nuclear Regulatory Commission (NRC) Surveillance Dosimetry Improvement Programme, and stresses the significance of including standard, known-response materials in irradiation programs. U.K. involvement in other international programs is also described.

U.K. national program results on strain aging, dynamic strain aging, background underlying small angle nuclear scattering (SANS), and microstructural and positron annihilation studies are reported. The role of phosphorus in the neutron irradiation embrittlement of lowcopper steels is described. Recent results from modelling studies are noted and the results from a recent irradiation program mentioned.
Characteristics of the IAEA Correlation Monitor Material for Surveillance Programs
Authors: Wallin K , Valo MJ , Rintamaa R , Torronen K , Ahlstrand R
Published: December 2008

Within the International Atomic Energy Commission (IAEA) coordinated program on the optimizing of reactor pressure vessel surveillance programs and their analysis, Phase 3, a specially tailored "radiation sensitive" correlation monitor material has been fabricated. This material will serve as a reference to the IAEA program for future vessel surveillance programs throughout the world.

An extensive evaluation of the correlation monitor material in the as-received condition has been carried out in Finland and the results are presented here. The mechanical properties measured at different temperatures include Charpy V-notch and instrumented precracked Charpy data, and elastic-plastic fracture toughness (J and T). The specimen size and geometry have been varied in the tests. Correlation between different fracture properties are evaluated and discussed.
Irradiation Programs to Establish the Safety Margins of German Licensing Rules Related to RPV Steel Embrittlement
Authors: Ahlf J , Bellmann D , Schmitt FJ
Published: December 2008

Under German licensing rules, irradiation-induced embrittlement of a reactor pressure vessel (RPV) in the core belt region is taken into account basically by determining the shift of the 41-J transition temperature of the Charpy impact energy versus temperature curve and then adjusting either the exclusion line of the modified Porse diagram, or the KIR curve, by this 41-J shift.

The accuracy limits of T 41 Jand Δ T 41 J determination are discussed and quantified. The transition temperature concept is shown to be conservative in the validity range of the respec-tive licensing rules because of the uncertainties in Δ T 41 J determination.

Investigations with respect to irradiation effects on fracture toughness deserve high priority in current programs. Results from a A 533-B 2 steel (HSST03) are presented, and the shift of the KIC curve is evaluated for two fluence levels.

Experiments related to the question of whether neutron flux density has an influence on embrittlement are briefly reported.
Fatigue of Composite Materials—Damage Model and Life Prediction
Authors: Hwang W , Han KS
Published: December 2008

Fatigue life prediction on composite materials is studied analytically using degradation and damage models, resultant strains, and fatigue modulus. Definition of fatigue modulus, new damage models using fatigue modulus and resultant strain, and prediction of fatigue life of composite materials using degradation and damage models are discussed. This approach can predict accurately the multi-stress level fatigue life as well as single-stress level fatigue life of composite materials. Fatigue life is predicted by the following procedures: (1) establish the fatigue modulus degradation model, (2) find fatigue life equation as a function of fatigue modulus, (3) calculate the fatigue life using strain failure criterion. Degradation models for composite damage are generalized; the three-parameter degradation model is found most suitable to predicting fatigue life of composites. Also the predicted two-stress level fatigue life using the proposed cumulative damage models is reasonably close to the experimental data.
Micromechanics of Compression Failures in Open Hole Composite Laminates
Authors: Guynn EG , Bradley WL , Elber W
Published: December 2008

Compression failures in laminates with holes are often preceded by the development of a damage zone which grows with increasing compressive load. This damage zone is due to local fiber buckling and/or shear crippling. The local softening in the damage zone has been modeled using a Dugdale-type approach. This paper compares this analytical model to the actual development of the damage zone size as a function of load. Comparison of the model predictions to the experimental observations indicates that the Dugdale model does not accurately predict the load-damage zone size relationship in open hole composite specimens loaded in compression. Hole size and resin ductility were the two primary variables used in this investigation. Three hole diameters were used in specimens 2.54 cm (1 in.) wide containing 5.08 cm (2 in.) gauge length. Matrix ductility and stiffness were also varied by using matrices of polyetheretherketone (PEEK) and Hexcel F155. Very brittle resins were not studied because the damage zone development that precedes unstable damage extension is too small to record. Several coupon tests were interrupted prior to catastrophic damage growth to allow for a more careful examination of the fiber shear crippling and/or buckling. These observations were accomplished using nondestructive examination (C-scan and X-ray) and scanning electron microscopy. A preliminary sectioning study was conducted through the thickness of the damage zone of an AS4/PEEK specimen; each section was observed in the scanning electron microscope.
Free-Edge Delamination Characteristics in S2/CE9000 Glass/Epoxy Laminates Under Static and Fatigue Loads
Authors: Chan WS , Wang ASD
Published: December 2008

The static and fatigue characteristics of delamination growth in the S2/CE9000 glass/epoxy laminates under cyclic loading and various environmental conditions were investigated. From the resulting data, a growth model with α = 3 × 10−5 and β = 5 was established. In the many cases reviewed in this paper, the values of α and β remain unchanged until there is a change in temperature, a change in moisture content, or a change in the R ratio.
Future Fuels for General Aviation
Authors: Strauss KH , Gonzalez C
Published: December 2008

Description

Information and predictions on future general aviation fuel requirements and availability. 11 papers are presented in sections on:

• Motor Gasoline Use in Aircraft

• Alternative Fuel Use in Aircraft

• Future Fuel Requirements
Science and Technology of Glazing Systems
Authors: Parise CJ
Published: December 2008

Description

10 peer-reviewed papers on structural sealant glazing, preformed tape sealant glazing, laboratory sealant testing, and insulating glass. For architects; curtain wall consultants and designers; building owners; sealants, gasket and accessory manufacturers; testing laboratories; inspection and quality control agencies; university instructors.
Thermal Envelope Case History for a School District
Authors: Coyle WT
Published: December 2008

This paper discusses the actual selection and application of thermal envelope energy conservation measures for the 102 223 m2 (1 100 000 ft2) of Weld County School District No. 6 buildings, which are located in the cities of Evans and Greeley, Colorado. Since 1976, the district has followed an intensive energy conservation program in which mechanical, electrical, and structural retrofits have been prioritized on a cost/benefit basis, and measures have been financed by school funds or by 50–50 grants from the Institutional Grants Program of the U.S. Department of Energy. The thermal envelope measures discussed include replacement windows, storm windows, vestibules, overlay of thermal insulation on glass block, attic insulation, and rigid roof insulation. These measures, along with the usual retrofitting of controls for mechanical and electrical systems, have resulted in a cost savings of $305 342 for the district in 1983, in comparison with 1976. Finally, mention is made in this paper of the systemizing of the district's total energy conservation efforts in order to recognize the need for motivational measures aimed at the building occupants. This effort complements the ongoing thermal envelope and hardware retrofit measures.
Foamed-in-Place Polyurethane Foam Insulation System Design and Application for Low-Temperature Storage Tanks
Authors: Duff MP
Published: December 2008

Energy savings from reduced fuel consumption due to thermal insulation systems are frequently compared with the capital investment cost of the insulation system. Energy-saving thermal insulation programs for large storage tanks are not always implemented because the rate of return on the insulation investment may not be as attractive as the return on other investments competing for the same capital equipment expenditure dollars.

Seeking to develop a low-cost, thermally efficient, long-lived thermal insulation system that could increase energy savings and reduce first costs, the author selected foamed-in-place polyurethane foam as the system's basic insulation material. Insulation system details were selected to exploit the advantages and to overcome the disadvantages of polyurethane foam as a field-applied insulation material. A unique application method and application machinery were developed, specially suited to application to large, flat-bottomed, low-temperature storage tanks. The important features of the insulation system, Chicago Bridge and Iron Company's horizontal foamed-in-place (HFIP) insulation system, and the special application method are discussed in detail in the paper.
Design Heat Loss Factors for Basement and Slab Floors
Authors: Kusuda T , Bean JW
Published: December 2008

The heat loss factors for selected types of earth contact surfaces, such as basement walls and floors and slab-on-grade floors, are presented to supplement data in the ASHRAE Handbook of Fundamentals for estimating the building design heat loss. The perimeter heat loss factors are derived from the procedure developed by Mitalas and from monthly normal temperature cycles of many localities in the United States. Except for those for cities in California, the heat loss factors are found to be a relatively well-defined function of degree-days and remain constant for degree-days beyond 3000 (engineering units). The heat loss factors show that the most effective way to reduce the earth contact surface heat loss is to insulate the inside corners of wall/floor joints. The insulation installed below the floor slab is found to be the least effective as long as the wall foundation is left uninsulated.