TELEsarPHONE: Mutual Telexistence Master-Slave Communication System Based on Retroreflective Projection Technology

Science.gov (United States)

Tachi, Susumu; Kawakami, Naoki; Nii, Hideaki; Watanabe, Kouichi; Minamizawa, Kouta

TELEsarPHONE is a conceptual prototype of a mutual telexistence system, designed for face-to-face telecommunication via robots. Because of the development of telexistence technology, we can acquire a feeling that we are present in several actual remote places using remote robots as our surrogates and can work and act freely there. However, people in the place where someone telexists using a robot see only the robot, and they cannot feel the existence of the telexisting person. Mutual telexistence aims to solve this problem so that the existence of a telexisting person (visitor) is apparent to the people in the remote environment by providing mutual sensations of presence. On the basis of the concept of mutual telexistence, we have designed and developed a prototype of a telexistence master-slave system for remote communication by applying retroreflective projection technology. In the TELEsarPHONE system, the face and chest of the slave robot TELESAR II are covered by retroreflective material. To provide the feeling of existence, the real-time image of the visitor is projected onto the robot so that people can see the visitor in real time.

Optimized phase mask to realize retro-reflection reduction for optical systems

Science.gov (United States)

He, Sifeng; Gong, Mali

2017-10-01

Aiming at the threats to the active laser detection systems of electro-optical devices due to the cat-eye effect, a novel solution is put forward to realize retro-reflection reduction in this paper. According to the demands of both cat-eye effect reduction and the image quality maintenance of electro-optical devices, a symmetric phase mask is achieved from a stationary phase method and a fast Fourier transform algorithm. Then, based on a comparison of peak normalized cross-correlation (PNCC) between the different defocus parameters, the optimal imaging position can be obtained. After modification with the designed phase mask, the cat-eye effect peak intensity can be reduced by two orders of magnitude while maintaining good image quality and high modulation transfer function (MTF). Furthermore, a practical design example is introduced to demonstrate the feasibility of our proposed approach.

Aperture area measurement facility

Data.gov (United States)

Federal Laboratory Consortium — NIST has established an absolute aperture area measurement facility for circular and near-circular apertures use in radiometric instruments. The facility consists of...

Facilities projects performance measurement system

International Nuclear Information System (INIS)

Erben, J.F.

1979-01-01

The two DOE-owned facilities at Hanford, the Fuels and Materials Examination Facility (FMEF), and the Fusion Materials Irradiation Test Facility (FMIT), are described. The performance measurement systems used at these two facilities are next described

LLL transient-electromagnetics-measurement facility

International Nuclear Information System (INIS)

Deadrick, F.J.; Miller, E.K.; Hudson, H.G.

1975-01-01

The operation and hardware of the Lawrence Livermore Laboratory's transient-electromagnetics (EM)-measurement facility are described. The transient-EM range is useful for determining the time-domain transient responses of structures to incident EM pulses. To illustrate the accuracy and utility of the EM-measurement facility, actual experimental measurements are compared to numerically computed values

76 FR 46213 - National Standards for Traffic Control Devices; the Manual on Uniform Traffic Control Devices for...

Science.gov (United States)

2011-08-02

... Transportation, Dockets Management Facility, 1200 New Jersey Avenue, SE., Washington, DC 20590, or submit... retroreflectivity of longitudinal pavement markings. The deadline for comments to that docket has passed and the... the proposed revisions regarding maintaining minimum retroreflectivity of longitudinal pavement...

Stockbridge Antenna Measurement and Research Facility

Data.gov (United States)

Federal Laboratory Consortium — The Stockbridge Antenna Measurement Facility is located 23 miles southwest of AFRL¹s Rome Research Site. This unique measurement facility is designed to evaluate the...

International Mapping of Antenna-Measurement Facilities

DEFF Research Database (Denmark)

Boccia, Luigi; Breinbjerg, Olav; Di Massa, Giuseppe

2006-01-01

This paper presents a comprehensive international mapping of antenna-measurement facilities. This initiative, conducted within the framework of the Antenna Centre of Excellence (ACE) of the European Union, is oriented toward all institutions having research, development, or operational activities...... measurements, in particular from the wireless communication industry, to identify and contact antenna-measurement facilities. The first phase of the mapping showed a significant and encouraging reaction to this initiative, with more than 50 European facilities currently registered. The next phase aims...

Electronic Warfare Signature Measurement Facility

Data.gov (United States)

Federal Laboratory Consortium — The Electronic Warfare Signature Measurement Facility contains specialized mobile spectral, radiometric, and imaging measurement systems to characterize ultraviolet,...

Algorithm for the Evaluation of Imperfections in Auto Bodywork Using Profiles from a Retroreflective Image

Directory of Open Access Journals (Sweden)

Ramon Barber

2014-02-01

Full Text Available Nowadays the automobile industry is becoming more and more demanding as far as quality is concerned. Within the wide variety of processes in which this quality must be ensured, those regarding the squeezing of the auto bodywork are especially important due to the fact that the quality of the resulting product is tested manually by experts, leading to inaccuracies of all types. In this paper, an algorithm is proposed for the automated evaluation of the imperfections in the sheets of the bodywork after the squeezing process. The algorithm processes the profile signals from a retroreflective image and characterizes an imperfection. It is based on a convergence criterion that follows the line of the maximum gradient of the imperfection and gives its geometrical characteristics as a result: maximum gradient, length, width, and area.

Fabrication of corner cube array retro-reflective structure with DLP-based 3D printing technology

Science.gov (United States)

Riahi, Mohammadreza

2016-06-01

In this article, the fabrication of a corner cube array retro-reflective structure is presented by using DLP-based 3D printing technology. In this additive manufacturing technology a pattern of a cube corner array is designed in a computer and sliced with specific software. The image of each slice is then projected from the bottom side of a reservoir, containing UV cure resin, utilizing a DLP video projector. The projected area is cured and attached to a base plate. This process is repeated until the entire part is made. The best orientation of the printing process and the effect of layer thicknesses on the surface finish of the cube has been investigated. The thermal reflow surface finishing and replication with soft molding has also been presented in this article.

Aircraft Horizontal Thrust Measurement Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility is designed to support the DoD mission by providing unique air vehicle installed engine performance (thrust output) measurements. This system consists...

The magnet measurement facility for the Advanced Photon Source

International Nuclear Information System (INIS)

Kim, S.H.; Doose, C.; Hogrefe, R.; Kim, K.; Merl, R.

1993-01-01

A magnet measurement facility has been developed to measure the prototype and production magnets for the Advance Photon Source. The measurement facility is semi-automatic in measurement control and data analysis. One dipole system and three rotating coil measurement systems for quadrupole and sextupole magnets and corresponding probe coils are described

Measurement of Outflow Facility Using iPerfusion.

Directory of Open Access Journals (Sweden)

Joseph M Sherwood

Full Text Available Elevated intraocular pressure (IOP is the predominant risk factor for glaucoma, and reducing IOP is the only successful strategy to prevent further glaucomatous vision loss. IOP is determined by the balance between the rates of aqueous humour secretion and outflow, and a pathological reduction in the hydraulic conductance of outflow, known as outflow facility, is responsible for IOP elevation in glaucoma. Mouse models are often used to investigate the mechanisms controlling outflow facility, but the diminutive size of the mouse eye makes measurement of outflow technically challenging. In this study, we present a new approach to measure and analyse outflow facility using iPerfusion™, which incorporates an actuated pressure reservoir, thermal flow sensor, differential pressure measurement and an automated computerised interface. In enucleated eyes from C57BL/6J mice, the flow-pressure relationship is highly non-linear and is well represented by an empirical power law model that describes the pressure dependence of outflow facility. At zero pressure, the measured flow is indistinguishable from zero, confirming the absence of any significant pressure independent flow in enucleated eyes. Comparison with the commonly used 2-parameter linear outflow model reveals that inappropriate application of a linear fit to a non-linear flow-pressure relationship introduces considerable errors in the estimation of outflow facility and leads to the false impression of pressure-independent outflow. Data from a population of enucleated eyes from C57BL/6J mice show that outflow facility is best described by a lognormal distribution, with 6-fold variability between individuals, but with relatively tight correlation of facility between fellow eyes. iPerfusion represents a platform technology to accurately and robustly characterise the flow-pressure relationship in enucleated mouse eyes for the purpose of glaucoma research and with minor modifications, may be applied

Direct shaft torque measurements in a transient turbine facility

International Nuclear Information System (INIS)

Beard, Paul F; Povey, Thomas

2011-01-01

This paper describes the development and implementation of a shaft torque measurement system for the Oxford Turbine Research Facility (formerly the Turbine Test Facility (TTF) at QinetiQ, Farnborough), or OTRF. As part of the recent EU TATEF II programme, the facility was upgraded to allow turbine efficiency measurements to be performed. A shaft torque measurement system was developed as part of this upgrade. The system is unique in that, to the authors' knowledge, it provided the first direct measurement of shaft torque in a transient turbine facility although the system has wider applicability to rotating test facilities in which power measurement is a requirement. The adopted approach removes the requirement to quantify bearing friction, which can be difficult to accurately calibrate under representative operating conditions. The OTRF is a short duration (approximately 0.4 s run time) isentropic light-piston facility capable of matching all of the non-dimensional parameters important for aerodynamic and heat studies, namely Mach number, Reynolds number, non-dimensional speed, stage pressure ratio and gas-to-wall temperature ratio. The single-stage MT1 turbine used for this study is a highly loaded unshrouded design, and as such is relevant to modern military, or future civil aero-engine design. Shaft torque was measured directly using a custom-built strain gauge-based torque measurement system in the rotating frame of reference. This paper describes the development of this measurement system. The system was calibrated, including the effects of temperature, to a traceable primary standard using a purpose-built facility. The bias and precision uncertainties of the measured torque were ±0.117% and ±0.183%, respectively. To accurately determine the shaft torque developed by a turbine in the OTRF, small corrections due to inertial torque (associated with changes in the rotational speed) and aerodynamic drag (windage) are required. The methods for performing these

Experimental measurements at the MASURCA facility

International Nuclear Information System (INIS)

Assal, W.; Bosq, J.C.; Mellier, F.

2012-01-01

Dedicated to the neutronics studies of fast and semi-fast reactor lattices, MASURCA (meaning 'mock-up facility for fast breeder reactor studies at Cadarache') is an airflow cooled fast reactor operating at a maximum power of 5 kW playing an important role in the CEA research activities. At this facility, a lot of neutron integral experimental programs were undertaken. The purpose of this poster is to show a panorama of the facility from this experimental measurement point of view. A hint at the forthcoming refurbishment will be included. These programs include various experimental measurements (reactivity, distributions of fluxes, reaction rates), performed essentially with fission chambers, in accordance with different methods (noise methods, radial or axial traverses, rod drops) and involving several devices systems (monitors, fission chambers, amplifiers, power supplies, data acquisition systems). For this purpose are implemented electronics modules to shape the signals sent from the detectors in various mode (fluctuation, pulse, current). All the electric and electronic devices needed for these measurements and the relating wiring will be fully explained through comprehensive layouts. Data acquired during counting performed at the time of startup phase or rod drops are analyzed by the mean of a Neutronic Measurement Treatment (TMN in French) programmed on the basis of the MATLAB software. This toolbox gives the opportunity of data files management, reactivity valuation from neutronics measurements and transient or divergence simulation at zero power. Particular TMN using at MASURCA will be presented. (authors)

Experimental Measurements at the MASURCA Facility

Science.gov (United States)

Assal, W.; Bosq, J. C.; Mellier, F.

2012-12-01

Dedicated to the neutronics studies of fast and semi-fast reactor lattices, MASURCA (meaning “mock-up facility for fast breeder reactor studies at CADARACHE”) is an airflow cooled fast reactor operating at a maximum power of 5 kW playing an important role in the CEA research activities. At this facility, a lot of neutron integral experimental programs were undertaken. The purpose of this poster is to show a panorama of the facility from this experimental measurement point of view. A hint at the forthcoming refurbishment will be included. These programs include various experimental measurements (reactivity, distributions of fluxes, reaction rates), performed essentially with fission chambers, in accordance with different methods (noise methods, radial or axial traverses, rod drops) and involving several devices systems (monitors, fission chambers, amplifiers, power supplies, data acquisition systems ...). For this purpose are implemented electronics modules to shape the signals sent from the detectors in various mode (fluctuation, pulse, current). All the electric and electronic devices needed for these measurements and the relating wiring will be fully explained through comprehensive layouts. Data acquired during counting performed at the time of startup phase or rod drops are analyzed by the mean of a Neutronic Measurement Treatment (TMN in French) programmed on the basis of the MATLAB software. This toolbox gives the opportunity of data files management, reactivity valuation from neutronics measurements and transient or divergence simulation at zero power. Particular TMN using at MASURCA will be presented.

Experimental measurements at the Masurca facility

International Nuclear Information System (INIS)

AssaI, W.; Bosq, J. C.; Mellier, F.

2009-01-01

Dedicated to the neutronics studies of fast and semi-fast reactor lattices, Masurca (meaning 'mock-up facility for fast breeder reactor studies at Cadarache') is an airflow cooled fast reactor operating at a maximum power of 5 kW playing an important role in the CEA research activities. At this facility, a lot of neutron integral experimental programs were undertaken. The purpose of this poster is to show a panorama of the facility from this experimental measurement point of view. A hint at the forthcoming refurbishment will be included. These programs include various experimental measurements (reactivity, distributions of fluxes, reaction rates), performed essentially with fission chambers, in accordance with different methods (noise methods, radial or axial traverses, rod drops) and involving several devices systems (monitors, fission chambers, amplifiers, power supplies, data acquisition systems...). For this purpose electronics modules are implemented to shape the signals sent from the detectors in various mode (fluctuation, pulse, current). All the electrical and electronic devices needed for these measurements and the relating wiring will be fully explained through comprehensive layouts. Data acquired during counting performed at the time of startup phase or rod drops are analyzed by the mean of a Neutronic Measurement Treatment (TMN in French) programmed on the basis of the MATLAB software. This toolbox gives the opportunity of data files management, reactivity valuation from neutronics measurements and transient or divergence simulation at zero power. Particular TMN using at Masurca will be presented. (authors)

Biosecurity measures in 48 isolation facilities managing highly infectious diseases.

Science.gov (United States)

Puro, Vincenzo; Fusco, Francesco M; Schilling, Stefan; Thomson, Gail; De Iaco, Giuseppina; Brouqui, Philippe; Maltezou, Helena C; Bannister, Barbara; Gottschalk, René; Brodt, Hans-Rheinhard; Ippolito, Giuseppe

2012-06-01

Biosecurity measures are traditionally applied to laboratories, but they may also be usefully applied in highly specialized clinical settings, such as the isolation facilities for the management of patients with highly infectious diseases (eg, viral hemorrhagic fevers, SARS, smallpox, potentially severe pandemic flu, and MDR- and XDR-tuberculosis). In 2009 the European Network for Highly Infectious Diseases conducted a survey in 48 isolation facilities in 16 European countries to determine biosecurity measures for access control to the facility. Security personnel are present in 39 facilities (81%). In 35 facilities (73%), entrance to the isolation area is restricted; control methods include electronic keys, a PIN system, closed-circuit TV, and guards at the doors. In 25 facilities (52%), identification and registration of all staff entering and exiting the isolation area are required. Access control is used in most surveyed centers, but specific lacks exist in some facilities. Further data are needed to assess other biosecurity aspects, such as the security measures during the transportation of potentially contaminated materials and measures to address the risk of an "insider attack."

Description and Results: Antenna Measurement Facility Comparisons [Measurements Corner

DEFF Research Database (Denmark)

Alberica Saporetti, Maria; Foged, Lars; Sierra Castañer, Manuel

2017-01-01

In recent years, formalized facility comparison activities have become important for the documentation and validation of laboratory proficiency and competence and mandatory for achieving accreditation such as that of the International Organization for Standardization (ISO) 17025 or similar...... for Antennas (VISTA) IC1102, including still ongoing campaigns [3]-[5]. Results of these activities have led to improvements in antenna measurement procedures and protocols in facilities and standards [6], [7]. Due to the direct benefits available to the participants, the activities have been very successful...

Temperature Measurements in the Magnetic Measurement Facility

Energy Technology Data Exchange (ETDEWEB)

Wolf, Zachary

2010-12-13

Several key LCLS undulator parameter values depend strongly on temperature primarily because of the permanent magnet material the undulators are constructed with. The undulators will be tuned to have specific parameter values in the Magnetic Measurement Facility (MMF). Consequently, it is necessary for the temperature of the MMF to remain fairly constant. Requirements on undulator temperature have been established. When in use, the undulator temperature will be in the range 20.0 {+-} 0.2 C. In the MMF, the undulator tuning will be done at 20.0 {+-} 0.1 C. For special studies, the MMF temperature set point can be changed to a value between 18 C and 23 C with stability of {+-}0.1 C. In order to ensure that the MMF temperature requirements are met, the MMF must have a system to measure temperatures. The accuracy of the MMF temperature measurement system must be better than the {+-}0.1 C undulator tuning temperature tolerance, and is taken to be {+-}0.01 C. The temperature measurement system for the MMF is under construction. It is similar to a prototype system we built two years ago in the Sector 10 alignment lab at SLAC. At that time, our goal was to measure the lab temperature to {+-}0.1 C. The system has worked well for two years and has maintained its accuracy. For the MMF system, we propose better sensors and a more extensive calibration program to achieve the factor of 10 increase in accuracy. In this note we describe the measurement system under construction. We motivate our choice of system components and give an overview of the system. Most of the software for the system has been written and will be discussed. We discuss error sources in temperature measurements and show how these errors have been dealt with. The calibration system is described in detail. All the LCLS undulators must be tuned in the Magnetic Measurement Facility at the same temperature to within {+-}0.1 C. In order to ensure this, we are building a system to measure the temperature of the

A comparison of goniophotometric measurement facilities

DEFF Research Database (Denmark)

Thorseth, Anders; Lindén, Johannes; Dam-Hansen, Carsten

2016-01-01

In this paper, we present the preliminary results of a comparison between widely different goniophotometric and goniospectroradiometric measurement facilities. The objective of the comparison is to increase consistency and clarify the capabilities among Danish test laboratories. The study will seek...... to find the degree of equivalence between the various facilities and methods. The collected data is compared by using a three-way variation of principal component analysis, which is well suited for modelling large sets of correlated data. This method drastically decreases the number of numerical values...

New luminescence measurement facilities in retrospective dosimetry

DEFF Research Database (Denmark)

Lapp, Torben; Jain, Mayank; Thomsen, Kristina Jørkov

2012-01-01

), this facility has been used to measure natural doses in feldspar using the decaying NIR RL signal.Secondly, we present a method for mapping radiation field of the built-in 90Sr/90Y β-source and estimating grain-location specific dose-rates. This is important for the accuracy of single grain results, when......This paper gives a review of recent developments in luminescence measurement facilities on the Risø TL/OSL reader including radio-luminescence (RL), exo-electron and violet stimulation attachments, and a method for characterising and if necessary correcting for beta irradiation source non...... radiation field is spatially non-uniform across the sample area. We document the effect of this correction method and further investigate on the effect of lifting the source to achieve a better dose-rate uniformity.Finally we summarise two recently-developed novel facilities to help investigate (i) the time...

Apparatus and method of optical marker projection for the three-dimensional shape measurement

Science.gov (United States)

Chen, Zhe; Qu, Xinghua; Geng, Xin; Zhang, Fumin

2015-08-01

Optical photography measurement and three-dimensional (3-D) scanning measurement have been widely used in the field of the fast dimensional and surface metrology. In the measurement process, however, retro-reflective markers are often pasted on the surface in advance for image registration and positioning the 3-D measuring instruments. For the large-scale workpiece with freeform surface, the process of pasting markers is time consuming, which reduces the measurement efficiency. Meanwhile, the measurement precision is impaired owing to the thickness of the marker. In this paper, we propose a system that projects two-dimensional (2-D) array optical markers with uniform energy on the surface of the workpiece instead of pasting retro-reflective markers, which achieves large-range and automated optical projection of the mark points. In order to conjunction with the 3-D handheld scanner belonging to our team, we develop an apparatus of optical marker projection, which is mainly composed of the high-power laser, the optical beam expander system, adjustable aperture stop and Dammann grating of dibasic spectrophotometric device. The projection apparatus can achieve the function of beams of 15 * 15 uniformly light of the two-dimensional lattice. And it's much cheaper than the existing systems.

Operating instructions for LBL radon measurement facilities

International Nuclear Information System (INIS)

Ingersoll, J.G.

1980-06-01

This manual is intended for users of the radon-measuring facilities of the Radon Project of the Building Ventilation and Indoor Air Quality Program at Lawrence Berkeley Laboratory. The manual comprises three parts. Part 1 sets out the steps involved in collecting, transferring, and counting radon. Part 2 describes the calibration of the transfer system and of the Lucas cells in the counting system. Part 3 outlines the maintenance procedures for the facility

Measurement Capabilities of the DOE ARM Aerial Facility

Science.gov (United States)

Schmid, B.; Tomlinson, J. M.; Hubbe, J.; Comstock, J. M.; Kluzek, C. D.; Chand, D.; Pekour, M. S.

2012-12-01

The Department of Energy Atmospheric Radiation Measurement (ARM) Program is a climate research user facility operating stationary ground sites in three important climatic regimes that provide long-term measurements of climate relevant properties. ARM also operates mobile ground- and ship-based facilities to conduct shorter field campaigns (6-12 months) to investigate understudied climate regimes around the globe. Finally, airborne observations by ARM's Aerial Facility (AAF) enhance the surface-based ARM measurements by providing high-resolution in situ measurements for process understanding, retrieval algorithm development, and model evaluation that is not possible using ground-based techniques. AAF started out in 2007 as a "virtual hangar" with no dedicated aircraft and only a small number of instruments owned by ARM. In this mode, AAF successfully carried out several missions contracting with organizations and investigators who provided their research aircraft and instrumentation. In 2009, the Battelle owned G-1 aircraft was included in the ARM facility. The G-1 is a large twin turboprop aircraft, capable of measurements up to altitudes of 7.5 km and a range of 2,800 kilometers. Furthermore the American Recovery and Reinvestment Act of 2009 provided funding for the procurement of seventeen new instruments to be used aboard the G-1 and other AAF virtual-hangar aircraft. AAF now executes missions in the virtual- and real-hangar mode producing freely available datasets for studying aerosol, cloud, and radiative processes in the atmosphere. AAF is also heavily engaged in the maturation and testing of newly developed airborne sensors to help foster the next generation of airborne instruments. In the presentation we will showcase science applications based on measurements from recent field campaigns such as CARES, CALWATER and TCAP.

Neutron cross-section measurements at the nTOF facility at CERN

CERN Document Server

Colonna, N

2004-01-01

A neutron Time-of-Flight facility (n_TOF) has recently become operative at CERN. The innovative features of the neutron beam, in particular the high instantaneous flux, the wide energy range, the high resolution and the low background, make this facility unique for measurements of neutron-induced reactions relevant to the field of emerging nuclear technologies, as well as to Nuclear Astrophysics and fundamental Nuclear Physics. The n_TOF facility is here described, together with the main features of the experimental apparata used for cross-section measurements. The results of the first measurement campaign, which have confirmed the innovative aspects of the facility, are presented. The measurement plan of the n_TOF collaboration, in particular with regard to implications to ADS, is briefly discussed.

Error analysis of thermocouple measurements in the Radiant Heat Facility

International Nuclear Information System (INIS)

Nakos, J.T.; Strait, B.G.

1980-12-01

The measurement most frequently made in the Radiant Heat Facility is temperature, and the transducer which is used almost exclusively is the thermocouple. Other methods, such as resistance thermometers and thermistors, are used but very rarely. Since a majority of the information gathered at Radiant Heat is from thermocouples, a reasonable measure of the quality of the measurements made at the facility is the accuracy of the thermocouple temperature data

White source gamma-ray production spectral measurement facilities in the USA

International Nuclear Information System (INIS)

Larson, D.C.; Dickens, J.K.; Nelson, R.O.; Wender, S.A.

1991-01-01

The two primary neutron sources for measuring gamma-ray production (GRP) cross sections for basic and applied work in the USA are the Oak Ridge Electron Linear Accelerator (ORELA) located at the Oak Ridge National Laboratory (ORNL) and the Weapons Neutron Research (WNR) facility located at the Los Alamos National Laboratory (LANL). ORELA is based on a 180-MeV electron linear accelerator, while the WNR facility uses the Los Alamos Meson Physics Facility 800 MeV proton beam to produce neutrons. The facilities collectively cover the neutron-energy range from thermal to over 700 MeV. The paper describes the present capabilities for GRP measurements at each facility. 18 refs

47 CFR 2.948 - Description of measurement facilities.

Science.gov (United States)

2010-10-01

... description of the measurement facilities employed. (1) If the measured equipment is subject to the... number; (v) FCC Registration Number (FRN); (vi) A statement as to whether or not the laboratory performs... supporting structures, and all structures within 5 times the distance between the measuring antenna and the...

Methods for nondestructive assay holdup measurements in shutdown uranium enrichment facilities

International Nuclear Information System (INIS)

Hagenauer, R.C.; Mayer, R.L. II.

1991-09-01

Measurement surveys of uranium holdup using nondestructive assay (NDA) techniques are being conducted for shutdown gaseous diffusion facilities at the Oak Ridge K-25 Site (formerly the Oak Ridge Gaseous Diffusion Plant). When in operation, these facilities processed UF 6 with enrichments ranging from 0.2 to 93 wt % 235 U. Following final shutdown of all process facilities, NDA surveys were initiated to provide process holdup data for the planning and implementation of decontamination and decommissioning activities. A three-step process is used to locate and quantify deposits: (1) high-resolution gamma-ray measurements are performed to generally define the relative abundances of radioisotopes present, (2) sizable deposits are identified using gamma-ray scanning methods, and (3) the deposits are quantified using neutron measurement methods. Following initial quantitative measurements, deposit sizes are calculated; high-resolution gamma-ray measurements are then performed on the items containing large deposits. The quantitative estimates for the large deposits are refined on the basis of these measurements. Facility management is using the results of the survey to support a variety of activities including isolation and removal of large deposits; performing health, safety, and environmental analyses; and improving facility nuclear material control and accountability records. 3 refs., 1 tab

The insertion device magnetic measurement facility: Prototype and operational procedures

International Nuclear Information System (INIS)

Burkel, L.; Dejus, R.; Maines, J.; O'Brien, J.; Vasserman, I.; Pfleuger, J.

1993-03-01

This report is a description of the current status of the magnetic measurement facility and is a basic instructional manual for the operation of the facility and its components. Please refer to the appendices for more detailed information about specific components and procedures. The purpose of the magnetic measurement facility is to take accurate measurements of the magnetic field in the gay of the IDs in order to determine the effect of the ID on the stored particle beam and the emitted radiation. The facility will also play an important role when evaluating new ideas, novel devices, and inhouse prototypes as part of the ongoing research and development program at the APS. The measurements will be performed with both moving search coils and moving Hall probes. The IDs will be evaluated by computer modeling of the emitted radiation for any given (measured) magnetic field map. The quality of the magnetic field will be described in terms of integrated multipoles for the effect on Storage Ring performance and in terms of the derived trajectories for the emitted radiation. Before being installed on the Storage Ring, every device will be measured and characterized to assure that it is compatible with Storage Ring requirements and radiation specifications. The accuracy that the APS needs to achieve for magnetic measurements will be based on these specifications

Evaluation of double drop beads pavement edge lines : SPR project description.

Science.gov (United States)

2009-01-01

In UTCA projects 01465 and 04405, the retroreflectivities and the life cycle costs were measured and compared for standard Alabama Department of Transportation (ALDOT) thermoplastic edge : stripes that contained only one size of retroreflective beads...

Measurement of photoneutron spectrum at Pohang Neutron Facility

Energy Technology Data Exchange (ETDEWEB)

Kim, G.N.; Kovalchuk, V.; Lee, Y.S.; Skoy, V.; Cho, M.H.; Ko, I.S.; Namkung, W. [POSTECH, Pohang Accelerator Laboratory, Pohang, Kyungbuk (Korea)

2001-03-01

Pohang Neutron Facility, which is the pulsed neutron facility based on the 100-MeV electron linear accelerator, was constructed for nuclear data production in Korea. The Pohang Neutron Facility consists of an electron linear accelerator, a water-cooled Ta target with a water moderator and a time-of-flight path with an 11 m length. The neutron energy spectra are measured for different water levels inside the moderator and compared with the MCNP calculation. The optimum size of the water moderator is determined on the base of this result. The time dependent spectra of neutrons in the water moderator are investigated with the MCNP calculation. (author)

Instrumentation and measurement method for the ATLAS test facility

Energy Technology Data Exchange (ETDEWEB)

Yun, Byong Jo; Chu, In Chul; Eu, Dong Jin; Kang, Kyong Ho; Kim, Yeon Sik; Song, Chul Hwa; Baek, Won Pil

2007-03-15

An integral effect test loop for pressurized water reactors (PWRs), the ATLAS is constructed by thermal-hydraulic safety research division in KAERI. The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400 which is a Korean evolution type nuclear reactors. A total 1300 instrumentations is equipped in the ATLAS test facility. In this report, the instrumentation of ATLAS test facility and related measurement methods were introduced.

Adherence to blood pressure measurement guidelines in long-term care facilities: A cross sectional study.

Science.gov (United States)

Ozone, Sachiko; Sato, Mikiya; Takayashiki, Ayumi; Sakamoto, Naoto; Yoshimoto, Hisashi; Maeno, Tetsuhiro

2018-05-01

To assess the extent to which long-term care facilities in Japan adhere to blood pressure (BP) measurement guidelines. Cross-sectional, observational survey. Japan (nationwide). Geriatric health service facilities that responded to a questionnaire among 701 facilities that provide short-time daycare rehabilitation services in Japan. A written questionnaire that asked about types of measurement devices, number of measurements used to obtain an average BP, resting time prior to measurement, and measurement methods when patients' arms were covered with thin (eg, a light shirt) or thick sleeves (eg, a sweater) was administered. Proportion of geriatric health service facilities adherent to BP measurement guidelines. The response rate was 63.2% (443/701). Appropriate upper-arm BP measurement devices were used at 302 facilities (68.2%). The number of measurements was appropriate at 7 facilities (1.6%). Pre-measurement resting time was appropriate (≥5 minutes) at 205 facilities (46.3%). Of the 302 facilities that used appropriate BP measurement devices, 4 (1.3%) measured BP on a bare arm if it was covered with a thin sleeve, while 266 (88.1%) measured BP over a thin sleeve. When arms were covered with thick sleeves, BP was measured on a bare arm at 127 facilities (42.1%) and over a sleeve at 78 facilities (25.8%). BP measurement guidelines were not necessarily followed by long-term care service facilities in Japan. Modification of guidelines regarding removing thick sweaters and assessing BP on a visit-to-visit basis might be needed.

Preliminary concepts for materials measurement and accounting in critical facilities

International Nuclear Information System (INIS)

Cobb, D.D.; Sapir, J.L.

1978-01-01

Preliminary concepts are presented for improved materials measurement and accounting in large critical facilities. These concepts will be developed as part of a study that will emphasize international safeguarding of critical facilities. The major safeguards problem is the timely verification of in-reactor inventory during periods of reactor operation. This will require a combination of measurement, statistical sampling, and data analysis techniques. Promising techniques include integral measurements of reactivity and other reactor parameters that are sensitive to the total fissile inventory, and nondestructive assay measurements of the fissile material in reactor fuel drawers and vault storage canisters coupled with statistical sampling plans tailored for the specific application. The effectiveness of proposed measurement and accounting strategies will be evaluated during the study

Chemical Hygiene Plan for Onsite Measurement and Sample Shipping Facility Activities

International Nuclear Information System (INIS)

Price, W.H.

1998-01-01

This chemical hygiene plan presents the requirements established to ensure the protection of employee health while performing work in mobile laboratories, the sample shipping facility, and at the onsite radiological counting facility. This document presents the measures to be taken to promote safe work practices and to minimize worker exposure to hazardous chemicals. Specific hazardous chemicals present in the mobile laboratories, the sample shipping facility, and in the radiological counting facility are presented in Appendices A through G

Neutron fluence measurement in nuclear facilities

International Nuclear Information System (INIS)

Camacho L, M.E.

1997-01-01

The objective of present work is to determine the fluence of neutrons in nuclear facilities using two neutron detectors designed and built at Instituto Nacional de Investigaciones Nucleares (ININ), Mexico. The two neutron detectors are of the passive type, based on solid state nuclear tracks detectors (SSNTD). One of the two neutron detectors was used to determine the fluence distribution of the ports at the nuclear research reactor TRIGA Mark III, which belongs to ININ. In these facilities is important to know the neutron fluence distribution characteristic to carried out diverse kind of research activities. The second neutron detector was employed in order to carry out environmental neutron surveillance. The detector has the property to separate the thermal, intermediate and fast components of the neutron fluence. This detector was used to measure the neutron fluence at hundred points around the primary container of the first Mexican Nuclear Power plant 'Laguna Verde'. This last detector was also used to determine the neutron fluence in some points of interest, around and inside a low scattering neutron room at the 'Centro de Metrologia de Radiaciones Ionizantes' of the ININ, to know the background neutron field produced by the neutron sources used there. The design of the two neutron detector and the results obtained for each of the surveying facilities, are described in this work. (Author)

Atmospheric Radiation Measurement (ARM) Climate Research Facility Management Plan

Energy Technology Data Exchange (ETDEWEB)

Mather, James [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-04-01

Mission and Vision Statements for the U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility Mission The ARM Climate Research Facility, a DOE scientific user facility, provides the climate research community with strategically located in situ and remote-sensing observatories designed to improve the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their interactions and coupling with the Earth’s surface. Vision To provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes to resolve the uncertainties in climate and Earth system models toward the development of sustainable solutions for the nation's energy and environmental challenges.

Questionnaire survey report on measurement of radioactivity in working environment of radioisotopes facility

International Nuclear Information System (INIS)

Kawano, Takao; Nomura, Kiyoshi

2008-01-01

To look over the current measurement of radioactivity concentration in working environment of many radioisotopes facilities, a questionnaire survey was carried out under the auspices of the Planning Committee of the Japan Society of Radiation Safety Management. 64 responses were obtained in 128 radiation facilities, which the questionnaires were sent to. The main results were obtained by aggregate analysis of the answers for questionnaires as the followings. Major nuclides subject to measurement were 3 H, 14 C, 32 P and 125 I Sampling of radioisotopes in air was mainly performed using collectors like dust samplers and HC-collectors. Liquid scintillation counters and gamma counters were used to measure β and γ radioactivity contained in airborne particles or gas samples. Contamination by radioactivity was not detected in 55% facilities surveyed, but in 40% facilities at the same level as or at lower levels than a hundredth part of the regulated concentration limit of each nuclide. Almost all facilities is found to consider that the measurement of radioactivity concentration in working environments is not always necessary. (author)

Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

International Nuclear Information System (INIS)

Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

1978-01-01

This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period

Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

Energy Technology Data Exchange (ETDEWEB)

Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

1978-01-01

This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period.

Overview of nuclear data measurement facilities in OECD countries

International Nuclear Information System (INIS)

Bioux, P.; Rowlands, J.L.

1996-06-01

In 1992 EDF commissioned a review of activity in the fields of nuclear data for fission power technology applications in OECD countries. The review was carried out in cooperation with the consultants EUROGRAM. This paper presents a summary. The situation is of concern to the French nuclear industry because of the few measurement facilities which are now funded for work in the field and the reductions in the numbers of scientists expert in measurement and evaluation of nuclear data. There are requirements which justify work to improve knowledge of many items of nuclear data. To ensure maintenance of expertise the French Nuclear Industry has arranged for several young scientists to work with leading experts in the different fields. However, the problem of continued availability of facilities remains. (authors)

Biosafety and biosecurity measures: management of biosafety level 3 facilities.

Science.gov (United States)

Zaki, Adel N

2010-11-01

With the increasing biological threat from emerging infectious diseases and bioterrorism, it has become essential for governments around the globe to increase awareness and preparedness for identifying and containing those agents. This article introduces the basic concepts of laboratory management, laboratory biosafety and laboratory biosecurity. Assessment criteria for laboratories' biorisk should include both biosafety and biosecurity measures. The assessment requires setting specific goals and selecting management approaches. In order to implement technologies at the laboratory working level, a management team should be created whose role is to implement biorisk policies, rules and regulations appropriate for that facility. Rules and regulations required by government authorities are presented, with special emphasis on methods for air control, and liquid and solid waste management. Management and biorisk measures and appropriate physical facilities must keep pace, ensuring efficient facilities that protect workers, the environment, the product (research, diagnostic and/or vaccine) and the biological pathogen. Published by Elsevier B.V.

"Atmospheric Radiation Measurement (ARM) Research Facility at Oliktok Point Alaska"

Science.gov (United States)

Helsel, F.; Ivey, M.; Hardesty, J.; Roesler, E. L.; Dexheimer, D.

2017-12-01

Scientific Infrastructure To Support Atmospheric Science, Aerosol Science and UAS's for The Department Of Energy's Atmospheric Radiation Measurement Programs At The Mobile Facility 3 Located At Oliktok Point, Alaska.The Atmospheric Radiation Measurement (ARM) Program's Mobile Facility 3 (AMF3) located at Oliktok Point, Alaska is a U.S. Department of Energy (DOE) site designed to collect data and help determine the impact that clouds and aerosols have on solar radiation. AMF3 provides a scientific infrastructure to support instruments and collect arctic data for the international arctic research community. The infrastructure at AMF3/Oliktok is designed to be mobile and it may be relocated in the future to support other ARM science missions. AMF3's present base line instruments include: scanning precipitation Radars, cloud Radar, Raman Lidar, Eddy correlation flux systems, Ceilometer, Balloon sounding system, Atmospheric Emitted Radiance Interferometer (AERI), Micro-pulse Lidar (MPL) Along with all the standard metrological measurements. In addition AMF3 provides aerosol measurements with a Mobile Aerosol Observing System (MAOS). Ground support for Unmanned Aerial Systems (UAS) and tethered balloon flights. Data from these instruments and systems are placed in the ARM data archives and are available to the international research community. This poster will discuss what instruments and systems are at the ARM Research Facility at Oliktok Point Alaska.

Measurement of C-14 distribution in forest around nuclear facilities

International Nuclear Information System (INIS)

Atarashi-Andoh, Mariko; Amano, Hikaru; Arakhatoon, Jahan

2003-01-01

A simple analytical method of C-14 measurement using fast bomb combustion and liquid scintillation counting (LSC) has been developed for measuring C-14 distribution in the terrestrial environment. Specific activities of C-14 in cedar leaves and soils collected from an area around nuclear facilities and control areas were measured using this method. Depth distribution of Cs-137 in soils was also measured at the same sampling sites and compared with the depth distribution of C-14. C-14 specific activity in cedar leaves examined around nuclear facilities exceeded that in the control areas by 8 to 30 mBq (g carbon) -1 . The depth distribution of C-14 in forest soil shows that C-14 has peak values in the top 10 cm of the soil profiles ascribed to the highest bomb C-14 level in the 1960's. The data were made available to assess the behavior of fallout C-14 in the surface environment. (author)

Environmental exposure measurements in and around the site of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Moriuchi, S [Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment

1977-04-01

Problems in measurement of ..gamma..-ray in environment generated by an operation of nuclear facilities, and practical measurement methods were given an outline. /sup 85/Kr and /sup 133/Xe were mentioned as main nuclides which were released from various kinds of atomic piles for commercial business or research. Problems in measurement of low level ..gamma..-ray by measurement instruments such as a ionizing chamber, NaI (TL) detector, GM counter, and TLD were mentioned. Measurement of accumulated dose with TLD was described, and the change with a progress of time in the measurement objects (..gamma..-ray, fallout ..gamma..-ray, and plume ..gamma..-ray in nature) and its characteristic patterns were showed. Information which were used for identification of minute components in facilities and natural radiation, and method for identification were described. Last, comparison of results of dose measurements and values estimated by calculation was described, and importance of storage of monitoring data was described.

Fire and earthquake counter measures in radiation handling facilities

International Nuclear Information System (INIS)

1985-01-01

'Fire countermeasures in radiation handling facilities' published in 1961 is still widely utilized as a valuable guideline for those handling radiation through the revision in 1972. However, science and technology rapidly advanced, and the relevant laws were revised after the publication, and many points which do not conform to the present state have become to be found. Therefore, it was decided to rewrite this book, and the new book has been completed. The title was changed to 'Fire and earthquake countermeasures in radiation handling facilities', and the countermeasures to earthquakes were added. Moreover, consideration was given so that the book is sufficiently useful also for those concerned with fire fighting, not only for those handling radiation. In this book, the way of thinking about the countermeasures against fires and earthquakes, the countermeasures in normal state and when a fire or an earthquake occurred, the countermeasures when the warning declaration has been announced, and the data on fires, earthquakes, the risk of radioisotopes, fire fighting equipment, the earthquake counter measures for equipment, protectors and radiation measuring instruments, first aid, the example of emergency system in radiation handling facilities, the activities of fire fighters, the example of accidents and so on are described. (Kako, I.)

Compendium of Neutron Beam Facilities for High Precision Nuclear Data Measurements

International Nuclear Information System (INIS)

2014-07-01

The recent advances in the development of nuclear science and technology, demonstrating the globally growing economy, require highly accurate, powerful simulations and precise analysis of the experimental results. Confidence in these results is still determined by the accuracy of the atomic and nuclear input data. For studying material response, neutron beams produced from accelerators and research reactors in broad energy spectra are reliable and indispensable tools to obtain high accuracy experimental results for neutron induced reactions. The IAEA supports the accomplishment of high precision nuclear data using nuclear facilities in particular, based on particle accelerators and research reactors around the world. Such data are essential for numerous applications in various industries and research institutions, including the safety and economical operation of nuclear power plants, future fusion reactors, nuclear medicine and non-destructive testing technologies. The IAEA organized and coordinated the technical meeting Use of Neutron Beams for High Precision Nuclear Data Measurements, in Budapest, Hungary, 10–14 December 2012. The meeting was attended by participants from 25 Member States and three international organizations — the European Organization for Nuclear Research (CERN), the Joint Research Centre (JRC) and the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (OECD/NEA). The objectives of the meeting were to provide a forum to exchange existing know-how and to share the practical experiences of neutron beam facilities and associated instrumentation, with regard to the measurement of high precision nuclear data using both accelerators and research reactors. Furthermore, the present status and future developments of worldwide accelerator and research reactor based neutron beam facilities were discussed. This publication is a summary of the technical meeting and additional materials supplied by the international

Total body-calcium measurements: comparison of two delayed-gamma neutron activation facilities

International Nuclear Information System (INIS)

Ma, R.; Ellis, K.J.; Shypailo, R.J.; Pierson, R.N. Jr.

1999-01-01

This study compares two independently calibrated delayed-gamma neutron activation (DGNA) facilities, one at the Brookhaven National Laboratory (BNL), Upton, New York, and the other at the Children's Nutrition Research Center (CNRC), Houston, Texas that measure total body calcium (TBCa). A set of BNL phantoms was sent to CNRC for neutron activation analysis, and a set of CNRC phantoms was measured at BNL. Both facilities showed high precision (<2%), and the results were in good agreement, within 5%. (author)

Initial tank calibration at NUCEF critical facility. 1. Measurement procedure and its result

International Nuclear Information System (INIS)

Yanagisawa, Hiroshi; Mineo, Hideaki; Tonoike, Kotaro; Takeshita, Isao; Hoshi, Katsuya; Hagiwara, Hiroyuki.

1994-07-01

Initial tank calibrations were carried out prior to hot operation of critical facilities in NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility, for the purpose of the nuclear material accountancy and control for the facility. Raw calibration data were collected from single run per one tank by measuring differential pressure with dip-tube systems, weight of calibration liquid (demineralized water) poured into the tank, temperature in the tank and so on, without operation of tank ventilation system. Volume and level data were obtained by applying density and buoyancy corrections to the raw data. As a result, the evaluated measurement errors of volume and level were small enough, e.g. within 0.2 lit. and 1.0 mm, respectively, for Pu accountancy tanks. This paper summarizes the above-mentioned measurement procedures, collected data, data correction procedures and evaluated measurement errors. (author)

Absolute measurement of the DT primary neutron yield on the National Ignition Facility

Directory of Open Access Journals (Sweden)

Leeper R.J.

2013-11-01

Full Text Available The measurement of the absolute neutron yield produced in inertial confinement fusion target experiments conducted on the National Ignition Facility (NIF is essential in benchmarking progress towards the goal of achieving ignition on this facility. This paper describes three independent diagnostic techniques that have been developed to make accurate and precise DT neutron yield measurements on the NIF.

Consideration on Preventive and Protective Measures Against Insider Threats at R.O.K. Nuclear Facilities

International Nuclear Information System (INIS)

Lee, Seung Min; Lee, Jung Ho; Koh, Moon Sung

2016-01-01

This paper focuses on the current status of measures used to prevent, detect and respond to potential insiders at nuclear facilities in the Republic of KOREA. Measures against insiders are then analyzed based on IAEA guidelines. Insiders are able to take advantage of their access rights and knowledge of a facility to bypass dedicated security measures. They can also threaten cyber security, safety measures, and material control and accountancy (MC and A). Insiders are likely to have the time to plan their actions. In addition, they may work with an external adversary who shares their objectives. An insider threat is a great risk to a security system because of the access, authority, and special knowledge that someone within a facility possesses. Therefore, it is imperative that effective measures be taken to prevent insider incidents. A combination of preventive and protective measures offers the best solution to mitigating rogue elements within a facility

Consideration on Preventive and Protective Measures Against Insider Threats at R.O.K. Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Min; Lee, Jung Ho; Koh, Moon Sung [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

This paper focuses on the current status of measures used to prevent, detect and respond to potential insiders at nuclear facilities in the Republic of KOREA. Measures against insiders are then analyzed based on IAEA guidelines. Insiders are able to take advantage of their access rights and knowledge of a facility to bypass dedicated security measures. They can also threaten cyber security, safety measures, and material control and accountancy (MC and A). Insiders are likely to have the time to plan their actions. In addition, they may work with an external adversary who shares their objectives. An insider threat is a great risk to a security system because of the access, authority, and special knowledge that someone within a facility possesses. Therefore, it is imperative that effective measures be taken to prevent insider incidents. A combination of preventive and protective measures offers the best solution to mitigating rogue elements within a facility.

Neutron measurements at BRIT/BARC medical cyclotron facility of RMC, Parel

International Nuclear Information System (INIS)

Sathian, Deepa; Sathian, V.; Phandnis, U.V.; Soni, P.S.; Mohite, D.Y.

2005-01-01

Neutron leakage and its long distance propagation in the atmosphere from the intense neutron facilities such as high energy accelerators like Cyclotron are very important for the shielding design of the facilities and resulting dose reduction to nearby population, because of strong penetrability of high energy neutrons. The neutron interaction cross sections are highly energy dependent, so different methods are adopted for measuring different energy neutrons. The method also depends on the amount of neutron fluence rate expected at the location. When the fluence rate is very high, the foil activation is the best method for the measurement of neutron fluence rate. In foil activation technique an inactive material is activated by neutrons and the activity is measured and correlated to the neutron fluence rate. In this paper, neutron fluence rate measurement using different activation foils at medical cyclotron room of Radiation Medicine Centre (RMC) is discussed. (author)

Commissioning experience and beam physics measurements at the SwissFEL Injector Test Facility

Directory of Open Access Journals (Sweden)

T. Schietinger

2016-10-01

Full Text Available The SwissFEL Injector Test Facility operated at the Paul Scherrer Institute between 2010 and 2014, serving as a pilot plant and test bed for the development and realization of SwissFEL, the x-ray Free-Electron Laser facility under construction at the same institute. The test facility consisted of a laser-driven rf electron gun followed by an S-band booster linac, a magnetic bunch compression chicane and a diagnostic section including a transverse deflecting rf cavity. It delivered electron bunches of up to 200 pC charge and up to 250 MeV beam energy at a repetition rate of 10 Hz. The measurements performed at the test facility not only demonstrated the beam parameters required to drive the first stage of an FEL facility, but also led to significant advances in instrumentation technologies, beam characterization methods and the generation, transport and compression of ultralow-emittance beams. We give a comprehensive overview of the commissioning experience of the principal subsystems and the beam physics measurements performed during the operation of the test facility, including the results of the test of an in-vacuum undulator prototype generating radiation in the vacuum ultraviolet and optical range.

Wavefront error measurement of the concave ellipsoidal mirrors of the METIS coronagraph on ESA Solar Orbiter mission

Science.gov (United States)

Sandri, P.

2017-12-01

The paper describes the alignment technique developed for the wavefront error measurement of ellipsoidal mirrors presenting a central hole. The achievement of a good alignment with a classic setup at the finite conjugates when mirrors are uncoated cannot be based on the identification and materialization at naked eye of the retro-reflected spot by the mirror under test as the intensity of the retro-reflected spot results to be ≈1E-3 of the intensity of the injected laser beam of the interferometer. We present the technique developed for the achievement of an accurate alignment in the setup at the finite conjugate even in condition of low intensity based on the use of an autocollimator adjustable in focus position and a small polished flat surface on the rear side of the mirror. The technique for the alignment has successfully been used for the optical test of the concave ellipsoidal mirrors of the METIS coronagraph of the ESA Solar Orbiter mission. The presented method results to be advantageous in terms of precision and of time saving also when the mirrors are reflective coated and integrated into their mechanical hardware.

The n_TOF facility: Neutron beams for challenging future measurements at CERN

Science.gov (United States)

Chiaveri, E.; Aberle, O.; Andrzejewski, J.; Audouin, L.; Bacak, M.; Balibrea, J.; Barbagallo, M.; Bečvář, F.; Berthoumieux, E.; Billowes, J.; Bosnar, D.; Brown, A.; Caamaño, M.; Calviño, F.; Calviani, M.; Cano-Ott, D.; Cardella, R.; Casanovas, A.; Cerutti, F.; Chen, Y. H.; Colonna, N.; Cortés, G.; Cortés-Giraldo, M. A.; Cosentino, L.; Damone, L. A.; Diakaki, M.; Domingo-Pardo, C.; Dressler, R.; Dupont, E.; Durán, I.; Fernández-Domínguez, B.; Ferrari, A.; Ferreira, P.; Finocchiaro, P.; Göbel, K.; García, A. R.; Gawlik, A.; Gilardoni, S.; Glodariu, T.; Gonçalves, I. F.; González, E.; Griesmayer, E.; Guerrero, C.; Gunsing, F.; Harada, H.; Heinitz, S.; Heyse, J.; Jenkins, D. G.; Jericha, E.; Käppeler, F.; Kadi, Y.; Kalamara, A.; Kavrigin, P.; Kimura, A.; Kivel, N.; Kokkoris, M.; Krtička, M.; Kurtulgil, D.; Leal-Cidoncha, E.; Lederer, C.; Leeb, H.; Lerendegui-Marco, J.; Meo, S. Lo; Lonsdale, S. J.; Macina, D.; Marganiec, J.; Martínez, T.; Masi, A.; Massimi, C.; Mastinu, P.; Mastromarco, M.; Maugeri, E. A.; Mazzone, A.; Mendoza, E.; Mengoni, A.; Milazzo, P. M.; Mingrone, F.; Musumarra, A.; Negret, A.; Nolte, R.; Oprea, A.; Patronis, N.; Pavlik, A.; Perkowski, J.; Porras, I.; Praena, J.; Quesada, J. M.; Radeck, D.; Rauscher, T.; Reifarth, R.; Rubbia, C.; Ryan, J. A.; Sabaté-Gilarte, M.; Saxena, A.; Schillebeeckx, P.; Schumann, D.; Smith, A. G.; Sosnin, N. V.; Stamatopoulos, A.; Tagliente, G.; Tain, J. L.; Tarifeño-Saldivia, A.; Tassan-Got, L.; Tsinganis, A.; Valenta, S.; Vannini, G.; Variale, V.; Vaz, P.; Ventura, A.; Vlachoudis, V.; Vlastou, R.; Wallner, A.; Warren, S.; Woods, P. J.; Wright, T.; Žugec, P.

2017-09-01

The CERN n_TOF neutron beam facility is characterized by a very high instantaneous neutron flux, excellent TOF resolution at the 185 m long flight path (EAR-1), low intrinsic background and coverage of a wide range of neutron energies, from thermal to a few GeV. These characteristics provide a unique possibility to perform high-accuracy measurements of neutron-induced reaction cross-sections and angular distributions of interest for fundamental and applied Nuclear Physics. Since 2001, the n_TOF Collaboration has collected a wealth of high quality nuclear data relevant for nuclear astrophysics, nuclear reactor technology, nuclear medicine, etc. The overall efficiency of the experimental program and the range of possible measurements has been expanded with the construction of a second experimental area (EAR-2), located 20 m on the vertical of the n_TOF spallation target. This upgrade, which benefits from a neutron flux 30 times higher than in EAR-1, provides a substantial extension in measurement capabilities, opening the possibility to collect data on neutron cross-section of isotopes with short half-lives or available in very small amounts. This contribution will outline the main characteristics of the n_TOF facility, with special emphasis on the new experimental area. In particular, we will discuss the innovative features of the EAR-2 neutron beam that make possible to perform very challenging measurements on short-lived radioisotopes or sub-mg samples, out of reach up to now at other neutron facilities around the world. Finally, the future perspectives of the facility will be presented.

Does Nursing Facility Use of Habilitation Therapy Improve Performance on Quality Measures?

Science.gov (United States)

Fitzler, Sandra; Raia, Paul; Buckley, Fredrick O; Wang, Mei

2016-12-01

The purpose of the project, Centers for Medicare & Medicaid Services (CMS) Innovation study, was to evaluate the impact on 12 quality measures including 10 Minimum Data Set (MDS) publicly reported measures and 2 nursing home process measures using habilitation therapy techniques and a behavior team to manage dementia-related behaviors. A prospective design was used to assess the changes in the measures. A total of 30 Massachusetts nursing homes participated in the project over a 12-month period. Project participation required the creation of an interdisciplinary behavior team, habilitation therapy training, facility visit by the program coordinator, attendance at bimonthly support and sharing calls, and monthly collection of process measure data. Participating facilities showed improvement in 9 of the 12 reported measures. Findings indicate potential quality improvement in having nursing homes learn habilitation therapy techniques and know how to use the interdisciplinary team to manage problem behaviors. © The Author(s) 2016.

Facility for the measurement of proton polarization in nuclear reactions

Energy Technology Data Exchange (ETDEWEB)

Slobodrian, R J; Irshad, M; Labrie, R; Rioux, C; Roy, R; Pigeon, R [Laval Univ., Quebec City (Canada). Lab. de Physique Nucleaire

1979-02-15

A polarimetry facility based on high resolution and high efficiency silicon polarimeters with on-line particle identification is described. It has proven its capability to measure polarization in (/sup 3/He, p(pol)) reaction with cross section levels of 40 ..mu..b/sr.

Animal-eyeball vs. road-sign retroreflectors.

Science.gov (United States)

Greene, Nathaniel R; Filko, Brian J

2010-01-01

The retroreflective characteristics of ex-vitro cow and deer eyeballs were compared to those of man-made materials used in road signs and bicycle-style reflectors. Reflected intensities were measured using a goniometer that consists of a green He-Ne laser as the light source, and a photomultiplier tube as the detector. It was found that the best quality road-sign reflector, made from a 200-micron-scale, close-packed array of corner cubes, is approximately six times more efficient than a cow eyeball at returning light in the direction of the incoming beam. Less expensive man-made retroreflectors, utilizing 35-micron glass beads (as in mailbox decals) or millimeter-scale arrays of corner cubes (bicycle-style reflectors) are, however, less efficient than the cow eye. The high quality of animal eyeball optics is evidenced by their extremely tight angular spread (full width half maximum congruent with 1 degrees) of retroreflected intensity about the incident path. Moreover, as the reflector itself is rotated relative to the incident beam, the eyeballs preserve their efficiency of retroreflection better than the man-made materials. Interference-diffraction patterns were observed in the retroreflected beams from the small-scale corner cubes, but were not observed in eyeball retroreflection.

Completely automated measurement facility (PAVICOM) for track-detector data processing

CERN Document Server

Aleksandrov, A B; Feinberg, E L; Goncharova, L A; Konovalova, N S; Martynov, A G; Polukhina, N G; Roussetski, A S; Starkov, NI; Tsarev, V A

2004-01-01

A review of technical capabilities and investigations performed using the completely automated measuring facility (PAVICOM) is presented. This very efficient facility for track-detector data processing in the field of nuclear and high-energy particle physics has been constructed in the Lebedev physical institute. PAVICOM is widely used in Russia for treatment of experimental data from track detectors (emulsion and solid-state trackers) in high- and low-energy physics, cosmic ray physics, etc. PAVICOM provides an essential improvement of the efficiency of experimental studies. In contrast to semi-automated microscopes widely used until now, PAVICOM is capable of performing completely automated measurements of charged particle tracks in nuclear emulsions and track detectors without employing hard visual work. In this case, track images are recorded by CCD cameras and then are digitized and converted into files. Thus, experimental data processing is accelerated by approximately a thousand times. Completely autom...

Development and applications of retro-reflective surfaces for ultrasound in LBE

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-07-01

The Belgian Nuclear Research Centre SCK-CEN is in the process of developing MYRRHA - a fast flux research reactor to replace the aging BR2. MYRRHA is conceptualized as an accelerator driven system cooled by lead bismuth eutectic mixture (LBE). As LBE is opaque to visual light, ultrasonic measurement techniques are employed as the main technology to provide feedback to submerged operations when needed. Conceptually, MYRRHA is a pool type reactor divided in a cold lower plenum and hot upper plenum separated by a diaphragm that forces the main flow through the core. The main flow is cooled by four heat exchangers and driven by two liquid metal pumps. One of the tasks tackled using ultrasound is locating a potentially lost fuel assembly to assist a recovery operation. As all fuel manipulations in MYRRHA are performed in the lower plenum, a potentially lost fuel assembly is located in the lower plenum. Buoyancy will force the lost fuel assembly to float against the diaphragm unless it is still partially inserted in the core. Because of the latter situation, an ultrasonic scan localizing the fuel assembly should be performed from a large distance to avoid a collision with such a partially inserted fuel assembly. Unfortunately, standard machined stainless steel objects, such as a fuel assembly, reflect an ultrasonic pulse in a specular way which induces stringent requirements on the alignment of the ultrasonic sensor with respect to the fuel assembly as we cannot rely on diffuse reflections and/or scattering of the ultrasonic pulse. Moreover, increasing the distance also increases geometric spreading and absorption of the pulse weakening the signal amplitude even faster to noise levels when deviating from perfect alignment. An alternative approach consists in relying on reflections from the known surroundings: a lost fuel assembly will block the line-of-sight to the diaphragm resulting in an anomaly in the reflection - either a shorter than expected time-of-flight of the

Start of operation of the barrel measuring facility II-01. Implementation into operational processes

International Nuclear Information System (INIS)

Buesing, B.; Escher, M.

2013-01-01

For the operation of the barrel measuring facility (FAME) II-01 a variety requirements to the measuring techniques were defined and tested in the frame of start-up. The used mechanical engineering and measuring technique complies with the state-of-the-art. Using the barrel measuring facility quality assured determinations of the dose rate and the nuclide-specific activity inventory were performed. For the evaluation of the gamma spectrometric measurements of FAME II-01 appropriately qualified personnel is available. The implementation of the facility in combination with the connection to the data base system PIK-AS and AVK it guaranteed that important data are available in real-time for the measuring process and the subsequent work steps. Besides this it is guaranteed that using the import/export functions relevant data are reviewed, supplemented and exchanged between the systems without transfer errors. The determined data of the dose rate and gamma spectrometric measurements allow an activity determination of the waste package with quality assurance and close to reality. Conservative assumptions in the frame of activity calculations for the later final disposal can be reduced. The automated operation of FAME allows also the reduction of radiation exposure of the personnel.

Measurements of nuclear data and possibility to construct the nuclear data production facility based on electron linac

Energy Technology Data Exchange (ETDEWEB)

Namkung, Won; Ko, In Soo; Cho, Moo Hyun; Kim, Gui Nyun; Lee, Young Seok; Kang, Heung Sik [Pohang University of Science and Technology, Pohang(Korea)

2001-04-01

In order to construct an infrastructure to produce nuclear data, we studied three main items; (1) Study on the possibility to construct a facility for nuclear data production, (2) Production of nuclear data for nuclear power plant, and (3) Pulsed neutron source based on a 100-MeV electron linac at Pohang Accelerator Laboratory (PAL). We confirmed the possibility to build a nuclear data production facility utilizing a 100-MeV electron linac at PAL and manpower who wanted to participate the nuclear data production experiments. In order to measure the nuclear data for nuclear power plant, we used several nuclear data production facilities in abroad. We measured total cross sections and neutron caprure cross sections for {sup nat}Dy and {sup nat}Hf using the pulsed neutron facility in the Research Reactor Institute, Kyoto University (KURRI). The neutron capture cross sections for {sup 161,162,163,164}Dy were measured at KURRI in the neutron energy region between 0.001 eV and several tens keV, and at the fast neutron facility in Tokyo Institute of Technology in the neutron energy region between 10 keV and 100 keV. We also measured the neutron capture cross sections and gamma multiplicity of {sup 232}Th at the IBR30 in Dubna, Russia. We have construct a pulsed neutron source using a 100-MeV electron linac at PAL. We measured neutron time-of-flight (TOF) spectra in order to check the characteristics of the pulsed neutron source. We also measured a neutron total cross sections of W and Cu. The pulsed neutron facility can be utilized in the education facility for nuclear data production and the test facility for the R and D purpose of the nuclear data production facility. 29 refs., 57 figs., 22 tabs. (Author)

Measuring Inpatient Rehabilitation Facility Quality of Care: Discharge Self-Care Functional Status Quality Measure.

Science.gov (United States)

Pardasaney, Poonam K; Deutsch, Anne; Iriondo-Perez, Jeniffer; Ingber, Melvin J; McMullen, Tara

2018-06-01

To describe the calculation and psychometric properties of the discharge self-care functional status quality measure implemented in the Centers for Medicare & Medicaid Services' (CMS) Inpatient Rehabilitation Facility (IRF) Quality Reporting Program on October 1, 2016. Medicare fee-for-service (FFS) patients from 38 IRFs that participated in the CMS Post-Acute Care Payment Reform Demonstration were included in this cohort study. Data came from the Continuity Assessment Record and Evaluation Item Set, IRF-Patient Assessment Instrument, and Medicare claims. For each patient, we calculated an expected discharge self-care score, risk-adjusted for demographic and baseline clinical characteristics. The performance score of each IRF equaled the percentage of patient stays where the observed discharge self-care score met or exceeded the expected score. We assessed the measure's discriminatory ability across IRFs and reliability. IRFs. Medicare FFS patients aged ≥21 years (N=4769). Not applicable. Facility-level discharge self-care quality measure performance score. A total of 4769 patient stays were included; 57% of stays were in women, and 12.1% were in patients aged quality measure showed strong reliability, with intraclass correlation coefficients of .91. The discharge self-care quality measure showed strong discriminatory ability and reliability, representing an important initial step in evaluation of IRF self-care outcomes. A wide range in performance scores suggested a gap in quality of care across IRFs. Future work should include testing the measure with nationwide data from all IRFs. Published by Elsevier Inc.

Wire Scanner Beam Profile Measurements for the LANSCE Facility

International Nuclear Information System (INIS)

Gilpatrick, John D.; Gruchalla, Michael E.; Martinez, Derwin; Pillai, Chandra; Rodriguez Esparza, Sergio; Sedillo, James Daniel; Smith, Brian G.

2012-01-01

The Los Alamos Neutron Science Center (LANSCE) is replacing beam profile measurement systems, commonly known as Wire Scanners (WS). Using the principal of secondary electron emission, the WS measurement system moves a wire or fiber across an impinging particle beam, sampling a projected transverse-beam distribution. Because existing WS actuators and electronic components are either no longer manufactured or home-built with antiquated parts, a new WS beam profile measurement is being designed, fabricated, and tested. The goals for these new WS's include using off-the-shelf components while eliminating antiquated components, providing quick operation while allowing for easy maintainability, and tolerating external radioactivation. The WS measurement system consists of beam line actuators, a cable plant, an electronics processor chassis, and software located both in the electronics chassis (National Instruments LabVIEW) and in the Central Control Room (EPICS-based client software). This WS measurement system will measure Hand H + LANSCE-facility beams and will also measure less common beams. This paper describes these WS measurement systems.

Regulatory measures of BARC Safety Council to control radiation exposure in BARC Facilities

International Nuclear Information System (INIS)

Rajdeep; Jolly, V.M.; Jayarajan, K.

2018-01-01

Bhabha Atomic Research Centre is involved in multidisciplinary research and developmental activities, related to peaceful use of nuclear energy including societal benefits. BARC facilities at different parts of India include nuclear fuel fabrication facilities, research reactors, nuclear recycle facilities and various Physics, Chemistry and Biological laboratories. BARC Safety Council (BSC) is the regulatory body for BARC facilities and takes regulatory measures for radiation protection. BSC has many safety committees for radiation protection including Operating Plants Safety Review Committee (OPSRC), Committee to Review Applications for Authorization of Safe Disposal of Radioactive Wastes (CRAASDRW) and Design Safety Review Committees (DSRC) in 2 nd tier and Unit Level Safety Committees (ULSCs) in 3 rd tier under OPSRC

Model measurements in the cryogenic National Transonic Facility - An overview

Science.gov (United States)

Holmes, H. K.

1985-01-01

In the operation of the National Transonic Facility (NTF) higher Reynolds numbers are obtained on the basis of a utilization of low operational temperatures and high pressures. Liquid nitrogen is used as cryogenic medium, and temperatures in the range from -320 F to 160 F can be employed. A maximum pressure of 130 psi is specified, while the NTF design parameter for the Reynolds number is 120,000,000. In view of the new requirements regarding the measurement systems, major developments had to be undertaken in virtually all wind tunnel measurement areas and, in addition, some new measurement systems were needed. Attention is given to force measurement, pressure measurement, model attitude, model deformation, and the data system.

Chlorine measurements at the 5MV French AMS national facility ASTER: Associated external uncertainties and comparability with the 6MV DREAMS facility

Science.gov (United States)

Braucher, R.; Keddadouche, K.; Aumaître, G.; Bourlès, D. L.; Arnold, M.; Pivot, S.; Baroni, M.; Scharf, A.; Rugel, G.; Bard, E.

2018-04-01

After 6 years of 36Cl routine operation, more than 6000 unknown samples have been measured at the 5MV French accelerator mass spectrometry (AMS) national facility ASTER (CEREGE, Aix en Provence). This paper presents the long term behavior of ASTER through the analysis of the measurements of the most used chlorine standards and reference materials, KNSTD1600, SM-Cl-12 and SM-CL-13 over a 46 months' time period. Comparison of measured chlorine concentrations (both 35Cl and 36Cl) from ice samples on two AMS facilities operating at 5MV (ASTER) and 6MV (DREAMS, Helmholtz-Zentrum Dresden-Rossendorf) and normalizing to two different reference materials agree within uncertainties making both reference materials (SM-Cl-12 and KNSTD1600) suitable for 36Cl measurement at ASTER.

Measuring the quality of child health care at first-level facilities.

Science.gov (United States)

Gouws, Eleanor; Bryce, Jennifer; Pariyo, George; Armstrong Schellenberg, Joanna; Amaral, João; Habicht, Jean-Pierre

2005-08-01

Sound policy and program decisions require timely information based on valid and relevant measures. Recent findings suggest that despite the availability of effective and affordable guidelines for the management of sick children in first-level health facilities in developing countries, the quality and coverage of these services remains low. We report on the development and evaluation of a set of summary indices reflecting the quality of care received by sick children in first-level facilities. The indices were first developed through a consultative process to achieve face validity by involving technical experts and policymakers. The definition of evaluation measures for many public health programs stops at this point. We added a second phase in which standard statistical techniques were used to evaluate the content and construct validity of the indices and their reliability, drawing on data sets from the multi-country evaluation of integrated management of childhood illness (MCE) in Brazil, Tanzania and Uganda. The statistical evaluation identified important conceptual errors in the indices arising from the theory-driven expert review. The experts had combined items into inappropriate indicators resulting in summary indices that were difficult to interpret and had limited validity for program decision making. We propose a revised set of summary indices for the measurement of child health care in developing countries that is supported by both expert and statistical reviews and that led to similar programmatic insights across the three countries. We advocate increased cross-disciplinary research within public health to improve measurement approaches. Child survival policymakers, program planners and implementers can use these tools to improve their monitoring and so increase the health impact of investments in health facility care.

Performance measurements at the fast flux test facility

International Nuclear Information System (INIS)

Baumhardt, R.J.; Newland, D.J.; Praetorius, P.R.

1987-01-01

In 1984, Fast Flux Test Facility (FFTF) management recognized the need to develop a measurement system that would quantify the operational performance of the FFTF and the human resources needed to operate it. Driven by declining budgets and the need to safely manage a manpower rampdown at FFTF, an early warning system was developed. Although the initiating event for the early warning system was the need to safely manage a manpower rampdown, many related uses have evolved. The initial desired objective for the FFTF performance measurements was to ensure safety and control of key performance trends. However, the early warning system has provided a more quantitative, supportable basis upon which to make decisions. From this initial narrow focus, efforts in the FFTF plant and supporting organizations are leading to measurement of and, subsequently, improvements in productivity. Pilot projects utilizing statistical process control have started with longer range productivity improvement

Model for Predicting Traffic Signs Functional Service Life – The Republic of Croatia Case Study

Directory of Open Access Journals (Sweden)

Dario Babić

2017-06-01

Full Text Available Traffic signs are the basic elements of communication between the relevant road authorities and road users. They manage, regulate, inform and warn road users to ensure their safe movement throughout transport networks. Traffic signs must be timely visible to all traffic participants in all weather and traffic conditions in order to fulfil their function, which means they must have satisfactory retroreflection properties. This paper presents a research of the deterioration of traffic signs retroreflection. The aim of this article is to develop models that will effectively enable predicting the retroreflection of traffic signs and thus optimize the maintenance activities and replacement of road signs to increase road safety. The research included measurements of retroreflection of retroreflective material Classes I and II (white, red and blue colour and Class III (red and yellow colour. Based on the collected data from the City of Zagreb (Republic of Croatia, the authors developed the models to estimate the functional service life of certain colours and materials used to make traffic signs. Considering that the average coefficient of determination for all the models is between 0.55-0.60, they present an effective tool in the traffic sign maintenance system.

235U Holdup Measurement Program in support of facility shutdown

International Nuclear Information System (INIS)

Thomason, R.S.; Griffin, J.C.; Lien, O.G.; McElroy, R.D.

1991-01-01

In 1989, the Department of Energy directed shutdown of an enriched uranium processing facility at Savannah River Site. As part of the shutdown requirements, deinventory and cleanout of process equipment and nondestructive measurement of the remaining 235 U holdup were required. The holdup measurements had safeguards, accountability, and nuclear criticality safety significance; therefore, a technically defensible and well-documented holdup measurement program was needed. Appropriate standards were fabricated, measurement techniques were selected, and an aggressive schedule was followed. Early in the program, offsite experts reviewed the measurement program, and their recommendations were adopted. Contact and far-field methods were used for most measurements, but some process equipment required special attention. All holdup measurements were documented, and each report was subjected to internal peer review. Some measured values were checked against values obtained by other methods; agreement was generally good

Wire Scanner Beam Profile Measurements for the LANSCE Facility

Energy Technology Data Exchange (ETDEWEB)

Gilpatrick, John D. [Los Alamos National Laboratory; Gruchalla, Michael E. [Los Alamos National Laboratory; Martinez, Derwin [Los Alamos National Laboratory; Pillai, Chandra [Los Alamos National Laboratory; Rodriguez Esparza, Sergio [Los Alamos National Laboratory; Sedillo, James Daniel [Los Alamos National Laboratory; Smith, Brian G. [Los Alamos National Laboratory

2012-05-15

The Los Alamos Neutron Science Center (LANSCE) is replacing beam profile measurement systems, commonly known as Wire Scanners (WS). Using the principal of secondary electron emission, the WS measurement system moves a wire or fiber across an impinging particle beam, sampling a projected transverse-beam distribution. Because existing WS actuators and electronic components are either no longer manufactured or home-built with antiquated parts, a new WS beam profile measurement is being designed, fabricated, and tested. The goals for these new WS's include using off-the-shelf components while eliminating antiquated components, providing quick operation while allowing for easy maintainability, and tolerating external radioactivation. The WS measurement system consists of beam line actuators, a cable plant, an electronics processor chassis, and software located both in the electronics chassis (National Instruments LabVIEW) and in the Central Control Room (EPICS-based client software). This WS measurement system will measure Hand H{sup +} LANSCE-facility beams and will also measure less common beams. This paper describes these WS measurement systems.

MEASURE: An integrated data-analysis and model identification facility

Science.gov (United States)

Singh, Jaidip; Iyer, Ravi K.

1990-01-01

The first phase of the development of MEASURE, an integrated data analysis and model identification facility is described. The facility takes system activity data as input and produces as output representative behavioral models of the system in near real time. In addition a wide range of statistical characteristics of the measured system are also available. The usage of the system is illustrated on data collected via software instrumentation of a network of SUN workstations at the University of Illinois. Initially, statistical clustering is used to identify high density regions of resource-usage in a given environment. The identified regions form the states for building a state-transition model to evaluate system and program performance in real time. The model is then solved to obtain useful parameters such as the response-time distribution and the mean waiting time in each state. A graphical interface which displays the identified models and their characteristics (with real time updates) was also developed. The results provide an understanding of the resource-usage in the system under various workload conditions. This work is targeted for a testbed of UNIX workstations with the initial phase ported to SUN workstations on the NASA, Ames Research Center Advanced Automation Testbed.

Experimental testing facilities for ultrasonic measurements in heavy liquid metal

International Nuclear Information System (INIS)

Cojocaru, V.; Ionescu, V.; Nicolescu, D.; Nitu, A.

2016-01-01

The thermo-physical properties of Heavy Liquid Metals (HLM), like lead or its alloy, Lead Bismuth Eutectic (LBE), makes them attractive as coolant candidates in advanced nuclear systems. The opaqueness, that is common to all liquid metals, disables all optical methods. For this reason ultrasound waves are used in different applications in heavy liquid metal technology, for example for flow and velocity measurements and for inspection techniques. The practical use of ultrasound in heavy liquid metals still needs to be demonstrated by experiments. This goal requires heavy liquid metal technology facility especially adapted to this task. In this paper is presented an experimental testing facility for investigations of Heavy Liquid Metals acoustic properties, designed and constructed in RATEN ICN. (authors)

Automated System Calibration and Verification of the Position Measurements for the Los Alamos Isotope Production Facility and the Switchyard Kicker Facilities

Science.gov (United States)

Barr, D.; Gilpatrick, J. D.; Martinez, D.; Shurter, R. B.

2004-11-01

The Los Alamos Neutron Science Center (LANSCE) facility at Los Alamos National Laboratory has constructed both an Isotope Production Facility (IPF) and a Switchyard Kicker (XDK) as additions to the H+ and H- accelerator. These additions contain eleven Beam Position Monitors (BPMs) that measure the beam's position throughout the transport. The analog electronics within each processing module determines the beam position using the log-ratio technique. For system reliability, calibrations compensate for various temperature drifts and other imperfections in the processing electronics components. Additionally, verifications are periodically implemented by a PC running a National Instruments LabVIEW virtual instrument (VI) to verify continued system and cable integrity. The VI communicates with the processor cards via a PCI/MXI-3 VXI-crate communication module. Previously, accelerator operators performed BPM system calibrations typically once per day while beam was explicitly turned off. One of this new measurement system's unique achievements is its automated calibration and verification capability. Taking advantage of the pulsed nature of the LANSCE-facility beams, the integrated electronics hardware and VI perform calibration and verification operations between beam pulses without interrupting production beam delivery. The design, construction, and performance results of the automated calibration and verification portion of this position measurement system will be the topic of this paper.

Commissioning experience and beam physics measurements at the SwissFEL Injector test Facility

CERN Document Server

Schietinger, T.; Aiba, M.; Arsov, V.; Bettoni, S.; Beutner, B.; Calvi, M.; Craievich, P.; Dehler, M.; Frei, F.; Ganter, R.; Hauri, C. P.; Ischebeck, R.; Ivanisenko, Y.; Janousch, M.; Kaiser, M.; Keil, B.; Löhl, F.; Orlandi, G. L.; Ozkan Loch, C.; Peier, P.; Prat, E.; Raguin, J.-Y.; Reiche, S.; Schilcher, T.; Wiegand, P.; Zimoch, E.; Anicic, D.; Armstrong, D.; Baldinger, M.; Baldinger, R.; Bertrand, A.; Bitterli, K.; Bopp, M.; Brands, H.; Braun, H. H.; Brönnimann, M.; Brunnenkant, I.; Chevtsov, P.; Chrin, J.; Citterio, A.; Csatari Divall, M.; Dach, M.; Dax, A.; Ditter, R.; Divall, E.; Falone, A.; Fitze, H.; Geiselhart, C.; Guetg, M. W.; Hämmerli, F.; Hauff, A.; Heiniger, M.; Higgs, C.; Hugentobler, W.; Hunziker, S.; Janser, G.; Kalantari, B.; Kalt, R.; Kim, Y.; Koprek, W.; Korhonen, T.; Krempaska, R.; Laznovsky, M.; Lehner, S.; Le Pimpec, F.; Lippuner, T.; Lutz, H.; Mair, S.; Marcellini, F.; Marinkovic, G.; Menzel, R.; Milas, N.; Pal, T.; Pollet, P.; Portmann, W.; Rezaeizadeh, A.; Ritt, S.; Rohrer, M.; Schär, M.; Schebacher, L.; Scherrer, St.; Schlott, V.; Schmidt, T.; Schulz, L.; Smit, B.; Stadler, M.; Steffen, Bernd; Stingelin, L.; Sturzenegger, W.; Treyer, D. M.; Trisorio, A.; Tron, W.; Vicario, C.; Zennaro, R.; Zimoch, D.

2016-10-26

The SwissFEL Injector Test Facility operated at the Paul Scherrer Institute between 2010 and 2014, serving as a pilot plant and test bed for the development and realization of SwissFEL, the x-ray Free Electron Laser facility under construction at the same institute. The test facility consisted of a laser-driven rf electron gun followed by an S-band booster linac, a magnetic bunch compression chicane and a diagnostic section including atransverse deflecting rf cavity. It delivered electron bunchesof up to200 pC chargeand up to 250 MeV beam energy at a repetition rate of 10 Hz. The measurements performed at the test facility not only demonstrated the beam parameters required to drive the first stage of a FEL facility, but also led to significant advances in instrumentation technologies, beam characterization methods and the generation, transport and compression of ultralow-emittance beams. We give a comprehensive overview of the commissioning experience of the principal subsystems and the beam physics measureme...

Noble Gas Measurement and Analysis Technique for Monitoring Reprocessing Facilities

International Nuclear Information System (INIS)

William S. Charlton

1999-01-01

An environmental monitoring technique using analysis of stable noble gas isotopic ratios on-stack at a reprocessing facility was developed. This technique integrates existing technologies to strengthen safeguards at reprocessing facilities. The isotopic ratios are measured using a mass spectrometry system and are compared to a database of calculated isotopic ratios using a Bayesian data analysis method to determine specific fuel parameters (e.g., burnup, fuel type, fuel age, etc.). These inferred parameters can be used by investigators to verify operator declarations. A user-friendly software application (named NOVA) was developed for the application of this technique. NOVA included a Visual Basic user interface coupling a Bayesian data analysis procedure to a reactor physics database (calculated using the Monteburns 3.01 code system). The integrated system (mass spectrometry, reactor modeling, and data analysis) was validated using on-stack measurements during the reprocessing of target fuel from a U.S. production reactor and gas samples from the processing of EBR-II fast breeder reactor driver fuel. These measurements led to an inferred burnup that matched the declared burnup with sufficient accuracy and consistency for most safeguards applications. The NOVA code was also tested using numerous light water reactor measurements from the literature. NOVA was capable of accurately determining spent fuel type, burnup, and fuel age for these experimental results. Work should continue to demonstrate the robustness of this system for production, power, and research reactor fuels

Design and development of a 3 axis magnetic field measurement facility using Hall probe

International Nuclear Information System (INIS)

Sahoo, Shantonu; Bhattacharyya, Sumantra; Chaddha, Niraj; Mishra, Santosh Kr.; Nandy, Partha P.; Nandi, Chinmay; Bhole, Rajendra B.; Pal, Sarbajit; Pal, Gautam

2015-01-01

A 3-axis drive system has been designed and developed in-house to measure the magnetic field with positional accuracy of 0.2 mm in a volume of 1.5 x 1.3 x 0.15 cubic-meter. Hall sensor based magnetometer is used to measure the magnetic field with a precision of 100 μT(1 Gauss). The drive of each axis has linear guide and zero backlash ball screw combination to achieve accurate movement of the hall probe with positional repeatability of +/- 0.2 micron per 50 mm. The hardware and software, also developed in-house, facilitate precise probe positioning and sophisticated visualization of field map. Dedicated microcontroller based motor controllers and encoder read-out cards for each axis have been developed. The facility is integrated with a rich touch-screen based intelligent GUI for automated scanning and data acquisition. This facility can be used for accurate magnetic field mapping of big dipole magnets, solenoids, etc. The facility has been tested successfully to characterize a Dipole Magnet designed for Radioactive Ion Beam (RIB) facility. (author)

Gas temperature measurements in short duration turbomachinery test facilities

Science.gov (United States)

Cattafesta, L. N.; Epstein, A. H.

1988-07-01

Thermocouple rakes for use in short-duration turbomachinery test facilities have been developed using very fine thermocouples. Geometry variations were parametrically tested and showed that bare quartz junction supports (76 microns in diameter) yielded superior performance, and were rugged enough to survive considerable impact damage. Using very low cost signal conditioning electronics, temperature accuracies of 0.3 percent were realized yielding turbine efficiency measurements at the 1-percent level. Ongoing work to improve this accuracy is described.

Neutron dose rate at the SwissFEL injector test facility: first measurements

International Nuclear Information System (INIS)

Hohmann, E.; Frey, N.; Fuchs, A.; Harm, C.; Hoedlmoser, H.; Luescher, R.; Mayer, S.; Morath, O.; Philipp, R.; Rehmann, A.; Schietinger, T.

2014-01-01

At the Paul Scherrer Institute, the new SwissFEL Free Electron Laser facility is currently in the design phase. It is foreseen to accelerate electrons up to a maximum energy of 7 GeV with a pulsed time structure. An injector test facility is operated at a maximum energy of 300 MeV and serves as the principal test and demonstration plant for the SwissFEL project. Secondary radiation is created in unavoidable interactions of the primary beam with beamline components. The resulting ambient dose-equivalent rate due to neutrons was measured along the beamline with different commercially available survey instruments. The present study compares the readings of these neutron detectors (one of them is specifically designed for measurements in pulsed fields). The experiments were carried out in both, a normal and a diagnostic mode of operation of the injector. Measurements were taken at the SwissFEL injector test facility using three different types of commercially available survey instruments for normal and diagnostic mode of operation at different positions inside the accelerator vault. During normal operation, the doses indicated by the different instruments agree within the measurement uncertainty except for the beam dump region. There, due to its limited energy range and high sensitivity, the LB6411 shows significantly lower dose values than the other instruments. The photon background in the vault associated with each pulse causes the scintillator used by the LB6419 to saturate. As a result, only the channel using the delayed 12 C(n,p)12-reaction could be used during the measurements. The highest doses per pulse were measured next to the beam dump and the bunch compressor. For the optimisation of the accelerator, luminescent screens can be inserted into the beam path causing a dose distributed over several metres depending on the screen type. The dose arise to 40 % from neutrons with energies of >20 MeV. Although the charge of each pulse were reduced to decrease

Compendium of Neutron Beam Facilities for High Precision Nuclear Data Measurements. Annex: Individual Reports

International Nuclear Information System (INIS)

2014-07-01

The recent advances in the development of nuclear science and technology, demonstrating the globally growing economy, require highly accurate, powerful simulations and precise analysis of the experimental results. Confidence in these results is still determined by the accuracy of the atomic and nuclear input data. For studying material response, neutron beams produced from accelerators and research reactors in broad energy spectra are reliable and indispensable tools to obtain high accuracy experimental results for neutron induced reactions. The IAEA supports the accomplishment of high precision nuclear data using nuclear facilities in particular, based on particle accelerators and research reactors around the world. Such data are essential for numerous applications in various industries and research institutions, including the safety and economical operation of nuclear power plants, future fusion reactors, nuclear medicine and non-destructive testing technologies. The IAEA organized and coordinated the technical meeting Use of Neutron Beams for High Precision Nuclear Data Measurements, in Budapest, Hungary, 10–14 December 2012. The meeting was attended by participants from 25 Member States and three international organizations — the European Organization for Nuclear Research (CERN), the Joint Research Centre (JRC) and the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (OECD/NEA). The objectives of the meeting were to provide a forum to exchange existing know-how and to share the practical experiences of neutron beam facilities and associated instrumentation, with regard to the measurement of high precision nuclear data using both accelerators and research reactors. Furthermore, the present status and future developments of worldwide accelerator and research reactor based neutron beam facilities were discussed. This publication is a summary of the technical meeting and additional materials supplied by the international

Facility for the measurement of proton polarization in the range 50-70 MeV

Energy Technology Data Exchange (ETDEWEB)

Nakamura, M; Sakaguchi, H; Sakamoto, H; Ogawa, H; Cynshi, O; Kobayashi, S [Kyoto Univ. (Japan). Dept. of Physics; Kato, S [Osaka Univ., Toyonaka (Japan). Lab. of Nuclear Studies; Matsuoka, N; Hatanaka, K; Noro, T [Osaka Univ., Toyonaka (Japan). Research Center for Nuclear Physics

1983-07-01

A proton polarimetry facility based on silicon analyzers combined with high-purity germanium detectors is described. The scattering efficiency is 1.5 x 10/sup -5/ at 60 MeV with an effective analyzing power of 0.71 and the energy resolution is about 300 keV fwhm. The facility has succeeded in measuring the depolarization in p-/sup 13/C elastic scattering separated clearly from inelastic events. In order to use a silicon detector as an analyzer target, measurements of cross sections and analyzing powers have been performed at proton energies of 65, 60, 55, 50 and 45 MeV.

Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P.O.1236909. Final report

International Nuclear Information System (INIS)

Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

1978-12-01

This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design

Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P. O. 1236909. Final report

Energy Technology Data Exchange (ETDEWEB)

Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

1978-12-01

This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design.

Microdosimetric measurements in the thermal neutron irradiation facility of LENA reactor

International Nuclear Information System (INIS)

Colautti, P.; Moro, D.; Chiriotti, S.; Conte, V.; Evangelista, L.; Altieri, S.; Bortolussi, S.; Protti, N.; Postuma, I.

2014-01-01

A twin TEPC with electric-field guard tubes has been constructed to be used to characterize the BNCT field of the irradiation facility of LENA reactor. One of the two mini TEPC was doped with 50 ppm of 10 B in order to simulate the BNC events occurring in BNCT. By properly processing the two microdosimetric spectra, the gamma, neutron and BNC spectral components can be derived with good precision (∼6%). However, direct measurements of 10 B in some doped plastic samples, which were used for constructing the cathode walls, point out the scarce accuracy of the nominal 10 B concentration value. The influence of the Boral ® door, which closes the irradiation channel, has been measured. The gamma dose increases significantly (+51%) when the Boral ® door is closed. The crypt-cell-regeneration weighting function has been used to measure the quality, namely the RBE µ value, of the radiation field in different conditions. The measured RBE µ values are only partially consistent with the RBE values of other BNCT facilities. - Highlights: • A counter with two mini TEPCs, both equipped with electrical-field guard tubes, has been constructed. • The microdosimetric spectrum of the LENA-reactor irradiation vane has been studied. • The radiation-field quality (RBE) assessment confirms that the D n /D tot ratio is not an accurate parameter to characterize the BNCT radiation field

Calculation and experimental measurements in the Argonauta reactor subcritical and exponential facility

International Nuclear Information System (INIS)

Voi, Dante L.; Furieri, Rosane C.A.A.; Renke, Carlos A.C.; Bastos, Wilma S.; Ferreira, Francisco J.O.

1997-01-01

Initial measurements were performed on the exponential and subcritical facility installed on the internal thermal column of the Argonauta reactor at IEN-CNEN-Rio de Janeiro, Brazil. The measurements are include in the reactor physics experimental program for integral parameters determination, for both valid and confirmed theoretical models for reactor calculation. Gamma doses and neutron fluxes were measured with telescopic, proportional counters, wire and foil detectors. Experimental data were compared with results obtained by application of CITATION code. (author). 4 refs., 8 figs

Regulatory measures for occupational health monitoring in BARC facilities

International Nuclear Information System (INIS)

Rajdeep; Chattopadhyay, S.

2017-01-01

Bhabha Atomic Research Centre (BARC) is the premier organization actively engaged in the research and developmental activities related to nuclear science and technology for the benefit of society and the nation. BARC has various facilities like nuclear fuel fabrication facilities, research reactors, spent fuel storage facilities, nuclear fuel re-cycling facilities, radioactive waste management facilities, machining workshops and various Physics, Chemistry and Biological laboratories. In BARC, aspects related to Occupational Safety and Health (OSH) are given paramount importance. The issues related OSH are subjected to multi-tier review process. BARC Safety Council (BSC) is the apex committee in the three-tier safety and security review framework of BARC. BSC functions as regulatory body for BARC facilities. BSC is responsible for occupational safety and health of employees in BARC facilities

NGRI LAM-MC-ICPMS National Facility: reproducibility of Sr, Nd and Hf isotopic measurements

International Nuclear Information System (INIS)

Bhaskar Rao, Y.J.; Vijaya Gopal, B.; Babu, E.V.S.S.K.; Sukumaran, N.P.; Sreenivas, B.; Vijaya Kumar, T.; Krishna, K.V.S.S.; Tomson, J.K.

2009-01-01

A laboratory facility was established at the NGRI, primarily to support research in Isotope Geochemistry and Geochronology. Central to this facility are a Multiple Collector-Inductively Coupled Plasma Mass Spectrometer (MC-ICPMS: Nu Plasma HR, Nu Instruments, UK) and a 213 nm Nd-YAG UV Laser Ablation Microprobe (LAM: UP-213, New Wave Research, USA) and a clean chemistry laboratory for dissolution and chromatographic extraction of a range of elements. This article presents a summary of the accuracy and precision of MC-ICPMS Sr, Nd and Hf isotopic measurements (solution mode) on Standard Reference Materials: SRM-987, JNd i and JMC-475 respectively, measured between October 2007 and August 2009

Atmospheric Radiation Measurement Climate Research Facility (ACRF) Annual Report 2007

Energy Technology Data Exchange (ETDEWEB)

LR Roeder

2007-12-01

This annual report describes the purpose and structure of the program, and presents key accomplishments in 2007. Notable achievements include: • Successful review of the ACRF as a user facility by the DOE Biological and Environmental Research Advisory Committee. The subcommittee reinforced the importance of the scientific impacts of this facility, and its value for the international research community. • Leadership of the Cloud Land Surface Interaction Campaign. This multi-agency, interdisciplinary field campaign involved enhanced surface instrumentation at the ACRF Southern Great Plains site and, in concert with the Cumulus Humilis Aerosol Processing Study sponsored by the DOE Atmospheric Science Program, coordination of nine aircraft through the ARM Aerial Vehicles Program. • Successful deployment of the ARM Mobile Facility in Germany, including hosting nearly a dozen guest instruments and drawing almost 5000 visitors to the site. • Key advancements in the representation of radiative transfer in weather forecast models from the European Centre for Medium-Range Weather Forecasts. • Development of several new enhanced data sets, ranging from best estimate surface radiation measurements from multiple sensors at all ACRF sites to the extension of time-height cloud occurrence profiles to Niamey, Niger, Africa. • Publication of three research papers in a single issue (February 2007) of the Bulletin of the American Meteorological Society.

Emission Spectroscopy and Radiometric Measurements in the NASA Ames IHF Arc Jet Facility

Science.gov (United States)

Winter, Michael W.; Raiche, George A.; Prabhu, Dinesh K.

2012-01-01

Plasma diagnostic measurement campaigns in the NASA Ames Interaction Heating Facility (IHF) have been conducted over the last several years with a view towards characterizing the flow in the arc jet facility by providing data necessary for modeling and simulation. Optical emission spectroscopy has been used in the plenum and in the free jet of the nozzle. Radiation incident over a probe surface has also been measured using radiometry. Plenum measurements have shown distinct radial profiles of temperature over a range of operating conditions. For cases where large amounts of cold air are added radially to the main arc-heated stream, the temperature profiles are higher by as much as 1500 K than the profiles assumed in flow simulations. Optical measurements perpendicular to the flow direction in the free jet showed significant contributions to the molecule emission through inverse pre-dissociation, thus allowing determination of atom number densities from molecular emission. This has been preliminarily demonstrated with the N2 1st Positive System. Despite the use of older rate coefficients, the resulting atom densities are reasonable and surprisingly close to flow predictions.

Measuring Athletic Facility Managers’ Knowledge Of Access And The Americans With Disabilities Act: A Pilot Study

OpenAIRE

Joshua R. Pate; Steven N. Waller

2012-01-01

The purpose of this exploratory research was measuring facility managers’ knowledge of the Americans with Disabilities Act (ADA), and it may assist in decreasing the gap in knowledge between facility managers and the needs of people with physical disabilities. An existing survey examining ADA knowledge was slightly modified and used for this study. Four athletic facility managers from universities in a large Bowl Championship Series conference participated in the study. Results provided a pre...

Measurements of the ionising radiation level at a nuclear medicine facility performing PET/CT examinations

International Nuclear Information System (INIS)

Tulik, P.; Kowalska, M.; Golnik, N.; Budzynska, A.; Dziuk, M.

2017-01-01

This paper presents the results of radiation level measurements at workplaces in a nuclear medicine facility performing PET/ CT examinations. This study meticulously determines the staff radiation exposure in a PET/CT facility by tracking the path of patient movement. The measurements of the instantaneous radiation exposure were performed using an electronic radiometer with a proportional counter that was equipped with the option of recording the results on line. The measurements allowed for visualisation of the staff's instantaneous exposure caused by a patient walking through the department after the administration of "1"8F-FDG. An estimation of low doses associated with each working step and the exposure during a routine day in the department was possible. The measurements were completed by determining the average radiation level using highly sensitive thermoluminescent detectors. (authors)

Measurement of neutron total cross-sections for {sup nat}Dy at Pohang Neutron Facility

Energy Technology Data Exchange (ETDEWEB)

Shin, S. G.; Kye, Y. U.; Shvetsov, Valery; Cho, M. H. [POSTECH, Pohang (Korea, Republic of); Namkung, W.; Cho, M. H. [Pohang Accelerator Laboratory, Pohang (Korea, Republic of); Kim, G. N. [Kyungpook National Univ., Daegu (Korea, Republic of); Lee, M. W. [Dongnam Inst. of radiological and Medical Science, Busan (Korea, Republic of)

2013-05-15

There are few measurements for Dy below 100 eV. Moreover, there exist discrepancies among the measurements. In the present work, the total neutron cross-sections for {sup nat}Dy were measured by using the time-of-flight (TOF) method at the Pohang Neutron Facility (PNF). The PNF consists of an electron linac, a water-cooled Ta target, and an 11-m-long TOF path. The characteristics of PNF are described elsewhere. We also briefly discuss the future plan to verify our experimental result. We have measured the total neutron cross-sections of {sup nat}Dy in the neutron energy region from 0.1 eV to 100 eV with the TOF method at the Po hang Neutron Facility. The present result is in good agreement with the previous data and the evaluated data in ENDF/B-VI. We would like to get resonance parameters by using SAMMY or REFIT codes.

Safety measures to address the year 2000 issue at medical facilities which use radiation generators and radioactive materials

International Nuclear Information System (INIS)

1999-03-01

In resolution GC(42)/RES/11 on 'Measures to Address the Year 2000 (Y2K) Issue', adopted on 25 September 1998, the General Conference of the International Atomic Energy Agency (IAEA) - inter alia - urged Member States 'to share information with the Secretariat regarding diagnostic and corrective actions being planned or implemented by operating and regulatory organizations at their ... medical facilities which use radioactive materials to make those facilities Year 2000 ready', encouraged the Secretariat 'within existing resources to act as a clearing-house and central point of contact for Member States to exchange information regarding diagnostic and remediation actions being taken at ... medical facilities which use radioactive materials to make these facilities Year 2000 ready', urged the Secretariat 'to handle the information provided by Member States carefully' and requested the Director General to report to it at its next (1999) regular session on the implementation of that resolution. The IAEA Secretariat convened a group of consultants who met in Vienna from 14 to 18 December 1998 and produced this report. The consultants decided that the report should cover not just 'medical facilities which use radioactive materials' but also medical facilities which, while perhaps not using radioactive materials, use ionizing radiation produced by radiation generators such as accelerators. The reports issued together are: Achieving Year 2000 Readiness: Basic Processes; Safety Measures to Address the Year 2000 Issue at Medical Facilities Which Use Radiation Generators and Radioactive Materials; and Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management Facilities. This report addresses means of dealing with the Y2K problem at medical facilities which use radiation generators and radioactive materials

Measurements and FLUKA simulations of bismuth and aluminium activation at the CERN Shielding Benchmark Facility (CSBF)

Science.gov (United States)

Iliopoulou, E.; Bamidis, P.; Brugger, M.; Froeschl, R.; Infantino, A.; Kajimoto, T.; Nakao, N.; Roesler, S.; Sanami, T.; Siountas, A.

2018-03-01

The CERN High Energy AcceleRator Mixed field facility (CHARM) is located in the CERN Proton Synchrotron (PS) East Experimental Area. The facility receives a pulsed proton beam from the CERN PS with a beam momentum of 24 GeV/c with 5 ṡ1011 protons per pulse with a pulse length of 350 ms and with a maximum average beam intensity of 6.7 ṡ1010 p/s that then impacts on the CHARM target. The shielding of the CHARM facility also includes the CERN Shielding Benchmark Facility (CSBF) situated laterally above the target. This facility consists of 80 cm of cast iron and 360 cm of concrete with barite concrete in some places. Activation samples of bismuth and aluminium were placed in the CSBF and in the CHARM access corridor in July 2015. Monte Carlo simulations with the FLUKA code have been performed to estimate the specific production yields for these samples. The results estimated by FLUKA Monte Carlo simulations are compared to activation measurements of these samples. The comparison between FLUKA simulations and the measured values from γ-spectrometry gives an agreement better than a factor of 2.

Relative risk measure suitable for comparison of design alternatives of interim spent nuclear fuel storage facility

International Nuclear Information System (INIS)

Ferjencik, M.

1997-01-01

Accessible reports on risk assessment of interim spent nuclear fuel storage facilities presume that only releases of radioactive substances represent undesired consequences. However, only certain part of the undesired consequences is represented by them. Many other events are connected with safety and are able to cause losses to the operating company. The following two presumptions are pronounced based on this. 1. Any event causing a disturbance of a safety function of the storage facility is an incident event. 2. Any disturbance of a safety function is an undesired consequence. If the facility safety functions are identified and if the severity of their disturbances is quantified, then it is possible to combine consequence severity quantifications and event frequencies into a risk measure. Construction and application of such a risk measure is described in this paper. The measure is shown to be a tool suitable for comparison of interim storage technology design alternatives. (author)

The Full Aperture Backscatter Station Measurement System on the National Ignition Facility

International Nuclear Information System (INIS)

Bower, D; McCarville, T; Alvarez, S; Ault, L; Brown, M; Chrisp, M; Damian, C; DeHope, W; Froula, D; Glenzer, S; Grace, S; Gu, K; Holdener, F; Huffer, C; Kamperschroer, J; Kelleher, T; Kimbrough, J

2004-01-01

A Full Aperture Backscatter Station (FABS) target diagnostic has been activated on the first four beams of the National Ignition Facility (NIF). Backscattered light from the target propagates back down the beam path into the FABS diagnostic system. FABS measures both stimulated Brillouin scattering (SBS) and stimulated Raman scattering (SRS) with a suite of measurement instruments. Digital cameras and spectrometers record spectrally resolved energy for both P and S polarized light. Streaked spectrometers measure the spectral and temporal behavior of the backscattered light. Calorimeters and fast photodetectors measure the integrated energy and temporal behavior of the light, respectively. This paper provides an overview of the FABS measurements system and detailed descriptions of the diagnostic instruments and the optical path

Cryogenic system for the HERA magnet measurement facility

International Nuclear Information System (INIS)

Barton, H.R. Jr.; Clausen, M.; Kebler, G.

1986-01-01

This paper describes the design for a helium, cryogenic distribution system that allows independent operation and testing of superconducting magnets of the HERA project before they are installed in the 6-km ring tunnel. The 820-GeV proton storage ring of HERA will contain approximately 650 magnets having superconducting coils which are clamped by aluminum/stainless-steel collars and surrounded by a yoke of magnetic iron at liquid helium temperature. When the magnets arive at DESY from the manufacture, each magnet will be individually tested at helium operating conditions in the magnet measurement facility to insure the quality of the magnetic characteristics and the cryogenic performance. The capabilities of the cryogenic system and the schedule for magnet testing are discussed

Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1-December 31, 2016

Energy Technology Data Exchange (ETDEWEB)

Voyles, Jimmy [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-01-01

Individual datastreams from instrumentation at the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research observatories (sites) are collected and routed to the ARM Data Center (ADC). The Data Management Facility (DMF), a component of the ADC, executes datastream processing in near-real time. Processed data are then delivered approximately daily to the ARM Data Archive, also a component of the ADC, where they are made freely available to the research community. For each instrument, ARM calculates the ratio of the actual number of processed data records received daily at the ARM Data Archive to the expected number of data records. DOE requires national user facilities to report time-based operating data.

Results of measurements of particulate matter concentrations inside a pig fattening facility

Directory of Open Access Journals (Sweden)

Ulens, T.

2016-01-01

Full Text Available Description of the subject. This research note discusses the results of measurements of particulate matter concentrations inside a pig fattening facility. Objectives. The objectives of the present study were to investigate the correlations between the different size fractions of indoor particulate matter (PM inside a pig fattening facility and to investigate the evolution of particle size distribution (PSD through a fattening period and between two housing systems and two cleaning protocols. Method. Data from two consecutive fattening periods in a commercial pig barn were used. Results. Very high correlations were found between PM10 and PM2.5 indoor concentrations. Depending on the measuring instrument, high or low correlations were found between PM1 and PM10 or PM2.5 indoor concentrations. No differences in PSD could be found between the two housing systems or the two cleaning protocols. Conclusions. The results from the present study showed high correlations between the indoor concentrations of PM10 and PM2.5. In the present study, no differences in PSD were found.

Force Measurement Improvements to the National Transonic Facility Sidewall Model Support System

Science.gov (United States)

Goodliff, Scott L.; Balakrishna, Sundareswara; Butler, David; Cagle, C. Mark; Chan, David; Jones, Gregory S.; Milholen, William E., II

2016-01-01

The National Transonic Facility is a transonic pressurized cryogenic facility. The development of the high Reynolds number semi-span capability has advanced over the years to include transonic active flow control and powered testing using the sidewall model support system. While this system can be used in total temperatures down to -250Â F for conventional unpowered configurations, it is limited to temperatures above -60Â F when used with powered models that require the use of the high-pressure air delivery system. Thermal instabilities and non-repeatable mechanical arrangements revealed several data quality shortfalls by the force and moment measurement system. Recent modifications to the balance cavity recirculation system have improved the temperature stability of the balance and metric model-to-balance hardware. Changes to the mechanical assembly of the high-pressure air delivery system, particularly hardware that interfaces directly with the model and balance, have improved the repeatability of the force and moment measurement system. Drag comparisons with the high-pressure air system removed will also be presented in this paper.

International measures needed to protect metal recycling facilities from radioactive materials

International Nuclear Information System (INIS)

Mattia, M.; Wiener, R.

1999-01-01

. The government of every country that licences the use of radioactive material should institute a program to determine both the location of every known source and the effectiveness of current controls over that source. (ii) Control of orphaned material. Each government should institute a program for the safe removal and control of orphaned radioactive sources and material without penalty to the individual that has unintentionally received it. (iii) Transportation rules. International agreements should be developed that allow discovered radioactive material to be easily yet safely transported to either its point of origin or to a facility for its safe disposal. (iv) Registry of events. An international mechanism should be developed for the documentation and reporting of radiation related incidents and the discovery of potentially orphaned radioactive sources and material. (v) Universal measurements. There are several highly technical ways to describe radioactivity. None of these can be easily understood by the individuals who may encounter this material. The international community should agree on how radioactivity will be measured and qualified in a manner that is easily understood by all individuals. (vi) Technology sharing. As new, user-friendly technology is being advanced, the international community should keep track of such advances, share this information, as well as fund the development of technology that will accurately and consistently identify radioactive material that could be found in all forms of metal or containers. (author)

Aerial 3D display by use of a 3D-shaped screen with aerial imaging by retro-reflection (AIRR)

Science.gov (United States)

Kurokawa, Nao; Ito, Shusei; Yamamoto, Hirotsugu

2017-06-01

The purpose of this paper is to realize an aerial 3D display. We design optical system that employs a projector below a retro-reflector and a 3D-shaped screen. A floating 3D image is formed with aerial imaging by retro-reflection (AIRR). Our proposed system is composed of a 3D-shaped screen, a projector, a quarter-wave retarder, a retro-reflector, and a reflective polarizer. Because AIRR forms aerial images that are plane-symmetric of the light sources regarding the reflective polarizer, the shape of the 3D screen is inverted from a desired aerial 3D image. In order to expand viewing angle, the 3D-shaped screen is surrounded by a retro-reflector. In order to separate the aerial image from reflected lights on the retro- reflector surface, the retro-reflector is tilted by 30 degrees. A projector is located below the retro-reflector at the same height of the 3D-shaped screen. The optical axis of the projector is orthogonal to the 3D-shaped screen. Scattered light on the 3D-shaped screen forms the aerial 3D image. In order to demonstrate the proposed optical design, a corner-cube-shaped screen is used for the 3D-shaped screen. Thus, the aerial 3D image is a cube that is floating above the reflective polarizer. For example, an aerial green cube is formed by projecting a calculated image on the 3D-shaped screen. The green cube image is digitally inverted in depth by our developed software. Thus, we have succeeded in forming aerial 3D image with our designed optical system.

Radioactivity measuring and control method and the system for facility of nuclear power plant

International Nuclear Information System (INIS)

Urata, Megumu.

1996-01-01

In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

Radioactivity measuring and control method and the system for facility of nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Urata, Megumu

1996-12-03

In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

Comparison of Antenna Measurement Facilities with the DTU-ESA 12 GHz Validation Standard Antenna within the EU Antenna Centre of Excellence

DEFF Research Database (Denmark)

Pivnenko, Sergey; Pallesen, Janus Engberg; Breinbjerg, Olav

2009-01-01

The primary objective of many antenna measurement facilities is to provide a specified high accuracy of the measured data. The validation of an antenna measurement facility is the process of proving that such a specified accuracy can be achieved. Since this constitutes a very challenging task, an...

A new and inexpensive temperature-measuring system. Application to photovoltaic solar facilities

Energy Technology Data Exchange (ETDEWEB)

Bohorquez, Miguel Angel Martinez; Enrique Gomez, Juan Manuel; Andujar Marquez, Jose Manuel [Departamento de Ingenieria Electronica, de Sistemas Informaticos y Automatica, Universidad de Huelva, Carretera Huelva - Palos de la, Frontera S/N, 21819 Huelva (Spain)

2009-06-15

This article presents the design, construction and testing of a new and inexpensive digital sensor-based temperature-measuring system, whose principal characteristics are: precision, ease of connection, immunity to noise, remote operation and easy scaling, and all this at a very low cost. This new digital sensor-based measuring system overcomes the traditional problems of digital measuring sensors, offering characteristics similar to Pt100-based measuring systems, and therefore can be used in any installation where reliable temperature measurement is necessary. It is especially suitable for installations where cost is a deciding factor in the choice of measuring system. It presents a practical application of the developed instrumentation system for use in photovoltaic solar facilities. This new temperature-measuring system has been registered in the Spanish Patent and Trademark Office with the number P200803364. (author)

Tuberculosis in healthcare workers and infection control measures at primary healthcare facilities in South Africa.

Science.gov (United States)

Claassens, Mareli M; van Schalkwyk, Cari; du Toit, Elizabeth; Roest, Eline; Lombard, Carl J; Enarson, Donald A; Beyers, Nulda; Borgdorff, Martien W

2013-01-01

Challenges exist regarding TB infection control and TB in hospital-based healthcare workers in South Africa. However, few studies report on TB in non-hospital based healthcare workers such as primary or community healthcare workers. Our objectives were to investigate the implementation of TB infection control measures at primary healthcare facilities, the smear positive TB incidence rate amongst primary healthcare workers and the association between TB infection control measures and all types of TB in healthcare workers. One hundred and thirty three primary healthcare facilities were visited in five provinces of South Africa in 2009. At each facility, a TB infection control audit and facility questionnaire were completed. The number of healthcare workers who had had TB during the past three years was obtained. The standardised incidence ratio of smear positive TB in primary healthcare workers indicated an incidence rate of more than double that of the general population. In a univariable logistic regression, the infection control audit score was significantly associated with reported cases of TB in healthcare workers (OR=1.04, 95%CI 1.01-1.08, p=0.02) as was the number of staff (OR=3.78, 95%CI 1.77-8.08). In the multivariable analysis, the number of staff remained significantly associated with TB in healthcare workers (OR=3.33, 95%CI 1.37-8.08). The high rate of TB in healthcare workers suggests a substantial nosocomial transmission risk, but the infection control audit tool which was used did not perform adequately as a measure of this risk. Infection control measures should be monitored by validated tools developed and tested locally. Different strategies, such as routine surveillance systems, could be used to evaluate the burden of TB in healthcare workers in order to calculate TB incidence, monitor trends and implement interventions to decrease occupational TB.

Tuberculosis in Healthcare Workers and Infection Control Measures at Primary Healthcare Facilities in South Africa

Science.gov (United States)

Claassens, Mareli M.; van Schalkwyk, Cari; du Toit, Elizabeth; Roest, Eline; Lombard, Carl J.; Enarson, Donald A.; Beyers, Nulda; Borgdorff, Martien W.

2013-01-01

Background Challenges exist regarding TB infection control and TB in hospital-based healthcare workers in South Africa. However, few studies report on TB in non-hospital based healthcare workers such as primary or community healthcare workers. Our objectives were to investigate the implementation of TB infection control measures at primary healthcare facilities, the smear positive TB incidence rate amongst primary healthcare workers and the association between TB infection control measures and all types of TB in healthcare workers. Methods One hundred and thirty three primary healthcare facilities were visited in five provinces of South Africa in 2009. At each facility, a TB infection control audit and facility questionnaire were completed. The number of healthcare workers who had had TB during the past three years was obtained. Results The standardised incidence ratio of smear positive TB in primary healthcare workers indicated an incidence rate of more than double that of the general population. In a univariable logistic regression, the infection control audit score was significantly associated with reported cases of TB in healthcare workers (OR=1.04, 95%CI 1.01-1.08, p=0.02) as was the number of staff (OR=3.78, 95%CI 1.77-8.08). In the multivariable analysis, the number of staff remained significantly associated with TB in healthcare workers (OR=3.33, 95%CI 1.37-8.08). Conclusion The high rate of TB in healthcare workers suggests a substantial nosocomial transmission risk, but the infection control audit tool which was used did not perform adequately as a measure of this risk. Infection control measures should be monitored by validated tools developed and tested locally. Different strategies, such as routine surveillance systems, could be used to evaluate the burden of TB in healthcare workers in order to calculate TB incidence, monitor trends and implement interventions to decrease occupational TB. PMID:24098461

Measurements in support of a neutron radiography facility for the SLOWPOKE-2 at RMC

International Nuclear Information System (INIS)

Lewis, W.J.; Andrews, W.S.; Bennett, L.G.I.; Beeley, P.A.; Royal Military Coll. of Canada, Kingston, ON

1990-01-01

The feasibility of using the small (20 kWh) SLOWPOKE-2 research reactor for neutron radiography has been investigated. Although designed primarily for neutron activation analysis (NAA) and radioisotope production, the SLOWPOKE-2 at RMC was installed with a thermal column of heavy water in a sector of the water gap between the beryllium reflector and the reactor container. The thermal-neutron flux in the reactor pool, just beyond the reactor container, has been measured to be a factor of 2.7 higher than in similar locations remote from the thermal column. Placed in this location was a prototype neutron radiography facility, consisting of a beam tube (or collimator), vertically tangential to the reactor core, and a beam stop. Once the feasibility of using a SLOWPOKE-2 for neutron radiography was demonstrated, subsequent investigations were carried out to optimize the quality of the obtainable radiographs. Both neutron radiographic and thermal-neutron flux measurements were undertaken to determine the optimum placement and arrangement of the beam tube. A Category III (as defined by the ASTM Standard E545-86) neutron radiography facility was obtained, although Category I or II were indicated as feasible. Based on this prototype design and experimentation, a permanent neutron radiography facility will be installed. The design calculations have been finalized, construction blueprints have been prepared, and work is proceeding with the construction, installation and commissioning of the facility. (orig.)

Atmospheric Radiation Measurement Climate Research Facility (ACRF) Annual Report 2008

Energy Technology Data Exchange (ETDEWEB)

LR Roeder

2008-12-01

The Importance of Clouds and Radiation for Climate Change: The Earth’s surface temperature is determined by the balance between incoming solar radiation and thermal (or infrared) radiation emitted by the Earth back to space. Changes in atmospheric composition, including greenhouse gases, clouds, and aerosols, can alter this balance and produce significant climate change. Global climate models (GCMs) are the primary tool for quantifying future climate change; however, there remain significant uncertainties in the GCM treatment of clouds, aerosol, and their effects on the Earth’s energy balance. In 1989, the U.S. Department of Energy (DOE) Office of Science created the Atmospheric Radiation Measurement (ARM) Program to address scientific uncertainties related to global climate change, with a specific focus on the crucial role of clouds and their influence on the transfer of radiation in the atmosphere. To reduce these scientific uncertainties, the ARM Program uses a unique twopronged approach: • The ARM Climate Research Facility, a scientific user facility for obtaining long-term measurements of radiative fluxes, cloud and aerosol properties, and related atmospheric characteristics in diverse climate regimes; and • The ARM Science Program, focused on the analysis of ACRF and other data to address climate science issues associated with clouds, aerosols, and radiation, and to improve GCMs. This report provides an overview of each of these components and a sample of achievements for each in fiscal year (FY) 2008.

Activity measurements at a waste volume reduction facility

International Nuclear Information System (INIS)

Richardson, J.; Lee, D.A.

1979-01-01

The monitoring program for Ontario Hydro's radioactive waste management site will be described, several aspects of which will be discussed in detail. The program at this facility includes categorization, volume reduction processing, and storage of solid radioactive wastes from nuclear generating stations of the CANDU type. At the present time, two types of volume reduction process are in operation - incineration and compaction. Following categorization and processing, wastes are stored in in-ground concrete trenches or tile-holes, or in above-ground quadricells. The monitoring program is divided into three areas: public safety, worker safety, and structural integrity. Development projects with respect to the monitoring program have been undertaken to achieve activity accounting for the total waste management program. In particular, a field measurement for the radioactivity content of radioactive ash containers and compacted waste drums

Dosimeter calibration facilities and methods at the Radiation Measurement Laboratory of the Centre d'etudes nucleaires, Grenoble

International Nuclear Information System (INIS)

Choudens, H. de; Herbaut, Y.; Haddad, A.; Giroux, J.; Rouillon, J.; CEA Centre d'Etudes Nucleaires de Grenoble, 38

1975-01-01

At the Centre d'etudes nucleaires, Grenoble, the Radiation Measurement Laboratory, which forms part of the Environmental Protection and Research Department, serves the entire Centre for purposes of dosimetry and the calibration of dose meters. The needs of radiation protection are such that one must have facilities for checking periodically the calibration of radiation-monitoring instruments and developing special dosimetry techniques. It was thought a good idea to arrange for the dosimetry and radiation protection team to assist other groups working at the Centre - in particular, the staff of the biology and radiobiology laboratories - and also bodies outside the framework of the French Commissariat a l'energie atomique. Thus, technical collaboration has been established with, for example, Grenoble's Centre hospitalier universitaire (university clinic), which makes use of the facilities and skills available at the Radiation Measurement Laboratory for solving special dosimetry problems. With the Laboratory's facilities it is possible to calibrate dose meters for gamma, beta and neutron measurements

Atmospheric Radiation Measurement Program facilities newsletter, January 2001.; TOPICAL

International Nuclear Information System (INIS)

Holdridge, D. J.

2001-01-01

In the realm of global climate modeling, numerous variables affect the state of the atmosphere and climate. One important area is soil moisture and temperature. The ARM Program uses several types of instruments to gather soil moisture information. An example is the soil water and temperature system (SWATS). A SWATS is located at each of 21 extended facility sites within the CART site boundary. Each system is configured to measure soil moisture and temperature at eight distinct subsurface levels. A special set of probes used in the SWATS measures soil temperature, soil-water potential, and volumetric water content. Sensors are placed at eight different depths below the soil surface, starting at approximately 5 cm (2 in.) below the surface and ending as deep as 175 cm (69 in.). Each site has two identical sets of probes buried 1 m (3.3 ft) apart, to yield duplicate measurements as a quality control measure. At some sites, impenetrable soil or rock layers prevented installation of probes at the deeper levels. The sensors are connected to an electronic data logger that collects and stores the data. Communication equipment transfers data from the site. All of the electronic equipment is housed in a weatherproof enclosure mounted on a concrete slab

Inpatient Psychiatric Facility Quality Measure Data – by State

Data.gov (United States)

U.S. Department of Health & Human Services — Psychiatric facilities that are eligible for the Inpatient Psychiatric Facility Quality Reporting (IPFQR) program are required to meet all program requirements,...

Expanding the suite of measures of gender-based discrimination: gender differences in ablution facilities in South Africa

Directory of Open Access Journals (Sweden)

Renier Steyn

2012-06-01

Full Text Available International treaties, national legislation and local by-laws all advocate the equal treatment of men and women, but claims of gender-based discrimination continue. Indicators of discrimination against women, including employment ratios and differences in income, show that there have been considerable gains in the recent past. These measures are, however, often biased. In this study a different, specific and concrete method of describing and detecting discrimination is presented, namely the difference in the number of ablution facilities provided for each gender group in public spaces. Ablution facilities at airports, train stations and shopping centres in four major South African cities (N=128 were inspected. Medium to large differences in the respective number of facilities were found (eta2 .05 to .13, with women receiving fewer service facilities than men. These results suggest that, despite progressive legislation and vigorous affirmative action in South Africa, local women are still being discriminated against on a very concrete, visible level. The effectiveness of the measurement tool is also discussed.

Regulation for delivery of subsidies for urgent safety measures for atomic power generating facilities

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law for the proper enforcement of subsidy budgets and the ordinance for the execution of this law and to practice these provisions. It is applied to the delivery of subsidies for the expenses of the measures taken beforehand for the security of inhabitants in the surrounding areas of atomic power generating facilities in the emergency time of hazard or the danger of the occurrence of hazard by such facilities. Basic terms are defined, such as atomic power generating facilities and others, prefecture concerned, cities, towns and villages concerned, emergency communication network arrangement business, emergency medical facility arrangement business, business of holding hazard prevention course and expected date of beginning operation. Directors of ministries and agencies concerned deliver, if necessary, to prefectures concerned subsidies for all or a part of the expenses needed for the businesses of emergency communication network arrangement, emergency medical facility arrangement and holding hazard prevention course. The terms of delivery and the amounts of subsidies vary according to the kinds of businesses. Prefectures which intend to apply for the delivery of subsidies shall file to the director of the ministry or agency concerned the specified application attaching the operation plans of businesses and the general explanation of atomic power generating facilities, etc. The decision and conditions of delivery, reports on the situations and results of businesses and other related matters are defined, respectively. (Okada, K.)

Requirements for facilities and measurement techniques to support CFD development for hypersonic aircraft

Science.gov (United States)

Sellers, William L., III; Dwoyer, Douglas L.

1992-01-01

The design of a hypersonic aircraft poses unique challenges to the engineering community. Problems with duplicating flight conditions in ground based facilities have made performance predictions risky. Computational fluid dynamics (CFD) has been proposed as an additional means of providing design data. At the present time, CFD codes are being validated based on sparse experimental data and then used to predict performance at flight conditions with generally unknown levels of uncertainty. This paper will discuss the facility and measurement techniques that are required to support CFD development for the design of hypersonic aircraft. Illustrations are given of recent success in combining experimental and direct numerical simulation in CFD model development and validation for hypersonic perfect gas flows.

The measurement programme at the neutron time-of-flight facility n_TOF at CERN

Directory of Open Access Journals (Sweden)

Gunsing F.

2017-01-01

Full Text Available Neutron-induced reaction cross sections are important for a wide variety of research fields ranging from the study of nuclear level densities, nucleosynthesis to applications of nuclear technology like design, and criticality and safety assessment of existing and future nuclear reactors, radiation dosimetry, medical applications, nuclear waste transmutation, accelerator-driven systems and fuel cycle investigations. Simulations and calculations of nuclear technology applications largely rely on evaluated nuclear data libraries. The evaluations in these libraries are based both on experimental data and theoretical models. CERN’s neutron time-of-flight facility n_TOF has produced a considerable amount of experimental data since it has become fully operational with the start of its scientific measurement programme in 2001. While for a long period a single measurement station (EAR1 located at 185 m from the neutron production target was available, the construction of a second beam line at 20 m (EAR2 in 2014 has substantially increased the measurement capabilities of the facility. An outline of the experimental nuclear data activities at n_TOF will be presented.

Design and construction of a cryogenic facility providing absolute measurements of radon 222 activity for developing a primary standard

International Nuclear Information System (INIS)

Picolo, Jean-Louis

1995-06-01

Radon 222 metrology is required to obtain higher accuracy in assessing human health risks from exposure to natural radiation. This paper describes the development of a cryogenic facility that allows absolute measurements of radon 222 in order to obtain a primary standard. The method selected is the condensation of a radon 222 sample on a geometrically defined cold surface with a constant, well known and adjustable temperature and facing an alpha particles detector. Counting of the alpha particles reaching the detector and the precisely known detection geometry provide an absolute measurement of the source activity. After describing the cryogenic facility, the measurement accuracy and precision are discussed and a comparison made with other measurement systems. The relative uncertainty is below 1 pc (1 σ). The facility can also be used to improve our knowledge of the nuclear properties of radon 222 and to produce secondary standards. (author) [fr

Secondary gamma-ray skyshine from 14 MeV Neutron Source Facility (OKTAVIAN). Comparison of measurement with its simulation

Energy Technology Data Exchange (ETDEWEB)

Morotomi, Ryutaro; Kondo, Tetsuo; Murata, Isao; Yoshida, Shigeo; Takahashi, Akito [Osaka Univ., Department of Nuclear Engineering, Suita, Osaka (Japan); Yamamoto, Takayoshi [Osaka Univ., Radio Isotope Research Center, Suita, Osaka (Japan)

2000-03-01

Measurement of secondary gamma-ray skyshine was performed at the Intense 14 MeV Neutron Source Facility (OKTAVIAN) of Osaka University with NaI and Hp-Ge detectors. From the result of measurements, some mechanism of secondary gamma-ray skyshine from 14 MeV neutron source facility was found out. The analysis of the measured result were carried out with MCNP-4B for four nuclear data files of JENDL-3.2, JENDL-F.F., FENDL-2, and ENDF/B-VI. It was confirmed that all the nuclear data are fairly reliable for calculations of secondary gamma-ray skyshine. (author)

Magnetic Measurement System for the NSLS Superconducting Undulator Vertical Test Facility

CERN Document Server

Harder, David; Skaritka, John

2005-01-01

One of the challenges of small-gap superconducting undulators is measurement of magnetic fields within the cold bore to characterize the device performance and to determine magnetic field errors for correction or shimming, as is done for room-temperature undulators. Both detailed field maps and integrated field measurements are required. This paper describes a 6-element, cryogenic Hall probe field mapper for the NSLS Superconducting Undulator Vertical Test Facility (VTF). The probe is designed to work in an aperture only 3 mm high. A pulsed-wire insert is also being developed, for visualization of the trajectory, for locating steering errors and for determining integrated multi-pole errors. The pulsed-wire insert will be interchangeable with the Hall probe mapper. The VTF and the magnetic measurement systems can accommodate undulators up to 0.4 m in length.

Dissemination of data measured at the CERN n_TOF facility

Science.gov (United States)

Dupont, E.; Otuka, N.; Cabellos, O.; Aberle, O.; Aerts, G.; Altstadt, S.; Alvarez, H.; Alvarez-Velarde, F.; Andriamonje, S.; Andrzejewski, J.; Audouin, L.; Bacak, M.; Badurek, G.; Balibrea, J.; Barbagallo, M.; Barros, S.; Baumann, P.; Bécares, V.; Bečvář, F.; Beinrucker, C.; Belloni, F.; Berthier, B.; Berthoumieux, E.; Billowes, J.; Boccone, V.; Bosnar, D.; Brown, A.; Brugger, M.; Caamaño, M.; Calviani, M.; Calviño, F.; Cano-Ott, D.; Capote, R.; Cardella, R.; Carrapiço, C.; Casanovas, A.; Castelluccio, D. M.; Cennini, P.; Cerutti, F.; Chen, Y. H.; Chiaveri, E.; Chin, M.; Colonna, N.; Cortés, G.; Cortés-Giraldo, M. A.; Cosentino, L.; Couture, A.; Cox, J.; Damone, L. A.; David, S.; Deo, K.; Diakaki, M.; Dillmann, I.; Domingo-Pardo, C.; Dressler, R.; Dridi, W.; Duran, I.; Eleftheriadis, C.; Embid-Segura, M.; Fernández-Domínguez, B.; Ferrant, L.; Ferrari, A.; Ferreira, P.; Finocchiaro, P.; Fraval, K.; Frost, R. J. W.; Fujii, K.; Furman, W.; Ganesan, S.; Garcia, A. R.; Gawlik, A.; Gheorghe, I.; Gilardoni, S.; Giubrone, G.; Glodariu, T.; Göbel, K.; Gomez-Hornillos, M. B.; Goncalves, I. F.; Gonzalez-Romero, E.; Goverdovski, A.; Gramegna, F.; Griesmayer, E.; Guerrero, C.; Gunsing, F.; Gurusamy, P.; Haight, R.; Harada, H.; Heftrich, T.; Heil, M.; Heinitz, S.; Hernández-Prieto, A.; Heyse, J.; Igashira, M.; Isaev, S.; Jenkins, D. G.; Jericha, E.; Kadi, Y.; Kaeppeler, F.; Kalamara, A.; Karadimos, D.; Karamanis, D.; Katabuchi, T.; Kavrigin, P.; Kerveno, M.; Ketlerov, V.; Khryachkov, V.; Kimura, A.; Kivel, N.; Kokkoris, M.; Konovalov, V.; Krtička, M.; Kroll, J.; Kurtulgil, D.; Lampoudis, C.; Langer, C.; Leal-Cidoncha, E.; Lederer, C.; Leeb, H.; Naour, C. Le; Lerendegui-Marco, J.; Leong, L. S.; Licata, M.; Meo, S. Lo; Lonsdale, S. J.; Losito, R.; Lozano, M.; Macina, D.; Manousos, A.; Marganiec, J.; Martinez, T.; Marrone, S.; Masi, A.; Massimi, C.; Mastinu, P.; Mastromarco, M.; Matteucci, F.; Maugeri, E. A.; Mazzone, A.; Mendoza, E.; Mengoni, A.; Milazzo, P. M.; Mingrone, F.; Mirea, M.; Mondelaers, W.; Montesano, S.; Moreau, C.; Mosconi, M.; Musumarra, A.; Negret, A.; Nolte, R.; O'Brien, S.; Oprea, A.; Palomo-Pinto, F. R.; Pancin, J.; Paradela, C.; Patronis, N.; Pavlik, A.; Pavlopoulos, P.; Perkowski, J.; Perrot, L.; Pigni, M. T.; Plag, R.; Plompen, A.; Plukis, L.; Poch, A.; Porras, I.; Praena, J.; Pretel, C.; Quesada, J. M.; Radeck, D.; Rajeev, K.; Rauscher, T.; Reifarth, R.; Riego, A.; Robles, M.; Roman, F.; Rout, P. C.; Rudolf, G.; Rubbia, C.; Rullhusen, P.; Ryan, J. A.; Sabaté-Gilarte, M.; Salgado, J.; Santos, C.; Sarchiapone, L.; Sarmento, R.; Saxena, A.; Schillebeeckx, P.; Schmidt, S.; Schumann, D.; Sedyshev, P.; Smith, A. G.; Sosnin, N. V.; Stamatopoulos, A.; Stephan, C.; Suryanarayana, S. V.; Tagliente, G.; Tain, J. L.; Tarifeño-Saldivia, A.; Tarrío, D.; Tassan-Got, L.; Tavora, L.; Terlizzi, R.; Tsinganis, A.; Valenta, S.; Vannini, G.; Variale, V.; Vaz, P.; Ventura, A.; Versaci, R.; Vermeulen, M. J.; Villamarin, D.; Vicente, M. C.; Vlachoudis, V.; Vlastou, R.; Voss, F.; Wallner, A.; Walter, S.; Ware, T.; Warren, S.; Weigand, M.; Weiß, C.; Wolf, C.; Wiesher, M.; Wisshak, K.; Woods, P. J.; Wright, T.; Žugec, P.

2017-09-01

The n_TOF neutron time-of-flight facility at CERN is used for high quality nuclear data measurements from thermal energy up to hundreds of MeV. In line with the CERN open data policy, the n_TOF Collaboration takes actions to preserve its unique data, facilitate access to them in standardised format, and allow their re-use by a wide community in the fields of nuclear physics, nuclear astrophysics and various nuclear technologies. The present contribution briefly describes the n_TOF outcomes, as well as the status of dissemination and preservation of n_TOF final data in the international EXFOR library.

Recent Advances in Antenna Measurement Techniques at the DTU-ESA Spherical Near-Field Antenna Test Facility

DEFF Research Database (Denmark)

Breinbjerg, Olav; Pivnenko, Sergey; Kim, Oleksiy S.

2014-01-01

This paper reports recent antenna measurement projects and research at the DTU-ESA Spherical Near-Field Antenna Test Facility at the Technical University of Denmark. High-accuracy measurement projects for the SMOS, SENTINEL-1, and BIOMASS missions of the European Space Agency were driven...

Communication grounding facility

International Nuclear Information System (INIS)

Lee, Gye Seong

1998-06-01

It is about communication grounding facility, which is made up twelve chapters. It includes general grounding with purpose, materials thermal insulating material, construction of grounding, super strength grounding method, grounding facility with grounding way and building of insulating, switched grounding with No. 1A and LCR, grounding facility of transmission line, wireless facility grounding, grounding facility in wireless base station, grounding of power facility, grounding low-tenton interior power wire, communication facility of railroad, install of arrester in apartment and house, install of arrester on introduction and earth conductivity and measurement with introduction and grounding resistance.

Molecular Tagging Velocimetry Development for In-situ Measurement in High-Temperature Test Facility

Science.gov (United States)

Andre, Matthieu A.; Bardet, Philippe M.; Burns, Ross A.; Danehy, Paul M.

2015-01-01

The High Temperature Test Facility, HTTF, at Oregon State University (OSU) is an integral-effect test facility designed to model the behavior of a Very High Temperature Gas Reactor (VHTR) during a Depressurized Conduction Cooldown (DCC) event. It also has the ability to conduct limited investigations into the progression of a Pressurized Conduction Cooldown (PCC) event in addition to phenomena occurring during normal operations. Both of these phenomena will be studied with in-situ velocity field measurements. Experimental measurements of velocity are critical to provide proper boundary conditions to validate CFD codes, as well as developing correlations for system level codes, such as RELAP5 (http://www4vip.inl.gov/relap5/). Such data will be the first acquired in the HTTF and will introduce a diagnostic with numerous other applications to the field of nuclear thermal hydraulics. A laser-based optical diagnostic under development at The George Washington University (GWU) is presented; the technique is demonstrated with velocity data obtained in ambient temperature air, and adaptation to high-pressure, high-temperature flow is discussed.

Measurement of secondary gamma-ray skyshine and groundshine from intense 14 MeV neutron source facility

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Shigeo; Morotomi, Ryutaro; Kondo, Tetsuo; Murata, Isao; Takahashi, Akito [Osaka Univ., Suita (Japan). Dept. of Nuclear Engineering

2000-03-01

Secondary gamma-ray skyshine and groundshine, including the direct contribution from the facility building, have been measured with an Hp-Ge detector and an NaI(Tl) detector at the Intense 14 MeV Neutron Source Facility OKTAVIAN of Osaka University, Japan. The mechanism of secondary gamma-rays propagation were analyzed with the measured spectrum with the Hp-Ge detector. The contribution of the skyshine was shown to be a continuum spectrum that was composed of mainly Compton scattered high energy secondary gamma-rays generated in the facility building created by (n, {gamma}) reaction. The contribution of the groundshine considerably contained secondary gamma-rays generated by {sup nat}Si (n, {gamma}) reaction in soil, including the albedo contribution from the ground. And the total contribution contained capture gamma-rays from iron (Fe) and other nuclides. The measurements with the NaI(Tl) detector as well as the Hp-Ge detector were carried out to investigate the dependence of gamma-ray dose as a function of distance from the neutron source up to hundreds meters. Consequently, it was found that the dependence could be fitted with the function of const.{center_dot}exp(-r/{lambda})/r{sup n}, where n values were around 2 except for the skyshine (n {approx} 1). It was thus indicated that the contribution of the skyshine could be propagated farther downfield than the direct contribution from the facility. The measured ratios of the three contributions (skyshine, groundshine, and direct contributions) and the distance dependence in each path were shown to be in good agreement with calculated results by the Monte Carlo transport code MCNP-4A. And the total contributions for the two detectors of NaI(Tl) and Hp-Ge agree excellently with each other. (author)

Properties of light reflected from road signs in active imaging for driving safety

Science.gov (United States)

Halstuch, Aviran; Yitzhaky, Yitzhak

2007-10-01

Night-vision systems in vehicles are a new emerging technology. A crucial problem in active (illumination-based) systems is distortion of images by saturation and blooming, due to strong retro-reflections from road signs. In this work we quantified this phenomenon. We measured the Mueller matrices and the polarization state of the reflected light from three different types of road signs commonly used. Measurements of the reflected intensity were taken also with respect to the angle of reflection. We found that different types of signs have different reflection properties. It is concluded from our measurements that the optimal solution for attenuating the retro-reflected intensity is using a linear horizontal polarized light source and a linear vertical polarizer. Unfortunately, while the performance of this solution is good for two types of road signs, it is less efficient for the third sign type.

Pitfalls and Security Measures for the Mobile EMR System in Medical Facilities.

Science.gov (United States)

Yeo, Kiho; Lee, Keehyuck; Kim, Jong-Min; Kim, Tae-Hun; Choi, Yong-Hoon; Jeong, Woo-Jin; Hwang, Hee; Baek, Rong Min; Yoo, Sooyoung

2012-06-01

The goal of this paper is to examine the security measures that should be reviewed by medical facilities that are trying to implement mobile Electronic Medical Record (EMR) systems designed for hospitals. The study of the security requirements for a mobile EMR system is divided into legal considerations and sectional security investigations. Legal considerations were examined with regard to remote medical services, patients' personal information and EMR, medical devices, the establishment of mobile systems, and mobile applications. For the 4 sectional security investigations, the mobile security level SL-3 from the Smartphone Security Standards of the National Intelligence Service (NIS) was used. From a compliance perspective, legal considerations for various laws and guidelines of mobile EMR were executed according to the model of the legal considerations. To correspond to the SL-3, separation of DMZ and wireless network is needed. Mobile access servers must be located in only the smartphone DMZ. Furthermore, security measures like 24-hour security control, WIPS, VPN, MDM, and ISMS for each section are needed to establish a secure mobile EMR system. This paper suggested a direction for applying regulatory measures to strengthen the security of a mobile EMR system in accordance with the standard security requirements presented by the Smartphone Security Guideline of the NIS. A future study on the materialization of these suggestions after their application at actual medical facilities can be used as an illustrative case to determine the degree to which theory and reality correspond with one another.

The Implementation of Performance Measurement System (PMS: Malaysian Facilities Management (FM Industry

Directory of Open Access Journals (Sweden)

Myeda N.E.

2014-01-01

Full Text Available Performance Measurement System (PMS is an effective performance measurement tool and technique that is being widely implemented in the global industries. Literature has suggested the significant contributions of its implementation in enhancing the strategic service delivery and performance. However, there is little study undertaken to explore the PMS implementation in Facilities Management (FM industry, particularly focusing on Malaysia. This study explores the PMS practice among FM practitioners and their knowledge in Performance Measurement (PM generally. Findings from this study also proposed the 20 contributing factors that the FM practitioners believed are the barriers in implementing PMS. This research also suggests the future research opportunities in developing a PMS framework that can be used as guidance for FM service delivery in Malaysia.

Present status of TANDETRON accelerator age measurement facility in Nagoya University

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Toshio; Ikeda, Akiko; Ota, Tomoko; Okuno, Mitsuru; Oda, Hirotaka; Aoki, Hiroshi; Ito, Seisuke; Adachi, Mamoru [Nagoya Univ. (Japan)

1996-12-01

Already 14 years have elapsed since a TANDETRON accelerator mass analyzer was introduced in Nagoya University. During this period, the research on environmental C-14 concentration distribution and the C-14 age measurement of environmental samples have been carried out by using C-14 as the tracer. The number of measurement as of the end of 1995 exceeded 5800. The TANDETRON analyzer has been utilized for research and education as the joint utilization facility within the university. As to the performance of the TANDETRON analyzer, C-14 measurement is feasible with 0.2-1 mg of the CO{sub 2} for forming graphite. The measurable limit of old age is 40-50 thousand years age, and the error of measurement is {+-}0.8-{+-}1.0% for relatively young samples when graphite targets are used, which can be attained by the measurement of 2-3 hours. In the old samples exceeding 20,000 years ago, as the age value becomes larger, the error increases. The state of operation and utilization is reported. In Nagoya University, the carbon dating system of Model 4130 AMS made in Netherlands was introduced in fiscal year 1995. (K.I.)

Rocketball Test Facility

Data.gov (United States)

Federal Laboratory Consortium — This test facility offers the capability to emulate and measure guided missile radar cross-section without requiring flight tests of tactical missiles. This facility...

Special Relativity Corrections for Space-Based Lidars

Science.gov (United States)

RaoGudimetla, Venkata S.; Kavaya, Michael J.

1999-01-01

The theory of special relativity is used to analyze some of the physical phenomena associated with space-based coherent Doppler lidars aimed at Earth and the atmosphere. Two important cases of diffuse scattering and retroreflection by lidar targets are treated. For the case of diffuse scattering, we show that for a coaligned transmitter and receiver on the moving satellite, there is no angle between transmitted and returned radiation. However, the ray that enters the receiver does not correspond to a retroreflected ray by the target. For the retroreflection case there is misalignment between the transmitted ray and the received ray. In addition, the Doppler shift in the frequency and the amount of tip for the receiver aperture when needed are calculated, The error in estimating wind because of the Doppler shift in the frequency due to special relativity effects is examined. The results are then applied to a proposed space-based pulsed coherent Doppler lidar at NASA's Marshall Space Flight Center for wind and aerosol backscatter measurements. The lidar uses an orbiting spacecraft with a pulsed laser source and measures the Doppler shift between the transmitted and the received frequencies to determine the atmospheric wind velocities. We show that the special relativity effects are small for the proposed system.

Compact 5 x 1012 AMP/SEC rail-gun pulser for a laser plasma shutter

International Nuclear Information System (INIS)

Bradley, L.P.; Orham, E.L.; Stowers, I.F.

1979-01-01

We have developed a rail-gun plasma source to produce a plasma of 10 12 cm -3 particle density and project it with a velocity of 3.9 cm/μs. This device will be used in a output spatial filter of Nova to project a critical density plasma across an optical beam path and block laser retroreflected light. The object of this paper is to describe the design of a pulser appropriate to the Shiva laser fusion facility, and to describe the preliminary design of a higher current prototype pulser for Nova the laser fusion research facility under construction at Lawrence Livermore Laboratory

Structure stability index allocation theory and measurement of laser prototype facility

International Nuclear Information System (INIS)

Zhang Junwei; China Academy of Engineering Physics, Mianyang; Zhou Hai; Feng Bin; Lin Donghui; Jing Feng; Zhou Yi; Wang Shilong

2008-01-01

Structure stability is an important design index of ICF driver. Based on laser prototype facility(TIL) design characteristic of multi-pass amplifier and frame structure, the optical matrix is used to analyze the single optical element influence on the beam drift and get the mathematic model. Considering all the optical elements influence on the beam drift, the mathematic model of the optical element stability index allocation is built, the parameter relation of the mathematic model is defined according to the structure characteristic of TIL, the stability index of each optical element is got as the support structure design index. Charge-coupled device(CCD) detect technology is used to measure the general beam stability of TIL. The root mean square beam drift in x and y direction are 2.78 μm, the difference between peak and valley values are 14.4 μm and 15.60 μm, respectively. The result indicates that the stability drift of the prototype facility can satisfy the design requirement, the way of the stability allocation is reasonable. (authors)

Cosmic muon flux measurements at the Kimballton Underground Research Facility

International Nuclear Information System (INIS)

Kalousis, L N; Guarnaccia, E; Link, J M; Mariani, C; Pelkey, R

2014-01-01

In this article, the results from a series of muon flux measurements conducted at the Kimballton Underground Research Facility (KURF), Virginia, United States, are presented. The detector employed for these investigations, is made of plastic scintillator bars readout by wavelength shifting fibers and multianode photomultiplier tubes. Data was taken at several locations inside KURF, spanning rock overburden values from ∼ 200 to 1450 m.w.e. From the extracted muon rates an empirical formula was devised, that estimates the muon flux inside the mine as a function of the overburden. The results are in good agreement with muon flux calculations based on analytical models and MUSIC

Dissemination of data measured at the CERN n_TOF facility

Directory of Open Access Journals (Sweden)

Dupont E.

2017-01-01

Full Text Available The n_TOF neutron time-of-flight facility at CERN is used for high quality nuclear data measurements from thermal energy up to hundreds of MeV. In line with the CERN open data policy, the n_TOF Collaboration takes actions to preserve its unique data, facilitate access to them in standardised format, and allow their re-use by a wide community in the fields of nuclear physics, nuclear astrophysics and various nuclear technologies. The present contribution briefly describes the n_TOF outcomes, as well as the status of dissemination and preservation of n_TOF final data in the international EXFOR library.

FFTF [Fast Flux Test Facility] performance measurements for safety, productivity and control

International Nuclear Information System (INIS)

Newland, D.J.; Praetorius, P.R.; Tomaszewski, T.A.

1987-05-01

A useful set of performance measurements for Safety, Productivity and Control has evolved at the Fast Flux Test Facility (FFTF). In response to declining budgets and the resulting need to safely manage a manpower rampdown, an ''Early Warning System'' was developed in 1984. Its purpose was to monitor the effects of the staffing rampdown such that appropriate remedial action could be taken to correct adverse trends before a significant problem occurred. 1 tab

Atmospheric Radiation Measurement Climate Research Facility (ACRF Instrumentation Status: New, Current, and Future)

Energy Technology Data Exchange (ETDEWEB)

JW Voyles

2008-01-30

The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following four sections: (1) new instrumentation in the process of being acquired and deployed, (2) existing instrumentation and progress on improvements or upgrades, (3) proposed future instrumentation, and (4) Small Business Innovation Research instrument development.

Measuring the preparedness of health facilities to deliver emergency obstetric care in a South African district.

Science.gov (United States)

Thwala, Siphiwe Bridget Pearl; Blaauw, Duane; Ssengooba, Freddie

2018-01-01

Improving the delivery of emergency obstetric care (EmNOC) remains critical in addressing direct causes of maternal mortality. United Nations (UN) agencies have promoted standard methods for evaluating the availability of EmNOC facilities although modifications have been proposed by others. This study presents an assessment of the preparedness of public health facilities to provide EmNOC using these methods in one South African district with a persistently high maternal mortality ratio. Data collection took place in the final quarter of 2014. Cross-sectional surveys were conducted to classify the 7 hospitals and 8 community health centres (CHCs) in the district as either basic EmNOC (BEmNOC) or comprehensive EmNOC (CEmNOC) facilities using UN EmNOC signal functions. The required density of EmNOC facilities was calculated using UN norms. We also assessed the availability of EmNOC personnel, resuscitation equipment, drugs, fluids, and protocols at each facility. The workload of skilled EmNOC providers at hospitals and CHCs was compared. All 7 hospitals in the district were classified as CEmNOC facilities, but none of the 8 CHCs performed all required signal functions to be classified as BEmNOC facilities. UN norms indicated that 25 EmNOC facilities were required for the district population, 5 of which should be CEmNOCs. None of the facilities had 100% of items on the EmNOC checklists. Hospital midwives delivered an average of 36.4±14.3 deliveries each per month compared to only 7.9±3.2 for CHC midwives (pfacilities in the district. Full EmNOC services were centralised to hospitals to assure patient safety even though national policy guidelines sanction more decentralisation to CHCs. Studies measuring EmNOC availability need to consider facility opening hours, capacity and staffing in addition to the demonstrated performance of signal functions.

Treatment of measurement uncertainties at the power burst facility

International Nuclear Information System (INIS)

Meyer, L.C.

1980-01-01

The treatment of measurement uncertainty at the Power Burst Facility provides a means of improving data integrity as well as meeting standard practice reporting requirements. This is accomplished by performing the uncertainty analysis in two parts, test independent uncertainty analysis and test dependent uncertainty analysis. The test independent uncertainty analysis is performed on instrumentation used repeatedly from one test to the next, and does not have to be repeated for each test except for improved or new types of instruments. A test dependent uncertainty analysis is performed on each test based on the test independent uncertainties modified as required by test specifications, experiment fixture design, and historical performance of instruments on similar tests. The methodology for performing uncertainty analysis based on the National Bureau of Standards method is reviewed with examples applied to nuclear instrumentation

Evolution of new reflective materials for overhead highway signage

Science.gov (United States)

2008-07-01

Unlighted highway signs using newly developed retroreflective materials were installed along the Gowanus Expressway. Photometric measurements of the signs were used to assess the visibility of the signs using the relative visual performance model. Th...

Optical Synchronization Systems for Femtosecond X-raySources

Energy Technology Data Exchange (ETDEWEB)

Wilcox, Russell; Staples, John W.; Holzwarth, Ronald

2004-05-09

In femtosecond pump/probe experiments using short X-Ray and optical pulses, precise synchronization must be maintained between widely separated lasers in a synchrotron or FEL facility. We are developing synchronization systems using optical signals for applications requiring different ranges of timing error over 100 meter of glass fiber. For stabilization in the hundred femtosecond range a CW laser is amplitude modulated at 1 10 GHz, the signal retroreflected from the far end, and the relative phase used to correct the transit time with a piezoelectric phase modulator. For the sub-10 fsec range the laser frequency itself is upshifted 55 MHz with an acousto-optical modulator, retroreflected, upshifted again and phase compared at the sending end to a 110 MHz reference. Initial experiments indicate less than 1 fsec timing jitter. To lock lasers in the sub-10 fs range we will lock two single-frequency lasers separated by several tera Hertz to a master modelocked fiber laser, transmit the two frequencies over fiber, and lock two comb lines of a slave laser to these frequencies, thus synchronizing the two modelocked laser envelopes.

Optical Synchronization Systems for Femtosecond X-ray Sources

International Nuclear Information System (INIS)

Wilcox, Russell; Staples, John W.; Holzwarth, Ronald

2004-01-01

In femtosecond pump/probe experiments using short X-Ray and optical pulses, precise synchronization must be maintained between widely separated lasers in a synchrotron or FEL facility. We are developing synchronization systems using optical signals for applications requiring different ranges of timing error over 100 meter of glass fiber. For stabilization in the hundred femtosecond range a CW laser is amplitude modulated at 1 10 GHz, the signal retroreflected from the far end, and the relative phase used to correct the transit time with a piezoelectric phase modulator. For the sub-10 fsec range the laser frequency itself is upshifted 55 MHz with an acousto-optical modulator, retroreflected, upshifted again and phase compared at the sending end to a 110 MHz reference. Initial experiments indicate less than 1 fsec timing jitter. To lock lasers in the sub-10 fs range we will lock two single-frequency lasers separated by several tera Hertz to a master modelocked fiber laser, transmit the two frequencies over fiber, and lock two comb lines of a slave laser to these frequencies, thus synchronizing the two modelocked laser envelopes

Fast neutron measurements at the nELBE time-of-flight facility

Directory of Open Access Journals (Sweden)

Junghansa A. R.

2015-01-01

Full Text Available The compact neutron-time-of-flight facility nELBE at the superconducting electron accelerator ELBE of Helmholtz-Zentrum Dresden-Rossendorf has been rebuilt. A new enlarged experimental hall with a flight path of up to 10 m is available for neutron time-of-flight experiments in the fast energy range from about 50 keV to 10 MeV. nELBE is intended to deliver nuclear data of fast neutron nuclear interactions e.g. for the transmutation of nuclear waste and improvement of neutron physical simulations of innovative nuclear systems. The experimental programme consists of transmission measurements of neutron total cross sections, elastic and inelastic scattering cross section measurements, and neutron induced fission cross sections. The inelastic scattering to the first few excited states in 56Fe was investigated by measuring the gamma production cross section with an HPGe detector. The neutron induced fission of 242Pu was studied using fast ionisation chambers with large homogeneous actinide deposits.

Natural gas facility methane emissions: measurements by tracer flux ratio in two US natural gas producing basins

Directory of Open Access Journals (Sweden)

Tara I. Yacovitch

2017-11-01

Full Text Available Methane (CH4 emission rates from a sample of natural gas facilities across industry sectors were quantified using the dual tracer flux ratio methodology. Measurements were conducted in study areas within the Fayetteville shale play, Arkansas (FV, Sept–Oct 2015, 53 facilities, and the Denver-Julesburg basin, Colorado, (DJ, Nov 2014, 21 facilities. Distributions of methane emission rates at facilities by type are computed and statistically compared with results that cover broader geographic regions in the US (Allen et al., 2013, Mitchell et al., 2015. DJ gathering station emission rates (kg CH4 hr–1 are lower, while FV gathering and production sites are statistically indistinguishable as compared to these multi-basin results. However, FV gathering station throughput-normalized emissions are statistically lower than multi-basin results (0.19% vs. 0.44%. This implies that the FV gathering sector is emitting less per unit of gas throughput than would be expected from the multi-basin distribution alone. The most common emission rate (i.e. mode of the distribution for facilities in this study is 40 kg CH4 hr–1 for FV gathering stations, 1.0 kg CH4 hr–1 for FV production pads, and 11 kg CH4 hr–1 for DJ gathering stations. The importance of study design is discussed, including the benefits of site access and data sharing with industry and of a scientist dedicated to measurement coordination and site choice under evolving wind conditions.

Pitfalls and Security Measures for the Mobile EMR System in Medical Facilities

Science.gov (United States)

Yeo, Kiho; Lee, Keehyuck; Kim, Jong-Min; Kim, Tae-Hun; Choi, Yong-Hoon; Jeong, Woo-Jin; Hwang, Hee; Baek, Rong Min

2012-01-01

Objectives The goal of this paper is to examine the security measures that should be reviewed by medical facilities that are trying to implement mobile Electronic Medical Record (EMR) systems designed for hospitals. Methods The study of the security requirements for a mobile EMR system is divided into legal considerations and sectional security investigations. Legal considerations were examined with regard to remote medical services, patients' personal information and EMR, medical devices, the establishment of mobile systems, and mobile applications. For the 4 sectional security investigations, the mobile security level SL-3 from the Smartphone Security Standards of the National Intelligence Service (NIS) was used. Results From a compliance perspective, legal considerations for various laws and guidelines of mobile EMR were executed according to the model of the legal considerations. To correspond to the SL-3, separation of DMZ and wireless network is needed. Mobile access servers must be located in only the smartphone DMZ. Furthermore, security measures like 24-hour security control, WIPS, VPN, MDM, and ISMS for each section are needed to establish a secure mobile EMR system. Conclusions This paper suggested a direction for applying regulatory measures to strengthen the security of a mobile EMR system in accordance with the standard security requirements presented by the Smartphone Security Guideline of the NIS. A future study on the materialization of these suggestions after their application at actual medical facilities can be used as an illustrative case to determine the degree to which theory and reality correspond with one another. PMID:22844648

Inpatient Psychiatric Facility Follow-Up After Hospitalization for Mental Illness (FUH) Quality Measure Data – by Facility

Data.gov (United States)

U.S. Department of Health & Human Services — Psychiatric facilities that are eligible for the Inpatient Psychiatric Facility Quality Reporting (IPFQR) program are required to meet all program requirements,...

Automation of the radiation measuring facilities for samples in health physics - MA 9

International Nuclear Information System (INIS)

Martini, M.

1980-12-01

Routine radation measurements of samples are performed by the HMI health physics department by means of test stations for individual samples and multiple samples (using a changing equipment). The basic device of these test stations is a SCALER/TIMER system (BF 22/25, BERTHOLD Corp.). This measuring facility has been extended by a CAMAC intrumentation which incorporates an autonomous CAMAC processor (CAPRO-1, INCAA B.V.) for monitoring an automatic control of the system. The programming language is BASIC. A DECwriter (LA 34) is used for user interaction and for printing the measurement results. This report describes the features of this system and present some examples of, the dialogue with the system and the printout of data. (orig.) [de

Differential current measurement in the BNL energy recovery linac test facility

International Nuclear Information System (INIS)

Cameron, Peter

2006-01-01

An energy recovery linac (ERL) test facility is presently under construction at BNL [V.N. Litvinenko, et al., High current energy recovery linac at BNL, PAC, 2005; I. Ben-Zvi, et al., Extremely high current, high brightness energy recovery linac, PAC, 2005]. The goal of this test facility is to demonstrate CW operation with an average beam current greater than 100mA, and with greater than 99.95% efficiency of current recovery. This facility will serve as a test bed for the novel high current CW photo-cathode [A. Burrill, et al., Multi-alkali photocathode development at BNL, PAC, 2005; A. Murray, et al., State-of-the-art electron guns and injector designs for energy recovery linacs, PAC, 2005], the superconducting RF cavity with HOM dampers [R. Calaga, et al., High current superconducting cavities at RHIC, EPAC, 2004; R. Calaga, et al., in: Proceedings of the 11th workshop on RF superconductivity, Lubeck, Germany, 2003], and the lattice [D. Kayran, V. Litvinenko, Novel method of emittance preservation in ERL merging system in presence of strong space charge forces, PAC, 2005; D. Kayran, et al., Optics for high brightness and high current ERL project at BNL, PAC, 2005] and feedback systems needed to insure the specified beam parameters. It is an important stepping stone for electron cooling in RHIC [I. Ben-Zvi, et al., Electron cooling of RHIC, PAC, 2005], and essential to meet the luminosity specifications of RHICII [T. Hallman, et al., RHICII/eRHIC white paper, available at http://www.bnl.gov/henp/docs/NSAC_RHICII-eRHIC_2-15-03.pdf]. The expertise and experience gained in this effort might also extend forward into a 10-20GeV ERL for the electron-ion collider eRHIC [http://www.agsrhichome.bnl.gov/eRHIC/, Appendix A, The linac-ring option, 2005]. We report here on the use of a technique of differential current measurement to monitor the efficiency of current recovery in the test facility, and investigate the possibility of using such a monitor in the machine

Implosion dynamics measurements at the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Hicks, D. G.; Meezan, N. B.; Dewald, E. L.; Mackinnon, A. J.; Callahan, D. A.; Doeppner, T.; Benedetti, L. R.; Bradley, D. K.; Celliers, P. M.; Clark, D. S.; Di Nicola, P.; Dixit, S. N.; Dzenitis, E. G.; Eggert, J. E.; Farley, D. R.; Glenn, S. M.; Glenzer, S. H.; Hamza, A. V.; Heeter, R. F.; Holder, J. P. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); and others

2012-12-15

Measurements have been made of the in-flight dynamics of imploding capsules indirectly driven by laser energies of 1-1.7 MJ at the National Ignition Facility [Miller et al., Nucl. Fusion 44, 228 (2004)]. These experiments were part of the National Ignition Campaign [Landen et al., Phys. Plasmas 18, 051002 (2011)] to iteratively optimize the inputs required to achieve thermonuclear ignition in the laboratory. Using gated or streaked hard x-ray radiography, a suite of ablator performance parameters, including the time-resolved radius, velocity, mass, and thickness, have been determined throughout the acceleration history of surrogate gas-filled implosions. These measurements have been used to establish a dynamically consistent model of the ablative drive history and shell compressibility throughout the implosion trajectory. First results showed that the peak velocity of the original 1.3-MJ Ge-doped polymer (CH) point design using Au hohlraums reached only 75% of the required ignition velocity. Several capsule, hohlraum, and laser pulse changes were then implemented to improve this and other aspects of implosion performance and a dedicated effort was undertaken to test the sensitivity of the ablative drive to the rise time and length of the main laser pulse. Changing to Si rather than Ge-doped inner ablator layers and increasing the pulse length together raised peak velocity to 93% {+-} 5% of the ignition goal using a 1.5 MJ, 420 TW pulse. Further lengthening the pulse so that the laser remained on until the capsule reached 30% (rather than 60%-70%) of its initial radius, reduced the shell thickness and improved the final fuel {rho}R on companion shots with a cryogenic hydrogen fuel layer. Improved drive efficiency was observed using U rather than Au hohlraums, which was expected, and by slowing the rise time of laser pulse, which was not. The effect of changing the Si-dopant concentration and distribution, as well as the effect of using a larger initial shell

Implosion dynamics measurements at the National Ignition Facility

International Nuclear Information System (INIS)

Hicks, D. G.; Meezan, N. B.; Dewald, E. L.; Mackinnon, A. J.; Callahan, D. A.; Döppner, T.; Benedetti, L. R.; Bradley, D. K.; Celliers, P. M.; Clark, D. S.; Di Nicola, P.; Dixit, S. N.; Dzenitis, E. G.; Eggert, J. E.; Farley, D. R.; Glenn, S. M.; Glenzer, S. H.; Hamza, A. V.; Heeter, R. F.; Holder, J. P.

2012-01-01

Measurements have been made of the in-flight dynamics of imploding capsules indirectly driven by laser energies of 1–1.7 MJ at the National Ignition Facility [Miller et al., Nucl. Fusion 44, 228 (2004)]. These experiments were part of the National Ignition Campaign [Landen et al., Phys. Plasmas 18, 051002 (2011)] to iteratively optimize the inputs required to achieve thermonuclear ignition in the laboratory. Using gated or streaked hard x-ray radiography, a suite of ablator performance parameters, including the time-resolved radius, velocity, mass, and thickness, have been determined throughout the acceleration history of surrogate gas-filled implosions. These measurements have been used to establish a dynamically consistent model of the ablative drive history and shell compressibility throughout the implosion trajectory. First results showed that the peak velocity of the original 1.3-MJ Ge-doped polymer (CH) point design using Au hohlraums reached only 75% of the required ignition velocity. Several capsule, hohlraum, and laser pulse changes were then implemented to improve this and other aspects of implosion performance and a dedicated effort was undertaken to test the sensitivity of the ablative drive to the rise time and length of the main laser pulse. Changing to Si rather than Ge-doped inner ablator layers and increasing the pulse length together raised peak velocity to 93% ± 5% of the ignition goal using a 1.5 MJ, 420 TW pulse. Further lengthening the pulse so that the laser remained on until the capsule reached 30% (rather than 60%–70%) of its initial radius, reduced the shell thickness and improved the final fuel ρR on companion shots with a cryogenic hydrogen fuel layer. Improved drive efficiency was observed using U rather than Au hohlraums, which was expected, and by slowing the rise time of laser pulse, which was not. The effect of changing the Si-dopant concentration and distribution, as well as the effect of using a larger initial shell

Implosion dynamics measurements at the National Ignition Facility

Science.gov (United States)

Hicks, D. G.; Meezan, N. B.; Dewald, E. L.; Mackinnon, A. J.; Olson, R. E.; Callahan, D. A.; Döppner, T.; Benedetti, L. R.; Bradley, D. K.; Celliers, P. M.; Clark, D. S.; Di Nicola, P.; Dixit, S. N.; Dzenitis, E. G.; Eggert, J. E.; Farley, D. R.; Frenje, J. A.; Glenn, S. M.; Glenzer, S. H.; Hamza, A. V.; Heeter, R. F.; Holder, J. P.; Izumi, N.; Kalantar, D. H.; Khan, S. F.; Kline, J. L.; Kroll, J. J.; Kyrala, G. A.; Ma, T.; MacPhee, A. G.; McNaney, J. M.; Moody, J. D.; Moran, M. J.; Nathan, B. R.; Nikroo, A.; Opachich, Y. P.; Petrasso, R. D.; Prasad, R. R.; Ralph, J. E.; Robey, H. F.; Rinderknecht, H. G.; Rygg, J. R.; Salmonson, J. D.; Schneider, M. B.; Simanovskaia, N.; Spears, B. K.; Tommasini, R.; Widmann, K.; Zylstra, A. B.; Collins, G. W.; Landen, O. L.; Kilkenny, J. D.; Hsing, W. W.; MacGowan, B. J.; Atherton, L. J.; Edwards, M. J.

2012-12-01

Measurements have been made of the in-flight dynamics of imploding capsules indirectly driven by laser energies of 1-1.7 MJ at the National Ignition Facility [Miller et al., Nucl. Fusion 44, 228 (2004)]. These experiments were part of the National Ignition Campaign [Landen et al., Phys. Plasmas 18, 051002 (2011)] to iteratively optimize the inputs required to achieve thermonuclear ignition in the laboratory. Using gated or streaked hard x-ray radiography, a suite of ablator performance parameters, including the time-resolved radius, velocity, mass, and thickness, have been determined throughout the acceleration history of surrogate gas-filled implosions. These measurements have been used to establish a dynamically consistent model of the ablative drive history and shell compressibility throughout the implosion trajectory. First results showed that the peak velocity of the original 1.3-MJ Ge-doped polymer (CH) point design using Au hohlraums reached only 75% of the required ignition velocity. Several capsule, hohlraum, and laser pulse changes were then implemented to improve this and other aspects of implosion performance and a dedicated effort was undertaken to test the sensitivity of the ablative drive to the rise time and length of the main laser pulse. Changing to Si rather than Ge-doped inner ablator layers and increasing the pulse length together raised peak velocity to 93% ± 5% of the ignition goal using a 1.5 MJ, 420 TW pulse. Further lengthening the pulse so that the laser remained on until the capsule reached 30% (rather than 60%-70%) of its initial radius, reduced the shell thickness and improved the final fuel ρR on companion shots with a cryogenic hydrogen fuel layer. Improved drive efficiency was observed using U rather than Au hohlraums, which was expected, and by slowing the rise time of laser pulse, which was not. The effect of changing the Si-dopant concentration and distribution, as well as the effect of using a larger initial shell thickness

Nuclear decay data measurements at the INEL ISOL facility

International Nuclear Information System (INIS)

Greenwood, R.C.; Helmer, R.G.; Putnam, M.H.; Struttmann, D.A.; Watts, K.D.

1991-01-01

In recent years, the use of the mass separation technique coupled on-line to a source of fission product nuclides has provided a wealth of new information on the nuclear decay properties of such nuclides. In addition to their relevance in basic studies of nuclear properties of neutron-rich nuclei, the fission product nuclides as a group, because of their intimate link with energy production in fission reactors, occupy a unique position in the field of applied nuclear decay data. Further, in addition to their critical role in nuclear reactor technology (decay heat source term, environmental concerns, etc.), such data have important applications in astrophysical calculations involving the rapid neutron capture process (r-process) of elemental synthesis in stellar environments. The scope of the nuclear decay data measurements being undertaken using the Idaho National Engineering Laboratory's (INEL) isotope separation on-line (ISOL) facility is focused on a systematic study of the gross nuclear decay properties of short-lived fission product isotopes, i.e., ground-state half-lives, beta-decay energies and beta-decay feeding (or beta-strength) distributions. In this paper, the authors discuss the results of new measurements of beta-decay energies and feeding distributions

Measurements of gas filled halfraum energetics at the national ignition facility using a single quad

Energy Technology Data Exchange (ETDEWEB)

Kline, J.L.; Fernandez, J.C.; Goldman, S.R.; Gautier, D.C.; Hegelich, B.M.; Montgomery, D.S.; Lanier, N.E.; Rose, H.A.; Workman, J.B. [Los Alamos National Laboratory, Los Alamos, NM (United States); Braun, D.; Landen, O.; Niemann, C.; Campbell, K.; Celeste, J.; Dewald, E.; Glenzer, S.; Hinkel, D.; Holder, J.; Kalantar, D.; Kamperschroer, J.; Kimbrough, J.; Kirkwood, R.; Lee, F.D.; MacGowan, B.; MacKinnon, A.; McDonald, J.; Schein, J.; Schneider, M.; Suter, L.; Young, B. [Lawrence Livermore National Lab., CA (United States)

2006-06-15

Gas filled halfraum experiments were conducted at the National Ignition Facility which provided an excellent test of the tools needed to understand halfraum energetics in an ignition relevant regime. The experiments used a highly shaped laser pulse and measured large levels of backscattered laser energy. These two components challenge the ability of radiation hydrodynamic simulations to model the experiments. The results show good agreement between experimental measurements and simulations. (authors)

Measurements of gas filled halfraum energetics at the national ignition facility using a single quad

International Nuclear Information System (INIS)

Kline, J.L.; Fernandez, J.C.; Goldman, S.R.; Gautier, D.C.; Hegelich, B.M.; Montgomery, D.S.; Lanier, N.E.; Rose, H.A.; Workman, J.B.; Braun, D.; Landen, O.; Niemann, C.; Campbell, K.; Celeste, J.; Dewald, E.; Glenzer, S.; Hinkel, D.; Holder, J.; Kalantar, D.; Kamperschroer, J.; Kimbrough, J.; Kirkwood, R.; Lee, F.D.; MacGowan, B.; MacKinnon, A.; McDonald, J.; Schein, J.; Schneider, M.; Suter, L.; Young, B.

2006-01-01

Gas filled halfraum experiments were conducted at the National Ignition Facility which provided an excellent test of the tools needed to understand halfraum energetics in an ignition relevant regime. The experiments used a highly shaped laser pulse and measured large levels of backscattered laser energy. These two components challenge the ability of radiation hydrodynamic simulations to model the experiments. The results show good agreement between experimental measurements and simulations. (authors)

Influence of condensation on heat flux and pressure measurements in a detonation-based short-duration facility

Science.gov (United States)

Haase, S.; Olivier, H.

2017-10-01

Detonation-based short-duration facilities provide hot gas with very high stagnation pressures and temperatures. Due to the short testing time, complex and expensive cooling techniques of the facility walls are not needed. Therefore, they are attractive for economical experimental investigations of high-enthalpy flows such as the flow in a rocket engine. However, cold walls can provoke condensation of the hot combustion gas at the walls. This has already been observed in detonation tubes close behind the detonation wave, resulting in a loss of tube performance. A potential influence of condensation at the wall on the experimental results, like wall heat fluxes and static pressures, has not been considered so far. Therefore, in this study the occurrence of condensation and its influence on local heat flux and pressure measurements has been investigated in the nozzle test section of a short-duration rocket-engine simulation facility. This facility provides hot water vapor with stagnation pressures up to 150 bar and stagnation temperatures up to 3800 K. A simple method has been developed to detect liquid water at the wall without direct optical access to the flow. It is shown experimentally and theoretically that condensation has a remarkable influence on local measurement values. The experimental results indicate that for the elimination of these influences the nozzle wall has to be heated to a certain temperature level, which exclusively depends on the local static pressure.

Associations between Moderate-to-Vigorous Physical Activity and Neighbourhood Recreational Facilities: The Features of the Facilities Matter

Directory of Open Access Journals (Sweden)

Ka Yiu Lee

2014-12-01

Full Text Available Objectives: To examine the associations between objectively-assessed moderate-to-vigorous physical activity (MVPA and perceived/objective measures of neighbourhood recreational facilities categorized into indoor or outdoor, public, residential or commercial facilities. The associations between facility perceptions and objectively-assessed numbers of recreational facilities were also examined. Method: A questionnaire was used on 480 adults to measure local facility perceptions, with 154 participants wearing ActiGraph accelerometers for ≥4 days. The objectively-assessed number of neighbourhood recreational facilities were examined using direct observations and Geographical Information System data. Results: Both positive and negative associations were found between MVPA and perceived/objective measures of recreational facilities. Some associations depended on whether the recreational facilities were indoor or outdoor, public or residential facilities. The objectively-assessed number of most public recreational facilities was associated with the corresponding facility perceptions, but the size of effect was generally lower than for residential recreational facilities. Conclusions: The objectively-assessed number of residential outdoor table tennis courts and public indoor swimming pools, the objectively-assessed presence of tennis courts and swimming pools, and the perceived presence of bike lanes and swimming pools were positive determinants of MVPA. It is suggested to categorize the recreational facilities into smaller divisions in order to identify unique associations with MVPA.

General principles governing sampling and measurement techniques for monitoring radioactive effluents from nuclear facilities

International Nuclear Information System (INIS)

Fitoussi, L.

1978-01-01

An explanation is given of the need to monitor the release of radioactive gases and liquid effluents from nuclear facilities, with particular emphasis on the ICRP recommendations and on the interest in this problem shown by the larger international organizations. This is followed by a description of the classes of radionuclides that are normally monitored in this way. The characteristics of monitoring 'in line' and 'by sample taking' are described; the disadvantages of in line monitoring and the problem of sample representativity are discussed. There follows an account of the general principles for measuring gaseous and liquid effluents that are applied in the techniques normally employed at nuclear facilities. Standards relating to the specifications for monitoring instruments are at present being devised by the International Electrotechnical Commission, and there are still major differences in national practices, at least as far as measurement thresholds are concerned. In conclusion, it is shown that harmonization of practices and standardization of equipment would probably help to make international relations in the field more productive. (author)

submitter Dissemination of data measured at the CERN n_TOF facility

CERN Document Server

Dupont, E; Cabellos, O; Aberle, O; Aerts, G; Altstadt, S; Alvarez, H; Alvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Audouin, L; Bacak, M; Badurek, G; Balibrea, J; Barbagallo, M; Barros, S; Baumann, P; Bécares, V; Bečvář, F; Beinrucker, C; Belloni, F; Berthier, B; Berthoumieux, E; Billowes, J; Boccone, V; Bosnar, D; Brown, A; Brugger, M; Caamaño, M; Calviani, M; Calviño, F; Cano-Ott, D; Capote, R; Cardella, R; Carrapiço, C; Casanovas, A; Castelluccio, D M; Cennini, P; Cerutti, F; Chen, Y H; Chiaveri, E; Chin, M; Colonna, N; Cortés, G; Cortés-Giraldo, M A; Cosentino, L; Couture, A; Cox, J; Damone, L A; David, S; Deo, K; Diakaki, M; Dillmann, I; Domingo-Pardo, C; Dressler, R; Dridi, W; Duran, I; Eleftheriadis, C; Embid-Segura, M; Fernández-Domínguez, B; Ferrant, L; Ferrari, A; Ferreira, P; Finocchiaro, P; Fraval, K; Frost, R J W; Fujii, K; Furman, W; Ganesan, S; Garcia, A R; Gawlik, A; Gheorghe, I; Gilardoni, S; Giubrone, G; Glodariu, T; Göbel, K; Gomez-Hornillos, M B; Goncalves, I F; Gonzalez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Guerrero, C; Gunsing, F; Gurusamy, P; Haight, R; Harada, H; Heftrich, T; Heil, M; Heinitz, S; Hernández-Prieto, A; Heyse, J; Igashira, M; Isaev, S; Jenkins, D G; Jericha, E; Kadi, Y; Kaeppeler, F; Kalamara, A; Karadimos, D; Karamanis, D; Katabuchi, T; Kavrigin, P; Kerveno, M; Ketlerov, V; Khryachkov, V; Kimura, A; Kivel, N; Kokkoris, M; Konovalov, V; Krtička, M; Kroll, J; Kurtulgil, D; Lampoudis, C; Langer, C; Leal-Cidoncha, E; Lederer, C; Leeb, H; Le Naour, C; Lerendegui-Marco, J; Leong, L S; Licata, M; Lo Meo, S; Lonsdale, S J; Losito, R; Lozano, M; Macina, D; Manousos, A; Marganiec, J; Martinez, T; Marrone, S; Masi, A; Massimi, C; Mastinu, P; Mastromarco, M; Matteucci, F; Maugeri, E A; Mazzone, A; Mendoza, E; Mengoni, A; Milazzo, P M; Mingrone, F; Mirea, M; Mondelaers, W; Montesano, S; Moreau, C; Mosconi, M; Musumarra, A; Negret, A; Nolte, R; O'Brien, S; Oprea, A; Palomo-Pinto, F R; Pancin, J; Paradela, C; Patronis, N; Pavlik, A; Pavlopoulos, P; Perkowski, J; Perrot, L; Pigni, M T; Plag, R; Plompen, A; Plukis, L; Poch, A; Porras, I; Praena, J; Pretel, C; Quesada, J M; Radeck, D; Rajeev, K; Rauscher, T; Reifarth, R; Riego, A; Robles, M; Roman, F; Rout, P C; Rudolf, G; Rubbia, C; Rullhusen, P; Ryan, J A; Sabaté-Gilarte, M; Salgado, J; Santos, C; Sarchiapone, L; Sarmento, R; Saxena, A; Schillebeeckx, P; Schmidt, S; Schumann, D; Sedyshev, P; Smith, A G; Sosnin, N V; Stamatopoulos, A; Stephan, C; Suryanarayana, S V; Tagliente, G; Tain, J L; Tarifeño-Saldivia, A; Tarrío, D; Tassan-Got, L; Tavora, L; Terlizzi, R; Tsinganis, A; Valenta, S; Vannini, G; Variale, V; Vaz, P; Ventura, A; Versaci, R; Vermeulen, M J; Villamarin, D; Vicente, M C; Vlachoudis, V; Vlastou, R; Voss, F; Wallner, A; Walter, S; Ware, T; Warren, S; Weigand, M; Weiß, C; Wolf, C; Wiesher, M; Wisshak, K; Woods, P J; Wright, T; Žugec, P

2017-01-01

The n_TOF neutron time-of-flight facility at CERN is used for high quality nuclear data measurements from thermal energy up to hundreds of MeV. In line with the CERN open data policy, the n_TOF Collaboration takes actions to preserve its unique data, facilitate access to them in standardised format, and allow their re-use by a wide community in the fields of nuclear physics, nuclear astrophysics and various nuclear technologies. The present contribution briefly describes the n_TOF outcomes, as well as the status of dissemination and preservation of n_TOF final data in the international EXFOR library.

Changing methodology for measuring airborne radioactive discharges from nuclear facilities

International Nuclear Information System (INIS)

Glissmeyer, J.A.; Ligotke, M.W.

1995-05-01

The US Environmental Protection Agency (USEPA) requires that measurements of airborne radioactive discharges from nuclear facilities be performed following outdated methods contained in the American National Standards Institute (ANSI) N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities. Improved methods are being introduced via two paths. First, the ANSI standard is being revised, and second, EPA's equivalency granting process is being used to implement new technology on a case-by-case or broad basis. The ANSI standard is being revised by a working group under the auspices of the Health Physics Society Standards Committee. The revised standard includes updated methods based on current technology and a performance-based approach to design. The performance-based standard will present new challenges, especially in the area of performance validation. Progress in revising the standard is discussed. The US Department of Energy recently received approval from the USEPA for an alternate approach to complying with air-sampling regulations. The alternate approach is similar to the revised ANSI standard. New design tools include new types of sample extraction probes and a model for estimating line-losses for particles and radioiodine. Wind tunnel tests are being performed on various sample extraction probes for use at small stacks. The data show that single-point sampling probes are superior to ANSI-Nl3.1-1969 style multiple-point sample extraction probes

On-line tritium production and heat deposition rate measurements at the Lotus facility

International Nuclear Information System (INIS)

Joneja, O.P.; Scherrer, P.; Anand, R.P.

1994-01-01

Integral tritium production and heat deposition measurement in a prototype fusion blanket would enable verification of the computational codes and the data based employed for the calculations. A large number of tritium production rate measurements have been reported for different type of blankets, whereas the direct heat deposition due to the mixed radiation field in the fusion environment, is still in its infancy. In order to ascertain the kerma factors and the photon production libraries, suitable techniques must be developed to directly measure the nuclear heat deposition rates in the materials required for the fusion systems. In this context, at the Lotus facility, we have developed an extremely efficient double ionizing chamber, for the on-line tritium production measurements and employed a pure graphite calorimeter to measure the nuclear heat deposition due to the mixed radiation field of the 14 MeV, Haefely neutron generator. This paper presents both systems and some of the recent measurements. (authors). 8 refs., 13 figs

Irradiation facilities in JRR-3M

International Nuclear Information System (INIS)

Ohtomo, Akitoshi; Sigemoto, Masamitsu; Takahashi, Hidetake

1992-01-01

Irradiation facilities have been installed in the upgraded JRR-3 (JRR-3M) in Japan Atomic Energy Research Institute (JAERI). There are hydraulic rabbit facilities (HR), pneumatic rabbit facilities (PN), neutron activation analysis facility (PN3), uniform irradiation facility (SI), rotating irradiation facility and capsule irradiation facilities to carry out the neutron irradiation in the JRR-3M. These facilities are operated using a process control computer system to centerize the process information. Some of the characteristics for the facilities were satisfactorily measured at the same time of reactor performance test in 1990. During reactor operation, some of the tests are continued to confirm the basic characteristics on facilities, for example, PN3 was confirmed to have enough performance for activation analysis. Measurement of neutron flux at all irradiation positions has been carried out for the equilibrium core. (author)

Experimental measurements and theoretical simulations for neutron flux in self-serve facility of Dhruva reactor

International Nuclear Information System (INIS)

Rana, Y.S.; Mishra, Abhishek; Singh, Tej

2016-06-01

Dhruva is a 100 MW th tank type research reactor with natural metallic uranium as fuel and heavy water as coolant, moderator and reflector. The reactor is utilized for production of a large variety of radioisotopes for fulfilling growing demands of various applications in industrial, agricultural and medicinal sectors, and neutron beam research in condensed matter physics. The core consists of two on-power tray rods for radioisotope production and fifteen experimental beam holes for neutron beam research. Recently, a self-serve facility has also been commissioned in one of the through tubes in the reactor for carrying out short term irradiations. To get accurate information about neutron flux spectrum, measurements have been carried out in self-serve facility of Dhruva reactor. The present report describes measurement method, analysis technique and results. Theoretical estimations for neutron flux were also carried out and a comparison between theoretical and experimental results is made. (author)

Measures taken by the supervisory authority to reduce extremity doses in nuclear medicine facilities in Switzerland

International Nuclear Information System (INIS)

Stritt, Nicolas; Linder, Reto

2011-01-01

In its capacity as the supervisory authority, the Swiss Federal Office of Public Health (SFOPH) has responded to the increase in extremity doses observed in nuclear medicine facilities in Switzerland over the past decade by introducing facility-specific radiation protection audits. These audits have raised the awareness of the staff members concerned with the problem of high extremity doses which arise from handling beta emitters and PET nuclides and prevented any further rise in the extremity doses. However, the evaluation of these audits has also shown that there is still considerable scope for improvement in terms of reducing extremity doses and that further measures are therefore required. Facility-specific and person-specific investigations are currently being conducted with the support of the SFOPH. Their aim is to show facilities which operations during the preparation and application of diagnostic and therapeutic radiopharmaceuticals lead to high extremity doses. This will enable the reduction of extremity doses for nuclear medicine staff as well as ensure that the dose limits are adhered to, in spite of the increasing numbers of examinations.

The CERN n_TOF Facility: Neutron Beams Performances for Cross Section Measurements

CERN Document Server

Chiaveri, E; Andrzejewski, J; Audouin, L; Barbagallo, M; Bécares, V; Bečvář, F; Belloni, F; Berthoumieux, E; Billowes, J; Boccone, V; Bosnar, D; Brugger, M; Calviani, M; Calviño, F; Cano-Ott, D; Carrapiço, C; Cerutti, F; Chin, M; Colonna, N; Cortés, G; Cortés-Giraldo, M A; Diakaki, M; Domingo-Pardo, C; Duran, I; Dressler, R; Dzysiuk, N; Eleftheriadis, C; Ferrari, A; Fraval, K; Ganesan, S; García, A R; Giubrone, G; Gómez-Hornillos, M B; Gonçalves, I F; González-Romero, E; Griesmayer, E; Guerrero, C; Gunsing, F; Gurusamy, P; Hernández-Prieto, A; Jenkins, D G; Jericha, E; Kadi, Y; Käppeler, F; Karadimos, D; Kivel, N; Koehler, P; Kokkoris, M; Krtička, M; Kroll, J; Lampoudis, C; Langer, C; Leal-Cidoncha, E; Lederer, C; Leeb, H; Leong, L S; Losito, R; Mallick, A; Manousos, A; Marganiec, J; Martínez, T; Massimi, C; Mastinu, P F; Mastromarco, M; Meaze, M; Mendoza, E; Mengoni, A; Milazzo, P M; Mingrone, F; Mirea, M; Mondalaers, W; Paradela, C; Pavlik, A; Perkowski, J; Plompen, A; Praena, J; Quesada, J M; Rauscher, T; Reifarth, R; Riego, A; Robles, M S; Roman, F; Rubbia, C; Sabaté-Gilarte, M; Sarmento, R; Saxena, A; Schillebeeckx, P; Schmidt, S; Schumann, D; Tagliente, G; Tain, J L; Tarrío, D; Tassan-Got, L; Tsinganis, A; Valenta, S; Vannini, G; Variale, V; Vaz, P; Ventura, A; Versaci, R; Vermeulen, M J; Vlachoudis, V; Vlastou, R; Wallner, A; Ware, T; Weigand, M; Weiss, C; Wright, T; Žugec, P

2014-01-01

This paper presents the characteristics of the existing CERN n\\_TOF neutron beam facility (n\\_TOF-EAR1 with a flight path of 185 meters) and the future one (n\\_TOF EAR-2 with a flight path of 19 meters), which will operate in parallel from Summer 2014. The new neutron beam will provide a 25 times higher neutron flux delivered in 10 times shorter neutron pulses, thus offering more powerful capabilities for measuring small mass, low cross section and/or high activity samples.

Measurements and FLUKA Simulations of Bismuth, Aluminium and Indium Activation at the upgraded CERN Shielding Benchmark Facility (CSBF)

Science.gov (United States)

Iliopoulou, E.; Bamidis, P.; Brugger, M.; Froeschl, R.; Infantino, A.; Kajimoto, T.; Nakao, N.; Roesler, S.; Sanami, T.; Siountas, A.; Yashima, H.

2018-06-01

The CERN High energy AcceleRator Mixed field (CHARM) facility is situated in the CERN Proton Synchrotron (PS) East Experimental Area. The facility receives a pulsed proton beam from the CERN PS with a beam momentum of 24 GeV/c with 5·1011 protons per pulse with a pulse length of 350 ms and with a maximum average beam intensity of 6.7·1010 protons per second. The extracted proton beam impacts on a cylindrical copper target. The shielding of the CHARM facility includes the CERN Shielding Benchmark Facility (CSBF) situated laterally above the target that allows deep shielding penetration benchmark studies of various shielding materials. This facility has been significantly upgraded during the extended technical stop at the beginning of 2016. It consists now of 40 cm of cast iron shielding, a 200 cm long removable sample holder concrete block with 3 inserts for activation samples, a material test location that is used for the measurement of the attenuation length for different shielding materials as well as for sample activation at different thicknesses of the shielding materials. Activation samples of bismuth, aluminium and indium were placed in the CSBF in September 2016 to characterize the upgraded version of the CSBF. Monte Carlo simulations with the FLUKA code have been performed to estimate the specific production yields of bismuth isotopes (206 Bi, 205 Bi, 204 Bi, 203 Bi, 202 Bi, 201 Bi) from 209 Bi, 24 Na from 27 Al and 115 m I from 115 I for these samples. The production yields estimated by FLUKA Monte Carlo simulations are compared to the production yields obtained from γ-spectroscopy measurements of the samples taking the beam intensity profile into account. The agreement between FLUKA predictions and γ-spectroscopy measurements for the production yields is at a level of a factor of 2.

Visitor’s Guide to Oliktok Point Atmospheric Radiation Measurement Climate Research Facility, North Slope of Alaska

Energy Technology Data Exchange (ETDEWEB)

Desilets, Darin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Helsel, Fred M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bendure, Al O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lucero, Daniel A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ivey, Mark D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dexheimer, Danielle N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-04-01

The importance of Oliktok Point, Alaska, as a focal point for climate research in the Arctic continues to grow with the addition of a U.S. Department of Energy (DOE) Atmospheric Radiation Monitoring (ARM) Climate Research Facility Mobile Facility (AMF) and the expansion of infrastructure to support airborne measurements. The site hosts a suite of instruments for making multi-year, high-fidelity atmospheric measurements; serves as a base of operations for field campaigns; and contains the only Restricted Airspace and Warning Area in the U.S. Arctic, which enables the use of unmanned aircraft systems. The use of this site by climate researchers involves several considerations, including its remoteness, harsh climate, and location amid the North Slope oilfields. This guide is intended to help visitors to Oliktok Point navigate this unique physical and administrative environment, and thereby facilitate safe and productive operations.

77 FR 28460 - National Standards for Traffic Control Devices; the Manual on Uniform Traffic Control Devices for...

Science.gov (United States)

2012-05-14

... Section 2D.43 regarding street sign color, letter size, and other design features, including... regarding street sign color, letter size, and other design features, including retroreflectivity. III. Costs... regarding color, letter size, and other design features, including retroreflectivity. These communities...

Detailed measurements and modelling of thermo active components using a room size test facility

DEFF Research Database (Denmark)

Weitzmann, Peter; Svendsen, Svend

2005-01-01

measurements in an office sized test facility with thermo active ceiling and floor as well as modelling of similar conditions in a computer program designed for analysis of building integrated heating and cooling systems. A method for characterizing the cooling capacity of thermo active components is described...... typically within 1-2K of the measured results. The simulation model, whose room model splits up the radiative and convective heat transfer between room and surfaces, can also be used to predict the dynamical conditions, where especially the temperature rise during the day is important for designing...

Hypergol Maintenance Facility Hazardous Waste South Staging Areas, SWMU 070 Corrective Measures Implementation

Science.gov (United States)

Miller, Ralinda R.

2016-01-01

This document presents the Corrective Measures Implementation (CMI) Year 10 Annual Report for implementation of corrective measures at the Hypergol Maintenance Facility (HMF) Hazardous Waste South Staging Areas at Kennedy Space Center, Florida. The work is being performed by Tetra Tech, Inc., for the National Aeronautics and Space Administration (NASA) under Indefinite Delivery Indefinite Quantity (IDIQ) NNK12CA15B, Task Order (TO) 07. Mr. Harry Plaza, P.E., of NASA's Environmental Assurance Branch is the Remediation Project Manager for John F. Kennedy Space Center. The Tetra Tech Program Manager is Mr. Mark Speranza, P.E., and the Tetra Tech Project Manager is Robert Simcik, P.E.

Characteristics of beta detection and dose measurement at Department of Energy facilities

International Nuclear Information System (INIS)

Mulvehill, J.M.; Brackenbush, L.W.

1987-02-01

This report considers the current state of the art of beta dosimetry practices and beta detection methods used by health physicists at US Department of Energy facilities. This information is based on a survey of DOE facilities. Beta measurements are technically difficult and innovative efforts must be expended to improve their accuracy. Perhaps the most pronounced problem is that beta dosimetry and instrumentation in use are highly energy and angular dependent. Many believe that beta exposures are adequately controlled because beta to photon ratios are assumed to be low. This assumption is not always valid as demonstrated by the accident at Three Mile Island (TMI). Significant beta doses exist where personnel are exposed to mixed fission products; for example, chemical reprocessing plants, reactor accidents, or where uranium metals are processed. This report is part of an effort to increase the DOE response to this technically difficult area of health protection. Problem areas are addressed and methods recommended to improve beta dosimetry through a cooperative effort among the various DOE contractors. 34 refs., 2 figs., 16 tabs

New development for the reverse time of flight analysis of spectra measured using Fourier Diffractometer Facilities

CERN Document Server

Maayouf, R M A

2002-01-01

The present work introduces a new design to replace the (Finnish make) reverse time of flight (RTOF) analyzer used for the Fourier diffractometer facilities. The new design applies a data acquisition system, a special interface card and software program installed in a PC computer, to perform the cross-correlation functions between signals received from the chopper-decoder and detector. It has been found from test measurements performed with the Cairo Fourier diffractometer facility (CFDF) and the similar high resolution one at JINR (Dubna-Russia) that the new design can successfully replace the Finnish make RTOF analyzer.

Development of corrective measures technology for shallow land burial facilities at arid sites

International Nuclear Information System (INIS)

Nyhan, J.W.; Abeele, W.V.; Perkins, B.A.; Lane, L.J.

1984-01-01

The field research program involving corrective measure technologies for arid shallow land burial (SLB) sites is described. Soil erosion and infiltration of water into a simulated trench cap with various surface treatments was measured and compared with similar data from agricultural systems across the United States. Field testing of biointrustion barriers at closed-out waste disposal sites at Los Alamos and in the experimental clusters are reported. The final results of an experiment designed to measure the extent of contaminant transport to the surface of a SLB facility, and the influence of plants on this relationship, are presented. An experiment designed to determine the effects of subsidence on the performance of a cobble-gravel biobarrier system is described and current field data are presented. 11 references, 11 figures, 5 tables

Design of electronic measurement and quench detection equipment for the Current Lead Test facility Karlsruhe (CuLTKa)

International Nuclear Information System (INIS)

Hollik, Markus; Fietz, Walter H.; Fink, Stefan; Gehrlein, Mirko; Heller, Reinhard; Lange, Christian; Möhring, Tobias

2013-01-01

The Current Lead Test facility Karlsruhe (CuLTKa) is under construction at the Karlsruhe Institute of Technology (KIT) to perform acceptance tests of high temperature superconductor (HTS) current leads (CL). CuLTKa is in progress and present planning expects the completion in 2013. The data acquisition system is based on a modular design with electronic measurement and monitoring equipment covering a test voltage of 50 kV DC against ground. It provides plug-in units which enable temperature and voltage measurement at high voltage potential and in addition quench detection units which detect a loss of superconductivity reliably and quickly to avoid damage of the superconducting device under test. Prototype units for quench detection, temperature and voltage measurement have been successfully tested. Six temperature measurement units are already in use in the KIT test facility TOSKA and operated reliably during the acceptance tests of the HTS current leads for Wendelstein 7-X (W7-X) in 2011/2012. CuLTKa will be used first for 26 current leads which will be built in KIT for the fusion experiment JT-60SA. The present paper gives an overview of the design of the electronic measurement and quench detection equipment

Small Sample Reactivity Measurements in the RRR/SEG Facility: Reanalysis using TRIPOLI-4

Energy Technology Data Exchange (ETDEWEB)

Hummel, Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States); Palmiotti, Guiseppe [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-08-01

This work involved reanalyzing the RRR/SEG integral experiments performed at the Rossendorf facility in Germany throughout the 1970s and 80s. These small sample reactivity worth measurements were carried out using the pile oscillator technique for many different fission products, structural materials, and standards. The coupled fast-thermal system was designed such that the measurements would provide insight into elemental data, specifically the competing effects between neutron capture and scatter. Comparing the measured to calculated reactivity values can then provide adjustment criteria to ultimately improve nuclear data for fast reactor designs. Due to the extremely small reactivity effects measured (typically less than 1 pcm) and the specific heterogeneity of the core, the tool chosen for this analysis was TRIPOLI-4. This code allows for high fidelity 3-dimensional geometric modeling, and the most recent, unreleased version, is capable of exact perturbation theory.

Initial Results of the SSPX Transient Internal Probe System for Measuring Toroidal Field Profiles

Science.gov (United States)

Holcomb, C. T.; Jarboe, T. R.; Mattick, A. T.; Hill, D. N.; McLean, H. S.; Wood, R. D.; Cellamare, V.

2000-10-01

Lawrence Livermore National Laboratory, Livermore, CA 94550, USA. The Sustained Spheromak Physics Experiment (SSPX) is using a field profile diagnostic called the Transient Internal Probe (TIP). TIP consists of a verdet-glass bullet that is used to measure the magnetic field by Faraday rotation. This probe is shot through the spheromak by a light gas gun at speeds near 2 km/s. An argon laser is aligned along the path of the probe. The light passes through the probe and is retro-reflected to an ellipsometer that measures the change in polarization angle. The measurement is spatially resolved down to the probes’ 1 cm length to within 15 Gauss. Initial testing results are given. This and future data will be used to determine the field profile for equilibrium reconstruction. TIP can also be used in conjunction with wall probes to map out toroidal mode amplitudes and phases internally. This work was performed under the auspices of US DOE by the University of California Lawrence Livermore National Laboratory under Contract No. W-7405-ENG-48.

A calibration facility to provide traceable calibration to upper air humidity measuring sensors

Science.gov (United States)

Cuccaro, Rugiada; Rosso, Lucia; Smorgon, Denis; Beltramino, Giulio; Fernicola, Vito

2017-04-01

Accurate knowledge and high quality measurement of the upper air humidity and of its profile in atmosphere is essential in many areas of the atmospheric research, for example in weather forecasting, environmental pollution studies and research in meteorology and climatology. Moving from the troposphere to the stratosphere, the water vapour amount varies between some percent to few part per million. For this reason, through the years, several methods and instruments have been developed for the measurement of the humidity in atmosphere. Among the instruments used for atmospheric sounding, radiosondes, airborne and balloon-borne chilled mirror hygrometer (CMH) and tunable diode laser absorption spectrometers (TDLAS) play a key role. To avoid the presence of unknown biases and systematic errors and to obtain accurate and reliable humidity measurements, these instruments need a SI-traceable calibration, preferably carried out in conditions similar to those expected in the field. To satisfy such a need, a new calibration facility has been developed at INRIM. The facility is based on a thermodynamic-based frost-point generator designed to achieve a complete saturation of the carrier gas with a single passage through an isothermal saturator. The humidity generator covers the frost point temperature range between -98 °C and -20 °C and is able to work at any controlled pressure between 200 hPa and 1000 hPa (corresponding to a barometric altitude between ground level and approximately 12000 m). The paper reports the work carried out to test the generator performances, discusses the results and presents the evaluation of the measurement uncertainty. The present work was carried out within the European Joint Research Project "MeteoMet 2 - Metrology for Essential Climate Variables" co-funded by the European Metrology Research Programme (EMRP). The EMRP is jointly funded by the EMRP participating countries within EURAMET and the European Union.

The SCANDAL facility - How to measure elastic neutron scattering in the 50-130 MeV range

International Nuclear Information System (INIS)

Klug, Joakim

2001-01-01

The interest in neutrons of energies above 20 MeV is growing rapidly, since new applications are being developed or have been identified. Transmutation of nuclear waste and cancer therapy with neutron beams are two research fields that would benefit from new neutron scattering data at these energies. A facility for detection of scattered neutrons in the energy interval 50-130 MeV, SCANDAL (SCAttered Nucleon Detection AssembLy), has been developed and installed at the neutron beam facility of the The Svedberg Laboratory in Uppsala. It can be used to study the (n,n), (n,p) and (n,d) reactions. This thesis describes the layout of the setup, the experimental procedure, and data analysis principles. The performance of the spectrometer is illustrated with measurements of the (n,p) and (n,n) reactions on 1 H and 12 C. In addition, the neutron beam facility is described in some detail

New Laval facility for polarization measurements

Energy Technology Data Exchange (ETDEWEB)

Pouliot, J; Roy, R; Bricault, P; Slobodrian, R J

1985-12-01

A new polarimetry facility has been set up. The four polarimeters used in different geometries are equipped with silicon or carbon analyzers. Extreme care has been taken to cancel out false asymmetries from apparatus misalignments. To that purpose, an automatic beam centering system has been built, two polarimeters are always run simultaneously on both sides of the beam at symmetric angles and geometric means are performed on data reduction. The installation is described in detail and data analysis and calibration runs are presented and discussed.

New Laval facility for polarization measurements

Energy Technology Data Exchange (ETDEWEB)

Pouliot, J; Roy, R; Bricault, P; Slobodrian, R J

1985-12-01

A new polarimetry facility has been set up. The four polarimeters used in different geometries are equipped with silicon or carbon analyzers. Extreme care has been taken to cancel out false asymmetries from apparatus misalignments. To that purpose, an automatic beam centering system has been built, two polarimeters are always run simultaneously on both sides of the beam at symmetric angles and geometric means are performed on data reduction. The installation is described in detail and data analysis and calibration runs are presented and discussed. (orig.).

Design and calibration of a test facility for MLI thermal performance measurements below 80K

International Nuclear Information System (INIS)

Boroski, W.; Kunzelman, R.; Ruschman, M.; Schoo, C.

1992-04-01

The design geometry of the SSC dipole cryostat includes active thermal radiation shields operating at 80K and 20K respectively. Extensive measurements conducted in a Heat Leak Test Facility (HLTF) have been used to evaluate the thermal performance of candidate multilayer insulation (MLI) systems for the 80K thermal shield, with the present system design based upon those measurement results. With the 80K MLI geometry established, efforts have focused on measuring the performance of MLI systems near 20K. A redesign of the HLTF has produced a measurement facility capable of conducting measurements with the warm boundary fixed at 80K and the cold boundary variable from 10K to 50K. Removing the 80K shield permits measurements with a warm boundary at 300K. The 80K boundary consists of a copper shield thermally anchored to a liquid nitrogen reservoir. The cold boundary consists of a copper anchor plate whose temperature is varied through boil-off gas from a 500 liter helium supply dewar. A transfer line heat exchanger supplies the boil-off gas to the anchor plate at a constant and controlled rate. The gas, which serves as cooling gas, is routed through a copper cooling tube soldered into the anchor plate. Varying the cooling gas flow rate varies the amount of refrigeration supplied to the anchor plate, thereby determining the plate temperature. A resistance heater installed on the anchor plate is regulated by a cryogenic temperature controller to provide final temperature control. Heat leak values are measured using a heatmeter which senses heat flow as a temperature gradient across a fixed thermal impedance. Since the thermal conductivity of the thermal impedance changes with temperature, the heatmeter is calibrated at key cold boundary temperatures. Thus, the system is capable of obtaining measurement data under a variety of system conditions. 7 refs

Temperature-dependent attenuation of ex-vessel flux measurements at the Hanford Fast Flux Test Facility

International Nuclear Information System (INIS)

McLane, F.E.; Wood, M.R.; Rathbun, J.L.

1982-01-01

Indicated nuclear power, developed by measuring leakage neutrons, has been found to be temperature dependent at the Hanford Fast Flux Test Facility (FFTF). The magnitude, sense and speed of response of the effect suggest that hot sodium above th core and shield is a significant cause. Future designs which may minimize this effect are discussed

Blowdown mass flow measurements during the Power Burst Facility LOC-11C test

International Nuclear Information System (INIS)

Broughton, J.M.; MacDonald, P.E.

1979-01-01

An interpretation and evaluation of the two-phase coolant mass flow measurements obtained during Test LOC-11C performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL) are presented. Although a density gradient existed within the pipe between 1 and 6 s, the homogeneous flow model used to calculate the coolant mass flow from the measured mixture density, momentum flux, and volumetric flow was found to be generally satisfactory. A cross-sectional average density was determined by fitting a linear density gradient through the upper and lower chordal densities obtained from a three-beam gamma densitometer and then combining the result with the middle beam density. The integrated measured coolant mass flow was subsequently found to be within 5% if the initial mass inventory of the PBF loss-of-coolant accident (LOCA) system. The posttest calculations using the RELAP4/MOD6 computer code to determine coolant mass flow for Test LOC-11C also agreed well with the measured data

Measurement of 36Cl induced in shielding concrete of various accelerator facilities

International Nuclear Information System (INIS)

Bessho, K.; Matsumura, H.; Matsuhiro, T.

2003-01-01

The concentrations of 36 Cl induced in shielding concrete of the various accelerators has been measured by accelerator mass spectrometry. For three kinds of accelerator facilities, SF cyclotron (Center for Nuclear Study, the University of Tokyo), 300 MeV electron LINAC (Laboratory of Nuclear Science, Tohoku University), and 12 GeV proton synchrotron (High Energy Accelerator Research Organization), the depth profiles of 36 Cl/ 35 Cl ratios in concrete samples near the beam lines were analyzed. The depth profiles of 36 Cl/ 35 Cl are consistent with those of the radioactive concentrations of 152 Eu and 60 Co, which are formed by thermal neutron capture reactions. These results imply that 36 Cl formed in shielding concrete of these accelerators is mainly produced by thermal neutron capture of 35 Cl. The maximum 36 Cl/ 35 Cl ratio of 3x10 -8 (300 MeV electron LINAC, depth of 8 cm) corresponds to the specific radioactivity of 2x10 -3 Bq/g, which is not serious for radioactive waste management in reconstruction or decommissioning of accelerator facilities, compared with specific radioactivity of 3 H, 152 Eu and 60 Co. (author)

Investigation on candidates of principal facilities for exposure dose to public for the facilities using nuclear material

International Nuclear Information System (INIS)

Shimazaki, Yosuke; Sawahata, Hiroaki; Takada, Shoji; Fujimoto, Nozomu

2015-01-01

HTTR holds the nuclear fuel material use facilities in its reactor facilities, for the purpose of study on the fracture behavior of fuel and release behavior of fission products, development of high-performance fuel, and measurement of neutron flux. Due to the revision of the 'Act on the regulation of nuclear source material, nuclear fuel material and reactor', the facilities having the 'Important safety-related facilities' among the facilities applicable to the Enforcement Ordinance Article 41 (Article 41 facilities) has come to need to conform to the 'Regulations concerning standards for the location, structure, and equipment of used facilities and others'. In this case, actions such as modification by all possible means are required. The nuclear fuel substance use facilities of HTTR correspond to Article 41 facilities. So, whether it is a candidate for the 'Important safety-related facilities' has been examined. As a result, it is confirmed that the facilities are not correspond to the 'Important safety-related facilities', and it has been concluded that modification measures for the purpose of conforming to this approval standard rule are not necessary as of the present. (A.O.)

Neutron calibration facility with an Am-Be source for pulse shape discrimination measurement of CsI(Tl) crystals

International Nuclear Information System (INIS)

Lee, H.S.; Bhang, H.; Choi, J.H.; Choi, S.; Joo, H.W.; Kim, G.B.; Kim, K.W.; Kim, S.C.; Kim, S.K.; Lee, J.H.; Lee, J.K.; Myung, S.S.; Hahn, I.S.; Jeon, E.J.; Kang, W.G.; Kim, Y.D.; Kim, Y.H.; Li, J.; Kim, H.J.; Leonard, D.S.

2014-01-01

We constructed a neutron calibration facility based on a 300-mCi Am-Be source in conjunction with a search for weakly interacting massive particle candidates for dark matter. The facility is used to study the response of CsI(Tl) crystals to nuclear recoils induced by neutrons from the Am-Be source and comparing them with the response to electron recoils produced by Compton scattering of 662-keV γ-rays from a 137 Cs source. The measured results on pulse shape discrimination (PSD) between nuclear- and electron-recoil events are quantified in terms of quality factors. A comparison with our previous result from a neutron generator demonstrate the feasibility of performing calibrations of PSD measurements using neutrons from a Am-Be source

Basic Design of Experimental Facility for Measuring Pressure Drop of IHX in a SFR

Energy Technology Data Exchange (ETDEWEB)

Ko, Yung-Joo; Eoh, Jae-Hyuk; Kim, Hyungmo; Lee, Dong-Won; Jeong, Ji-Young; Lee, Hyeong-Yeon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Eok [Kyungpook National Univ., Daegu (Korea, Republic of)

2015-05-15

The conceptual design of the Prototype gen-IV SFR (PGSFR) with a 150 MWe capacity was commenced in 2012 through the national long-term R and D program by KAERI. Then, PGSFR is now being designed with the defense in depth concept with active, passive and inherent safety features to acquire design approval for PGSFR from the Korean regulatory authority by 2020. PGSFR is a sodium-cooled pool-type fast reactor with all primary components including the primary heat transport system (PHTS) pumps and IHXs are located inside a sodium pool. The heat produced due to fission in the core is transported by primary sodium to secondary sodium in a sodium to sodium intermediate heat exchanger (IHX), which in turn is transferred to water in a steam generator (SG). Basic design of the IHX flow characteristic test facility, WEIPA was conducted based on the three-level scaling methodology in order to preserve the flow characteristics of the IHX in PGSFR. This test facility is intended to measure a high precision pressure drop at the shell-side of the IHX. This paper describes the aspects of the current design features of the IHX in PGSFR, scaling and basic design features of the facility.

Current status of radiation safety of disposal facility in the Republic of Moldova and measures of its improvement

International Nuclear Information System (INIS)

Zaharia, G.

2000-01-01

The infrastructure and waste management safety in the Republic of Moldova is presented. The current situation in the waste disposal facility is described. The radioactive waste inventory shows a total activity of 16.4 TBq. The radiological survey of soils at the CRWDF show a significant increase of the contamination by 226 Ra and 90 Sr at depths 3 - 5.5 m, considered as an accidental situation provoked by the disintegration of the facility protective walls. Measures for the prevention of further contamination and ground water are discussed. Construction of a new radioactive waste shallow land disposal facility on the site combined with some engineering improvements of the site is considered the best solution. Some problems of the waste management in the country are presented

Monte Carlo Simulation of the Time-Of-Flight Technique for the Measurement of Neutron Cross-section in the Pohang Neutron Facility

Energy Technology Data Exchange (ETDEWEB)

An, So Hyun; Lee, Young Ouk; Lee, Cheol Woo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Young Seok [National Fusion Research Institute, Daejeon (Korea, Republic of)

2007-10-15

It is essential that neutron cross sections are measured precisely for many areas of research and technique. In Korea, these experiments have been performed in the Pohang Neutron Facility (PNF) with the pulsed neutron facility based on the 100 MeV electron linear accelerator. In PNF, the neutron energy spectra have been measured for different water levels inside the moderator and compared with the results of the MCNPX calculation. The optimum size of the water moderator has been determined on the base of these results. In this study, Monte Carlo simulations for the TOF technique were performed and neutron spectra of neutrons were calculated to predict the measurements.

Dose measurements for characterization of a semi-industrial cobalt-60 gamma-irradiation facility

International Nuclear Information System (INIS)

Farah, K.; Jerbi, T.; Kuntz, F.; Kovacs, A.

2006-01-01

Cobalt-60 irradiation facility has been put into operation at the National Centre of Nuclear Sciences and Technology, Sidi-thabet, Tunisia. Its technical specifications were controlled by dosimetry commissioning experiments and compared to the data specified by the plant manufacturer. Installation qualification has been carried out to measure absorbed dose distribution in the irradiation cell and products. Two dosimeter systems were used for measurements: Red and Amber Perspex and Cellulose Triacetate (CTA). The regions of minimum and maximum absorbed dose within a homogeneous dummy product (sawdust) with a bulk density of 114kg/m 3 and the dose uniformity ratio were determined. The isodose curves and the three-dimensional views were built using an automatic geostatistical gridding method, the kriging method

Assessment of the effectiveness of personal visual observation as a safeguards measure in a uranium enrichment facility

International Nuclear Information System (INIS)

Ohno, Fubito; Okamoto, Tsuyoshi; Yokochi, Akira; Nidaira, Kazuo

2003-01-01

In a centrifuge enrichment facility, a cascade that produces low enriched uranium is composed of a large number of UF 6 gas centrifuges interconnected with pipes. It is possible to divert the cascade to the illegal production of highly enriched uranium (HEU) by changing the piping arrangement within the cascade. If integrated type centrifuges that contain a few tens of advanced centrifuges are introduced into the facility, the number of pipes will greatly decrease. The smaller the number of pipes, the less the labor required to change the piping arrangement. Because personal visual observation by an inspector is considered as one of measures against changing the piping arrangement, its effectiveness is assessed in this study. First, a model centrifuge enrichment facility that has a capacity of 2,400 ton-SWU/y is designed. In this model facility, integrated type centrifuges that contain advanced centrifuges are installed. Second, the diversion path analysis is carried out for the model facility under the assumption that a facility operator's goal is to produce 75 kg of HEU with 20% enrichment in a month. The analysis shows that, in our assumed diversion path, changes of the piping arrangement can be certainly detected by personal visual observation of a part of pipes connected with integrated type centrifuges that compose the cascade diverted to the HEU production. Finally, inspections in a cascade area are modeled as two-person noncooperative games between the inspector and the facility operator. As a result, it is found that all the cascades in the model facility will be investigated if the inspector can devote the inspection effort of 0.83 man-day per month to personal visual observation in the cascade area. Therefore, it is suggested that personal visual observation of the piping arrangement is worth carrying out in a uranium enrichment facility where integrated type centrifuges that contain advanced centrifuges are installed. (author)

First Measurement of Reaction-in-Flight Neutrons at the National Ignition Facility

Science.gov (United States)

Tonchev, A.; Becker, J.; Bleuel, D.; Bionta, R.; Fortner, D.; Henry, E.; Khater, H.; Shaughnessy, D.; Schnider, D.; Stoeffl, W.; Yeamans, C.; Boswell, M.; Bredeweg, T.; Grim, G.; Jungman, G.; Fowler, M.; Hayes, A.; Obst, A.; Rundberg, R.; Schulz, A.; Wilhelmy, J.; Tornow, W.; Bhike, M.; Howell, C.; Gooden, M.; LLNL/LANL/TUNL Collaboration

2013-10-01

The first measurement of reaction-in-flight (RIF) neutrons, also known as tertiary neutrons, has been performed at the National Ignition Facility (NIF) using an activation technique. Thulium foils positioned at 50 cm from the burning deuterium-tritium (DT) capsule have been exposed to the characteristic DT neutron spectrum. The high-energy part of these neutrons with energies above 15.0 MeV can produce 167Tm via the 169Tm(n,3n) reaction. The 208-keV γ-ray, emitted from the decay of 167Tm with a half-life of 9.2 days, has been measured using two clover detectors. The first preliminary result implies that the ratio of RIF neutrons (En > 15.0 MeV) versus the total neutrons is 1 × 10 -4 +/- 3 × 10 -5. The important implication of these measurements on our knowledge of the charged-particle stopping power in strongly coupled quantum-degenerate plasma will be presented. This work was performed under the auspices of the Lawrence Livermore National Security, LLC, (LLNS) under Contract No. DE-AC52-07NA27344.

Beam position and phase measurements of microampere beams at the Michigan State University REA3 facility

CERN Document Server

Crisp, J; Durickovic, B; Kiupel, G; Krause, S; Leitner, D; Nash, S; Rodriguez, J A; Russo, T; Webber, R; Wittmer, W; Eddy, N; Briegel, C; Fellenz, B; Slimmer, D; Wendt, M

2013-01-01

A high power CW, heavy ion linac will be the driver accelerator for the Facility for Rare Isotope Beams (FRIB) being designed at Michigan State University (MSU). The linac requires a Beam Position Monitoring (BPM) system with better than 100 micron resolution at 100 microamperes beam current. A low beam current test of the candidate technology, button pick-ups and direct digital down-conversion signal processing, was conducted in the ReA3 re-accelerated beam facility at Michigan State University. The test is described. Beam position and phase measurement results, demonstrating ~250 micron and ~1.5 degree resolution in a 45 kHz bandwidth for a 1.0 microampere beam current, are reported.

Use of the Long Duration Exposure Facility's thermal measurement system for the verification of thermal models

Science.gov (United States)

Berrios, William M.

1992-01-01

The Long Duration Exposure Facility (LDEF) postflight thermal model predicted temperatures were matched to flight temperature data recorded by the Thermal Measurement System (THERM), LDEF experiment P0003. Flight temperatures, recorded at intervals of approximately 112 minutes for the first 390 days of LDEF's 2105 day mission were compared with predictions using the thermal mathematical model (TMM). This model was unverified prior to flight. The postflight analysis has reduced the thermal model uncertainty at the temperature sensor locations from +/- 40 F to +/- 18 F. The improved temperature predictions will be used by the LDEF's principal investigators to calculate improved flight temperatures experienced by 57 experiments located on 86 trays of the facility.

Research on fire extinguishing and disaster measures techniques for nuclear facilities

International Nuclear Information System (INIS)

Tsuruda, Takashi; Amano, Hisanori; Liao, Chihong

2004-01-01

As for a fire of alkali metals in nuclear facilities, measures to cope with the situation should be prepared. It has been experimentally investigated with a success to stabilize and treat safe in the air the leavings of burned sodium, which were extinguished by the nitrogen and poured with fire extinguishing powder for metal fire. Furthermore research and development has been conducted on a series of robots such as installing protection wall between radiation sources and victims and carrying victims out of the disaster room. Basic functional experiments on key components of robot system have been carried out using a trial product. Total control system of a series of robots will be updated based on control mechanism and software of a trial robot system. (T. Tanaka)

An integrated model to measure service management and physical constraints' effect on food consumption in assisted-living facilities.

Science.gov (United States)

Huang, Hui-Chun; Shanklin, Carol W

2008-05-01

The United States is experiencing remarkable growth in the elderly population, which provides both opportunities and challenges for assisted-living facilities. The objective of this study was to explore how service management influences residents' actual food consumption in assisted-living facilities. Physical factors influencing residents' service evaluation and food consumption also were investigated. A total of 394 questionnaires were distributed to assisted-living residents in seven randomly selected facilities. The questionnaire was developed based on an in-depth literature review and pilot study. Residents' perceived quality evaluations, satisfaction, and physical constraints were measured. Residents' actual food consumption was measured using a plate waste technique. A total of 118 residents in five facilities completed both questionnaires and food consumption assessments. Descriptive, multivariate analyses and structural equation modeling techniques were employed. Service management, including food and service quality and customer satisfaction, was found to significantly influence residents' food consumption. Physical constraints associated with aging, including a decline in health status, chewing problems, sensory loss, and functional disability, also significantly influenced residents' food consumption. A significant relationship was found between physical constraints and customer satisfaction. Foodservice that provides good food and service quality increases customer satisfaction and affects residents' actual food consumption. Physical constraints also influence residents' food consumption directly, or indirectly through satisfaction. The findings suggest that food and nutrition professionals in assisted-living should consider the physical profiles of their residents to enhance residents' satisfaction and nutrient intake. Recommendations for exploring residents' perspectives are discussed.

Littoral Measurements Facility

Data.gov (United States)

Federal Laboratory Consortium — FUNCTION: Barny units measure ocean currents and sea surface heights on continental shelves and in ocean straits. SEPTR units are similar to Barnys but also record...

Techniques for measuring aerosol attenuation using the Central Laser Facility at the Pierre Auger Observatory

Energy Technology Data Exchange (ETDEWEB)

Collaboration, The Pierre Auger

2013-04-01

The Pierre Auger Observatory in Malargüe, Argentina, is designed to study the properties of ultra-high energy cosmic rays with energies above 10(18)eV. It is a hybrid facility that employs a Fluorescence Detector to perform nearly calorimetric measurements of Extensive Air Shower energies. To obtain reliable calorimetric information from the FD, the atmospheric conditions at the observatory need to be continuously monitored during data acquisition. In particular, light attenuation due to aerosols is an important atmospheric correction. The aerosol concentration is highly variable, so that the aerosol attenuation needs to be evaluated hourly. We use light from the Central Laser Facility, located near the center of the observatory site, having an optical signature comparable to that of the highest energy showers detected by the FD. This paper presents two procedures developed to retrieve the aerosol attenuation of fluorescence light from CLF laser shots. Cross checks between the two methods demonstrate that results from both analyses are compatible, and that the uncertainties are well understood. The measurements of the aerosol attenuation provided by the two procedures are currently used at the Pierre Auger Observatory to reconstruct air shower data.

6D Phase Space Measurements at the SLAC Gun Test Facility

CERN Document Server

Schmerge, J

2003-01-01

Proposed fourth generation light sources using SASE FELs to generate short pulse, coherent X-rays require demonstration of high brightness electron sources. The Gun Test Facility (GTF) at SLAC was built to test high brightness sources for the proposed Linac Coherent Light Source at SLAC. The GTF is composed of an Sband photocathode rf gun with a Cu cathode, emittance compensating solenoid, single 3 m SLAC linac section and e-beam diagnostic section with a UV drive laser system. The longitudinal emittance exiting the gun has been determined by measuring the energy spectrum downstream of the linac as a function of the linac phase. The e-beam pulse width, correlated and uncorrelated energy spread at the linac entrance have been fit to the measured energy spectra using a least square error fitting routine. The fit yields a pulse width of 2.9 ps FWHM for a 4.3 ps FWHM laser pulse width and 2% rms correlated energy spread with 0.07% rms uncorrelated energy spread. The correlated energy spread is enhanced in the lin...

Preparing and measuring ultra-small radiocarbon samples with the ARTEMIS AMS facility in Saclay, France

Energy Technology Data Exchange (ETDEWEB)

Delque-Kolic, E., E-mail: emmanuelle.delque-kolic@cea.fr [LMC14, CEA Saclay, Batiment 450 Porte 4E, 91191 Gif sur Yvette (France); Comby-Zerbino, C.; Ferkane, S.; Moreau, C.; Dumoulin, J.P.; Caffy, I.; Souprayen, C.; Quiles, A.; Bavay, D.; Hain, S.; Setti, V. [LMC14, CEA Saclay, Batiment 450 Porte 4E, 91191 Gif sur Yvette (France)

2013-01-15

The ARTEMIS facility in Saclay France measures, on average, 4500 samples a year for French organizations working in an array of fields, including environmental sciences, archeology and hydrology. In response to an increasing demand for the isolation of specific soil compounds and organic water fractions, we were motivated to evaluate our ability to reduce microgram samples using our standard graphitization lines and to measure the graphite thus obtained with our 3MV NEC Pelletron AMS. Our reduction facility consists of two fully automated graphitization lines. Each line has 12 reduction reactors with a reduction volume of 18 ml for the first line and 12 ml for the second. Under routine conditions, we determined that we could reduce the samples down to 10 {mu}g of carbon, even if the graphitization yield is consequently affected by the lower sample mass. Our results when testing different Fe/C ratios suggest that an amount of 1.5 mg of Fe powder was ideal (instead of lower amounts of catalyst) to prevent the sample from deteriorating too quickly under the Cs+ beam, and to facilitate pressing procedures. Several sets of microsamples produced from HOxI standard, international references and backgrounds were measured. When measuring {sup 14}C-free wood charcoal and HOxI samples we determined that our modern and dead blanks, due to the various preparation steps, were of 1.1 {+-} 0.8 and 0.2 {+-} 0.1 {mu}g, respectively. The results presented here were obtained for IAEA-C1, {sup 14}C-free wood, IAEA-C6, IAEA-C2 and FIRI C.

Preparing and measuring ultra-small radiocarbon samples with the ARTEMIS AMS facility in Saclay, France

International Nuclear Information System (INIS)

Delqué-Količ, E.; Comby-Zerbino, C.; Ferkane, S.; Moreau, C.; Dumoulin, J.P.; Caffy, I.; Souprayen, C.; Quilès, A.; Bavay, D.; Hain, S.; Setti, V.

2013-01-01

The ARTEMIS facility in Saclay France measures, on average, 4500 samples a year for French organizations working in an array of fields, including environmental sciences, archeology and hydrology. In response to an increasing demand for the isolation of specific soil compounds and organic water fractions, we were motivated to evaluate our ability to reduce microgram samples using our standard graphitization lines and to measure the graphite thus obtained with our 3MV NEC Pelletron AMS. Our reduction facility consists of two fully automated graphitization lines. Each line has 12 reduction reactors with a reduction volume of 18 ml for the first line and 12 ml for the second. Under routine conditions, we determined that we could reduce the samples down to 10 μg of carbon, even if the graphitization yield is consequently affected by the lower sample mass. Our results when testing different Fe/C ratios suggest that an amount of 1.5 mg of Fe powder was ideal (instead of lower amounts of catalyst) to prevent the sample from deteriorating too quickly under the Cs+ beam, and to facilitate pressing procedures. Several sets of microsamples produced from HOxI standard, international references and backgrounds were measured. When measuring 14 C-free wood charcoal and HOxI samples we determined that our modern and dead blanks, due to the various preparation steps, were of 1.1 ± 0.8 and 0.2 ± 0.1 μg, respectively. The results presented here were obtained for IAEA-C1, 14 C-free wood, IAEA-C6, IAEA-C2 and FIRI C.

Neutron measurements from beam-target reactions at the ELISE neutral beam test facility

International Nuclear Information System (INIS)

Xufei, X.; Fan, T.; Nocente, M.; Gorini, G.; Bonomo, F.; Franzen, P.; Fröschle, M.; Grosso, G.; Tardocchi, M.; Grünauer, F.; Pasqualotto, R.

2014-01-01

Measurements of 2.5 MeV neutron emission from beam-target reactions performed at the ELISE neutral beam test facility are presented in this paper. The measurements are used to study the penetration of a deuterium beam in a copper dump, based on the observation of the time evolution of the neutron counting rate from beam-target reactions with a liquid scintillation detector. A calculation based on a local mixing model of deuterium deposition in the target up to a concentration of 20% at saturation is used to evaluate the expected neutron yield for comparison with data. The results are of relevance to understand neutron emission associated to beam penetration in a solid target, with applications to diagnostic systems for the SPIDER and MITICA Neutral Beam Injection prototypes

Design of a High Viscosity Couette Flow Facility for Patterned Surface Drag Measurements

Science.gov (United States)

Johnson, Tyler; Lang, Amy

2009-11-01

Direct drag measurements can be difficult to obtain with low viscosity fluids such as air or water. In this facility, mineral oil is used as the working fluid to increase the shear stress across the surface of experimental models. A mounted conveyor creates a flow within a plexiglass tank. The experimental model of a flat or patterned surface is suspended above a moving belt. Within the gap between the model and moving belt a Couette flow with a linear velocity profile is created. PIV measurements are used to determine the exact velocities and the Reynolds numbers for each experiment. The model is suspended by bars that connect to the pillow block housing of each bearing. Drag is measured by a force gauge connected to linear roller bearings that slide along steel rods. The patterned surfaces, initially consisting of 2-D cavities, are embedded in a plexiglass plate so as to keep the total surface area constant for each experiment. First, the drag across a flat plate is measured and compared to theoretical values for laminar Couette flow. The drag for patterned surfaces is then measured and compared to a flat plate.

Neutron fluence measurement in nuclear facilities.; Medicion de flujos de neutrones en instalaciones nucleares.

Energy Technology Data Exchange (ETDEWEB)

Camacho L, M E

1997-12-01

The objective of present work is to determine the fluence of neutrons in nuclear facilities using two neutron detectors designed and built at Instituto Nacional de Investigaciones Nucleares (ININ), Mexico. The two neutron detectors are of the passive type, based on solid state nuclear tracks detectors (SSNTD). One of the two neutron detectors was used to determine the fluence distribution of the ports at the nuclear research reactor TRIGA Mark III, which belongs to ININ. In these facilities is important to know the neutron fluence distribution characteristic to carried out diverse kind of research activities. The second neutron detector was employed in order to carry out environmental neutron surveillance. The detector has the property to separate the thermal, intermediate and fast components of the neutron fluence. This detector was used to measure the neutron fluence at hundred points around the primary container of the first Mexican Nuclear Power plant `Laguna Verde`. This last detector was also used to determine the neutron fluence in some points of interest, around and inside a low scattering neutron room at the `Centro de Metrologia de Radiaciones Ionizantes` of the ININ, to know the background neutron field produced by the neutron sources used there. The design of the two neutron detector and the results obtained for each of the surveying facilities, are described in this work. (Author).

Validation of a wind tunnel testing facility for blade surface pressure measurements

Energy Technology Data Exchange (ETDEWEB)

Fuglsang, P.; Antoniou, I.; Soerensen, N.N.; Madsen, H.A.

1998-04-01

This report concerns development and validation of a 2d testing facility for airfoil pressure measurements. The VELUX open jet wind tunnel was used with a test stand inserted. Reynolds numbers until 1.3 million were achieved with an airfoil chord of 0.45 m. The aerodynamic load coefficients were found from pressure distribution measurements and the total drag coefficient was calculated from wake rake measurements. Stationary inflow as well as dynamic inflow through pitching motion was possible. Wind tunnel corrections were applied for streamline curvature and down-wash. Even though the wind tunnel is not ideal for 2d testing, the overall quality of the flow was acceptable with a uniform flow field at the test stand position and a turbulence intensity of 1 % at the inlet of the test section. Reference values for free stream static and total pressure were found upstream of the test stand. The NACA 63-215 airfoil was tested and the results were compared with measurements from FFA and NACA. The measurements agreed well except for lift coefficient values at high angles of attack and the drag coefficient values at low angles of attack, that were slightly high. Comparisons of the measured results with numerical predictions from the XFOIL code and the EllipSys2D code showed good agreement. Measurements with the airfoil in pitching motion were carried out to study the dynamic aerodynamic coefficients. Steady inflow measurements at high angles of attack were used to investigate the double stall phenomenon. (au) EFP-94; EFP-95; EFP-97. 8 tabs., 82 ills., 16 refs.

Measurements of electron beam emittance in the Accelerator Test Facility damping ring operated in multibunch modes

Directory of Open Access Journals (Sweden)

Yosuke Honda

2003-09-01

Full Text Available We present the measurement results of electron beam emittance in the Accelerator Test Facility damping ring operated in multibunch modes. The measurements were carried out with an upgraded laser wire beam profile monitor. The monitor has now a vertical wire as well as a horizontal one and is able to make much faster measurements thanks to an increased effective laser power inside the cavity. The measured emittance shows no large bunch-to-bunch dependence in either the horizontal or vertical directions. The values of the vertical emittance are similar to those obtained in the single-bunch operation. The present results are an important step toward the realization of a high-energy linear collider.

Measurement and instrumentation techniques for monitoring plutonium and uranium particulates released from nuclear facilities

International Nuclear Information System (INIS)

Nero, A.V. Jr.

1976-08-01

The purpose of this work has been an analysis and evaluation of the state-of-the-art of measurement and instrumentation techniques for monitoring plutonium and uranium particulates released from nuclear facilities. The occurrence of plutonium and uranium in the nuclear fuel cycle, the corresponding potential for releases, associated radiological protection standards and monitoring objectives are discussed. Techniques for monitoring via decay radiation from plutonium and uranium isotopes are presented in detail, emphasizing air monitoring, but also including soil sampling and survey methods. Additionally, activation and mass measurement techniques are discussed. The availability and prevalence of these various techniques are summarized. Finally, possible improvements in monitoring capabilities due to alterations in instrumentation, data analysis, or programs are presented

Augmentation of Quick-EXAFS measurement facility at the energy scanning EXAFS beamline at INDUS-2 SRS

Energy Technology Data Exchange (ETDEWEB)

Poswal, A. K., E-mail: poswalashwini@gmail.com; Agrawal, Ankur; Bhattachryya, D.; Jha, S. N.; Sahoo, N. K. [Atomic and Molecular Physics Division, Bhabha Atomic Research Centre, Mumbai -400085 (India)

2015-06-24

In this paper implementation of Quick-EXAFS data acquisition facility at the Energy Scanning EXAFS beamline(BL-09) at INDUS-2 synchrotron source, Indore is presented. By adopting a continuous-scan mode in the Double Crystal monochromator (DCM), a high signal-to-noise ratio is maintained and the acquisition time is reduced to few seconds. The quality of spectra and repeatability is checked by measuring standards. The present mode of data acquisition would enable EXAFS measurement for in-situ studies even in fluorescence mode.

US-Russian Cooperation in Upgrading MC and A System at Rosatom Facilities: Measurement of Nuclear Materials

International Nuclear Information System (INIS)

Powell, Danny H.; Jensen, Bruce A.

2011-01-01

Improve protection of weapons-usable nuclear material from theft or diversion through the development and support of a nationwide sustainable and effective Material Control and Accountability (MC and A) program based on material measurement. The material protection, control, and accountability (MPC and A) cooperation has yielded significant results in implementing MC and A measurements at Russian nuclear facilities: (1) Establishment of MEM WG and MEMS SP; (2) Infrastructure for development, certification, and distribution of RMs; and (3) Coordination on development and implementation of MMs.

Methods and apparatus for measuring small leaks from carbon dioxide sequestration facilities

Science.gov (United States)

Nelson, Jr., David D.; Herndon, Scott C.

2018-01-02

In one embodiment, a CO.sub.2 leak detection instrument detects leaks from a site (e.g., a CO.sub.2 sequestration facility) using rapid concentration measurements of CO.sub.2, O.sub.2 and optionally water concentration that are achieved, for example, using laser spectroscopy (e.g. direct absorption laser spectroscopy). Water vapor in the sample gas may not be removed, or only partially removed. The sample gas may be collected using a multiplexed inlet assembly from a plurality of locations. CO.sub.2 and O.sub.2 concentrations may be corrected based on the water concentration. A resulting dataset of the CO.sub.2 and O.sub.2 concentrations is analyzed over time intervals to detect any changes in CO.sub.2 concentration that are not anti-correlated with O.sub.2 concentration, and to identify a potential CO.sub.2 leak in response thereto. The analysis may include determining eddy covariance flux measurements of sub-surface potential carbon.

Dosimetric And Fluence Measurements At Hadron Facilities For LHC Radiation Damage Studies

CERN Document Server

León-Florián, E

2001-01-01

Dosimetry plays an essential role in experiments assessing radiation damage and hardness for the components of detectors to be operated at the future Large Hadron Collider (LHC), CERN (European Laboratory for Particle Physics), Geneva, Switzerland. Dosimetry is used both for calibration of the radiation fields and estimate of fluences and doses during the irradiation tests. The LHC environment will result in a complex radiation field composed of hadrons (mainly neutrons, pions and protons) and photons, each having an energy spectrum ranging from a few keV to several hundreds of MeV or several GeV, even. In this thesis, are exposed the results of measurements of particle fluences and doses at different hadron irradiation facilities: SARA, πE1-PSI and ZT7PS used for testing the radiation hardness of materials and equipment to be used in the future experiments at LHC. These measurements are applied to the evaluation of radiation damage inflicted to various semiconductors (such as silicon) and electronics ...

Measuring School Facility Conditions: An Illustration of the Importance of Purpose

Science.gov (United States)

Roberts, Lance W.

2009-01-01

Purpose: The purpose of this paper is to argue that taking the educational purposes of schools into account is central to understanding the place and importance of facilities to learning outcomes. The paper begins by observing that the research literature connecting facility conditions to student outcomes is mixed. A closer examination of this…

Atmospheric radiation measurement program facilities newsletter, April 2001.; TOPICAL

International Nuclear Information System (INIS)

Holdridge, D. J.

2001-01-01

) Validation Campaign-Researchers from Lawrence Berkeley National Laboratory in California will be deploying instruments at the CART site in May. Portable micrometeorology towers will be used to measure fluxes of carbon dioxide, water, and heat between the surface and the atmosphere. The exchange of these constituents varies with regional climate, soil type, and surface vegetation. Greater knowledge will improve the accuracy of computer models (and hence predictions) of the exchanges. Measurements made with the portable instruments will be compared with measurements being collected by instruments at the central facility. AWS Campaign-The State University of New York at Albany will deploy an oxygen A-band and water vapor band spectrometer (AWS) at the CART site on May 20-June 30, 2001. Measurements made by the AWS will be used to determine absorption of radiation by water vapor within clouds, a quantity important to understanding the behavior of solar radiation as it passes through clouds

Pore pressure measurement plan of near field rock used on three dimensional groundwater flow analysis in demonstration test of cavern type disposal facility

International Nuclear Information System (INIS)

Onuma, Kazuhiro; Terada, Kenji; Matsumura, Katsuhide; Koyama, Toshihiro; Yajima, Kazuaki

2008-01-01

Demonstration test of underground cavern type disposal facilities is planed though carrying out construction of full scale engineering barrier system which simulated in the underground space in full scale and under actual environment. This test consists of three part, these are construction test, performance test and measurement test. Behavior of near field rock mass is measured about hydrological behavior under and after construction to evaluate effect at test facility. To make plan of pore pressure measurement, three dimensional groundwater flow analysis has been carried out. Based on comparison of analysis before and after test, detail plan has been studied. (author)

NIST display colorimeter calibration facility

Science.gov (United States)

Brown, Steven W.; Ohno, Yoshihiro

2003-07-01

A facility has been developed at the National Institute of Standards and Technology (NIST) to provide calibration services for color-measuring instruments to address the need for improving and certifying the measurement uncertainties of this type of instrument. While NIST has active programs in photometry, flat panel display metrology, and color and appearance measurements, these are the first services offered by NIST tailored to color-measuring instruments for displays. An overview of the facility, the calibration approach, and associated uncertainties are presented. Details of a new tunable colorimetric source and the development of new transfer standard instruments are discussed.

Materials Characterization Facility

Data.gov (United States)

Federal Laboratory Consortium — The Materials Characterization Facility enables detailed measurements of the properties of ceramics, polymers, glasses, and composites. It features instrumentation...

A standard fission neutron irradiation facility

International Nuclear Information System (INIS)

Sahasrabudhe, S.G.; Chakraborty, P.P.; Iyer, M.R.; Kirthi, K.N.; Soman, S.D.

1979-01-01

A fission neutron irradiation facility (FISNIF) has been set up at the thermal column of the CIRUS reactor at BARC. The spectrum and the flux have been measured using threshold detectors. The paper describes the setting up of the facility, measurement and application. A concentric cylinder containing UO 2 powder sealed inside surrounds the irradiation point of a pneumatic sample transfer system located in the thermal column of the reactor. Samples are loaded in a standard aluminium capsule with cadmium lining and transported pneumatically. A sample transfer time of 1 s can be achieved in the facility. Typical applications of the facility for studying activation of iron and sodium in fission neutrons are also discussed. (Auth.)

An Approach to Safeguards by Design (SBD) for Fuel Cycle Facilities

International Nuclear Information System (INIS)

Sankaran Nair, P.; Gangotra, S.; Karanam, R.

2015-01-01

Implementation of safeguards in bulk handling facilities such as fuel fabrication facilities and reprocessing facilities are a challenging task. This is attributed to the nuclear material present in the facility in the form of powder, pellet, green pellet, solution and gaseous. Additionally material hold up, material unaccounted for (MUF) and the operations carried out round the clock add to the difficulties in implementing safeguards. In facilities already designed or commissioned or operational, implementation of safeguards measures are relatively difficult. The authors have studied a number of measures which can be adopted at the design stage itself. Safeguard By Design (SBD) measures can help in more effective implementation of safeguards, reduction of cost and reduction in radiological dose to the installation personnel. The SBD measures in the power reactors are comparatively easier to implement than in the fuel fabrication plants, since reactors are item counting facilities while the fuel fabrication plants are bulk handling type of facilities and involves much rigorous nuclear material accounting methodology. The safeguards measures include technical measures like dynamic nuclear material accounting, near real time monitoring, remote monitoring, use of automation, facility imagery, Radio Frequency Identification (RFID) tagging, reduction of MUF in bulk handling facilities etc. These measures have been studied in the context of bulk handling facilities and presented in this paper. Incorporation of these measures at the design stage (SBD) is expected to improve the efficiency of safeguardability in such bulk handling and item counting facilities and proliferation resistance of nuclear material handled in such facilities. (author)

Facility Safeguardability Analysis In Support of Safeguards-by-Design

Energy Technology Data Exchange (ETDEWEB)

Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

2010-07-01

The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

Atmospheric Radiation Measurement Program facilities newsletter, February 2001.; TOPICAL

International Nuclear Information System (INIS)

Holdridge, D. J.

2001-01-01

This newsletter consists of the following: (1) ARM Science Team Meeting Scheduled-The 11th Annual ARM Science Team meeting is scheduled for March 19-23, 2001, in Atlanta, Georgia. Members of the science team will exchange research results achieved by using ARM data. The science team is composed of working groups that investigate four topics: instantaneous radiative flux, cloud parameterizations and modeling, cloud properties, and aerosols. The annual meeting brings together the science team's 150 members to discuss issues related to ARM and its research. The members represent universities, government laboratories and research facilities, and independent research companies. (2) Communications to Extended Facilities Upgraded-New communications equipment has been installed at all of the SGP extended facilities. Shelters were installed to house the new equipment used to transfer data from instruments via the Internet to the site data system at the central facility. This upgrade has improved data availability from the extended facilities to 100% and reduced telephone costs greatly. (3) SGP Goes ''Buggy''-Steve Sekelsky, a researcher from the University of Massachusetts, is planning to bring a 95-GHz radar to the SGP central facility for deployment in March-October 2001. The radar will help to identify signals due to insects flying in the air. The ARM millimeter cloud radar, which operates at 35 GHz, is sensitive to such insect interference. Testing will also be performed by using a second 35-GHz radar with a polarized radar beam, which can differentiate signals from insects versus cloud droplets. (4) Winter Fog-Fog can add to hazards already associated with winter weather. Common types of fog formation include advection, radiation, and steam. Advection fog: An advection fog is a dense fog that forms when a warm, moist air mass moves into an area with cooler ground below. For example, fog can form in winter when warmer, water-saturated air from the south (associated with

Thermal-Hydraulic Experiment Facility (THEF)

International Nuclear Information System (INIS)

Martinell, J.S.

1982-01-01

This paper provides an overview of the Thermal-Hydraulic Experiment Facility (THEF) at the Idaho National Engineering Laboratory (INEL). The overview describes the major test systems, measurements, and data acquisition system, and presents objectives, facility configuration, and results for major experimental projects recently conducted at the THEF. Plans for future projects are also discussed. The THEF is located in the Water Reactor Research Test Facility (WRRTF) area at the INEL

Detailed description of an SSAC at the facility level for research laboratory facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-08-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Study of 234U(n,f) Resonances Measured at the CERN n_TOF Facility

CERN Document Server

Leal-Cidoncha, E; Paradela, C; Tarrío, D; Leong, L S; Audouin, L; Tassan-Got, L; Praena, J; Berthier, B; Ferrant, L; Isaev, S; Le Naour, C; Stephan, C; Trubert, D; Abbondanno, U; Aerts, G; Álvarez, H; Álvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Badurek, G; Baumann, P; Bečvář, F; Berthoumieux, E; Calviño, F; Calviani, M; Cano-Ott, D; Capote, R; Carrapiço, C; Cennini, P.; Chepel, V; Chiaveri, E.; Colonna, N; Cortes, G; Couture, A; Cox, J; Dahlfors, M; David, S.; Dillmann, I; Domingo-Pardo, C; Dridi, W; Eleftheriadis, C; Embid-Segura, M; Ferrari, A.; Ferreira-Marques, R; Fujii, K; Furman, W; Gonçalves, I; González-Romero, E; Gramegna, F; Guerrero, C; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martinez, A.; Igashira, M; Jericha, E; Kadi, Y.; Käppeler, F; Karadimos, D; Kerveno, M; Koehler, P; Kossionides, E; Krtička, M; Lampoudis, C; Leeb, H; Lindote, A; Lopes, I; Lozano, M; Lukic, S; Marganiec, J; Marrone, S; Martínez, T; Massimi, C; Mastinu, P; Mengoni, A; Milazzo, P M; Moreau, C; Mosconi, M; Neves, F; Oberhummer, H; O'Brien, S; Oshima, M; Pancin, J; Papadopoulos, C; Pavlik, A; Pavlopoulos, P.; Perrot, L; Pigni, M T; Plag, R; Plompen, A; Plukis, A; Poch, A; Pretel, C; Quesada, J; Rauscher, T.; Reifarth, R; Rubbia, C.; Rudolf, G; Rullhusen, P; Salgado, J; Santos, C; Sarchiapone, L.; Savvidis, I; Tagliente, G; Tain, J L; Tavora, L; Terlizzi, R; Vannini, G; Vaz, P; Ventura, A.; Villamarin, D; Vincente, M C; Vlachoudis, V.; Vlastou, R; Voss, F; Walter, S; Wiescher, M; Wisshak, K

2014-01-01

We present the analysis of the resolved resonance region for the U-234(n,f) cross section data measured at the CERN n\\_TOF facility. The resonance parameters in the energy range from 1 eV to 1500 eV have been obtained with the SAMMY code by using as initial parameters for the fit the resonance parameters of the JENDL-3.3 evaluation. In addition, the statistical analysis has been accomplished, partly with the SAMDIST code, in order to study the level spacing and the Mehta-Dyson correlation.

Guidance for the Implementation and Follow-up of Identified Energy and Water Efficiency Measures in Covered Facilities

Energy Technology Data Exchange (ETDEWEB)

None

2012-09-01

This document provides specific guidance to agencies on the implementation and follow-up of energy and water efficiency measures identified and undertaken per Section 432 of the Energy Independence and Security Act of 2007 (EISA) (42 U.S.C. 8253(f)(4) and (5)) This guidance also provides context for how these activities fit into the comprehensive approach to facility energy and water management outlined by the statute and incorporates by reference previous DOE guidance released for Section 432 of EISA and other related documents. 42 U.S.C. 8253(f)(7)(A) specifies that facility energy managers shall certify compliance for each covered facility with the 42 U.S.C. 8253(f)(2)-(5) requirements via a web-based tracking system and make it publicly available. This document also describes the role of the tracking system that has been developed for the collection and reporting of data needed for the demonstration of compliance and progress toward meeting all energy and water efficiency requirements outlined in the statute.

Recent measurements of soft X-ray emission from the DPF-1000U facility

Directory of Open Access Journals (Sweden)

Surała Władysław

2015-06-01

Full Text Available Soft X-ray imaging is a very useful diagnostic technique in plasma-focus (PF experiments. This paper reports results of four experimental sessions which were carried out at the DPF-1000U plasma-focus facility in 2013 and 2014. Over 200 discharges were performed at various experimental conditions. Measurements were taken using two X-ray pinhole cameras with a line of sight perpendicular to the z-axis, at different azimuthal angles (about 20° and 200°, and looking towards the centre of the PF-pinch column. They were equipped with diaphragms 1000 μm or 200–300 μm in diameter and coated with filters of 500 μm Al foil and 10 μm Be foil, respectively. Data on the neutron emission were collected with silver activation counters. For time-resolved measurements the use was made of four PIN diodes equipped with various filters and oriented towards the centre of the PF-column, in the direction perpendicular to the electrode axis. The recorded X-ray images revealed that when the additional gas-puff system is activated during the discharge, the stability of the discharge is improved. The data collected in these experiments confirmed the appearance of a filamentary fine structure in the PF discharges. In the past years the formation of such filaments was observed in many Z-pinch type experiments. Some of the recorded X-ray images have also revealed the appearance of the so-called hot-spots, i.e. small plasma regions of a very intense X-ray emission. Such a phenomenon was observed before in many PF experiments, e.g. in the MAJA-PF device, but it has not been investigated so far in a large facility such as the DPF-1000U. The time-resolved measurements provided the evidence of a time lapse between the X-ray emission from plasma regions located at different distance from the anode surface. The formation of distinct ‘hot-spots’ in different instants of the DPF-1000U discharge was also observed.

Safeguards approach for conditioning facility for spent fuel

International Nuclear Information System (INIS)

Younkin, J.M.; Barham, M.; Moran, B.W.

1999-01-01

A safeguards approach has been developed for conditioning facilities associated with the final disposal of spent fuel in geologic repositories. The proposed approach is based on a generic conditioning facility incorporating common features of conditioning facility designs currently proposed. The generic facility includes a hot cell for consolidation of spent fuel pins and repackaging of spent fuel items such as assemblies and cans of pins. The consolidation process introduces safeguards concerns which have not previously been addressed in traditional safeguards approaches. In developing the safeguards approach, diversion of spent fuel was assessed in terms of potential target items, operational activities performed on the items, containment of the items, and concealment activities performed on the items. The combination of these factors defines the potential diversion pathways. Diversion pathways were identified for spent fuel pellets, pins, assemblies, canisters, and casks. Diversion activities provide for opportunities of detection along the diversion paths. Potential detection methods were identified at several levels of diversion activities. Detection methods can be implemented through safeguards measures. Safeguards measures were proposed for each of the primary safeguards techniques of design information verification (DIV), containment and surveillance (C/S), and material accountancy. Potential safeguards approaches were developed by selection of appropriate combinations of safeguards measures. For all candidate safeguards approaches, DIV is a fundamental component. Variations in the approaches are mainly in the degree of C/S measures and in the types and numbers of material accountancy verification measures. The candidate safeguards approaches were evaluated toward the goal of determining a model safeguards approach. This model approach is based on the integrated application of selected safeguards measures to use International Atomic Energy Agency resources

Measurement of angular differential cross sections at the SSL Atomic Scattering Facility

International Nuclear Information System (INIS)

Kvale, T.J.

1988-01-01

The design of the SSL Atomic Scattering Facility (ASF) located at the NASA/Marshall Space Flight Center as well as some of the initial experiments to be performed with it, are covered. The goal is to develop an apparatus capable of measuring angular differential cross sections (ADCS) for the scattering of 2 to 14 eV atomic oxygen from various gaseous targets. At present little is known about atomic oxygen scattering with kinetic energies of a few eV. This apparatus is designed to increase the understanding of collisions in this energy region. Atomic oxygen scattering processes are of vital interest to NASA because the space shuttle as well as other low earth orbit satellites will be subjected to a flux of 5 eV atomic oxygen on the ram surfaces while in orbit. The primary experiments will involve the measurements of ADCS for atomic oxygen scattering from gaseous targets (in particular, molecular nitrogen). These, as well as the related initial experiments involving thermal He scattering from N2 and O2 targets will be described

Guideline to good practices for control and calibration of measuring and test equipment (M ampersand TE) at DOE nuclear facilities

International Nuclear Information System (INIS)

1993-03-01

The purpose of the Guideline to Good Practices for Control and Calibration of Measuring and Test Equipment (M ampersand TE) at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a rigorously controlled maintenance program directed at controlling and calibrating M ampersand TE used for maintenance tasks at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 11. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing an M ampersand TE program applicable to their facility

Radon and radon daughter measurements and methods utilized by EPA's Eastern Environmental Radiation Facility

International Nuclear Information System (INIS)

Phillips, C.R.

1977-01-01

The Eastern Environmental Radiation Facility (EERF), Office of Radiation Programs, has the responsibility for conducting the Environmental Protection Agency's study of the radiological impact of the phosphate industry. Numerous measurements in structures constructed on land reclaimed from phosphate mining showed that working levels in these structures range from 0.001 to 0.9 WL. Sampling is performed by drawing air through a 0.8 micrometer pore size, 25 mm diameter filter at a flow rate of 10 to 15 liters/minute for from 5 to 20 minutes, depending on the daughter levels anticipated. The detection system consists of a ruggedized silicon surface barrier detector (450 mm 2 -100 micrometer depletion) connected through an appropriate pre-amplifier-amplifier to a 1024-channel multichannel analyzer. Other measurement methods are also discussed

Measurements of the fast ion distribution during neutral beam injection and ion cyclotron heating in ATF [Advanced Toroidal Facility

International Nuclear Information System (INIS)

Wade, M.R.; Kwon, M.; Thomas, C.E.; Colchin, R.J.; England, A.C.; Gossett, J.M.; Horton, L.D.; Isler, R.C.; Lyon, J.F.; Rasmussen, D.A.; Rayburn, T.M.; Shepard, T.D.; Bell, G.L.; Fowler, R.H.; Morris, R.N.

1990-01-01

A neutral particle analyzer (NPA) with horizontal and vertical scanning capability has been used to make initial measurements of the fast ion distribution during neutral beam injection (NBI) and ion cyclotron heating (ICH) on the Advanced Toroidal Facility (ATF). These measurements are presented and compared with the results of modeling codes that predict the analyzer signals during these heating processes. 6 refs., 5 figs

Calorimeter probes for measuring high thermal flux. [in electric-arc jet facilities for planetary entry heating simulation

Science.gov (United States)

Russell, L. D.

1979-01-01

The paper describes expendable, slug-type calorimeter probes developed for measuring high heat-flux levels of 10-30 kW/sq cm in electric-arc jet facilities. The probes are constructed with thin tungsten caps mounted on Teflon bodies; the temperature of the back surface of the tungsten cap is measured, and its rate of change gives the steady-state, absorbed heat flux as the calorimeter probe heats to destruction when inserted into the arc jet. It is concluded that the simple construction of these probes allows them to be expendable and heated to destruction to obtain a measurable temperature slope at high heating rates.

Measurement of the Tracer Gradient and Sampling System Bias of the Hot Fuel Examination Facility Stack Air Monitoring System

Energy Technology Data Exchange (ETDEWEB)

Glissmeyer, John A.; Flaherty, Julia E.

2011-07-20

This report describes tracer gas uniformity and bias measurements made in the exhaust air discharge of the Hot Fuel Examination Facility at Idaho National Laboratory. The measurements were a follow-up on earlier measurements which indicated a lack of mixing of the two ventilation streams being discharged via a common stack. The lack of mixing is detrimental to the accuracy of air emission measurements. The lack of mixing was confirmed in these new measurements. The air sampling probe was found to be out of alignment and that was corrected. The suspected sampling bias in the air sample stream was disproved.

Facility Modeling Capability Demonstration Summary Report

International Nuclear Information System (INIS)

Key, Brian P.; Sadasivan, Pratap; Fallgren, Andrew James; Demuth, Scott Francis; Aleman, Sebastian E.; Almeida, Valmor F. de; Chiswell, Steven R.; Hamm, Larry; Tingey, Joel M.

2017-01-01

A joint effort has been initiated by Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Savanah River National Laboratory (SRNL), Pacific Northwest National Laboratory (PNNL), sponsored by the National Nuclear Security Administration's (NNSA's) office of Proliferation Detection, to develop and validate a flexible framework for simulating effluents and emissions from spent fuel reprocessing facilities. These effluents and emissions can be measured by various on-site and/or off-site means, and then the inverse problem can ideally be solved through modeling and simulation to estimate characteristics of facility operation such as the nuclear material production rate. The flexible framework called Facility Modeling Toolkit focused on the forward modeling of PUREX reprocessing facility operating conditions from fuel storage and chopping to effluent and emission measurements.

Facility Modeling Capability Demonstration Summary Report

Energy Technology Data Exchange (ETDEWEB)

Key, Brian P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sadasivan, Pratap [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fallgren, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Aleman, Sebastian E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); de Almeida, Valmor F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Chiswell, Steven R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, Larry [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Tingey, Joel M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-02-01

A joint effort has been initiated by Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Savanah River National Laboratory (SRNL), Pacific Northwest National Laboratory (PNNL), sponsored by the National Nuclear Security Administration’s (NNSA’s) office of Proliferation Detection, to develop and validate a flexible framework for simulating effluents and emissions from spent fuel reprocessing facilities. These effluents and emissions can be measured by various on-site and/or off-site means, and then the inverse problem can ideally be solved through modeling and simulation to estimate characteristics of facility operation such as the nuclear material production rate. The flexible framework called Facility Modeling Toolkit focused on the forward modeling of PUREX reprocessing facility operating conditions from fuel storage and chopping to effluent and emission measurements.

A New Ka-Band Scanning Radar Facility: Polarimetric and Doppler Spectra Measurements of Snow Events

Science.gov (United States)

Oue, M.; Kollias, P.; Luke, E. P.; Mead, J.

2017-12-01

Polarimetric radar analyses offer the capability of identification of ice hydrometeor species as well as their spatial distributions. In addition to polarimetric parameter observations, Doppler spectra measurements offer unique insights into ice particle properties according to particle fall velocities. In particular, millimeter-wavelength radar Doppler spectra can reveal supercooled liquid cloud droplets embedded in ice precipitation clouds. A Ka-band scanning polarimetric radar, named KASPR, was installed in an observation facility at Stony Brook University, located 22 km west of the KOKX NEXRAD radar at Upton, NY. The KASPR can measure Doppler spectra and full polarimetric variables, including radar reflectivity, differential reflectivity (ZDR), differential phase (φDP), specific differential phase (KDP), correlation coefficient (ρhv), and linear depolarization ratio (LDR). The facility also includes a micro-rain radar and a microwave radiometer capable of measuring reflectivity profiles and integrated liquid water path, respectively. The instruments collected initial datasets during two snowstorm events and two snow shower events in March 2017. The radar scan strategy was a combination of PPI scans at 4 elevation angles (10, 20, 45, and 60°) and RHI scans in polarimetry mode, and zenith pointing with Doppler spectra collection. During the snowstorm events the radar observed relatively larger ZDR (1-1.5 dB) and enhanced KDP (1-2 ° km-1) at heights corresponding to a plate/dendrite crystal growth regime. The Doppler spectra showed that slower-falling particles ( 1 m s-1). The weakly increased ZDR could be produced by large, faster falling particles such as quasi-spherical aggregates, while the enhanced KDP could be produced by highly-oriented oblate, slowly-falling particles. Below 2 km altitude, measurements of dual wavelength ratio (DWR) based on Ka and S-band reflectivities from the KASPR and NEXRAD radars were available. Larger DWR (>10 dB) suggested

Measurement of the 241Am and the 243Am Neutron Capture Cross Sections at the n_TOF Facility at CERN

CERN Document Server

Mendoza, E; Guerrero, C; Altstadt, S; Andrzejewski, J; Audouin, L; Barbagallo, M; Bécares, V; Bečvář, F; Belloni, F; Berthoumieux, E; Billowes, J; Boccone, V; Bosnar, D; Brugger, M; Calviani, M; Calviño, F; Carrapiço, C; Cerutti, F; Chiaveri, E; Chin, M; Colonna, N; Cortés, G; Cortés-Giraldo, M A; Diakaki, M; Domingo-Pardo, C; Duran, I; Dressler, R; Dzysiuk, N; Eleftheriadis, C; Ferrari, A; Fraval, K; Ganesan, S; García, A R; Giubrone, G; Gómez-Hornillos, M B; Gonçalves, I F; González-Romero, E; Griesmayer, E; Gunsing, F; Gurusamy, P; Jenkins, D G; Jericha, E; Kadi, Y; Käppeler, F; Karadimos, D; Kivel, N; Koehler, P; Kokkoris, M; Korschinek, G; Krtička, M; Kroll, J; Langer, C; Lederer, C; Leeb, H; Leong, L S; Losito, R; Manousos, A; Marganiec, J; Martínez, T; Mastinu, P F; Mastromarco, M; Massimi, C; Meaze, M; Mengoni, A; Milazzo, P M; Mingrone, F; Mirea, M; Mondelaers, W; Paradela, C; Pavlik, A; Perkowski, J; Pignatari, M; Plompen, A; Praena, J; Quesada, J M; Rauscher, T; Reifarth, R; Riego, A; Roman, F; Rubbia, C; Sarmento, R; Schillebeeckx, P; Schmidt, S; Schumann, D; Tagliente, G; Tain, J L; Tarrío, D; Tassan-Got, L; Tsinganis, A; Valenta, S; Vannini, G; Variale, V; Vaz, P; Ventura, A; Versaci, R; Vermeulen, M J; Vlachoudis, V; Vlastou, R; Wallner, A; Ware, T; Weigand, M; Weiß, C; Wright, T J; Žugec, P

2014-01-01

The capture cross sections of Am-241 and Am-243 were measured at the n\\_TOF facility at CERN in the epithermal energy range with a BaF2 Total Absorption Calorimeter. A preliminary analysis of the Am-241 and a complete analysis of the Am-243 measurement, including the data reduction and the resonance analysis, have been performed.

Measurement facilities and accuracy limits of sampling digital interferometers. Meresi lehetoesegek es hibaanalizis digitalis mintavetelezoe interferometeren

Energy Technology Data Exchange (ETDEWEB)

Czitrovszky, A.; Jani, P.; Szoter, L.

1990-12-15

We discuss the measurement facilities of a recently development sampling digital interferometer for machine tool testing. As opposed to conventional interferometers the present device provides possibilities for the digital storage up to 4 kHz of the complete information of the motion so that displacement, velocity, acceleration and power density spectrum measurement can be performed. An estimation is given for the truncation, round-off, jitter and frequency-aliasing sources of error of the reconstructed motion parameters. On the basis of the Shannon sampling theory optimal conditions of measurement parameters are defined for the case when the accuracy of the reconstructed part of motion and vibration is equal to the resolution of the conventional interferometer. 7 refs., 3 figs., 1 tab.

A neutron scattering device for void fraction measurement in channels of the RD-14M thermalhydraulics test facility

Energy Technology Data Exchange (ETDEWEB)

Han, P; Hussein, E M.A. [New Brunswick Univ., Fredericton (Canada). Dept. of Mechanical Engineering; Ingham, P J [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1996-12-31

This paper presents a neutron scattering device designed for measuring the void fraction of two-phase flow in the channels or heated sections of the RD-14M Thermalhydraulics Test Facility, located at the AECL Whiteshell Laboratories. The results of an on-line test of the device are presented. The performance of the scatterometer is assessed and is shown to be in agreement with the results inferred from other independent process-parameter measurements. (author). 2 refs., 7 figs.

Measurements of Tip Vortices from a Full-Scale UH-60A Rotor by Retro- Reflective Background Oriented Schlieren and Stereo Photogrammetry

Science.gov (United States)

Schairer, Edward; Kushner, Laura K.; Heineck, James T.

2013-01-01

Positions of vortices shed by a full-scale UH-60A rotor in forward flight were measured during a test in the National Full- Scale Aerodynamics Complex at NASA Ames Research Center. Vortices in a region near the tip of the advancing blade were visualized from two directions by Retro-Reflective Background-Oriented Schlieren (RBOS). Correspondence of points on the vortex in the RBOS images from both cameras was established using epipolar geometry. The object-space coordinates of the vortices were then calculated from the image-plane coordinates using stereo photogrammetry. One vortex from the tip of the blade that had most recently passed was visible in most of the data. The visibility of the vortices was greatest at high thrust and low advance ratios. At these favorable conditions, vortices from the most recent passages of all four blades were detected. The vortex positions were in good agreement with PIV data for a case where PIV measurements were also made. RBOS and photogrammetry provided measurements of the angle at which each vortex passed through the PIV plane.

Development of an underground HPGe array facility for ultra low radioactivity measurements

Energy Technology Data Exchange (ETDEWEB)

Sala, E.; Kang, W. G.; Kim, Y. D.; Lee, M. H.; Leonard, D. S. [Center for Underground Physics - Institute for Basic Science, Daejeon (Korea, Republic of); Hahn, I. S.; Kim, G. W.; Park, S. Y. [Ewha Womans University, Physics Department, Seoul (Korea, Republic of)

2015-08-17

Low Level Counting techniques using low background facilities are continuously under development to increase the possible sensitivity needed for rare physics events experiments. The CUP (Center for Underground Physics) group of IBS is developing, in collaboration with Canberra, a ultra low background instrument composed of two arrays facing each other with 7 HPGe detectors each. The low radioactive background of each detector has been evaluated and improved by the material selection of the detector components. Samples of all the building materials have been provided by the manufacturer and the contaminations had been measured using an optimized low background 100% HPGe with a dedicated shielding. The evaluation of the intrinsic background has been performed using MonteCarlo simulations and considering the contribution of each material with the measured contamination. To further reduce the background, the instrument will be placed in the new underground laboratory at YangYang exploiting the 700m mountain coverage and radon-free air supplying system. The array has been designed to perform various Ultra Low background measurements; the sensitivity we are expecting will allow not only low level measurements of Ra and Th contaminations in Copper or other usually pure materials, but also the search for rare decays. In particular some possible candidates and configurations to detect the 0νECEC (for example {sup 106}Cd and {sup 156}Dy) and rare β decays ({sup 96}Zr, {sup 180m}Ta , etc ) are under study.

Fission cross-section measurements on 233U and minor actinides at the CERN n-TOF facility

International Nuclear Information System (INIS)

Calviani, M.; Cennini, P.; Chiaveri, E.; Dahlfors, M.; Ferrari, A.; Herrera-Martinez, A.; Kadi, Y.; Sarchiapone, L.; Vlachoudis, V.; Colonna, N.; Terlizzi, R.; Abbondanno, U.; Marrone, S.; Belloni, F.; Fujii, K.; Moreau, C.; Aerts, G.; Andriamonje, S.; Berthoumieux, E.; Dridi, W.; Gunsing, F.; Pancin, J.; Perrot, L.; Plukis, A.; Alvarez, H.; Duran, I.; Paradela, C.; Alvarez-Velarde, F.; Cano-Ott, D.; Embid-Sesura, M.; Gonzalez-Romero, E.; Guerrero, C.; Martinez, T.; Vincente, M. C.; Andrzejewski, J.; Assimakopoulos, P.; Audouin, L.; David, S.; Ferrant, L.; Stephan, C.; Tassan-Got, L.; Badurek, G.; Jericha, E.; Leeb, H.; Oberhummer, H.; Pigni, M. T.; Baumann, P.; Kerveno, M.; Lukic, S.; Rudolf, G.; Becvar, F.; Calvino, F.; Capote, R.; Carrapico, C.; Chepel, V.; Ferreira-Marques, R.; Goncalves, I.; Lindote, A.; Lopes, I.; Neves, F.; Cortes, G.; Poch, A.; Pretel, C.; Couture, A.; Cox, J.; O'Brien, S.; Wiescher, M.; Dillmann, I.; Heil, M.; Kaeppeler, F.; Mosconi, M.; Plag, R.; Walter, S.; Wisshak, K.; Domingo-Pardo, C.; Eleftheriadis, C.; Furman, W.; Goverdovski, A.; Gramegna, F.; Mastinu, P.; Praena, J.; Haas, B.; Haight, R.; Igashira, M.; Karadimos, D.; Karamanis, D.; Ketlerov, V.; Koehler, P.; Konovalov, V.; Kossionides, E.; Krticka, M.; Lampoudis, C.; Lozano, M.; Marganiec, J.; Massimi, C.; Mengoni, A.; Milazzo, P. M.; Papachristodoulou, C.; Papadopoulos, C.; Patronis, N.; Pavlik, A.; Pavlopoulos, P.; Plompen, A.; Quesada, J.; Rauscher, T.; Reifarth, R.; Rubbia, C.; Rullhusen, P.; Salgado, J.; Santos, C.; Savvidis, I.; Tagliente, G.; Tain, J. L.; Tavora, L.; Vannini, G.; Vaz, P.; Ventura, A.; Villamarin, D.; Vlastou, R.; Voss, F.

2010-01-01

Neutron-induced fission cross-sections of minor actinides have been measured at the white neutron source n-TOF at CERN, Geneva. The studied isotopes include 233 U, interesting for Th/U based nuclear fuel cycles, 241, 243 Am and 245 Cm, relevant for transmutation and waste reduction studies in new generation fast reactors (Gen-IV) or Accelerator Driven Systems. The measurements take advantage of the unique features of the n-TOF facility, namely the wide energy range, the high instantaneous neutron flux and the low background. Results for the involved isotopes are reported from ∼30 meV to around 1 MeV neutron energy. The measurements have been performed with a dedicated Fission Ionization Chamber (FIC), relative to the standard cross-section of the 235 U fission reaction, measured simultaneously with the same detector. Results are here reported. (authors)

Mass Properties Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility is used to acquire accurate weight, 3 axis center of gravity and 3 axis moment of inertia measurements for air launched munitions and armament equipment.

A Framework for Measuring Student and Staff Satisfaction with University Campus Facilities

Science.gov (United States)

Kärnä, Sami; Julin, Päivi

2015-01-01

Purpose: The purpose of the study is to evaluate and discuss the extent of the satisfaction as perceived by the students and staff towards university facilities and services in two campuses in Finland. The aim is to analyse which facility-related factors have the greatest impacts on students' and staff's overall satisfaction.…

High-resolution spectroscopy for Doppler-broadening ion temperature measurements of implosions at the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Koch, J. A.; Stewart, R. E.; Beiersdorfer, P.; Shepherd, R.; Schneider, M. B.; Miles, A. R.; Scott, H. A.; Smalyuk, V. A.; Hsing, W. W. [Lawrence Livermore National Laboratory, P.O. Box 808, L-493, Livermore, California 94550 (United States)

2012-10-15

Future implosion experiments at the national ignition facility (NIF) will endeavor to simultaneously measure electron and ion temperatures with temporal and spatial resolution in order to explore non-equilibrium temperature distributions and their relaxation toward equilibrium. In anticipation of these experiments, and with understanding of the constraints of the NIF facility environment, we have explored the use of Doppler broadening of mid-Z dopant emission lines, such as krypton He-{alpha} at 13 keV, as a diagnostic of time- and potentially space-resolved ion temperature. We have investigated a number of options analytically and with numerical raytracing, and we have identified several promising candidate spectrometer designs that meet the expected requirements of spectral and temporal resolution and data signal-to-noise ratio for gas-filled exploding pusher implosions, while providing maximum flexibility for use on a variety of experiments that potentially include burning plasma.

RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

Photovoltaic Engineering Testbed: A Facility for Space Calibration and Measurement of Solar Cells on the International Space Station

Science.gov (United States)

Landis, Geoffrey A.; Bailey, Sheila G.; Jenkins, Phillip; Sexton, J. Andrew; Scheiman, David; Christie, Robert; Charpie, James; Gerber, Scott S.; Johnson, D. Bruce

2001-01-01

The Photovoltaic Engineering Testbed ("PET") is a facility to be flown on the International Space Station to perform calibration, measurement, and qualification of solar cells in the space environment and then returning the cells to Earth for laboratory use. PET will allow rapid turnaround testing of new photovoltaic technology under AM0 conditions.

Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities

International Nuclear Information System (INIS)

Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

1994-02-01

This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km 2 Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included

Direct observation of the Andreev reflection of a quasiparticle beam by quantum turbulence in superfluid 3He-B

International Nuclear Information System (INIS)

Bradley, D.I.; Fisher, S.N.; Guenault, A.M.; Lowe, M.R.; Pickett, G.R.; Rahm, A.

2003-01-01

A beam of quasiparticles from a black-body radiator is directed at a localized region of quantum turbulence generated by a vibrating wire resonator driven at super-critical velocity. We are able to measure directly the fraction of the incident quasiparticle beam which is retro-reflected from the turbulence by Andreev processes. Combining these measurements with previous measurements on the spatial extent of the turbulence may allow us to infer the vortex line density

Concepts for inventory verification in critical facilities

International Nuclear Information System (INIS)

Cobb, D.D.; Sapir, J.L.; Kern, E.A.; Dietz, R.J.

1978-12-01

Materials measurement and inventory verification concepts for safeguarding large critical facilities are presented. Inspection strategies and methods for applying international safeguards to such facilities are proposed. The conceptual approach to routine inventory verification includes frequent visits to the facility by one inspector, and the use of seals and nondestructive assay (NDA) measurements to verify the portion of the inventory maintained in vault storage. Periodic verification of the reactor inventory is accomplished by sampling and NDA measurement of in-core fuel elements combined with measurements of integral reactivity and related reactor parameters that are sensitive to the total fissile inventory. A combination of statistical sampling and NDA verification with measurements of reactor parameters is more effective than either technique used by itself. Special procedures for assessment and verification for abnormal safeguards conditions are also considered. When the inspection strategies and inventory verification methods are combined with strict containment and surveillance methods, they provide a high degree of assurance that any clandestine attempt to divert a significant quantity of fissile material from a critical facility inventory will be detected. Field testing of specific hardware systems and procedures to determine their sensitivity, reliability, and operational acceptability is recommended. 50 figures, 21 tables

Comparison of Stereo-PIV and Plenoptic-PIV Measurements on the Wake of a Cylinder in NASA Ground Test Facilities.

Science.gov (United States)

Fahringer, Timothy W.; Thurow, Brian S.; Humphreys, William M., Jr.; Bartram, Scott M.

2017-01-01

A series of comparison experiments have been performed using a single-camera plenoptic PIV measurement system to ascertain the systems performance capabilities in terms of suitability for use in NASA ground test facilities. A proof-of-concept demonstration was performed in the Langley Advanced Measurements and Data Systems Branch 13-inch (33- cm) Subsonic Tunnel to examine the wake of a series of cylinders at a Reynolds number of 2500. Accompanying the plenoptic-PIV measurements were an ensemble of complementary stereo-PIV measurements. The stereo-PIV measurements were used as a truth measurement to assess the ability of the plenoptic-PIV system to capture relevant 3D/3C flow field features in the cylinder wake. Six individual tests were conducted as part of the test campaign using three different cylinder diameters mounted in two orientations in the tunnel test section. This work presents a comparison of measurements with the cylinders mounted horizontally (generating a 2D flow field in the x-y plane). Results show that in general the plenoptic-PIV measurements match those produced by the stereo-PIV system. However, discrepancies were observed in extracted pro les of the fuctuating velocity components. It is speculated that spatial smoothing of the vector fields in the stereo-PIV system could account for the observed differences. Nevertheless, the plenoptic-PIV system performed extremely well at capturing the flow field features of interest and can be considered a viable alternative to traditional PIV systems in smaller NASA ground test facilities with limited optical access.

Corrective Measures Study Modeling Results for the Southwest Plume - Burial Ground Complex/Mixed Waste Management Facility

International Nuclear Information System (INIS)

Harris, M.K.

1999-01-01

Groundwater modeling scenarios were performed to support the Corrective Measures Study and Interim Action Plan for the southwest plume of the Burial Ground Complex/Mixed Waste Management Facility. The modeling scenarios were designed to provide data for an economic analysis of alternatives, and subsequently evaluate the effectiveness of the selected remedial technologies for tritium reduction to Fourmile Branch. Modeling scenarios assessed include no action, vertical barriers, pump, treat, and reinject; and vertical recirculation wells

A brief, standardized tool for measuring HIV-related stigma among health facility staff: results of field testing in China, Dominica, Egypt, Kenya, Puerto Rico and St. Christopher & Nevis.

Science.gov (United States)

Nyblade, Laura; Jain, Aparna; Benkirane, Manal; Li, Li; Lohiniva, Anna-Leena; McLean, Roger; Turan, Janet M; Varas-Díaz, Nelson; Cintrón-Bou, Francheska; Guan, Jihui; Kwena, Zachary; Thomas, Wendell

2013-11-13

Within healthcare settings, HIV-related stigma is a recognized barrier to access of HIV prevention and treatment services and yet, few efforts have been made to scale-up stigma reduction programs in service delivery. This is in part due to the lack of a brief, simple, standardized tool for measuring stigma among all levels of health facility staff that works across diverse HIV prevalence, language and healthcare settings. In response, an international consortium led by the Health Policy Project, has developed and field tested a stigma measurement tool for use with health facility staff. Experts participated in a content-development workshop to review an item pool of existing measures, identify gaps and prioritize questions. The resulting questionnaire was field tested in six diverse sites (China, Dominica, Egypt, Kenya, Puerto Rico and St. Christopher & Nevis). Respondents included clinical and non-clinical staff. Questionnaires were self- or interviewer-administered. Analysis of item performance across sites examined both psychometric properties and contextual issues. The key outcome of the process was a substantially reduced questionnaire. Eighteen core questions measure three programmatically actionable drivers of stigma within health facilities (worry about HIV transmission, attitudes towards people living with HIV (PLHIV), and health facility environment, including policies), and enacted stigma. The questionnaire also includes one short scale for attitudes towards PLHIV (5-item scale, α=0.78). Stigma-reduction programmes in healthcare facilities are urgently needed to improve the quality of care provided, uphold the human right to healthcare, increase access to health services, and maximize investments in HIV prevention and treatment. This brief, standardized tool will facilitate inclusion of stigma measurement in research studies and in routine facility data collection, allowing for the monitoring of stigma within healthcare facilities and evaluation of

Gaseous radioactive effluent restrictions, measurement, and minimization at a PET/cyclotron facility

International Nuclear Information System (INIS)

Plascjak, P.S.; Kim, K.K.; Googins, S.W.; Meyer, W.C. Jr.

1993-01-01

In the US, restrictions on the release of radioactive effluents from PET (positron emission tomography)/cyclotron facilities are typically imposed by State regulatory agencies and may be based on various methodologies and limits published by numerous agencies. This work presents suitable effluent concentration limits for various chemical forms of radioisotopes routinely produced in PET/cyclotron facilities. They were determined by application of metabolic models defined by ICRP 53 and ICRP 26/30 which will result in compliance with effective dose equivalent limits of 100 mrem per year at the release point. The NIH Cyclotron Facility effluent air monitoring system, environmental dosimetry program, and simple, effective systems for radioactive effluent minimization are also described. (orig.)

Underwater-manipulation system for measuring- and cutting tasks in dismantling decommissioned nuclear facilities. Final report

International Nuclear Information System (INIS)

Stegemann, D.; Reimche, W.; Hansch, M.; Spitzer, M.

1995-01-01

Not only manipulators are necessary for dismantling and inspection of structure parts in decomissioned nuclear facilities, but flexible underwater-vehicles. Free-diving underwater-vehicles for inspection and dismantling tasks are still not developed and tested. Aim of the project is the development of sensors and devices for the position determination and the depth regulation. For inspection tasks an ultrasonic measurement and dosimeter device shall be built up. A measurement device has been developed which evaluates the ultrasonic time of flight from a transmitter at the vehicle to several receivers, installed in the reactor pressure vessel. The depth regulation is based on a pressure sensor and the direct control of the thrusters. The ultrasonic measurements are realized by an adapted ultrasonic card, the γ-dosimetry with an ionization chamber and a pA-amplifier. An acoustic orientation system was built up, which measures very accurately with one transmitter mounted on the vehicle and four receivers. Problem occur by reflection from the walls of the basin. The depth regulation is working faultless. The ultrasonic device is preferably used for distance measurement. The radiation measurement device was tested and mounted in the vehicle. (orig./HP) [de

Measuring Dirac CP-violating phase with intermediate energy beta beam facility

Science.gov (United States)

Bakhti, P.; Farzan, Y.

2014-02-01

Taking the established nonzero value of , we study the possibility of extracting the Dirac CP-violating phase by a beta beam facility with a boost factor . We compare the performance of different setups with different baselines, boost factors, and detector technologies. We find that an antineutrino beam from He decay with a baseline of km has a very promising CP-discovery potential using a 500 kton water Cherenkov detector. Fortunately this baseline corresponds to the distance between FermiLAB to Sanford underground research facility in South Dakota.

How women are treated during facility-based childbirth: development and validation of measurement tools in four countries - phase 1 formative research study protocol.

Science.gov (United States)

Vogel, Joshua P; Bohren, Meghan A; Tunçalp, Özge; Oladapo, Olufemi T; Adanu, Richard M; Baldé, Mamadou Diouldé; Maung, Thae Maung; Fawole, Bukola; Adu-Bonsaffoh, Kwame; Dako-Gyeke, Phyllis; Maya, Ernest Tei; Camara, Mohamed Campell; Diallo, Alfa Boubacar; Diallo, Safiatou; Wai, Khin Thet; Myint, Theingi; Olutayo, Lanre; Titiloye, Musibau; Alu, Frank; Idris, Hadiza; Gülmezoglu, Metin A

2015-07-22

Every woman has the right to dignified, respectful care during childbirth. Recent evidence has demonstrated that globally many women experience mistreatment during labour and childbirth in health facilities, which can pose a significant barrier to women attending facilities for delivery and can contribute to poor birth experiences and adverse outcomes for women and newborns. However there is no clear consensus on how mistreatment of women during childbirth in facilities is defined and measured. We propose using a two-phased, mixed-methods study design in four countries to address these research gaps. This protocol describes the Phase 1 qualitative research activities. We will employ qualitative research methodologies among women, healthcare providers and administrators in the facility catchment areas of two health facilities in each country: Ghana, Guinea, Myanmar and Nigeria. In-depth interviews (IDIs) and focus group discussions (FGDs) will be conducted among women of reproductive age (15-49 years) to explore their perceptions and experiences of facility-based childbirth care, focused on how they were treated by healthcare workers and perceived factors affecting how they were treated. IDIs will also be conducted with healthcare providers of different cadres (e.g.: nurses, midwives, medical officers, specialist obstetricians) and facility administrators working in the selected facilities to explore healthcare providers' perceptions and experiences of facility-based childbirth care and how staff are treated, colleagues and supervisors. Audio recordings will be transcribed and translated to English. Textual data will be analysed using a thematic framework approach and will consist of two levels of analysis: (1) conduct of local analysis workshops with the research assistants in each country; and (2) line-by-line coding to develop a thematic framework and coding scheme. This study serves several roles. It will provide an in-depth understanding of how women are

Measurement of oxytetracycline and emamectin benzoate in freshwater sediments downstream of land based aquaculture facilities in the Atlantic Region of Canada.

Science.gov (United States)

Lalonde, Benoit A; Ernst, William; Greenwood, Lyndsay

2012-09-01

This study investigated the occurrence of oxytetracycline (OTC) and emamectin benzoate (EB) in sediments located near the effluent outfall from four freshwater aquaculture facilities in Atlantic Canada. While two facilities had no detectable concentrations of EB or OTC, two facilities had detectable concentrations of one or both of these chemicals. Concentrations ranged from <0.05-18 mg/kg to <0.01-2.5 mg/kg for OTC and EB respectively. Although these values could not be compared with freshwater toxicant values, some of the concentrations of EB and OTC detected were higher than LC(50) values calculated for marine invertebrates. OTC concentrations measured in this study are also of a magnitude which has been known to produce resistant bacteria.

Retroreflectivity database study.

Science.gov (United States)

2009-07-16

Pavement marking delineation is one method to provide positive driver guidance on all roadway types. There are a variety of pavement markings used by local and state transportation agencies in the United States. The type of pavement marking applied t...

Establishment and Operation of User Facilities

International Nuclear Information System (INIS)

Kim, Kye Ryung; Park, B. S.; Lim, Y. K.; Lee, S. K.; Jung, J. P.

2005-08-01

The final goal of this project is to establish the proton beam user facility which can offer the suitable proton beam for the user's demand. In the first phase we developed the key technologies that were required for the establishment of 20MeV and 100MeV proton user facilities. The user's demand survey was also achieved, and the test user facility was established on the results of the demand survey. Using the test facility, the users performed their pilot studies. Now, we have finished the conceptual design for 20MeV proton user facility. During the first phase we performed the user's demand survey and produced many materials related to the proton beam utilizations in domestic or abroad. The survey results were reflected on the establishment of the test user facility and the conceptual design of 20MeV/100MeV proton beam user facilities. We have developed the key technologies which concern to beam energy control, flux control, uniform irradiation, dose and uniformity measurement, proton energy measurement, SOBP(Spread-out Bragg Peak) system using a rotating range modulator, and carried out the conceptual design of 20MeV proton user facility. The test user facility has been constructed and operated for both verifying the developed key technologies and performing the user's preliminary experiments. 45MeV low flux user facility was constructed in 2003 and has performed a lot of irradiation experiments. The development of 1.8MeV test user facility was completed. Also the low energy user facility that KAERI kept was upgraded and used for many users. Therefore, we provided our users with various beams. On the other hand, the following activities were carried out, such as, inviting the oversea researchers, giving support to users to use the beam in domestic and abroad, discussing the beam utilization technologies by visiting the foreign user facilities, etc

Pose Measurement Method and Experiments for High-Speed Rolling Targets in a Wind Tunnel

Directory of Open Access Journals (Sweden)

Zhenyuan Jia

2014-12-01

Full Text Available High-precision wind tunnel simulation tests play an important role in aircraft design and manufacture. In this study, a high-speed pose vision measurement method is proposed for high-speed and rolling targets in a supersonic wind tunnel. To obtain images with high signal-to-noise ratio and avoid impacts on the aerodynamic shape of the rolling targets, a high-speed image acquisition method based on ultrathin retro-reflection markers is presented. Since markers are small-sized and some of them may be lost when the target is rolling, a novel markers layout with which markers are distributed evenly on the surface is proposed based on a spatial coding method to achieve highly accurate pose information. Additionally, a pose acquisition is carried out according to the mentioned markers layout after removing mismatching points by Case Deletion Diagnostics. Finally, experiments on measuring the pose parameters of high-speed targets in the laboratory and in a supersonic wind tunnel are conducted to verify the feasibility and effectiveness of the proposed method. Experimental results indicate that the position measurement precision is less than 0.16 mm, the pitching and yaw angle precision less than 0.132° and the roll angle precision 0.712°.

Pose measurement method and experiments for high-speed rolling targets in a wind tunnel.

Science.gov (United States)

Jia, Zhenyuan; Ma, Xin; Liu, Wei; Lu, Wenbo; Li, Xiao; Chen, Ling; Wang, Zhengqu; Cui, Xiaochun

2014-12-12

High-precision wind tunnel simulation tests play an important role in aircraft design and manufacture. In this study, a high-speed pose vision measurement method is proposed for high-speed and rolling targets in a supersonic wind tunnel. To obtain images with high signal-to-noise ratio and avoid impacts on the aerodynamic shape of the rolling targets, a high-speed image acquisition method based on ultrathin retro-reflection markers is presented. Since markers are small-sized and some of them may be lost when the target is rolling, a novel markers layout with which markers are distributed evenly on the surface is proposed based on a spatial coding method to achieve highly accurate pose information. Additionally, a pose acquisition is carried out according to the mentioned markers layout after removing mismatching points by Case Deletion Diagnostics. Finally, experiments on measuring the pose parameters of high-speed targets in the laboratory and in a supersonic wind tunnel are conducted to verify the feasibility and effectiveness of the proposed method. Experimental results indicate that the position measurement precision is less than 0.16 mm, the pitching and yaw angle precision less than 0.132° and the roll angle precision 0.712°.

Measuring relative humidity in the radioactive environment of the IRRAD proton facility

CERN Document Server

Paerg, Marten

2017-01-01

The aim of the project was to obtain information on relative humidity conditions at different locations in the IRRAD proton facility. Due to high radiation levels inside the facility, different sensors had to be qualified and dedicated electronics had to be built to transfer the data of the sensors over long wires to a less radioactive area, where it could be collected.

Distribution of physical activity facilities in Scotland by small area measures of deprivation and urbanicity

Directory of Open Access Journals (Sweden)

Ogilvie David

2010-10-01

Full Text Available Abstract Background The aim of this study was to examine the distribution of physical activity facilities by area-level deprivation in Scotland, adjusting for differences in urbanicity, and exploring differences between and within the four largest Scottish cities. Methods We obtained a list of all recreational physical activity facilities in Scotland. These were mapped and assigned to datazones. Poisson and negative binomial regression models were used to investigate associations between the number of physical activity facilities relative to population size and quintile of area-level deprivation. Results The results showed that prior to adjustment for urbanicity, the density of all facilities lessened with increasing deprivation from quintiles 2 to 5. After adjustment for urbanicity and local authority, the effect of deprivation remained significant but the pattern altered, with datazones in quintile 3 having the highest estimated mean density of facilities. Within-city associations were identified between the number of physical activity facilities and area-level deprivation in Aberdeen and Dundee, but not in Edinburgh or Glasgow. Conclusions In conclusion, area-level deprivation appears to have a significant association with the density of physical activity facilities and although overall no clear pattern was observed, affluent areas had fewer publicly owned facilities than more deprived areas but a greater number of privately owned facilities.

A heat transport benchmark problem for predicting the impact of measurements on experimental facility design

International Nuclear Information System (INIS)

Cacuci, Dan Gabriel

2016-01-01

Highlights: • Predictive Modeling of Coupled Multi-Physics Systems (PM_CMPS) methodology is used. • Impact of measurements for reducing predicted uncertainties is highlighted. • Presented thermal-hydraulics benchmark illustrates generally applicable concepts. - Abstract: This work presents the application of the “Predictive Modeling of Coupled Multi-Physics Systems” (PM_CMPS) methodology conceived by Cacuci (2014) to a “test-section benchmark” problem in order to quantify the impact of measurements for reducing the uncertainties in the conceptual design of a proposed experimental facility aimed at investigating the thermal-hydraulics characteristics expected in the conceptual design of the G4M reactor (GEN4ENERGY, 2012). This “test-section benchmark” simulates the conditions experienced by the hottest rod within the conceptual design of the facility's test section, modeling the steady-state conduction in a rod heated internally by a cosinus-like heat source, as typically encountered in nuclear reactors, and cooled by forced convection to a surrounding coolant flowing along the rod. The PM_CMPS methodology constructs a prior distribution using all of the available computational and experimental information, by relying on the maximum entropy principle to maximize the impact of all available information and minimize the impact of ignorance. The PM_CMPS methodology then constructs the posterior distribution using Bayes’ theorem, and subsequently evaluates it via saddle-point methods to obtain explicit formulas for the predicted optimal temperature distributions and predicted optimal values for the thermal-hydraulics model parameters that characterized the test-section benchmark. In addition, the PM_CMPS methodology also yields reduced uncertainties for both the model parameters and responses. As a general rule, it is important to measure a quantity consistently with, and more accurately than, the information extant prior to the measurement. For

Measuring client satisfaction and the quality of family planning services: a comparative analysis of public and private health facilities in Tanzania, Kenya and Ghana.

Science.gov (United States)

Hutchinson, Paul L; Do, Mai; Agha, Sohail

2011-08-24

Public and private family planning providers face different incentive structures, which may affect overall quality and ultimately the acceptability of family planning for their intended clients. This analysis seeks to quantify differences in the quality of family planning (FP) services at public and private providers in three representative sub-Saharan African countries (Tanzania, Kenya and Ghana), to assess how these quality differentials impact upon FP clients' satisfaction, and to suggest how quality improvements can improve contraceptive continuation rates. Indices of technical, structural and process measures of quality are constructed from Service Provision Assessments (SPAs) conducted in Tanzania (2006), Kenya (2004) and Ghana (2002) using direct observation of facility attributes and client-provider interactions. Marginal effects from multivariate regressions controlling for client characteristics and the multi-stage cluster sample design assess the relative importance of different measures of structural and process quality at public and private facilities on client satisfaction. Private health facilities appear to be of higher (interpersonal) process quality than public facilities but not necessarily higher technical quality in the three countries, though these differentials are considerably larger at lower level facilities (clinics, health centers, dispensaries) than at hospitals. Family planning client satisfaction, however, appears considerably higher at private facilities - both hospitals and clinics - most likely attributable to both process and structural factors such as shorter waiting times and fewer stockouts of methods and supplies. Because the public sector represents the major source of family planning services in developing countries, governments and Ministries of Health should continue to implement and to encourage incentives, perhaps performance-based, to improve quality at public sector health facilities, as well as to strengthen regulatory

Implementation of gas concentration measurement systems using mass spectrometry in containment thermal-hydraulics test facilities: different approaches for calibration and measurement with steam/air/helium mixtures

International Nuclear Information System (INIS)

Auban, O.; Malet, J.; Brun, P.; Brinster, J.; Quillico, J. J.; Studer, E.

2003-01-01

Thermal-hydraulic test facilities are used to investigate various containment phenomena such as, for example, mixing and stratification of gases or steam condensation in the presence of noncondensable. Experiments are also required for validation of codes possessing capabilities for modelling such three-dimensional effects. The need for advanced instrumentation allowing to measure gas concentration in such conditions (typically: 100-180 .deg. C; 1-10 bar) and to get sufficiently refined information about spatial distribution of the different gas species has become apparent. This paper deals with the implementation of gas analysis systems using some commercial Quadrupole Mass Spectrometers (QMS) that have been recently added to the basic instrumentation in three thermal-hydraulics test facilities namely MISTRA (CEA, France), TOSQAN (IRSN, France) and PANDA (PSI, Switzerland). In recent years, QMS have increasingly been selected for various applications because of attractive metrological characteristics (sensibility, span of concentration range, response time, stability, etc.), relatively compact size and low cost. Although commercial QMS are sold as 'turnkey' systems, these instruments are delicate to bring into operation. As QMS are not absolute instruments, reliable calibration procedures are required for quantitative measurements. A mass spectrometer can be regarded as an ionisation gauge with subsequent separation system for the different ion species. The calculation of gas concentrations considers the partial pressure of a particular gas species to be proportional to the ion current it generates. Anyway, one must know the QMS sensitivity to the gases of interest and the only practical method is to use calibration gases. Calibration must be carried out using mixtures whose compositions are close to any possible sample compositions and the procedure selected should duplicate as closely as possible the measurement conditions established during the real experiment

Automated Computer-Based Facility for Measurement of Near-Field Structure of Microwave Radiators and Scatterers

DEFF Research Database (Denmark)

Mishra, Shantnu R.;; Pavlasek, Tomas J. F.;; Muresan, Letitia V.

1980-01-01

An automatic facility for measuring the three-dimensional structure of the near fields of microwave radiators and scatterers is described. The amplitude and phase for different polarization components can be recorded in analog and digital form using a microprocessor-based system. The stored data...... are transferred to a large high-speed computer for bulk processing and for the production of isophot and equiphase contour maps or profiles. The performance of the system is demonstrated through results for a single conical horn, for interacting rectangular horns, for multiple cylindrical scatterers...

Detailed description of an SSAC at the facility level for mixed oxide fuel fabrication facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-09-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a mixed oxide fuel fabrication facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Measurement of natural radioactivity: Calibration and performance of a high-resolution gamma spectrometry facility

DEFF Research Database (Denmark)

Murray, A. S.; Helsted, L. M.; Autzen, M.

2018-01-01

Murray et al. (2015) described an international inter-comparison of dose rate measurements undertaken using a homogenised beach ridge sand from Jutland, Denmark. The measured concentrations for 226Ra, 232Th and 40K from different laboratories varied considerably, with relative standard deviations...... of 26% (n=8), 59% (n=23) and 15% (n=23), respectively. In contrast, the relative standard deviations observed internally within our laboratory were 9%, 11% and 7%, respectively (n=20), and in addition our mean values were consistent with the global 40K mean, but significantly different from the 232Th...... mean. These problems in both accuracy and precision have led us to examine both the long term performance of our analytical facility, and its calibration. Our approach to the preparation of new absolute 238U, 232Th and 40K standards is outlined and tested against international standards. We also report...

Measuring neutron yield and ρR anisotropies with activation foils at the National Ignition Facility

Directory of Open Access Journals (Sweden)

Bleuel D.L.

2013-11-01

Full Text Available Neutron yields at the National Ignition Facility (NIF are measured with a suite of diagnostics, including activation of ∼20–200 g samples of materials undergoing a variety of energy-dependent neutron reactions. Indium samples were mounted on the end of a Diagnostic Instrument Manipulator (DIM, 25–50 cm from the implosion, to measure 2.45 MeV D-D fusion neutron yield. The 336.2 keV gamma rays from the 4.5 hour isomer of 115mIn produced by (n,n′ reactions are counted in high-purity germanium detectors. For capsules producing D-T fusion reactions, zirconium and copper are activated via (n,2n reactions at various locations around the target chamber and bay, measuring the 14 MeV neutron yield to accuracies on order of 7%. By mounting zirconium samples on ports at nine locations around the NIF chamber, anisotropies in the primary neutron emission due to fuel areal density asymmetries can be measured to a relative precision of 3%.

Diagnostics of PF-1000 facility operation and plasma concentration on the basis of spectral measurements

International Nuclear Information System (INIS)

Skladnik-Sadowska, E.; Malinowski, K.; Sadowski, M.J.; Scholz, M.; Tsarenko, A.V.

2005-01-01

The paper concerns the monitoring of the operation of high-current pulse discharges and the determination of the plasma concentration within the dense magnetized plasma column by means of optical spectroscopy methods. In experiments performed within the large PF-1000 facility, which is operated at IPPLM in Warsaw, particular attention was paid to possibility of the determination of correctness of the operational mode. In order to measure the visible radiation (VR), as emitted from the collapsing current sheath and the dense pinch region, the use was made of the MECHELLE R 900-optical-spectrometer, which was equipped with a CCD measuring head. The spectral measurements were performed at an angle of about 650 to the symmetry axis of the PF electrode system, through an optical window and a special collimator coupled with the quartz optical-cable. The observed VR emission originated from a part of the inner- and outer-electrode surfaces, the collapsing current-sheath layer and a portion of the dense plasma pinch-region (located a distance of 40-50 mm from the electrode ends). Considerable differences were found in the optical spectra recorded for so-called good shots and for cases of some failures. In the case of a breakdown (damage) of the main insulator there were observed different Al-lines, which originated from the eroded insulator material. At so-called bad vacuum conditions there were recorded various C-lines, and at an uncontrolled air-leakage into the experimental chamber there appeared numerous N-lines. The appearance of these characteristic spectral lines made possible to determine whether the operation of the PF-1000 facility was correct or incorrect. The paper reports also on estimates of plasma concentration values, which have been performed on the basis of a quantitative analysis of the Stark broadening of the selected spectral lines. (author)

Recent ion measurements within the modified DPF-1000U facility

Directory of Open Access Journals (Sweden)

Kwiatkowski Roch

2015-06-01

Full Text Available In this note we describe measurements of ion beams emitted along the z-axis of the DPF-1000U facility operated at 23 kV, 334 kJ, and with the initial deuterium pressure of 1.6–2 hPa. The DPF-1000U device was recently renewed and equipped with a dynamic gas-puff valve placed inside the inner electrode. The investigated ions were recorded by means of ion pinhole cameras equipped with solid state nuclear track detectors of the PM-355® (PADC type. The energy spectra of ions were determined using a Thomson spectrometer placed on the symmetry axis at a distance of 160 cm from the electrodes outlets. The ion images recorded during discharges performed under different experimental conditions show that the ion beams have a complex structure, usually in the form of a central bunch and an annular stream composed of many micro-beams. Energies of the registered deuterons have been in the range of 30–700 keV, while the fast protons (which originated from the hydrogen remnants had energies in the range of 300–850 keV.

Measurement of the $^{242}$Pu(n,f) reaction cross-section at the CERN n_TOF facility

CERN Document Server

AUTHOR|(CDS)2080481; Kokkoris, Michael; Vlachoudis, Vasilis

The accurate knowledge of relevant nuclear data, such as the neutron-induced fission cross sections of various plutonium isotopes and other minor actinides, is crucial for the design of advanced nuclear systems as well as the development of comprehensive theoretical models of the fission process. The $^{242}$Pu(n,f) cross section was measured at the CERN n_TOF facility taking advantage of the wide energy range and the high instantaneous flux of the neutron beam. In this work, results for the $^{242}$Pu(n,f) measurement are presented along with a detailed description of the experimental setup, Monte-Carlo simulations and the analysis procedure, and a theoretical cross section calculation performed with the EMPIRE code.

Is the closest facility the one actually used? An assessment of travel time estimation based on mammography facilities.

Science.gov (United States)

Alford-Teaster, Jennifer; Lange, Jane M; Hubbard, Rebecca A; Lee, Christoph I; Haas, Jennifer S; Shi, Xun; Carlos, Heather A; Henderson, Louise; Hill, Deirdre; Tosteson, Anna N A; Onega, Tracy

2016-02-18

Characterizing geographic access depends on a broad range of methods available to researchers and the healthcare context to which the method is applied. Globally, travel time is one frequently used measure of geographic access with known limitations associated with data availability. Specifically, due to lack of available utilization data, many travel time studies assume that patients use the closest facility. To examine this assumption, an example using mammography screening data, which is considered a geographically abundant health care service in the United States, is explored. This work makes an important methodological contribution to measuring access--which is a critical component of health care planning and equity almost everywhere. We analyzed one mammogram from each of 646,553 women participating in the US based Breast Cancer Surveillance Consortium for years 2005-2012. We geocoded each record to street level address data in order to calculate travel time to the closest and to the actually used mammography facility. Travel time between the closest and the actual facility used was explored by woman-level and facility characteristics. Only 35% of women in the study population used their closest facility, but nearly three-quarters of women not using their closest facility used a facility within 5 min of the closest facility. Individuals that by-passed the closest facility tended to live in an urban core, within higher income neighborhoods, or in areas where the average travel times to work was longer. Those living in small towns or isolated rural areas had longer closer and actual median drive times. Since the majority of US women accessed a facility within a few minutes of their closest facility this suggests that distance to the closest facility may serve as an adequate proxy for utilization studies of geographically abundant services like mammography in areas where the transportation networks are well established.

Regulation for delivery of subsidies for urgent safety measures for atomic power generating facilities

International Nuclear Information System (INIS)

1984-01-01

The regulations provide for subsidies for the emergency measures taken by the prefecture concerned in preparation for a major accident in a nuclear power generating, etc. facility. These activities include an emergency communication network, emergency medical care, personnel education, and outfitting of emergency personnel. The contents are as follows: terms of subsidy allocations, the sum of a subsidy allocation, applications for subsidies, determination of subsidy allocations, withdrawal of applications the conditions attached to the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of the subsidies, withdrawal of the decision for subsidies, limitations for the disposal of the properties, etc. (Mori, K.)

Upgrade and development of nuclear data production test facility

Energy Technology Data Exchange (ETDEWEB)

Namkung, Won; Ko, I. S.; Cho, M. H.; Lee, Y. S.; Kang, H. S. [Pohang Univ. of Science and Technology, Pohang (Korea, Republic of); Kim, G. N. [Kyungpook National Univ., Daegu (Korea, Republic of); Koh, S. K. [Univ. of Ulsan, Ulsan (Korea, Republic of); Ro, T. I. [Donga Univ., Busan (Korea, Republic of); Choi, G. U. [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

2005-04-15

It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: upgrade the electron linac, collimators inside the TOF beam pipe, the development and installation of an automatic sample changer, the extension of the TOF beam line, and the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students.

Centroid stabilization for laser alignment to corner cubes: designing a matched filter

Energy Technology Data Exchange (ETDEWEB)

Awwal, Abdul A. S.; Bliss, Erlan; Brunton, Gordon; Kamm, Victoria Miller; Leach, Richard R.; Lowe-Webb, Roger; Roberts, Randy; Wilhelmsen, Karl

2016-11-08

Automation of image-based alignment of National Ignition Facility high energy laser beams is providing the capability of executing multiple target shots per day. One important alignment is beam centration through the second and third harmonic generating crystals in the final optics assembly (FOA), which employs two retroreflecting corner cubes as centering references for each beam. Beam-to-beam variations and systematic beam changes over time in the FOA corner cube images can lead to a reduction in accuracy as well as increased convergence durations for the template-based position detector. A systematic approach is described that maintains FOA corner cube templates and guarantees stable position estimation.

Strategic facility planning improves capital decision making.

Science.gov (United States)

Reeve, J R

2001-03-01

A large, Midwestern IDS undertook a strategic facility-planning process to evaluate its facility portfolio and determine how best to allocate future investments in facility development. The IDS assembled a facility-planning team, which initiated the planning process with a market analysis to determine future market demands and identify service areas that warranted facility expansion. The team then analyzed each of the IDS's facilities from the perspective of uniform capacity measurements, highest and best use compared with needs, building condition and investment-worthiness, and facility growth and site development opportunities. Based on results of the analysis, the strategy adopted entailed, in part, shifting some space from inpatient care to ambulatory care services and demolishing and replacing the 11 percent of facilities deemed to be in the worst condition.

Laundry monitor for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Ishibashi, Mitsuo (Toshiba Corp., Fuchu (Japan). Fuchu Works)

1984-06-01

A laundry monitor has been developed for the detection and cleansification of radiation contamination on the clothes, headgear, footgear, etc. of workers in nuclear facilities. With this monitor, measurement is made irrespective of the size and shape of the objects; a large-area plastic scintillation detector is incorporated; it has stable and highly sensitive characteristics, with the merits of swift measurement, economical operation and easy maintenance. Connected with a folding machine, automatic carrying and storing compartment through a conveyor, it is capable of saving energy and man power, contributing to scheduled operation, and improving the efficiency of the facilities.

Laundry monitor for nuclear facilities

International Nuclear Information System (INIS)

Ishibashi, Mitsuo

1984-01-01

A laundry monitor has been developed for the detection and cleansification of radiation contamination on the clothes, headgear, footgear, etc. of workers in nuclear facilities. With this monitor, measurement is made irrespective of the size and shape of the objects ; a large-area plastic scintillation detector is incorporated ; it has stable and highly sensitive characteristics, with the merits of swift measurement, economical operation and easy maintenance. Connected with a folding machine, automatic carrying and storing compartment through a conveyor, it is capable of saving energy and man power, contributing to scheduled operation, and improving the efficiency of the facilities. (author)

Integral test of JENDL-3.2 data by re-analysis of sample reactivity measurements at SEG and STEK facilities

International Nuclear Information System (INIS)

Dietze, Klaus

2001-01-01

Sample reactivity measurements, which have been performed at the fast-thermal coupled facilities RRR/SEG and STEK, have been re-analyzed using the JNC route for reactor calculation JENDL-3.2 // SLAROM / CITATION / PERKY. C/E-values of central reactivity worths (CRW) of FP nuclides, structural materials, and standards are given. (author)

Measurements and calculations of air activation in the NuMI neutrino production facility at Fermilab with the 120-GeV proton beam on target

Energy Technology Data Exchange (ETDEWEB)

Rakhno, I. L.; Hylen, J.; Kasper, P.; Mokhov, N. V.; Quinn, M.; Striganov, S. I.; Vaziri, K.

2018-01-01

Measurements and calculations of the air activation at a high-energy proton accelerator are described. The quantity of radionuclides released outdoors depends on operation scenarios including details of the air exchange inside the facility. To improve the prediction of the air activation levels, the MARS15 Monte Carlo code radionuclide production model was modified to be used for these studies. Measurements were done to benchmark the new model and verify its use in optimization studies for the new DUNE experiment at the Long Baseline Neutrino Facility (LBNF) at Fermilab. The measured production rates for the most important radionuclides – 11C, 13N, 15O and 41Ar – are in a good agreement with those calculated with the improved MARS15 code.

Measurements and calculations of air activation in the NuMI neutrino production facility at Fermilab with the 120-GeV proton beam on target

Science.gov (United States)

Rakhno, I. L.; Hylen, J.; Kasper, P.; Mokhov, N. V.; Quinn, M.; Striganov, S. I.; Vaziri, K.

2018-01-01

Measurements and calculations of the air activation at a high-energy proton accelerator are described. The quantity of radionuclides released outdoors depends on operation scenarios including details of the air exchange inside the facility. To improve the prediction of the air activation levels, the MARS15 Monte Carlo code radionuclide production model was modified to be used for these studies. Measurements were done to benchmark the new model and verify its use in optimization studies for the new DUNE experiment at the Long Baseline Neutrino Facility (LBNF) at Fermilab. The measured production rates for the most important radionuclides - 11C, 13N, 15O and 41Ar - are in a good agreement with those calculated with the improved MARS15 code.

Summary of 1988 WIPP [Waste Isolation Pilot Plant] Facility horizon gas flow measurements

International Nuclear Information System (INIS)

Stormont, J.C.

1990-11-01

Numerous gas flow measurements have been made at the Waste Isolation Pilot Plant (WIPP) Facility horizon during 1988. All tests have been pressure decay or constant pressure tests from single boreholes drilled from the underground excavations. The test fluid has been nitrogen. The data have been interpreted as permeabilities and porosities by means of a transient numerical solution method. A closed-form steady-state approximation provides a reasonable order-of-magnitude permeability estimate. The effective resolution of the measurement system is less than 10 -20 m 2 . Results indicate that beyond 1 to 5 m from an excavation, the gas flow is very small and the corresponding permeability is below the system resolution. Within the first meter of an excavation, the interpreted permeabilities can be 5 orders of magnitude greater than the undisturbed or far-field permeability. The interpreted permeabilities in the region between the undisturbed region and the first meter from an excavation are in the range of 10 -16 to 10 -20 m 2 . Measurable gas flow occurs to a greater depth into the roof above WIPP excavations of different sizes and ages than into the ribs and floor. The gas flows into the formation surrounding the smallest excavation tested are consistently lower than those at similar locations surrounding larger excavations of comparable age. Gas flow measured in the interbed layers near the WIPP excavations is highly variable. Generally, immediately above and below excavations, relatively large gas flow is measured in the interbed layers. These results are consistent with previous measurements and indicate a limited disturbed zone surrounding WIPP excavations. 31 refs., 99 figs., 5 tabs

124Xe(n,γ)125Xe and 124Xe(n,2n)123Xe measurements for National Ignition Facility

Science.gov (United States)

Bhike, Megha; Ludin, Nurin; Tornow, Werner

2015-05-01

The cross section for the 124Xe(n,γ)125Xe reaction has been measured for the first time for neutron energies above 100 keV. In addition, the 124Xe(n,2n)123Xe reaction has been studied between threshold and 14.8 MeV. The results of these measurements provide sensitive diagnostic tools for investigating properties of the inertial confinement fusion plasma in Deuterium-Tritium (DT) capsules at the National Ignition Facility (NIF) located at Lawrence Livermore National Laboratory.

Comparison of calculations with neutron dosimetry measurements performed at the Oak Ridge Poolside Facility

Energy Technology Data Exchange (ETDEWEB)

Maerker, R.E.; Williams, M.L.

1981-01-01

The Oak Ridge Poolside Facility (PSF), like the Pool Critical Assembly (PCA), is used for benchmark dosimetry measurements which can serve to validate the transport methods used in calculating the high-energy neutron fluences (> 0.1 MeV) in LWR pressure vessels required to estimate the neutron damage to the pressure vessels in the form of embrittlement. The PSF consists of an arrangement of two water gaps of 4 and 12 cm thickness separated by a simulated thermal shield and followed by a simulated pressure vessel wall and then a void box to represent a reactor cavity. The PSF is driven by the 30 MW ORR reactor, whereas the geometrically similar core of the PCA has a maximum power of only 10 KW. This paper reports the results of some calculated activities and compares them with published PSF measurements performed by HEDL and other laboratories on the so-called Westinghouse surveillance capsule perturbation experiment.

Comparison of calculations with neutron dosimetry measurements performed at the Oak Ridge Poolside Facility

International Nuclear Information System (INIS)

Maerker, R.E.; Williams, M.L.

1981-01-01

The Oak Ridge Poolside Facility (PSF), like the Pool Critical Assembly (PCA), is used for benchmark dosimetry measurements which can serve to validate the transport methods used in calculating the high-energy neutron fluences (> 0.1 MeV) in LWR pressure vessels required to estimate the neutron damage to the pressure vessels in the form of embrittlement. The PSF consists of an arrangement of two water gaps of 4 and 12 cm thickness separated by a simulated thermal shield and followed by a simulated pressure vessel wall and then a void box to represent a reactor cavity. The PSF is driven by the 30 MW ORR reactor, whereas the geometrically similar core of the PCA has a maximum power of only 10 KW. This paper reports the results of some calculated activities and compares them with published PSF measurements performed by HEDL and other laboratories on the so-called Westinghouse surveillance capsule perturbation experiment

High-precision measurement of the 238U(n,γ) cross-section at the n-TOF facility, CERN

International Nuclear Information System (INIS)

Wright, Tobias James; Billowes, Jon; Mingrone, Federica; Massimi, Cristian; Berthoumieux, Eric; Gunsing, Frank; Cano-Ott, Daniel; Mendoza, Emilio; Guerrero, Carlos; Schillebeeckx, P.

2014-01-01

A new experiment to measure the 238 U(n,γ) cross-section has been carried out at the CERN n-TOF facility within the ANDES project. Two complementary detection systems have been used: two low neutron sensitivity C6D6 detectors and the Total Absorption Calorimeter (TAC) comprising 40 BaF 2 scintillators. High quality data has been obtained up to 10 keV with the TAC and up to a higher neutron energy unresolved region with the C 6 D 6 . All the steps in the measurements and the subsequent data analysis are dealt with in depth, aiming for overall 2-3% accuracy per detection system. (authors)

Line facilities outline

International Nuclear Information System (INIS)

1998-08-01

This book deals with line facilities. The contents of this book are outline line of wire telecommunication ; development of line, classification of section of line and theory of transmission of line, cable line ; structure of line, line of cable in town, line out of town, domestic cable and other lines, Optical communication ; line of optical cable, transmission method, measurement of optical communication and cable of the sea bottom, Equipment of telecommunication line ; telecommunication line facilities and telecommunication of public works, construction of cable line and maintenance and Regulation of line equipment ; regulation on technique, construction and maintenance.

Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities. Volume 4

Energy Technology Data Exchange (ETDEWEB)

Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

1994-02-01

This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km{sup 2} Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included.

Establishment and operation of a photovoltaic cell test facility

Energy Technology Data Exchange (ETDEWEB)

Pearsall, N.M.; Forbes, I.

1999-07-01

This report describes the setting up of a test facility at the University of Northumbria. Details of the equipment specification and procurement are given, and the commissioning and initial operation of the facility, and the measurement procedures for I-V characteristics, spectral response measurements, optical scanning and test charges are outlined. The business plan for the test facility is discussed, and operating experience is reviewed in terms of publicity, services provided, and collaboration.

Application of Plenoptic PIV for 3D Velocity Measurements Over Roughness Elements in a Refractive Index Matched Facility

Science.gov (United States)

Thurow, Brian; Johnson, Kyle; Kim, Taehoon; Blois, Gianluca; Best, Jim; Christensen, Ken

2014-11-01

The application of Plenoptic PIV in a Refractive Index Matched (RIM) facility housed at Illinois is presented. Plenoptic PIV is an emerging 3D diagnostic that exploits the light-field imaging capabilities of a plenoptic camera. Plenoptic cameras utilize a microlens array to measure the position and angle of light rays captured by the camera. 3D/3C velocity fields are determined through application of the MART algorithm for volume reconstruction and a conventional 3D cross-correlation PIV algorithm. The RIM facility is a recirculating tunnel with a 62.5% aqueous solution of sodium iodide used as the working fluid. Its resulting index of 1.49 is equal to that of acrylic. Plenoptic PIV was used to measure the 3D velocity field of a turbulent boundary layer flow over a smooth wall, a single wall-mounted hemisphere and a full array of hemispheres (i.e. a rough wall) with a k/ δ ~ 4.6. Preliminary time averaged and instantaneous 3D velocity fields will be presented. This material is based upon work supported by the National Science Foundation under Grant No. 1235726.

New applications of 14C measurements at the Lund AMS Facility

International Nuclear Information System (INIS)

Stenstroem, K.

1995-11-01

Some new applications of accelerator mass spectroscopy (AMS) with 14 C are presented. In the first part the sample preparation used for production of elemental carbon at the Lund AMS facility is described. The second part concerns the release of 14 C from nuclear power plants. In a one-year study, the total airborne discharge of 14 C from two Swedish reactors was measured. In another study, the fraction of 14 CO 2 of the total airborne 14 C release was determined. The third part of the thesis involves the use of 14 C in nuclear medicine. The long-term retention of 14 C-labelled triolein after a fat-malabsorption test has been investigated by means of AMS by analysis of expired CO 2 . The possibilities of using ultra-low amounts of activity for fat-malabsorption tests, employing AMS technique, is demonstrated. In the last part AMS and 14 C-labelled tracers are used in food chemistry studies of interactions between foods and packaging materials. 22 refs, 8 figs, 2 tabs

Space Power Facility (SPF)

Data.gov (United States)

Federal Laboratory Consortium — The Space Power Facility (SPF) houses the world's largest space environment simulation chamber, measuring 100 ft. in diameter by 122 ft. high. In this chamber, large...

A diamond detector for inertial confinement fusion X-ray bang-time measurements at the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

MacPhee, A G; Brown, C; Burns, S; Celeste, J; Glenzer, S H; Hey, D; Jones, O S; Landen, O; Mackinnon, A J; Meezan, N; Parker, J; Edgell, D; Glebov, V Y; Kilkenny, J; Kimbrough, J

2010-11-09

An instrument has been developed to measure X-ray bang-time for inertial confinement fusion capsules; the time interval between the start of the laser pulse and peak X-ray emission from the fuel core. The instrument comprises chemical vapor deposited polycrystalline diamond photoconductive X-ray detectors with highly ordered pyrolytic graphite X-ray monochromator crystals at the input. Capsule bang-time can be measured in the presence of relatively high thermal and hard X-ray background components due to the selective band pass of the crystals combined with direct and indirect X-ray shielding of the detector elements. A five channel system is being commissioned at the National Ignition Facility at Lawrence Livermore National Laboratory for implosion optimization measurements as part of the National Ignition Campaign. Characteristics of the instrument have been measured demonstrating that X-ray bang-time can be measured with {+-} 30ps precision, characterizing the soft X-ray drive to +/- 1eV or 1.5%.

Introduction of neutron research facilities in Indonesia Nuclear Agency

International Nuclear Information System (INIS)

Nishida, Masayuki; Muslih, M. Refai; Minakawa, Nobuaki

2004-01-01

In this report, some facilities for neutron diffraction installed in Indonesia nuclear Agency (BATAN) are introduced. Rough sketch of BATAN, and facility arrangement in the reactor hall and the guide hall are schematically shown. The four facilities (powder diffractometer, four-circle goniometer, three-axis goniometer and neutron radiography system) are installed in the reactor hall and the three (small angle neutron scattering (SANS), high resolution SANS and high resolution powder diffractometer) in the guide hall. Neutron wavelengths determined from four hk1 planes of standard Si powder by the BATAN's neutron diffraction facility are compared with those measured by the similar facility in Japan Atomic Energy Research Institute (JAERI). The neutron diffraction profile of W-fiber reinforced Cu composite is measured by the BATAN's facility. The experimental results show the strong 110 preferred orientation to the fiber direction. (author)

Methodology for analyzing risk at nuclear facilities

International Nuclear Information System (INIS)

Yoo, Hosik; Lee, Nayoung; Ham, Taekyu; Seo, Janghoon

2015-01-01

Highlights: • A new methodology for evaluating the risk at nuclear facilities was developed. • Five measures reflecting all factors that should be concerned to assess risk were developed. • The attributes on NMAC and nuclear security culture are included as attributes for analyzing. • The newly developed methodology can be used to evaluate risk of both existing facility and future nuclear system. - Abstract: A methodology for evaluating risks at nuclear facilities is developed in this work. A series of measures is drawn from the analysis of factors that determine risks. Five measures are created to evaluate risks at nuclear facilities. These include the legal and institutional framework, material control, physical protection system effectiveness, human resources, and consequences. Evaluation attributes are developed for each measure and specific values are given in order to calculate the risk value quantitatively. Questionnaires are drawn up on whether or not a state has properly established a legal and regulatory framework (based on international standards). These questionnaires can be a useful measure for comparing the status of the physical protection regime between two countries. Analyzing an insider threat is not an easy task and no methodology has been developed for this purpose. In this study, attributes that could quantitatively evaluate an insider threat, in the case of an unauthorized removal of nuclear materials, are developed by adopting the Nuclear Material Accounting & Control (NMAC) system. The effectiveness of a physical protection system, P(E), could be analyzed by calculating the probability of interruption, P(I), and the probability of neutralization, P(N). In this study, the Tool for Evaluating Security System (TESS) code developed by KINAC is used to calculate P(I) and P(N). Consequence is an important measure used to analyze risks at nuclear facilities. This measure comprises radiological, economic, and social damage. Social and

International safeguards in large scale nuclear facilities

International Nuclear Information System (INIS)

Gupta, D.; Heil, J.

1977-01-01

The trend in the energy sector in most of the industrialized areas of the world shows rather clearly, that the rate of installation of nuclear plants will be very high and that the largest possible units of nuclear material handling and storage facilities will be built. Various experiments and analyses of measurement methods relevant to safeguards, in typical nuclear facilities like a fuel reprocessing or a fabrication plant, have shown that the associated measurement errors as obtained under normal operating conditions are such that they are mainly dominated by systematic errors and that such systematic errors may lie in the range of percentages of the measured amount so that a material balance in such a plant could not normally be closed with high accuracy. The simplest way of going around the problem would be to increase the frequency of striking a material balance over a given period of time. This could however lead to an anormous increase in the technical and financial burden for the operator of a facility. The present paper analyses this problem in some detail for some facilities and shows that with a properly developed information system in such plants and a combination of containment, surveillance and accountancy measures, safeguards statements for relatively low significant amounts can be made with the attainable range of measurement accuracies

Scaling and instrumentation of the LOFT facility

International Nuclear Information System (INIS)

Modro, S.M.; Goodrich, L.D.; McPherson, G.D.

1985-01-01

This paper describes the LOFT experimental facility and instrumentation of the facility during small break loss-of-coolant experiments. Basic scaling considerations applied in the facility design are presented. Because LOFT was not designed with emphasis on small break LOCA some atypicalities with regard to small break transients are discussed. Review of important small break LOCA phenomena observed during the experiments and their measurability is provided

Measurement control program at model facility

International Nuclear Information System (INIS)

Schneider, R.A.

1984-01-01

A measurement control program for the model plant is described. The discussion includes the technical basis for such a program, the application of measurement control principles to each measurement, and the use of special experiments to estimate measurement error parameters for difficult-to-measure materials. The discussion also describes the statistical aspects of the program, and the documentation procedures used to record, maintain, and process the basic data

Upgrade and Development of Nuclear Data Production Test Facility

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-04-15

It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: (1) upgrade the electron linac, (2) collimators inside the TOF beam pipe, (3) the development and installation of an automatic sample changer, (4) the extension of the TOF beam line, and (5) the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students

Pelletron ion accelerator facilities at Inter University Accelerator Centre

International Nuclear Information System (INIS)

Chopra, S.

2011-01-01

Inter University Accelerator Centre has two tandem ion accelerators, 15UD Pelletron and 5SDH-2 Pelletron, for use in different areas of research. Recently Accelerator Mass Spectrometry facility has also been added to to the existing experimental facilities of 15UD Pelletron. In these years many modifications and up gradations have been performed to 15UD Pelletron facility. A new MCSNICS ion source has been procured to produce high currents for AMS program. Two foils stripper assemblies ,one each before and after analyzing magnet, have also been added for producing higher charge state beams for LINAC and for experiments requiring higher charge states of accelerated beams. A new 1.7 MV Pelletron facility has also been recently installed at IUAC and it is equipped with RBS and Channelling experimental facility. There are two beam lines installed in the system and five more beam lines can be added to the system. A clean chemistry laboratory with all the modern facilities has also been developed at IUAC for the chemical processing of samples prior to the AMS measurements. The operational description of the Pelletron facilities, chemical processing of samples, methods of measurements and results of AMS measurements are being presented. (author)

Los Alamos Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1991-01-01

The Critical Experiments Facility of the Los Alamos National Laboratory has been in existence for 45 years. In that period of time, thousands of measurements have been made on assemblies containing every fissionable material in various configurations that included bare metal and compounds of the nitrate, sulfate, fluoride, carbide, and oxide. Techniques developed or applied include Rossi-α, source-jerk, rod oscillator, and replacement measurements. Many of the original measurements of delay neutrons were performed at the site, and a replica of the Hiroshima weapon was operated at steady state to assist in evaluating the relative biological effectiveness (RBE) of neutrons. Solid, liquid, and gas fissioning systems were run at critical. Operation of this original critical facility has demonstrated the margin of safety that can be obtained through remote operation. Eight accidental excursions have occurred on the site, ranging from 1.5 x 10 16 to 1.2 x 10 17 fissions, with no significant exposure to personnel or damage to the facility beyond the machines themselves -- and in only one case was the machine damaged beyond further use. The present status of the facility, operating procedures, and complement of machines will be described in the context of programmatic activity. New programs will focus on training, validation of criticality alarm systems, experimental safety assessment of process applications, and dosimetry. Special emphasis will be placed on the incorporation of experience from 45 years of operation into present procedures and programs. 3 refs

International safeguards in large-scale nuclear facilities

International Nuclear Information System (INIS)

Gupta, D.; Heil, J.

1977-01-01

The trend in the energy sector in most of the world's industrialized areas shows rather clearly that the rate of installing nuclear plants will be very high and that the largest possible units of nuclear material handling and storage facilities will be built. Various experiments and analyses of measurement methods relevant to safeguards in typical nuclear facilities such as a fuel reprocessing or a fabrication plant have shown that the associated measurement errors as obtained under normal operating conditions are such that they are mainly dominated by systematic errors, which may lie in the range of percentages of the measured amount so that a material balance in such a plant could not normally be closed with any higher accuracy. For example, in a reprocessing plant with a throughput of 1500t U/a and a corresponding throughput of 15t Pu/a, a systematic error of 1% would cause a measurement uncertainty of around 70kg Pu in case a material balance is struck twice a year. Such a large amount may be considered to be unacceptable from the point of view of international safeguards since it arises out of a single plant. The simplest way of getting around the problem would be to strike a material balance more frequently over a given period. This could, however, lead to an enormous increase in the technical and financial burden for the operator of a facility. This paper analyses this problem in some detail for some facilities and shows that, for example, with a properly developed information system in such plants and a combination of containment, surveillance and accountancy measures, a safeguards system can be built up for such facilities. (author)

Test-retest reproducibility of accommodative facility measures in primary school children.

Science.gov (United States)

Adler, Paul; Scally, Andrew J; Barrett, Brendan T

2018-05-08

To determine the test-retest reproducibility of accommodative facility (AF) measures in an unselected sample of UK primary school children. Using ±2.00 DS flippers and a viewing distance of 40 cm, AF was measured in 136 children (range 4-12 years, average 8.1 ± 2.1) by five testers on three occasions (average interval between successive tests: eight days, range 1-21 days). On each occasion, AF was measured monocularly and binocularly, for two minutes. Full datasets were obtained in 111 children (81.6 per cent). Intra-individual variation in AF was large (standard deviation [SD] = 3.8 cycles per minute [cpm]) and there was variation due to the identity of the tester (SD = 1.6 cpm). On average, AF was greater: (i) in monocular compared to binocular testing (by 1.4 cpm, p cpm, p cpm lower than in children ≥ 10 years old, p = 0.009); and (iv) on subsequent testing occasions (for example, visit-2 AF was 2.0 cpm higher than visit-1 AF, p cpm monocularly and ≥ 8 cpm binocularly), but this rose to 83.8 per cent after the third test. Using less stringent pass criteria (≥ 6 cpm monocularly and ≥ 3 cpm binocularly), the equivalent figures were 82.9 and 96.4 per cent, respectively. Reduced AF did not co-exist with abnormal near point of accommodation or reduced visual acuity. The results reveal considerable intra-individual variability in raw AF measures in children. When the results are considered as pass/fail, children who initially exhibit normal AF continued to do so on repeat testing. Conversely, the vast majority of children with initially reduced AF exhibit normal performance on repeat testing. Using established pass/fail criteria, the prevalence of persistently reduced AF in this sample is 3.6 per cent. © 2018 Optometry Australia.

124Xe(n,γ125Xe and 124Xe(n,2n123Xe measurements for National Ignition Facility

Directory of Open Access Journals (Sweden)

Bhike Megha

2015-01-01

Full Text Available The cross section for the 124Xe(n,γ125Xe reaction has been measured for the first time for neutron energies above 100 keV. In addition, the 124Xe(n,2n123Xe reaction has been studied between threshold and 14.8 MeV. The results of these measurements provide sensitive diagnostic tools for investigating properties of the inertial confinement fusion plasma in Deuterium-Tritium (DT capsules at the National Ignition Facility (NIF located at Lawrence Livermore National Laboratory.

Shielding of Medical Radiation Facilities - National Council on Radiation Protection and Measurements Reports No. 147 and No. 151

International Nuclear Information System (INIS)

KASE, K.R.

2008-01-01

The National Council on Radiation Protection and Measurements of the United States (NCRP) has issued two reports in the past 18 months that provide methods and data for designing shielding for diagnostic radiological imaging and radiation therapy facilities. These reports update previous publications on this subject with revised methods that take into account new technologies, results from measurements and new data that have been published in the last 30 years. This paper gives a brief summary of the contents of these reports, the methods recommended for determining the shielding required and the data provided to aid in the calculations

Measurement and modeling of gamma-absorbed doses due to atmospheric releases from Los Alamos Meson Physics Facility

International Nuclear Information System (INIS)

Bowen, B.M.; Chen, A.I.; Olsen, W.A.; Van Etten, D.M.

1985-01-01

Short-term gamma-absorbed doses were measured by one high-pressure ionization chamber (HPIC) at an azimuth of 12 0 from the Los Alamos Meson Physics Facility (LAMPF) stack during the January 1 through February 8 operating cycle. Two HPICs were in the field during the September 8 through December 31 operating cycle, one north and the other north-northeast of the LAMPF stack, but they did not provide reliable data. Meteorological data were also measured at both East Gate and LAMPF. Airborne emission data were taken at the stack. Daily model predictions, based on the integration of modeled 15-min periods, were made for the first LAMPF operating cycle and were compared with the measured data. A comparison of the predicted and measured daily gamma doses due to LAMPF emissions is presented. There is very good correlation between measured and predicted values. During 39-day operating cycles, the model predicted an absorbed dose of 10.3 mrad compared with the 8.8 mrad that was measured, an overprediction of 17%

Measurements of reactor-relevant electromagnetic effects with the FELIX facility

International Nuclear Information System (INIS)

Turner, L.R.; Hua, T.Q.; Knott, M.J.; Lee, S.Y.; McGhee, D.G.; Wehrle, R.B.

1986-01-01

Recent experiments with the FELIX (Fusion Electromagnetic Induction eXperiment) facility at Argonne National Laboratory (ANL) suggest that the expected electromagnetic forces and torques in a tokamak first wall, blanket, and shield (FWBS) system can be modelled by a single eddy current mode, with a simple characterization

Berkeley Low Background Facility

International Nuclear Information System (INIS)

Thomas, K. J.; Norman, E. B.; Smith, A. R.; Poon, A. W. P.; Chan, Y. D.; Lesko, K. T.

2015-01-01

The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects

The monitoring system using laser light for the patient movement during radiation therapy

International Nuclear Information System (INIS)

Sano, Naoki; Onishi, Hiroshi; Yamaguchi, Motoshi; Kuriyama, Kengo; Akiyama, Saburou; Nakamura, Osamu; Araki, Tsutomu

1997-01-01

Purpose: The purpose of this study is to evaluate the usefulness of a newly developed real-time patient movement monitoring system built into the patient positioning light from the frontal and horizontal view. Materials and Techniques: This system is composed of 4 parts. They are a laser light projector, a retro-reflected tape, a sensor of photo-diode, and an alarm devise. First, this system projects a laser light for the patient movement monitor into the center of the crossed lines of the patient positioning light. The laser light (a diameter of 1.5mm and power of 0.5mW) for the patient movement monitor has a different wave length(633nm) from the patient positioning light. Then it is reflected into the direction of incidence with a retro-reflection tape affixed on three patient positioning points. And the system has a photo-diode which can sense the reflected laser light. This retro-reflected tape is made of tiny high reflective beads of glass which is fixed on a sheet with the thickness of 0.12mm and is able to be cut into any shape. This has a maximum retro-reflection angle of 70 degrees. We can select a tolerance of the patient movement by changing its shape and size. A buzzer strikes and a lamp is turned on to alarm for the error when the retro-reflected laser light is not sensed with the photo-diode. Results: The real-time monitoring accuracy of this system is only 0.17mm in the dimension of error for a selected tolerance of the phantom examination. Conclusion: This patient positioning system can be made simply and inexpensively and has a high monitoring accuracy. We can apply this system for a high-precision irradiation such as the three dimensional irradiation and small target irradiation

Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

International Nuclear Information System (INIS)

Smith, H.A. Jr.; Schillebeeckx, P.

1997-01-01

A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

Cost/schedule performance measurement system utilized on the Fast Flux Test Facility project

International Nuclear Information System (INIS)

Brown, R.K.; Frost, R.A.; Zimmerman, F.M.

1976-01-01

An Earned Value-Integrated Cost/Schedule Performance Measurement System has been applied to a major nonmilitary nuclear design and construction project. This system is similar to the Department of Defense Cost/Schedule Performance Measurement System. The project is the Fast Flux Test Facility (a Fuels and Materials test reactor for the Liquid Metal Fast Breeder Reactor Program) being built at the Hanford Engineering Development Laboratory, Richland, Washington, by Westinghouse Hanford Company for the U. S. Energy Research and Development Administration. Because the project was well into the construction phase when the Earned Value System was being considered, it was decided that the principles of DOD's Cost/Schedule Control System Criteria would be applied to the extent possible but no major changes in accounting practices or management systems were imposed. Implementation of this system enabled the following questions to be answered: For work performed, how do actual costs compare with the budget for that work. What is the impact of cost and schedule variances at an overall project level composed of different kinds of activities. Without the Earned Value system, these questions could be answered in a qualitative, subjective manner at best

Ambient dose equivalent measurements in secondary radiation fields at proton therapy facility CCB IFJ PAN in Krakow using recombination chambers

Directory of Open Access Journals (Sweden)

Jakubowska Edyta A.

2016-03-01

Full Text Available This work presents recombination methods used for secondary radiation measurements at the Facility for Proton Radiotherapy of Eye Cancer at the Institute for Nuclear Physics, IFJ, in Krakow (Poland. The measurements of H*(10 were performed, with REM-2 tissue equivalent chamber in two halls of cyclotrons AIC-144 and Proteus C-235 and in the corridors close to treatment rooms. The measurements were completed by determination of gamma radiation component, using a hydrogen-free recombination chamber. The results were compared with the measurements using rem meter types FHT 762 (WENDI-II and NM2 FHT 192 gamma probe and with stationary dosimetric system.

Study of measurement method of tritium induced in concrete of high-energy proton accelerator facilities

International Nuclear Information System (INIS)

Ohtsuka, N.; Ishihama, S.; Kunifuda, T.; Hayasaka, N.; Miura, T.

2001-01-01

Various long-loved radionuclides, 3 H, 7 Be, 22 Na, 51 Cr, 54 Mn, 56 Co, 57 Co, 60 Co, 134 Cs, 152 Eu and 154 Eu, have been produced in the shielding concrete of high energy proton accelerator facility through both nuclear spallation reactions and thermal neutron capture reactions of concrete elements, during machine operation. Tritium is the most important nuclide from the radiation protection. There were, however, few measurements of tritium concentration induced in the shielding concrete. In this study, the conditions of measurement method of tritium concentration induced in shielding concrete have been investigated using the activated shielding concrete of the 12 GeV proton beam-line tunnel at KEK and the standard rock (JG-1) irradiated of thermal neutron at the reactor. And the depth profiles of tritium induced in the shielding concrete of slow extracted proton beam line at KEK were determined using this method. (author)

Detailed description of an SSAC at the facility level for on-load refueled power reactor facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-11-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in an on-load refueled power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Measuring the diffusion of palliative care in long-term care facilities – a death census

Directory of Open Access Journals (Sweden)

Santos-Eggimann Brigitte

2009-01-01

Full Text Available Abstract Background The dissemination of palliative care for patients presenting complex chronic diseases at various stages has become an important matter of public health. A death census in Swiss long-term care facilities (LTC was set up with the aim of monitoring the frequency of selected indicators of palliative care. Methods The survey covered 150 LTC facilities (105 nursing homes and 45 home health services, each of which was asked to complete a questionnaire for every non-accidental death over a period of six months. The frequency of 4 selected indicators of palliative care (resort to a specialized palliative care service, the administration of opiates, use of any pain measurement scale or other symptom measurement scale was monitored in respect of the stages of care and analysed based on gender, age, medical condition and place of residence. Results Overall, 1200 deaths were reported, 29.1% of which were related to cancer. The frequencies of each indicator varied according to the type of LTC, mostly regarding the administration of opiate. It appeared that the access to palliative care remained associated with cancer, terminal care and partly with age, whereas gender and the presence of mental disorders had no effect on the indicators. In addition, the use of drugs was much more frequent than the other indicators. Conclusion The profile of patients with access to palliative care must become more diversified. Among other recommendations, equal access to opiates in nursing homes and in home health services, palliative care at an earlier stage and the systematic use of symptom management scales when resorting to opiates have to become of prime concern.

Study of the background in the measuring station at the n_TOF facility at CERN: sources and solutions

CERN Document Server

Zanini, L; Aerts, G; Andriamonje, Samuel A; Andrzejewski, J; Angelopoulous, A; Assimakopoulos, Panayiotis; Bacri, C-O; Badurek, G; Berthoumieux, E; Baumann, P; Beer, H; Benlliure, J; Berthier, B; Bondarenko, I; Borcea, C; Bos, A J J; Boscolo-Marchi, E; Bustreo, N; Calviño, F; Cano-Ott, D; Capote, R; Carlson, P; Charpak, Georges; Chauvin, N; Cennini, P; Chepel, V; Colonna, N; Cortés, G; Cortina-Gil, D; Corvi, F; Cusmano, A; Dababneh, S; Dahlfors, M; Damianoglou, D; David, S; Dimovasili, E; Domingo, C; Doroshenko, A; Duran-Escribano, I; Eleftheriadis, C; Embid, M; Ferrant, L; Ferrari, A; Ferreira-Marques, R; Frais-Kölbl, H; Furman, W; Fursov, B; Garzón, J A; Giomataris, Ioanis; Gledenov, Y; Gonzalez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Gunsing, F; Haefner, P; Haight, R; Heil, M; Herrera-martinez, A; Hollander, P; Ioannou, P; Isaev, S; Jericha, E; Kadi, Y; Kappeler, F; Karadimos, D; Karamanis, D; Kayukova, A; Kazakov, L; Kelic, A; Ketlerov, V; Kitis, G; Köhler, P E; Kopach, Y; Kossionides, E; Kroshkina, I; Lacoste, V; Lamboudis, C; Leeb, H; Leprêtre, A; Lopes, M; Lozano, M; Marrone, S; Martínez-Val, J M; Mastinu, P; Mengoni, A; Meunier, R; Mezentsev, A J; Milazzo, P; Minguez, E; Mitrofanov, V; Moreau, C; Müller, A; Nicolis, N; Nikolenkov, V; Oberhummer, Heinz; Pakou, A; Pancin, J; Papadopoulous, K; Papaevangelou, T; Paradela, C; Paradelis, T; Pavlik, A; Pavlopoulos, P; Perrez-Parra, A; Perriale, L; Perlado, J M; Peskov, Vladimir; Piksaikin, V; Plag, R; Plompen, A; Plukis, A; Poch, A; Policarpo, Armando; Popov, A; Popov, Y P; Pretel, C; Quesada, J M; Radermacher, E; Rapp, W; Rauscher, T; Reifarth, R; Rejmund, F; Rubbia, Carlo; Rudolf, G; Rullhusen, P; Sakelliou, L; Saldaña, F; Samylin, B; Savvidis, I; Savvidis, S; Sedyshev, P; Stéphan, C; Szalanski, P; Tagliente, G; Taín, J L; Tapia, C; Tassan-Got, L; Terchychnyi, R; Tsabaris, C; Tsangas, N; van Eijk, C W E; Vannini, G; Ventura, A; Villamarin, A; Vlachoudis, V; Vlastou, R; Voinov, A; Voss, F; Wendler, H; Wiescher, M; Wisshak, K; Zanini, L; Zeinalov, S; Zhuravlev, B; CERN. Geneva. SPS and LHC Division

2001-01-01

A background roughly two orders of magnitude higher than tolerable was found in the n_TOF facility at CERN during the first measurements [1]. This note describes a series of additional measurements performed in the n_TOF experimental area to study the origin and the characteristics of the background. The program of these measurements was determined taking into account the results from the simulations carried out by the EET group [2]. A first phase of measurements confirmed what was expected from the simulations, namely that the dominant source of background was due to neutrons generated by negative muon capture. Actions to reduce the background were taken according to the results from both measurements and simulations. An iron shielding wall 3.2 m thick was then placed in between the sweeping magnet and the second collimator, with the purpose of stopping most of the muons. In a second phase of measurements, results showed that the additional shielding reduced the main component of the background by about a fa...

A new 14C AMS facility at IUAC, New Delhi

International Nuclear Information System (INIS)

Kumar, Pankaj; Ojha, S.; Sharma, R.; Gargari, S.; Joshi, R.; Chopra, S.; Kanjilal, D.

2015-01-01

A new state of art Accelerator Mass Spectrometry (AMS) facility for 14 C has been developed at IUAC. This facility is based on the 0.5 MV Pelletron accelerator and an Automated Graphitization Equipment (AGE). In addition to the 14 C measurements, this system has the capability to perform 10 Be and 26 AI measurements also. The system is called XCAMS i.e., Compact, Accelerator Mass Spectrometer eXtended for 10 Be and 26 AI. A detailed description of the newly developed AMS facility and the recent measurements will be discussed

Electron temperature measurements inside the ablating plasma of gas-filled hohlraums at the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Barrios, M. A.; Liedahl, D. A.; Schneider, M. B.; Jones, O.; Brown, G. V.; Fournier, K. B.; Moore, A. S.; Ross, J. S.; Landen, O.; Kauffman, R. L.; Nikroo, A.; Kroll, J.; Callahan, D. A.; Hinkel, D. E.; Bradley, D.; Moody, J. D. [Lawrence Livermore National Laboratory, Livermore, California 94551 (United States); Regan, S. P. [Laboratory for Laser Energetics, Rochester, New York 14623 (United States); Jaquez, J.; Huang, H. [General Atomics, San Diego, California 92121 (United States); Hansen, S. B. [Sandia National Laboratories, Albuquerque, New Mexico 87123 (United States)

2016-05-15

The first measurement of the electron temperature (T{sub e}) inside a National Ignition Facility hohlraum is obtained using temporally resolved K-shell X-ray spectroscopy of a mid-Z tracer dot. Both isoelectronic- and interstage-line ratios are used to calculate the local T{sub e} via the collisional–radiative atomic physics code SCRAM [Hansen et al., High Energy Density Phys 3, 109 (2007)]. The trajectory of the mid-Z dot as it is ablated from the capsule surface and moves toward the laser entrance hole (LEH) is measured using side-on x-ray imaging, characterizing the plasma flow of the ablating capsule. Data show that the measured dot location is farther away from the LEH in comparison to the radiation-hydrodynamics simulation prediction using HYDRA [Marinak et al., Phys. Plasmas 3, 2070 (1996)]. To account for this discrepancy, the predicted simulation T{sub e} is evaluated at the measured dot trajectory. The peak T{sub e}, measured to be 4.2 keV ± 0.2 keV, is ∼0.5 keV hotter than the simulation prediction.

Monte Carlo simulation of neutron irradiation facility developed for accelerator based in vivo neutron activation measurements in human hand bones

International Nuclear Information System (INIS)

Aslam; Prestwich, W.V.; McNeill, F.E.; Waker, A.J.

2006-01-01

The neutron irradiation facility developed at the McMaster University 3 MV Van de Graaff accelerator was employed to assess in vivo elemental content of aluminum and manganese in human hands. These measurements were carried out to monitor the long-term exposure of these potentially toxic trace elements through hand bone levels. The dose equivalent delivered to a patient during irradiation procedure is the limiting factor for IVNAA measurements. This article describes a method to estimate the average radiation dose equivalent delivered to the patient's hand during irradiation. The computational method described in this work augments the dose measurements carried out earlier [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724]. This method employs the Monte Carlo simulation of hand irradiation facility using MCNP4B. Based on the estimated dose equivalents received by the patient hand, the proposed irradiation procedure for the IVNAA measurement of manganese in human hands [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724] with normal (1 ppm) and elevated manganese content can be carried out with a reasonably low dose of 31 mSv to the hand. Sixty-three percent of the total dose equivalent is delivered by non-useful fast group (>10 keV); the filtration of this neutron group from the beam will further decrease the dose equivalent to the patient's hand

Fission Cross-section Measurements of (233)U, (245)Cm and (241,243)Am at CERN n_TOF Facility

CERN Document Server

Calviani, M; Andriamonje, S; Chiaveri, E; Vlachoudis, V; Colonna, N; Meaze, M H; Marrone, S; Tagliente, G; Terlizzi, R; Belloni, F; Abbondanno, U; Fujii, K; Milazzo, P M; Moreau, C; Aerts, G; Berthoumieux, E; Dridi, W; Gunsing, F; Pancin, J; Perrot, L; Plukis, A; Alvarez, H; Duran, I; Paradela, C; Alvarez-Velarde, F; Cano-Ott, D; Gonzalez-Romero, E; Guerrero, C; Martinez, T; Villamarin, D; Vicente, M C; Andrzejewski, J; Marganiec, J; Assimakopoulos, P; Karadimos, D; Karamanis, D; Papachristodoulou, C; Patronis, N; Audouin, L; David, S; Ferrant, L; Isaev, S; Stephan, C; Tassan-Got, L; Badurek, G; Jericha, E; Leeb, H; Oberhummer, H; Pigni, M T; Baumann, P; Kerveno, M; Lukic, S; Rudolf, G; Becvar, F; Krticka, M; Calvino, F; Capote, R; Carrillo De Albornoz, A; Marques, L; Salgado, J; Tavora, L; Vaz, P; Cennini, P; Dahlfors, M; Ferrari, A; Gramegna, F; Herrera-Martinez, A; Kadi, Y; Mastinu, P; Praena, J; Sarchiapone, L; Wendler, H; Chepel, V; Ferreira-Marques, R; Goncalves, I; Lindote, A; Lopes, I; Neves, F; Cortes, G; Poch, A; Pretel, C; Couture, A; Cox, J; O'brien, S; Wiescher, M; Dillman, I; Heil, M; Kappeler, F; Mosconi, M; Plag, R; Voss, F; Walter, S; Wisshak, K; Dolfini, R; Rubbia, C; Domingo-Pardo, C; Tain, J L; Eleftheriadis, C; Savvidis, I; Frais-Koelbl, H; Griesmayer, E; Furman, W; Konovalov, V; Goverdovski, A; Ketlerov, V; Haas, B; Haight, R; Reifarth, R; Igashira, M; Koehler, P; Kossionides, E; Lampoudis, C; Lozano, M; Quesada, J; Massimi, C; Vannini, G; Mengoni, A; Oshima, M; Papadopoulos, C; Vlastou, R; Pavlik, A; Pavlopoulos, P; Plompen, A; Rullhusen, P; Rauscher, T; Rosetti, M; Ventura, A

2011-01-01

Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design of advanced reactor systems. The measurements at n_TOF take advantage of the innovative features of the n_TOF facility, namely the wide energy range, high instantaneous neutron flux and good energy resolution. Final results on the fission cross-section of 233U, 245Cm and 243Am from thermal to 20 MeV are here reported, together with preliminary results for 241Am. The measurement have been performed with a dedicated Fast Ionization Chamber (FIC), a fission fragment detector with a very high efficiency, relative to the very well known cross-section of 235U, measured simultaneously with the same detector.

Intercomparison of active, passive and continuous instruments for radon and radon progeny measurements in the EML chamber and test facility

International Nuclear Information System (INIS)

Scarpitta, S.C.; Tu, K.W.; Fisenne, I.M.; Cavallo, A.; Perry, P.

1996-10-01

Results are presented from the Fifth Intercomparison of Active, Passive and Continuous Instruments for Radon and Radon Progeny Measurements conducted in the EML radon exposure and test facility in May 1996. In total, thirty-four government, private and academic facilities participated in the exercise with over 170 passive and electronic devices exposed in the EML test chamber. During the first week of the exercise, passive and continuous measuring devices were exposed (usually in quadruplicate) to about 1,280 Bq m -3 222 Rn for 1--7 days. Radon progeny measurements were made during the second week of the exercise. The results indicate that all of the tested devices that measure radon gas performed well and fulfill their intended purpose. The grand mean (GM) ratio of the participants' reported values to the EML values, for all four radon device categories, was 0.99 ± 0.08. Eighty-five percent of all the radon measuring devices that were exposed in the EML radon test chamber were within ±1 standard deviation (SD) of the EML reference values. For the most part, radon progeny measurements were also quite good as compared to the EML values. The GM ratio for the 10 continuous PAEC instruments was 0.90 ± 0.12 with 75% of the devices within 1 SD of the EML reference values. Most of the continuous and integrating electronic instruments used for measuring the PAEC underestimated the EML values by about 10--15% probably because the concentration of particles onto which the radon progeny were attached was low (1,200--3,800 particles cm -3 ). The equilibrium factor at that particle concentration level was 0.10--0.22

Dose rate determinations in the Portuguese Gamma Irradiation Facility: Monte Carlo simulations and measurements

International Nuclear Information System (INIS)

Oliveira, C.; Salgado, J.; Ferro de Carvalho, A.

2000-01-01

A simulation study of the Portuguese Gamma Irradiation Facility, UTR, has been carried out using the MCNP code. The work focused on the optimisation of the dose distribution inside the irradiation cell, dose calculations inside irradiated samples and dose calculations in critical points for protection purposes. Calculations were carried out at points inside and outside the irradiation cell, where different behaviour was expected (distance from the source, radiation absorption and scattering in irradiator structure and walls). The contributions from source, irradiator structure, sample material, carriers, walls, ceiling and floor to the photon spectra and air kerma at those points are reported and discussed. Air kerma measurements were also carried out using an ionisation chamber. Good agreement was found between experimental and calculated air kermas. (author)

ORNL Isotopes Facilities Shutdown Program Plan

International Nuclear Information System (INIS)

Gibson, S.M.; Patton, B.D.; Sears, M.B.

1990-10-01

This plan presents the results of a technical and economic assessment for shutdown of the Oak Ridge National Laboratory (ORNL) isotopes production and distribution facilities. On December 11, 1989, the Department of Energy (DOE), Headquarters, in a memorandum addressed to DOE Oak Ridge Operations Office (DOE-ORO), gave instructions to prepare the ORNL isotopes production and distribution facilities, with the exception of immediate facility needs for krypton-85, tritium, and yttrium-90, for safe shutdown. In response to the memorandum, ORNL identified 17 facilities for shutdown. Each of these facilities is located within the ORNL complex with the exception of Building 9204-3, which is located at the Y-12 Weapons Production Plant. These facilities have been used extensively for the production of radioactive materials by the DOE Isotopes Program. They currently house a large inventory of radioactive materials. Over the years, these aging facilities have inherited the problems associated with storing and processing highly radioactive materials (i.e., facilities' materials degradation and contamination). During FY 1990, ORNL is addressing the requirements for placing these facilities into safe shutdown while maintaining the facilities under the existing maintenance and surveillance plan. The day-to-day operations associated with the surveillance and maintenance of a facility include building checks to ensure that building parameters are meeting the required operational safety requirements, performance of contamination control measures, and preventative maintenance on the facility and facility equipment. Shutdown implementation will begin in FY 1993, and shutdown completion will occur by the end of FY 1994

Preliminary Design of the AEGIS Test Facility

CERN Document Server

Dassa, Luca; Cambiaghi, Danilo

2010-01-01

The AEGIS experiment is expected to be installed at the CERN Antiproton Decelerator in a very close future, since the main goal of the AEGIS experiment is the measurement of gravity impact on antihydrogen, which will be produced on the purpose. Antihydrogen production implies very challenging environmental conditions: at the heart of the AEGIS facility 50 mK temperature, 1e-12 mbar pressure and a 1 T magnetic field are required. Interfacing extreme cryogenics with ultra high vacuum will affect very strongly the design of the whole facility, requiring a very careful mechanical design. This paper presents an overview of the actual design of the AEGIS experimental facility, paying special care to mechanical aspects. Each subsystem of the facility – ranging from the positron source to the recombination region and the measurement region – will be shortly described. The ultra cold region, which is the most critical with respect to the antihydrogen formation, will be dealt in detail. The assembly procedures will...

Trajectory measurements and correlations in the final focus beam line at the KEK Accelerator Test Facility

Science.gov (United States)

Renier, Y.; Bambade, P.; Tauchi, T.; White, G. R.; Boogert, S.

2013-06-01

The Accelerator Test Facility 2 (ATF2) commissioning group aims to demonstrate the feasibility of the beam delivery system of the next linear colliders (ILC and CLIC) as well as to define and to test the tuning methods. As the design vertical beam sizes of the linear colliders are about few nanometers, the stability of the trajectory as well as the control of the aberrations are very critical. ATF2 commissioning started in December 2008, and thanks to submicron resolution beam position monitors (BPMs), it has been possible to measure the beam position fluctuation along the final focus of ATF2 during the 2009 runs. The optics was not the nominal one yet, with a lower focusing to make the tuning easier. In this paper, a method to measure the noise of each BPM every pulse, in a model-independent way, will be presented. A method to reconstruct the trajectory’s fluctuations is developed which uses the previously determined BPM resolution. As this reconstruction provides a measurement of the beam energy fluctuations, it was also possible to measure the horizontal and vertical dispersion function at each BPMs parasitically. The spatial and angular dispersions can be fitted from these measurements with uncertainties comparable with usual measurements.

Trajectory measurements and correlations in the final focus beam line at the KEK Accelerator Test Facility

Directory of Open Access Journals (Sweden)

Y. Renier

2013-06-01

Full Text Available The Accelerator Test Facility 2 (ATF2 commissioning group aims to demonstrate the feasibility of the beam delivery system of the next linear colliders (ILC and CLIC as well as to define and to test the tuning methods. As the design vertical beam sizes of the linear colliders are about few nanometers, the stability of the trajectory as well as the control of the aberrations are very critical. ATF2 commissioning started in December 2008, and thanks to submicron resolution beam position monitors (BPMs, it has been possible to measure the beam position fluctuation along the final focus of ATF2 during the 2009 runs. The optics was not the nominal one yet, with a lower focusing to make the tuning easier. In this paper, a method to measure the noise of each BPM every pulse, in a model-independent way, will be presented. A method to reconstruct the trajectory’s fluctuations is developed which uses the previously determined BPM resolution. As this reconstruction provides a measurement of the beam energy fluctuations, it was also possible to measure the horizontal and vertical dispersion function at each BPMs parasitically. The spatial and angular dispersions can be fitted from these measurements with uncertainties comparable with usual measurements.

Facility safeguards at an LEU fuel fabrication facility in Japan

International Nuclear Information System (INIS)

Kuroi, H.; Osabe, T.

1984-01-01

A facility description of a Japanese LEU BWR-type fuel fabrication plant focusing on safeguards viewpoints is presented. Procedures and practices of MC and A plan, measurement program, inventory taking, and the report and record system are described. Procedures and practices of safeguards inspection are discussed and lessons learned from past experiences are reviewed

Interim Storage Facility decommissioning. Final report

International Nuclear Information System (INIS)

Johnson, R.P.; Speed, D.L.

1985-01-01

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

Safeguards at the Nuclear Regulatory Commission (NRC) facilities are discussed in this paper. The NRC is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

Nuclear material inventory estimation in a nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Bennett, J.E.; Beyerlein, A.L.

1981-01-01

A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

Electron temperature measurements by the plasma line technique at the French incoherent scatter radar facilities

International Nuclear Information System (INIS)

Kofman, W.; Lejeune, G.; Hagfors, T.; Bauer, P.

1981-01-01

The results of experiments aimed at the determination of the electron temperature by a plasma line technique are presented. Using the multistatic capabilities of the French incoherent scatter radar, the plasma line frequencies were simultaneously measured at two receiving stations (Mende and Nancay) at the altitude corresponding to the maximum of the F layer. Different plasma line frequencies are measued because of different effective k vectors that appear in the thermal term of the plasma dispersion relation. We derive and apply two data analysis procedures that enable us to determine this frequency difference. Comparison of this measured frequency difference to that calculated using the ion component electron temperature demonstrates that the plasma lines could indeed be used to determine the electron temperature. A strong dependence of the power in the plasma line as a function of the angle between k vector and magnetic field is observed in agreement with the theory. The future developments of this technique with the EISCAT radar facilities are discussed

Precision Munition Electro-Sciences Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility allows the characterization of the electro-magnetic environment produced by a precision weapon in free flight. It can measure the radiofrequency (RF)...

Dose apportionment for BARC facilities

International Nuclear Information System (INIS)

Preetha, J.; Sundar, D.; Munshi, S.K.; Pradeepkumar, K.S.

2017-01-01

One of the important responsibilities of BARC Safety Council (BSC) is to ensure that appropriate measures are in place to protect the members of the public and the environment from the undue effects of radioactive releases from the facilities regulated by BSC. It is with this aim in mind that a Standing Committee for Dose Apportionment (DAC) was constituted by BSC in 2005, to ensure that the limits are set by the regulatory body for release of low-level gaseous and liquid effluents into the environment from BARC facilities. There are three Committees for dose apportionment constituted by the Chairman, BSC, viz, DAC-TK for Tarapur and Kalpakkam facilities, DAC-TV for Trombay and DACSF for specific faculties

Regulatory inspection of BARC facilities

International Nuclear Information System (INIS)

Rajdeep; Jayarajan, K.

2017-01-01

Nuclear and radiation facilities are sited, constructed, commissioned, operated and decommissioned, in conformity with the current safety standards and codes. Regulatory bodies follow different means to ensure compliance of the standards for the safety of the personnel, the public and the environment. Regulatory Inspection (RI) is one of the important measures employed by regulatory bodies to obtain the safety status of a facility or project and to verify the fulfilment of the conditions stipulated in the consent

Astrophysics at nTOF facility

International Nuclear Information System (INIS)

Tagliente, G.; Colonna, N.; Maronne, S.; Terlizzi, R.; Abondanno, U.; Fujii, K.; Milazzo, P.M.; Moreau, C.; Belloni, F.; Aerts, G.; Berthoumieux, E.; Andriamonje, S.; Dridi, W.; Gunsing, F.; Pancin, J.; Perrot, L.; Alvarez, H.; Duran, I.; Paradela, C.; Alvarez-Velarde, F.; Cano-Ott, D.; Embid-Segura, M.; Guerrero, C.; Martinez, T.; Villamarin, D.; Vincente, M.C.; Gonzalez-Romero, E.; Andrzejewski, J.; Marganiec, J.; Assimakopoulos, P.; Karamanis, D.; Audouin, L.; Dillman, I.; Heil, M.; Kappeler, F.; Mosconi, M.; Plag, R.; Voss, F.; Walter, S.; Wissak, K.; Badurek, G.; Jericha, E.; Leeb, H.; Oberhummer, H.; Pigni, M.T.; Baumann, P.; David, S.; Kerveno, M.; Rudolf, G.; Lukic, S.; Becvar, F.; Krticka, M.; Bisterzo, S.; Ferrant, L.; Gallino, R.; Calvino, F.; Poch, A.; Pretel, C.; Calviani, M.; Gramegna, F.; Mastinu, P.; Capote, R.; Mengoni, A.; Capote, R.; Lozano, M.; Quesada, J.; Carrapico, C.; Salgado, J.; Santos, C.; Tavora, L.; Vaz, P.; Cennini, P.; Chiaveri, E.; Dahlfors, M.; Kadi, Y.; Sarchiapone, L.; Vlachoudis, V.; Wendler, H.; Chepel, V.; Ferreira-Marques, R.; Goncalves, I.; Lindote, A.; Lopes, I.; Neves, F.; Couture, A.; Cox, J.; O'Brien, S.; Wiescher, M.; Dominga-Pardo, C.; Tain, J.L.; Eleftheriadis, C.; Lamboudis, C.; Savvidis, I.; Stephan, C.; Tassan-Got, L.; Furman, W.; Haas, B.; Haight, R.; Reifarth, R.; Igashira, M.; Koehler, P.; Massimi, C.; Vannini, G.; Papadopoulos, C.; Pavlik, A.; Pavlopoulos, P.; Plomen, A.; Rullhusen, P.; Rauscher, T.; Rubbia, C.; Ventura, A.

2009-01-01

The neutron time of flight (n T OF) facility at CERN is a neutron spallation source, its white neutron energy spectrum ranges from thermal to several GeV, covering the full energy range of interest for nuclear astrophysics, in particular for measurements of the neutron capture cross-section required in s-process nucleosynthesis. This contribution gives an overview on the astrophysical program made at n T OF facility, the results and the implications will be considered.

Comparison of neutron dose measured by Albedo TLD and etched tracks detector at PNC plutonium fuel facilities

International Nuclear Information System (INIS)

Tsujimura, N.; Momose, T.; Shinohara, K.; Ishiguro, H.

1996-01-01

Power Reactor and Nuclear Fuel Development Corporation (PNC) has fabricated Plutonium and Uranium Mixed OXide (MOX) fuel for FBR MONJU at Tokai works. In this site, PNC/Panasonic albedo TLDs/1/ are used for personnel neutron monitoring. And a part of workers wore Etched Tracks Detector (ETD) combined with TLD in order to check the accuracy of the neutron dose estimated by albedo TLD. In this paper, the neutron dose measured by TLD and ETD in the routine monitoring is compared at PNC plutonium fuel facilities. (author)

RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

In Vivo Radiobioassay and Research Facility

International Nuclear Information System (INIS)

Lynch, Timothy P.

2011-01-01

Bioassay monitoring for intakes of radioactive material is an essential part of the internal dosimetry program for radiation workers at the Department of Energy's (DOE) Hanford Site. This monitoring program includes direct measurements of radionuclides in the body by detecting photons that exit the body and analyses of radionuclides in excreta samples. The specialized equipment and instrumentation required to make the direct measurements of these materials in the body are located at the In Vivo Radiobioassay and Research Facility (IVRRF). The IVRRF was originally built in 1960 and was designed expressly for the in vivo measurement of radioactive material in Hanford workers. Most routine in vivo measurements are performed annually and special measurements are performed as needed. The primary source terms at the Hanford Site include fission and activation products (primarily 137Cs and 90Sr), uranium, uranium progeny, and transuranic radionuclides. The facility currently houses five shielded counting systems, men's and women's change rooms and an instrument maintenance and repair shop. Four systems include high purity germanium detectors and one system utilizes large sodium iodide detectors. These systems are used to perform an average of 7,000 measurements annually. This includes approximately 5000 whole body measurements analyzed for fission and activation products and 2000 lung measurements analyzed for americium, uranium, and plutonium. Various other types of measurements are performed periodically to estimate activity in wounds, the thyroid, the liver, and the skeleton. The staff maintains the capability to detect and quantify activity in essentially any tissue or organ. The in vivo monitoring program that utilizes the facility is accredited by the Department of Energy Laboratory Accreditation Program for direct radiobioassay.

Measurements of an ablator-gas atomic mix in indirectly driven implosions at the National Ignition Facility.

Science.gov (United States)

Smalyuk, V A; Tipton, R E; Pino, J E; Casey, D T; Grim, G P; Remington, B A; Rowley, D P; Weber, S V; Barrios, M; Benedetti, L R; Bleuel, D L; Bradley, D K; Caggiano, J A; Callahan, D A; Cerjan, C J; Clark, D S; Edgell, D H; Edwards, M J; Frenje, J A; Gatu-Johnson, M; Glebov, V Y; Glenn, S; Haan, S W; Hamza, A; Hatarik, R; Hsing, W W; Izumi, N; Khan, S; Kilkenny, J D; Kline, J; Knauer, J; Landen, O L; Ma, T; McNaney, J M; Mintz, M; Moore, A; Nikroo, A; Pak, A; Parham, T; Petrasso, R; Sayre, D B; Schneider, M B; Tommasini, R; Town, R P; Widmann, K; Wilson, D C; Yeamans, C B

2014-01-17

We present the first results from an experimental campaign to measure the atomic ablator-gas mix in the deceleration phase of gas-filled capsule implosions on the National Ignition Facility. Plastic capsules containing CD layers were filled with tritium gas; as the reactants are initially separated, DT fusion yield provides a direct measure of the atomic mix of ablator into the hot spot gas. Capsules were imploded with x rays generated in hohlraums with peak radiation temperatures of ∼294  eV. While the TT fusion reaction probes conditions in the central part (core) of the implosion hot spot, the DT reaction probes a mixed region on the outer part of the hot spot near the ablator-hot-spot interface. Experimental data were used to develop and validate the atomic-mix model used in two-dimensional simulations.

Simulation of facility operations and materials accounting for a combined reprocessing/MOX fuel fabrication facility

International Nuclear Information System (INIS)

Coulter, C.A.; Whiteson, R.; Zardecki, A.

1991-01-01

We are developing a computer model of facility operations and nuclear materials accounting for a facility that reprocesses spent fuel and fabricates mixed oxide (MOX) fuel rods and assemblies from the recovered uranium and plutonium. The model will be used to determine the effectiveness of various materials measurement strategies for the facility and, ultimately, of other facility safeguards functions as well. This portion of the facility consists of a spent fuel storage pond, fuel shear, dissolver, clarifier, three solvent-extraction stages with uranium-plutonium separation after the first stage, and product concentrators. In this facility area mixed oxide is formed into pellets, the pellets are loaded into fuel rods, and the fuel rods are fabricated into fuel assemblies. These two facility sections are connected by a MOX conversion line in which the uranium and plutonium solutions from reprocessing are converted to mixed oxide. The model of the intermediate MOX conversion line used in the model is based on a design provided by Mike Ehinger of Oak Ridge National Laboratory (private communication). An initial version of the simulation model has been developed for the entire MOX conversion and fuel fabrication sections of the reprocessing/MOX fuel fabrication facility, and this model has been used to obtain inventory difference variance estimates for those sections of the facility. A significant fraction of the data files for the fuel reprocessing section have been developed, but these data files are not yet complete enough to permit simulation of reprocessing operations in the facility. Accordingly, the discussion in the following sections is restricted to the MOX conversion and fuel fabrication lines. 3 tabs

Argonne to open new facility for advanced vehicle testing

CERN Multimedia

2002-01-01

Argonne National Laboratory will open it's Advanced Powertrain Research Facility on Friday, Nov. 15. The facility is North America's only public testing facility for engines, fuel cells, electric drives and energy storage. State-of-the-art performance and emissions measurement equipment is available to support model development and technology validation (1 page).

Developments in radiation, stimulation and observation facilities in luminescence measurements

DEFF Research Database (Denmark)

Bøtter-Jensen, L.; Andersen, C.E.; Duller, G.A.T.

2003-01-01

of magnitude up to more than 2 Gy/s. A separate bleaching facility has also been added to the reader, new powerful infrared (IR) light-emitting diodes have replaced the IR laser diode in the general OSL unit, and an IR laser has been included in the single-grain OSL attachment. This paper describes these new...

Measurement of the tissue to A-150 tissue equivalent plastic kerma ratio at two p(66)Be neutron therapy facilities

International Nuclear Information System (INIS)

Langen, K M; Binns, P J; Schreuder, A N; Lennox, A J; Deluca, P M Jr.

2003-01-01

The ICRU tissue to A-150 tissue equivalent plastic kerma ratio is needed for neutron therapy dosimetry. The current ICRU protocol for neutron dosimetry recommends using a common conversion factor of 0.95 at all high-energy neutron therapy facilities. In an effort to determine facility specific ICRU tissue to A-150 plastic kerma ratios, an experimental approach was pursued. Four low pressure proportional counters that differed in wall materials (i.e. A-150, carbon, zirconium and zirconium-oxide) were used as dosimeters and integral kerma ratios were determined directly in the clinical beam. Measurements were performed at two p(66)Be facilities: iThemba LABS near Cape Town and Fermilab near Chicago. At the iThemba facility the clinical neutron beam is routinely filtered by a flattening and hardening filter combination. The influence of beam filtration on the kerma ratio was evaluated. Using two recent gas-to-wall dose conversion factor (r m,g value) evaluations a mean ICRU tissue to A-150 plastic kerma ratio of 0.93 ± 0.05 was determined for the clinical beam at iThemba LABS. The respective value for the Fermilab beam is 0.95 ± 0.05. The experimentally determined ICRU tissue to A-150 plastic kerma ratios for the two clinical beams are in agreement with theoretical evaluations. Beam filtration reduces the kerma ratio by 3 ± 2%

ORNL instrumentation performance for Slab Core Test Facility (SCTF)-Core I Reflood Test Facility

International Nuclear Information System (INIS)

Hardy, J.E.; Hess, R.A.; Hylton, J.O.

1983-11-01

Instrumentation was developed for making measurements in experimental refill-reflood test facilities. These unique instrumentation systems were designed to survive the severe environmental conditions that exist during a simulated pressurized water reactor loss-of-coolant accident (LOCA). Measurement of in-vessel fluid phenomena such as two-phase flow velocity and void fraction and film thickness and film velocity are required for better understanding of reactor behavior during LOCAs. The Advanced Instrumentation for Reflood Studies (AIRS) Program fabricated and delivered instrumentation systems and data reduction software algorithms that allowed the above measurements to be made. Data produced by AIRS sensors during three experimental runs in the Japanese Slab Core Test Facility are presented. Although many of the sensors failed before any useful data could be obtained, the remaining probes gave encouraging and useful results. These results are the first of their kind produced during simulated refill-reflood stage of a LOCA near actual thermohydrodynamic conditions

Status report and measurement of total cross-sections at the Pohang Neutron Facility

International Nuclear Information System (INIS)

Kim, G.N.; Meaze, A.K.M.M.H.; Ahmed, H.

2004-01-01

We report the status of the Pohang Neutron Facility which consists of an electron linear accelerator, a water-cooled Ta target, and an 11-m time-of-flight path. It has been equipped with a four-position sample changer controlled remotely by a CAMAC data acquisition system, which allows simultaneous accumulation of the neutron time of flight spectra from 4 different detectors. It is possible to measure the neutron total cross-sections in the neutron energy range from 0.1 eV to 100 eV by using the neutron time of flight method. A 6 LiZnS(Ag) glass scintillator was used as a neutron detector. The neutron flight path from the water-cooled Ta target to the neutron detector was 10.81±0.02 m. The background level was determined by using notch-filters of Co, In, Ta, and Cd sheets. In order to reduce the gamma rays from Bremsstrahlung and those from neutron capture, we employed a neutron-gamma separation system based on their different pulse shapes. The present measurements are in general agreement with the evaluated data in ENDF/B-VI. The resonance parameters were extracted from the transmission data from the SAMMY fitting and compared with the previous ones. (author)

The neutron total cross-section measurement of 56Fe and 57Fe by using Japan Proton Accelerator Research Complex facility

International Nuclear Information System (INIS)

Kim, Eun Ae; Shvetsov, Valery; Cho, Moo Hyun; Won, Nam Kung; Kim, Kwang Soo; Yang, Sung Chul; Lee, Man Woo; Kim, Guin Yun; Yi, Kyoung Rak; Choi, Hong Yub; Ro, Tae Ik; Mizumoto, Motoharu; Katabuchi, Tatsuya; Igashira, Masayuki

2012-01-01

The measurement of neutron cross section using Time-Of-Flight (TOF) method gives significant information for the nuclear data research. In the present work, the neutron total cross section of 56 Fe and 57 Fe has been measured in the energy range between 10 eV and 100 keV by using the neutron beam produced from 3-GeV proton synchrotron accelerator. The 3-GeV proton synchrotron accelerator is located at Japan Proton Accelerator Research Complex (J-PARC) facility in Tokai village. In this study, the neutron total cross section data measured by 6 Li glass scintillator detector was compared with the evaluated values of ENDF/B-VII.0

Color and appearance metrology facility

Data.gov (United States)

Federal Laboratory Consortium — The NIST Physical Measurement Laboratory has established the color and appearance metrology facility to support calibration services for 0°/45° colored samples, 20°,...

Fuel conditioning facility material accountancy

International Nuclear Information System (INIS)

Yacout, A.M.; Bucher, R.G.; Orechwa, Y.

1995-01-01

The operation of the Fuel conditioning Facility (FCF) is based on the electrometallurgical processing of spent metallic reactor fuel. It differs significantly, therefore, from traditional PUREX process facilities in both processing technology and safeguards implications. For example, the fissile material is processed in FCF only in batches and is transferred within the facility only as solid, well-characterized items; there are no liquid steams containing fissile material within the facility, nor entering or leaving the facility. The analysis of a single batch lends itself also to an analytical relationship between the safeguards criteria, such as alarm limit, detection probability, and maximum significant amount of fissile material, and the accounting system's performance, as it is reflected in the variance associated with the estimate of the inventory difference. This relation, together with the sensitivity of the inventory difference to the uncertainties in the measurements, allows a thorough evaluation of the power of the accounting system. The system for the accountancy of the fissile material in the FCF has two main components: a system to gather and store information during the operation of the facility, and a system to interpret this information with regard to meeting safeguards criteria. These are described and the precision of the inventory closure over one batch evaluated

Race, ethnicity, and noxious facilities: Environmental racism re- examined

Energy Technology Data Exchange (ETDEWEB)

Nieves, A.L. [Wheaton Coll., IL (United States)]|[Argonne National Lab., IL (United States); Nieves, L.A. [Argonne National Lab., IL (United States)

1992-10-01

The charge has been made that hazardous facilities tend to be located in proximity to minority populations. This study uses a facility density measure for three categories of noxious facilities to examine the relationship between facilities and minority population concentrations. County-level data are used in a correlation analysis for African Americans, Hispanics, and Asians in the four major regions of the US. Even controlling for income and housing value, and limiting the data set to urban areas, consistent patterns of moderate to strong association of facility densities with minority population percentages are found.

Operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Eun Ka; Park, Kwang Joon; Jeon, Yong Bum [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-02-01

In 1995, the post-irradiation examination (PIE) of nuclear fuels was performed as follows. The relation between burnup and top nozzle spring force of fuel assembly was obtained by measuring the holddown spring force on the Kori-1 reactor fuel assemblies. The resonance ultrasonic test for inspection of defect and moisture in fuel rod was carried out on fuel rods of C15 and J14 assemblies, and the change of fuel rod condition by storing in pool has been analyzed on the intentionally defected fuel rods (ID-C and ID-L) as well as intact fuel rod (1-2) by NDT in ht cell. The oxide layer thickness on cladding surface of J44-L12 fuel rod was measured by NDT method and metallography to reveal the oxidation as a function of temperature in the fuel rod, and the burnup of J44 fuel assembly was measured by chemical analysis. HVAC system and pool water treatment system of the PIE facility were continuously operated for air filtration and water purification. The monitoring of radiation and pool water in PIE facility has been carried out to maintain the facility safety, and electric power supply system was checked and maintained to supply the electric power to the facility normally. The developed measurement techniques of oxide layer thickness on fuel rod cladding and holddown spring force of top nozzle in fuel assembly were applied to examine the nuclear fuels. Besides, a radiation shielding glove box was designed and a hot cell compressor for volume reduction of radioactive materials was fabricated. 19 tabs., 38 figs., 7 refs. (Author) .new.

Mass measurement of cooled neutron-deficient bismuth projectile fragments with time-resolved Schottky mass spectrometry at the FRS-ESR facility

Energy Technology Data Exchange (ETDEWEB)

Litvinov, Yu.A.; Geissel, H. [Giessen Univ. (Germany); Radon, T. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (DE)] [and others

2005-06-01

Masses of 582 neutron-deficient nuclides (30{<=}Z{<=}85) were measured with time-resolved Schottky mass spectrometry at the FRS-ESR facility at GSI, 117 were used for calibration. The masses of 71 nuclides were obtained for the first time. A typical mass accuracy of 30 {mu}u was achieved. These data have entered the latest atomic mass evaluation. The mass determination of about 140 additional nuclides was possible via known energies (Q-values) of {alpha}-, {beta}-, or proton decays. The obtained results are compared with the results of other measurements. (orig.)

Measurement of the 241Am neutron capture cross section at the n_TOF facility at CERN

Directory of Open Access Journals (Sweden)

Mendoza E.

2017-01-01

Full Text Available New neutron cross section measurements of minor actinides have been performed recently in order to reduce the uncertainties in the evaluated data, which is important for the design of advanced nuclear reactors and, in particular, for determining their performance in the transmutation of nuclear waste. We have measured the 241Am(n,γ cross section at the n_TOF facility between 0.2 eV and 10 keV with a BaF2 Total Absorption Calorimeter, and the analysis of the measurement has been recently concluded. Our results are in reasonable agreement below 20 eV with the ones published by C. Lampoudis et al. in 2013, who reported a 22% larger capture cross section up to 110 eV compared to experimental and evaluated data published before. Our results also indicate that the 241Am(n,γ cross section is underestimated in the present evaluated libraries between 20 eV and 2 keV by 25%, on average, and up to 35% for certain evaluations and energy ranges.

Shielding design for positron emission tomography facility

International Nuclear Information System (INIS)

Abdallah, I.I.

2007-01-01

With the recent advent of readily available tracer isotopes, there has been marked increase in the number of hospital-based and free-standing positron emission tomography (PET) clinics. PET facilities employ relatively large activities of high-energy photon emitting isotopes, which can be dangerous to the health of humans and animals. This coupled with the current dose limits for radiation worker and members of the public can result in shielding requirements. This research contributes to the calculation of the appropriate shielding to keep the level of radiation within an acceptable recommended limit. Two different methods were used including measurements made at selected points of an operating PET facility and computer simulations by using Monte Carlo Transport Code. The measurements mainly concerned the radiation exposure at different points around facility using the survey meter detectors and Thermoluminescent Dosimeters (TLD). Then the set of manual calculation procedures were used to estimate the shielding requirements for a newly built PEF facility. The results from the measurement and the computer simulation were compared to the results obtained from the set manual calculation procedure. In general, the estimated weekly dose at the points of interest is lower than the regulatory limits for the little company of Mary Hospital. Furthermore, the density and the HVL for normal strength concrete and clay bricks are almost similar. In conclusion, PET facilities present somewhat different design requirements and are more likely to require additional radiation shielding. Therefore, existing shields at the little Company of Mary Hospital are in general found to be adequate and satisfactory and additional shielding was found necessary at the new PET facility in the department of Nuclear Medicine of the Dr. George Mukhari Hospital. By use of appropriate design, by implying specific shielding requirements and by maintaining good operating practices, radiation doses to

Status of the low frequency facility experiment

International Nuclear Information System (INIS)

Bracci, L; Calamai, G; Cuoco, E; Dominici, P; Fabbroni, L; Guidi, G; Losurdo, G; Martelli, F; Mazzoni, M; Stanga, R; Vetrano, F; Porzio, A; Ricciardi, I; Solimeno, S; Ballardin, G; Braccini, S; Bradaschia, C; Casciano, C; Cavalieri, R; Cecchi, R; Cella, G; Dattilo, V; Virgilio, A Di; Fazzi, M; Ferrante, I; Fidecaro, F; Frasconi, F; Gennaro, G; Giazotto, A; Holloway, L; Penna, P La; Lomtadze, T; Nenci, F; Nicolosi, L; Lelli, F; Paoletti, F; Pasqualetti, A; Passaquieti, R; Passuello, D; Poggiani, R; Raffaelli, F; Taddei, R; Vicere, A; Zhang, Z; Frasca, S; Majorana, E; Palomba, C; Perciballi, M; Puppo, P; Rapagnani, P; Ricci, F

2002-01-01

The low frequency facility is a VIRGO R and D experiment having the goal of performing a direct measurement of the thermal noise of the VIRGO suspensions by means of a two-mirror Fabry-Perot cavity suspended to the last stage of the attenuating chain. The present status of advancement of this experiment is reported: the apparatus, including mechanical and optical parts, has been completely built and put into operation. Vacuum facilities and the first control loops are active. First measurements on the suspended cavity are in progress

Status of the low frequency facility experiment

Energy Technology Data Exchange (ETDEWEB)

Bracci, L [Dipartimento di Fisica, Universita di Firenze, Florence (Italy); Calamai, G [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Cuoco, E [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Dominici, P [Dipartimento di Fisica, Universita di Firenze, Firenze (Italy); Fabbroni, L [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Guidi, G [Dipartimento di Fisica, Universita di Urbino, Urbino (Italy); Losurdo, G [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Martelli, F [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Mazzoni, M [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Stanga, R [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Vetrano, F [Dipartimento di Fisica, Universita di Urbino, Urbino (Italy); Porzio, A [Istituto Nazionale di Fisica Nucleare, Sez Naples (Italy); Ricciardi, I [Istituto Nazionale di Fisica Nucleare, Sez Naples (Italy); Solimeno, S [Istituto Nazionale di Fisica Nucleare, Sez Naples (Italy); Ballardin, G [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Braccini, S [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Bradaschia, C [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Casciano, C [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Cavalieri, R [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Cecchi, R [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Cella, G [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Dattilo, V [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Virgilio, A Di [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Fazzi, M [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Ferrante, I [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Fidecaro, F [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy)] [and others

2002-04-07

The low frequency facility is a VIRGO R and D experiment having the goal of performing a direct measurement of the thermal noise of the VIRGO suspensions by means of a two-mirror Fabry-Perot cavity suspended to the last stage of the attenuating chain. The present status of advancement of this experiment is reported: the apparatus, including mechanical and optical parts, has been completely built and put into operation. Vacuum facilities and the first control loops are active. First measurements on the suspended cavity are in progress.

Development of corrective measures and site stabilization technologies for shallow land burial facilities at semiarid sites: summary paper

International Nuclear Information System (INIS)

Nyhan, J.W.; Abeele, W.V.

1987-01-01

The overall purpose of the corrective measures task performed for the national Low-Level Waste Management Program (NLLWMP) has been to develop and test methods that can be used to correct any actual or anticipated problems with new and existing shallow land burial (SLB) sites in a semiarid environment. These field tests have not only evaluated remedial actions, but have also investigated phenomena suspected of being a possible problem at semiarid SLB sites. The approach the authors have taken in developing remedial action and site closure technologies for low-level waste sites is to recognize the physical and biological processes affecting site integrity are interdependent, and therefore, cannot be treated as separate problems. More specifically the field experiments performed for this task were to identify, evaluate, and model erosion control technologies, field test second generation biointrusion barriers, determine by field experiments the extent of upward radionuclide migration due to moisture cycling, and measure the effects of subsidence on remedial action of other system components. In the following sections of this final task summary report, the authors describe the progress made in establishing the facility in which many of these field experiments were performed, the Los Alamos Experimental Engineered Test Facility (EETF), as well as a brief description of the four research areas encompassed by this task. 45 references, 4 figures

Failure prevention with stress measurement for dismantling of nuclear facilities. Final report

International Nuclear Information System (INIS)

Komber, T.; Reimche, W.; Bach, F.W.

2003-07-01

The dismantling of nuclear facilities is in progress since 20 years in Germany. Practical experiences in decommissioning have shown, that problem can occur during dismantling operations caused by release of residual stresses. In this case cutting parts or cutting tools get jammed if mechanical cutting techniques are used. The aim of this research work was to develop measuring techniques for the determination of the stress state in RPV, to predict the deformation during dismantling operations. This can serve as additional base for improved decommissioning planning and for time optimised dismantling. For determination of the stress state in components two small and inexpensive measuring techniques were new designed, for remote-controlled on-site use in atmosphere and under water. For the nondestructive determination of the directional stress state, based on the magnetostriction and the Harmonic-Analysis of alternating magnetic fields, a new developed rotating sensor is in use with a principal magnetisation direction. Because of the mainly isotropic material properties and the directional stresses, measured Harmonic values are influenced mainly by the stress state in the surface areas. In this way it is possible to determine the stress state qualitatively and the direction of principal stresses in the surface areas of the component. As an alternative to the established wire strain gauge, which remote-controlled application is still not possible under water, a new slot jet cutting strain control technique was designed. This technique detects the deformation in the surface after stresses are cut free by a water jet. So the stress state could be determined quantitatively in the surface and assessed in the depth. With the help of these two measuring techniques it is possible to characterize the stress state along a planned cutting line. The use of an adapted FEM simulation enables to calculate and determine the deformation of the cutting gap beforehand. These information

An Overview of INEL Fusion Safety R&D Facilities

Science.gov (United States)

McCarthy, K. A.; Smolik, G. R.; Anderl, R. A.; Carmack, W. J.; Longhurst, G. R.

1997-06-01

The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.

First regulatory inspections measuring adherence to Good Pharmacy Practices in the public sector in Uganda: a cross-sectional comparison of performance between supervised and unsupervised facilities.

Science.gov (United States)

Trap, Birna; Kikule, Kate; Vialle-Valentin, Catherine; Musoke, Richard; Lajul, Grace Otto; Hoppenworth, Kim; Konradsen, Dorthe

2016-01-01

Since its inception, the Uganda National Drug Authority (NDA) has regularly inspected private sector pharmacies to monitor adherence to Good Pharmacy Practices (GPP). This study reports findings from the first public facility inspections following an intervention (SPARS: Supervision, Performance Assessment, and Recognition Strategy) to build GPP and medicines management capacity in the public sector. The study includes 455 public facilities: 417 facilities were inspected after at least four SPARS visits by trained managerial district staff (SPARS group), 38 before any exposure to SPARS. NDA inspectors measured 10 critical, 20 major, and 37 minor GPP indicators in every facility and only accredited facilities that passed all 10 critical and failed no more than 7 major indicators. Lack of compliance for a given indicator was defined as less than 75 % facilities passing that indicator. We assessed factors associated with certification using logistic regression analysis and compared number of failed indicators between the SPARS and comparative groups using two sample t-tests with equal or unequal variance. 57.4 % of inspected facilities obtained GPP certification: 57.1 % in the SPARS and 60.5 % in the comparative group (Adj. OR = 0.91, 95 % CI 0.45-1.85, p = 0.802). Overall, facilities failed an average of 10 indicators. SPARS facilities performed better than comparative facilities (9 (SD 6.1) vs. 13 (SD 7.7) failed indicators respectively; p = 0.017), and SPARS supported facilities scored better on indicators covered by SPARS. For all indicators but one minor, performance in the SPARS group was equal to or significantly better than in unsupervised facilities. Within the SPARS (intervention) group, certified facilities had practices and behavioral changes; some require infrastructure investments. We conclude that regular NDA inspections of public sector pharmacies in conjunction with interventions to improve GPP adherence can revolutionize patient

Measurement of radioactivity in air at the linear accelerator of Kyoto University reactor facility

International Nuclear Information System (INIS)

Ikebe, Yukimasa; Shimo, Michikuni

1976-01-01

It is well-known that the induced activities from a number of nuclides are generated in air during the operation of high energy accelerators. Of these, measurements were performed with the linear accelerator of Kyoto University reactor facility for the purpose of the clarification of the production mechanism and behavior of radioactive aerosols. The concentration in air and the size distribution of 13 N aerosols which have aerosols as the carrier among 13 N produced by the γ-n reaction of 14 N were measured with filter packs and by diffusion method, respectively. The density of number and size distribution of non-radioactive aerosols were measured to understand the production mechanism and behavior of 13 N aerosols. For the aerosol number density, Aitken nucleus number was measured with a Pollak counter. The results obtained show that (1) under the operating condition of the linear accelerator at that measurement time, 13 N aerosol concentration was (2 to 50) x 10 -13 Ci/cm 3 while 13 N gas component concentration was (1 to 25) x 10 -12 Ci/cm 3 , i.e. the ratio was approximately 1 : 10 (2) the average size of 13 N aerosols was 0.01 to 0.04 μm, and it was found that there was positive correlation to relative humidity; (3) during the operation of the accelerator, the generation of aerosols 10 to 100 times as much as the background level was observed. The size distribution of aerosols showed a peak around 0.01 μm; and others. Examination was carried out regarding a 13 N aerosol production model based on the sticking of aerosol-free 13 N to aerosols. (Wakatsuki, Y.)

Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia

Science.gov (United States)

Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; Prata, M.; Ballarini, F.; Carante, M. P.; Farias, R.; González, S. J.; Marrale, M.; Gallo, S.; Bartolotta, A.; Iacoviello, G.; Nigg, D.; Altieri, S.

2018-01-01

University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20 ± 0.03) ×1010 cm-2 s-1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2 ×10-13 Gy/(n/cm2).

The 236U neutron capture cross-section measured at the n_TOF CERN facility

Directory of Open Access Journals (Sweden)

Mastromarco M.

2017-01-01

Full Text Available The 236U isotope plays an important role in nuclear systems, both for future and currently operating ones. The actual knowledge of the capture reaction of this isotope is satisfactory in the thermal region, but it is considered insufficient for Fast Reactor and ADS applications. For this reason the 236U(n, γ reaction cross-section has been measured for the first time in the whole energy region from thermal energy up to 1 MeV at the n_TOF facility with two different detection systems: an array of C6D6 detectors, employing the total energy deposited method, and a FX1 total absorption calorimeter (TAC, made of 40 BaF2 crystals. The two n_TOF data sets agree with each other within the statistical uncertainty in the Resolved Resonance Region up to 800 eV, while sizable differences (up to ≃ 20% are found relative to the current evaluated data libraries. Moreover two new resonances have been found in the n_TOF data. In the Unresolved Resonance Region up to 200 keV, the n_TOF results show a reasonable agreement with previous measurements and evaluated data.

Analysis of Ozone And CO2 Profiles Measured At A Diary Facility

Science.gov (United States)

Ogunjemiyo, S. O.; Hasson, A. S.; Ashkan, S.; Steele, J.; Shelton, T.

2015-12-01

Ozone and carbon dioxide are both greenhouse gasses in the planetary boundary layer. Ozone is a harmful secondary pollutant in the troposphere produced mostly during the day when there is a photochemical reaction in which primary pollutant precursors such as nitrous oxide (NOx) or volatile organic compounds (VOC's) mix with sunlight. As with most pollutants in the lower troposphere, both ozone and carbon dioxide vary in spatial and temporal scale depending on sources of pollution, environmental conditions and the boundary layer dynamics. Among the several factors that influence ozone variation, the seasonal changes in meteorological parameters and availability of ozone precursors are crucial because they control ozone formation and decay. Understanding how the difference in emission sources affect vertical transport of ozone and carbon dioxide is considered crucial to the improvement of their regional inventory sources. The purpose of this study is to characterize vertical transport of ozone and carbon at a diary facility. The study was conducted in the summer of 2011 and 2012 at a commercial dairy facility in Central California and involved profile measurements of ozone and CO2 using electrochemical ozonesondes, meteorological sondes and CO2 probe tethered to a 9 cubic meters helium balloon. On each day of the data collection, multiple balloon launches were made over a period representing different stages of the boundary layer development. The results show ozone and CO2 profiles display different characteristics. Regardless of the time of the day, the CO2 concentration decreases with height with a sharp gradient near the surface that is strengthened by a stable atmospheric condition, a feature suggesting the surface as the source. On the other hand, ozone profiles show greater link to the evolution of the lower boundary layer. Ozone profiles display unique features indicating ozone destruction near the surface. This unusual near the surface, observed even in the

Emergency planning for fuel cycle facilities

International Nuclear Information System (INIS)

Lacey, L.R.

1991-01-01

In April 1989, NRC published new emergency planning regulations which apply to certain by-product, source, and special nuclear materials licensees including most fuel cycle facilities. In addition to these NRC regulations, other regulatory agencies such as EPA, OSHA, and DOT have regulations concerning emergency planning or notification that may apply to fuel cycle facilities. Emergency planning requirements address such areas as emergency classification, organization, notification and activation, assessment, corrective and protective measures, emergency facilities and equipment, maintaining preparedness, records and reports, and recovery. This article reviews applicable regulatory requirements and guidance, then concentrates on implementation strategies to produce an effective emergency response capability

Efficient rehabilitation care for joint replacement patients: skilled nursing facility or inpatient rehabilitation facility?

Science.gov (United States)

Tian, Wenqiang; DeJong, Gerben; Horn, Susan D; Putman, Koen; Hsieh, Ching-Hui; DaVanzo, Joan E

2012-01-01

There has been lengthy debate as to which setting, skilled nursing facility (SNF) or inpatient rehabilitation facility (IRF), is more efficient in treating joint replacement patients. This study aims to determine the efficiency of rehabilitation care provided by SNF and IRF to joint replacement patients with respect to both payment and length of stay (LOS). This study used a prospective multisite observational cohort design. Tobit models were used to examine the association between setting of care and efficiency. The study enrolled 948 knee replacement patients and 618 hip replacement patients from 11 IRFs and 7 SNFs between February 2006 and February 2007. Output was measured by motor functional independence measure (FIM) score at discharge. Efficiency was measured in 3 ways: payment efficiency, LOS efficiency, and stochastic frontier analysis efficiency. IRF patients incurred higher expenditures per case but also achieved larger motor FIM gains in shorter LOS than did SNF patients. Setting of care was not a strong predictor of overall efficiency of rehabilitation care. Great variation in characteristics existed within IRFs or SNFs and severity groups. Medium-volume facilities among both SNFs and IRFs were most efficient. Early rehabilitation was consistently predictive of efficient treatment. The advantage of either setting is not clear-cut. Definition of efficiency depends in part on preference between cost and time. SNFs are more payment efficient; IRFs are more LOS efficient. Variation within SNFs and IRFs blurred setting differences; a simple comparison between SNF and IRF may not be appropriate.

The operation of post-irradiation examination facility

International Nuclear Information System (INIS)

Kim, Eun Ka; Min, Duk Ki; Lee, Young Kil

1994-12-01

The operation of post-irradiation examination facility was performed as follow. HVAC and pool water treatment system were continuously operated, and radiation monitoring in PIE facility has been carried out to maintain the facility safely. Inspection of the fuel assembly (F02) transported from Kori Unit 1 was performed in pool, and fuel rods extracted from the fuel assembly (J44) of Kori Unit 2 NPP were examined in hot cell. A part of deteriorated pipe line of drinking water was exchanged for stainless steel pipe to prevent leaking accidents. Halon gas system was also installed in the exhausting blower room for fire fighting. And IAEA inspection camera for safeguard of nuclear materials was fixed at the wall in pool area. Radiation monitoring system were improved to display the area radioactive value at CRT monitor in health physics control room. And automatic check system for battery and emergency diesel generator was developed to measure the voltage and current of them. The performance test of oxide thickness measuring device installed in hot cell for irradiated fuel rod and improvement of the device were performed, and good measuring results using standard sample were obtained. The safeguard inspection of nuclear materials and operation inspection of the facility were carried out through the annual operation inspection, quarterly IAEA inspection and quality assurance auditing. 26 tabs., 43 figs., 14 refs. (Author) .new

The measurement, control, and validation of critical parameters in an electron beam sterilization facility

International Nuclear Information System (INIS)

Burns, P.; Drewell, N.H.; McKeown, J.

1996-01-01

The delivery and validation of a specified dose to a medical device are key concerns of operators of electron beam irradiation facilities. In an IMPELA-based irradiator, four of the parameters that directly influence the absorbed dose distribution in the product are controllable in real time - the electron energy, average beam current, scanned area, and the product exposure time. The 10 MeV accelerator operates at 50 kW with a stream of 200 μs wide, 100 mA pulses at a repetition rate of 250 Hz. The combination of short-term intra-pulse regulation with long-term pulse-to-pulse stability makes the IMPELA output attractive for the sterilization of medical products. The measurement and closed-loop control techniques used in the IMPELA design will be described with reference to facilitating compliance with medical sterilization standards. (orig.)

Role and Successes of Trilateral Liaison Frameworks (IAEA-SSACs/RSACs- Nuclear Fuel Cycle Facility Operators) in Monitoring the Quality of the Operator's Measurement and Accounting Systems

International Nuclear Information System (INIS)

Norman, C.; Zhao, K.; Christophe, P.; Binner, R.; Iso, S.

2015-01-01

Two of the three generic objectives of safeguards under a comprehensive safeguards agreement (CSA) are to detect any undeclared production or processing of nuclear material in declared facilities and locations outside facilities (LOFs) and to detect any diversion of declared nuclear material at facilities and LOFs. The effectiveness and efficiency of the IAEA in reaching these objectives strongly relies on the quality of the State or regional system of accounting for and control of nuclear material (SSAC/RSAC) which in turn depends on the nuclear fuel cycle facility operators' capabilities to establish accurate and precise estimates of the inventories and flow of nuclear material. To monitor the performance of the State's nuclear fuel cycle facilities' accounting and measurement systems in a collaborative way, the IAEA initiated yearly trilateral liaison meetings with relevant State or regional authorities and bulk handling facilities' operators to review material balance evaluation results for the elapsed material balance period and their trends over the facility lifetime. During these meetings, trends of concern are examined and the IAEA proposes remedial actions, drawing on its expertise and experience of observations in similar facilities. Pilot trilateral meetings held in Japan over the past years demonstrate the benefits of this collaborative framework. Biases in material balance variables are identified, their causes determined and a set of recommendations is drawn to implement remedial actions before they become a safeguards concern. In the margins of these meetings, workshops are also organised to foster exchanges in the fields of measurement and analytical methods as well as statistical methodologies used to determine their uncertainties and assess the sensitivity of material balances to these uncertainties. In the context of its strategy to enhance cooperation with States, reinforce mutual trust and pursue further efficiencies though

Addressing social aspects associated with wastewater treatment facilities

International Nuclear Information System (INIS)

Padilla-Rivera, Alejandro; Morgan-Sagastume, Juan Manuel; Noyola, Adalberto; Güereca, Leonor Patricia

2016-01-01

In wastewater treatment facilities (WWTF), technical and financial aspects have been considered a priority, while other issues, such as social aspects, have not been evaluated seriously and there is not an accepted methodology for assessing it. In this work, a methodology focused on social concerns related to WWTF is presented. The methodology proposes the use of 25 indicators as a framework for measuring social performance to evaluate the progress in moving towards sustainability. The methodology was applied to test its applicability and effectiveness in two WWTF in Mexico (urban and rural). This evaluation helped define the key elements, stakeholders and barriers in the facilities. In this context, the urban facility showed a better overall performance, a result that may be explained mainly by the better socioeconomic context of the urban municipality. Finally, the evaluation of social aspects using the semi-qualitative approach proposed in this work allows for a comparison between different facilities and for the identification of strengths and weakness, and it provides an alternative tool for achieving and improving wastewater management. - Highlights: • The methodology proposes 25 indicators as a framework for measuring social performance in wastewater treatment facilities. • The evaluation helped to define the key elements, stakeholders and barriers in the wastewater treatment facilities. • The evaluation of social aspects allows the identification of strengths and weakness for improving wastewater management. • It provides a social profile of the facility that highlights the best and worst performances.

Addressing social aspects associated with wastewater treatment facilities

Energy Technology Data Exchange (ETDEWEB)

Padilla-Rivera, Alejandro; Morgan-Sagastume, Juan Manuel; Noyola, Adalberto; Güereca, Leonor Patricia, E-mail: lguerecah@iingen.unam.mx

2016-02-15

In wastewater treatment facilities (WWTF), technical and financial aspects have been considered a priority, while other issues, such as social aspects, have not been evaluated seriously and there is not an accepted methodology for assessing it. In this work, a methodology focused on social concerns related to WWTF is presented. The methodology proposes the use of 25 indicators as a framework for measuring social performance to evaluate the progress in moving towards sustainability. The methodology was applied to test its applicability and effectiveness in two WWTF in Mexico (urban and rural). This evaluation helped define the key elements, stakeholders and barriers in the facilities. In this context, the urban facility showed a better overall performance, a result that may be explained mainly by the better socioeconomic context of the urban municipality. Finally, the evaluation of social aspects using the semi-qualitative approach proposed in this work allows for a comparison between different facilities and for the identification of strengths and weakness, and it provides an alternative tool for achieving and improving wastewater management. - Highlights: • The methodology proposes 25 indicators as a framework for measuring social performance in wastewater treatment facilities. • The evaluation helped to define the key elements, stakeholders and barriers in the wastewater treatment facilities. • The evaluation of social aspects allows the identification of strengths and weakness for improving wastewater management. • It provides a social profile of the facility that highlights the best and worst performances.

A facile electrode preparation method for accurate electrochemical measurements of double-side-coated electrode from commercial Li-ion batteries

Science.gov (United States)

Zhou, Ge; Wang, Qiyu; Wang, Shuo; Ling, Shigang; Zheng, Jieyun; Yu, Xiqian; Li, Hong

2018-04-01

The post mortem electrochemical analysis, including charge-discharge and electrochemical impedance spectroscopy (EIS) measurements, are critical steps for revealing the failure mechanisms of commercial lithium-ion batteries (LIBs). These post measurements usually require the reassembling of coin-cell with electrode which is often double-side-coated in commercial LIBs. It is difficult to use such double-side-coated electrode to perform accurate electrochemical measurements because the back side of the electrode is coated with active materials, rather than single-side-coated electrode that is often used in coin-cell measurements. In this study, we report a facile tape-covering sample preparation method, which can effectively suppress the influence of back side of the double-side-coated electrodes on capacity and EIS measurements in coin-cells. By tape-covering the unwanted side, the areal capacity of the desired investigated side of the electrode has been accurately measured with an experimental error of about 0.5% at various current densities, and accurate EIS measurements and analysis have been conducted as well.

Eighth experts meeting on environmental radioactivity monitoring: Technical and organisational means for an optimised measurement of ambient radioactivity in the environment of nuclear facilities

International Nuclear Information System (INIS)

1991-01-01

The plant-specific emission monitoring and environmental monitoring near nuclear facilities are part of the items of the agreement between the EC and the IAEA, for mutual rapid information in the case of accidents. The lectures presented to the technical discussion meeting deal with the legal and technical aspects involved. Dispersion models, computer-aided dispersion models, computer-aided information systems and advanced programs as well as measuring techniques and results of the emission monitoring and environmental monitoring near nuclear facilities are the aspects of main interest discussed at the meeting. (DG) [de

CERN radiation protection (RP) calibration facilities

Energy Technology Data Exchange (ETDEWEB)

Pozzi, Fabio

2016-04-14

Radiation protection calibration facilities are essential to ensure the correct operation of radiation protection instrumentation. Calibrations are performed in specific radiation fields according to the type of instrument to be calibrated: neutrons, photons, X-rays, beta and alpha particles. Some of the instruments are also tested in mixed radiation fields as often encountered close to high-energy particle accelerators. Moreover, calibration facilities are of great importance to evaluate the performance of prototype detectors; testing and measuring the response of a prototype detector to well-known and -characterized radiation fields contributes to improving and optimizing its design and capabilities. The CERN Radiation Protection group is in charge of performing the regular calibrations of all CERN radiation protection devices; these include operational and passive dosimeters, neutron and photon survey-meters, and fixed radiation detectors to monitor the ambient dose equivalent, H*(10), inside CERN accelerators and at the CERN borders. A new state-of-the-art radiation protection calibration facility was designed, constructed and commissioned following the related ISO recommendations to replace the previous ageing (more than 30 years old) laboratory. In fact, the new laboratory aims also at the official accreditation according to the ISO standards in order to be able to release certified calibrations. Four radiation fields are provided: neutrons, photons and beta sources and an X-ray generator. Its construction did not only involve a pure civil engineering work; many radiation protection studies were performed to provide a facility that could answer the CERN calibration needs and fulfill all related safety requirements. Monte Carlo simulations have been confirmed to be a valuable tool for the optimization of the building design, the radiation protection aspects, e.g. shielding, and, as consequence, the overall cost. After the source and irradiator installation

New Platforms for Suborbital Astronomical Observations and In Situ Atmospheric Measurements: Spacecraft, Instruments, and Facilities

Science.gov (United States)

Rodway, K.; DeForest, C. E.; Diller, J.; Vilas, F.; Sollitt, L. S.; Reyes, M. F.; Filo, A. S.; Anderson, E.

2014-12-01

Suborbital astronomical observations have over 50 years' history using NASA's sounding rockets and experimental space planes. The new commercial space industry is developing suborbital reusable launch vehicles (sRLV's) to provide low-cost, flexible, and frequent access to space at ~100 km altitude. In the case of XCOR Aerospace's Lynx spacecraft, the vehicle design and capabilities work well for hosting specially designed experiments that can be flown with a human-tended researcher or alone with the pilot on a customized mission. Some of the first-generation instruments and facilities that will conduct solar observations on dedicated Lynx science missions include the SwRI Solar Instrument Pointing Platform (SSIPP) and Atsa Suborbital Observatory, as well as KickSat sprites, which are picosatellites for in situ atmospheric and solar phenomena measurements. The SSIPP is a demonstration two-stage pointed solar observatory that operates inside the Lynx cockpit. The coarse pointing stage includes the pilot in the feedback loop, and the fine stage stabilizes the solar image to achieve arcsecond class pointing. SSIPP is a stepping-stone to future external instruments that can operate with larger apertures and shorter wavelengths in the solar atmosphere. The Planetary Science Institute's Atsa Suborbital Observatory combines the strengths of ground-based observatories and space-based observing to create a facility where a telescope is maintained and used interchangeably with either in-house facility instruments or user-provided instruments. The Atsa prototype is a proof of concept, hand-guided camera that mounts on the interior of the Lynx cockpit to test target acquisition and tracking for human-operated suborbital astronomy. KickSat sprites are mass-producible, one inch printed circuit boards (PCBs) populated by programmable off the shelf microprocessors and radios for real time data transmission. The sprite PCBs can integrate chip-based radiometers, magnetometers

Stores, Weight and Inertial System Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility provides stores weight, center of gravity, and inertia measurements in support of weapon/aircraft compatibility testing. System provides store weight...

Retroreflective Phase Retardation Prisms.

Science.gov (United States)

1981-06-01

resonant cavity of a 1.064 Mm laser. This report shows that it is possible to coat the reflecting surfaces of a porro prism so that incident plane...with controlled phase retardation can be made by coating each reflecting surface of a porro prism with a single dielectric film. The amount of phase...of angle of incidence (n, < n2) S. Phase change on reflection as a function of angle of incidence (n" n ) [RL-0202-’R 6. Porro prism 7. Phase change

Holdup measurements under realistic conditions

International Nuclear Information System (INIS)

Sprinkel, J.K. Jr.; Marshall, R.; Russo, P.A.; Siebelist, R.

1997-01-01

This paper reviews the documentation of the precision and bias of holdup (residual nuclear material remaining in processing equipment) measurements and presents previously unreported results. Precision and bias results for holdup measurements are reported from training seminars with simulated holdup, which represent the best possible results, and compared to actual plutonium processing facility measurements. Holdup measurements for plutonium and uranium processing plants are also compared to reference values. Recommendations for measuring holdup are provided for highly enriched uranium facilities and for low enriched uranium facilities. The random error component of holdup measurements is less than the systematic error component. The most likely factor in measurement error is incorrect assumptions about the measurement, such as background, measurement geometry, or signal attenuation. Measurement precision on the order of 10% can be achieved with some difficulty. Bias of poor quality holdup measurement can also be improved. However, for most facilities, holdup measurement errors have no significant impact on inventory difference, sigma, or safety (criticality, radiation, or environmental); therefore, it is difficult to justify the allocation of more resources to improving holdup measurements. 25 refs., 10 tabs

Near-Facility Environmental Monitoring Quality Assurance Project Plan

International Nuclear Information System (INIS)

MCKINNEY, S.M.

2000-01-01

This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards

Irradiation facilities on the TRIGA-SSR thermal column

Energy Technology Data Exchange (ETDEWEB)

Roth, C; Aioanei, L; Preda, M; Gugiu, D [Institute for Nuclear Research, Pitesti (Romania); Garlea, I; Kelerman, C; Garlea, C [SENDRA ' Nuclear Technologies' ltd. Bucharest (Romania)

2004-07-01

The development of thermal and intermediate energy neutron irradiation facilities at the steady state core of the Romanian TRIGA Reactor is described. The reference thermal neutron irradiation facility consists of a dry spherical cavity placed into the graphite thermal column of the SSR core and the intermediate energy neutron irradiation facility is a {sigma}{sigma} system located into the thermal flux cavity. The implementation of the irradiation facilities into the under-water thermal column represented an important challenge from the standpoint of instrumentation solutions. The neutron flux and spectrum measurements were performed using foil activation techniques and fission rate measurements by sealed fission chambers, followed by spectrum unfolding procedure. The absolute fission reaction measurements, using calibrated fission chambers, allow the neutron flux density unit transfer from international reference neutron fields. The MCNP-4C code package was used for neutron spectrum computations in the thermal flux cavity and in the {sigma}{sigma} system. The neutron characterization program demonstrates the accuracy of the spectrum characteristics and neutron flux densities reported to the local monitoring system count rates. Some discrepancies, as compared to other similar facilities, were identified and discussed. These are caused by thermal column particularities: the presence of a water layer between the graphite cells (thermal neutron absorption) and smaller geometrical dimensions (neutron escape phenomena). Based on these results the metrological certification process, according to Romanian metrological laws requirements, is now in progress. (nevyjel)

Comparing facility-level methane emission rate estimates at natural gas gathering and boosting stations

Directory of Open Access Journals (Sweden)

Timothy L. Vaughn

2017-11-01

Full Text Available Coordinated dual-tracer, aircraft-based, and direct component-level measurements were made at midstream natural gas gathering and boosting stations in the Fayetteville shale (Arkansas, USA. On-site component-level measurements were combined with engineering estimates to generate comprehensive facility-level methane emission rate estimates (“study on-site estimates (SOE” comparable to tracer and aircraft measurements. Combustion slip (unburned fuel entrained in compressor engine exhaust, which was calculated based on 111 recent measurements of representative compressor engines, accounts for an estimated 75% of cumulative SOEs at gathering stations included in comparisons. Measured methane emissions from regenerator vents on glycol dehydrator units were substantially larger than predicted by modelling software; the contribution of dehydrator regenerator vents to the cumulative SOE would increase from 1% to 10% if based on direct measurements. Concurrent measurements at 14 normally-operating facilities show relative agreement between tracer and SOE, but indicate that tracer measurements estimate lower emissions (regression of tracer to SOE = 0.91 (95% CI = 0.83–0.99, R2 = 0.89. Tracer and SOE 95% confidence intervals overlap at 11/14 facilities. Contemporaneous measurements at six facilities suggest that aircraft measurements estimate higher emissions than SOE. Aircraft and study on-site estimate 95% confidence intervals overlap at 3/6 facilities. The average facility level emission rate (FLER estimated by tracer measurements in this study is 17–73% higher than a prior national study by Marchese et al.

Quantification Of Greenhouse Gases From Three Danish Composting Facilities

DEFF Research Database (Denmark)

Scheutz, Charlotte; Andersen, Jacob Kragh; Samuelsson, J.

2011-01-01

A measurement method combining a controlled trace gas release with downwind concentrations measurements was successfully used to quantify greenhouse gas (GHG) emissions from three Danish open windrow composting facilities. Overall, the results showed that composting of organic waste generate GHG...... emissions in terms of methane (CH4) and nitrous oxide (N2O) and thus contribute to climate change. At all three facilities significant CH4 emissions were occurring. The CH4 emission varied between 0.50 and 5.73 kg CH4 h-1. The highest CH4 emission (5.73 kg CH4 h-1) were measured at the Aarhus composting...... facility and was believed to be a result of the windrow lay-out with very broad and high windrows and a low turning frequency. The lowest CH4 emission (0.50 kg CH4 h-1) was measured at Fakse composting area and was most likely a result of the relatively small windrows and frequent weekly turnings. For all...

Review of nuclear data improvement needs for nuclear radiation measurement techniques used at the CEA experimental reactor facilities

Directory of Open Access Journals (Sweden)

Destouches Christophe

2016-01-01

Full Text Available The constant improvement of the neutron and gamma calculation codes used in experimental nuclear reactors goes hand in hand with that of the associated nuclear data libraries. The validation of these calculation schemes always requires the confrontation with integral experiments performed in experimental reactors to be completed. Nuclear data of interest, straight as cross sections, or elaborated ones such as reactivity, are always derived from a reaction rate measurement which is the only measurable parameter in a nuclear sensor. So, in order to derive physical parameters from the electric signal of the sensor, one needs specific nuclear data libraries. This paper presents successively the main features of the measurement techniques used in the CEA experimental reactor facilities for the on-line and offline neutron/gamma flux characterizations: reactor dosimetry, neutron flux measurements with miniature fission chambers and Self Power Neutron Detector (SPND and gamma flux measurements with chamber ionization and TLD. For each technique, the nuclear data necessary for their interpretation will be presented, the main identified needs for improvement identified and an analysis of their impact on the quality of the measurement. Finally, a synthesis of the study will be done.

BWR Full Integral Simulation Test (FIST) program: facility description report

International Nuclear Information System (INIS)

Stephens, A.G.

1984-09-01

A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

Facility Activity Inference Using Radiation Networks

Energy Technology Data Exchange (ETDEWEB)

Rao, Nageswara S. [ORNL; Ramirez Aviles, Camila A. [ORNL

2017-11-01

We consider the problem of inferring the operational status of a reactor facility using measurements from a radiation sensor network deployed around the facility’s ventilation off-gas stack. The intensity of stack emissions decays with distance, and the sensor counts or measurements are inherently random with parameters determined by the intensity at the sensor’s location. We utilize the measurements to estimate the intensity at the stack, and use it in a one-sided Sequential Probability Ratio Test (SPRT) to infer on/off status of the reactor. We demonstrate the superior performance of this method over conventional majority fusers and individual sensors using (i) test measurements from a network of 21 NaI detectors, and (ii) effluence measurements collected at the stack of a reactor facility. We also analytically establish the superior detection performance of the network over individual sensors with fixed and adaptive thresholds by utilizing the Poisson distribution of the counts. We quantify the performance improvements of the network detection over individual sensors using the packing number of the intensity space.

Saltstone studies using the scaled continuous processing facility

Energy Technology Data Exchange (ETDEWEB)

Fowley, M. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hansen, E. K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-08-01

The Savannah River National Laboratory (SRNL) has supported the Saltstone Facility since its conception with bench-scale laboratory experiments, mid-scale testing at vendor facilities, and consultations and testing at the Saltstone Facility. There have been minimal opportunities for the measurement of rheological properties of the grout slurry at the Saltstone Production Facility (SPF); thus, the Scaled Continuous Processing Facility (SCPF), constructed to provide processing data related to mixing, transfer, and other operations conducted in the SPF, is the most representative process data for determining the expected rheological properties in the SPF. These results can be used to verify the laboratory scale experiments that support the SPF using conventional mixing processes that appropriately represent the shear imparted to the slurry in the SPF.

Developing of the protocol for electron beam food irradiation facility

International Nuclear Information System (INIS)

Petreska, Svetlana

2012-01-01

By establishing the needs for institution of new technologies in the process of food processing, in this case a randomized choice of electron beam accelerator facility, arises the need for designing a protocol for safe and secure performance of the facility. The protocol encompasses safety and security measures for protection from ionizing radiation of the individuals who work at the facility, as well as, the population and the environment in the immediate neighborhood of the facility. Thus, the adopted approach is the establishment of appropriate systems responding to the protocol. Dosimetry system, which includes appropriate procedures for accurate measure and recording of the absorbed dose values, according to the provisions for protection from ionizing radiation. Ionizing radiation protection system and providing the safety and security of the facility for food processing by means of ionizing radiation. System for providing quality and safety control of the facility for food processing by means of ionizing radiation. Pursuant to the designed a protocol for safe and secure performance of the facility for electron beam food processing, contributes to protection against ionizing radiation as occupationally exposed persons as well the population. (Author)

Respirator use and its impact on particulate matter exposure in aluminum manufacturing facilities.

Science.gov (United States)

Liu, Sa; Noth, Elizabeth; Eisen, Ellen; Cullen, Mark R; Hammond, Katharine

2018-05-31

Objectives As part of a large epidemiologic study of particulate health effect, this study aimed to report respirator use among total particulate matter (TPM) samples collected in a major aluminum manufacturing company from 1966‒2013 and evaluate the impact of respirator-use adjustment on exposure estimation. Methods Descriptive analyses were performed to evaluate respirator use across facilities and by facility type and job. Protection factors were applied to TPM measurements for recorded respirator use. Estimated TPM exposure for each job ‒ before and after respirator-use adjustment ‒ were compared to assess the impact of adjustment on exposure estimation. Results Respirator use was noted for 37% of 12 402 full-shift personal TPM samples. Measured TPM concentration ranged from less than detectable to 8220 mg/m3, with arithmetic mean, median and standard deviation being 10.6, 0.87 and 130 mg/m 3 , respectively. Respirators were used more often in smelting facilities (52% of TPM measurements) than in fabricating (17%) or refinery facilities (28%) (Pfacilities were subject to respirator-use adjustment, whereas it was 20% and 70% in fabricating and refinery facilities, respectively. Applying protection factors to TPM measurements significantly reduced estimated job mean TPM exposures and changed exposure categories in these facilities, with larger impact in smelting than fabricating facilities. Conclusions Respirator use varied by time, facility and job. Adjusting respirator use resulted in differential impact in smelting and fabricating facilities, which will need to be incorporated into ongoing epidemiologic studies accordingly.

Electron beam irradiation facility for low to high dose irradiation applications

International Nuclear Information System (INIS)

Petwal, V.C.; Wanmode, Yashwant; Verma, Vijay Pal; Bhisikar, Abhay; Dwivedi, Jishnu; Shrivastava, P.; Gupta, P.D.

2013-01-01

Electron beam based irradiation facilities are becoming more and more popular over the conventional irradiator facilities due to many inherent advantages such as tunability of beam energy, availability of radiation both in electron mode and X-ray mode, wide range of the dose rate, control of radiation from a ON-OFF switch and other safety related merits. A prototype experimental facility based on electron accelerator has been set-up at RRCAT to meet the low-dose, medium dose and high-dose requirements for radiation processing of food, agricultural and medical products. The facility can be operated in the energy range from 7-10 MeV at variable power level from 0.05-3 kW to meet the dose rate requirement of 100 Gy to kGy. The facility is also equipped with a Bremsstrahlung converter optimized for X-ray irradiation at 7.5 MV. Availability of dose delivery in wide range with precision control and measurement has made the facility an excellent tool for researchers interested in electron/X-ray beam irradiation. A precision dosimetry lab based on alanine EPR and radiochromic film dosimetry system have been established to characterize the radiation field and precise dose measurements. Electron beam scattering technique has been developed to achieve low dose requirement for EB irradiation of various seeds such as groundnut, wheat, soybeans, moong beans, black gram etc. for mutation related studies. This paper describes various features of the facility together with the dosimetric measurements carried out for qualification of the facility and recent irradiation experiments carried out using this facility. (author)

Long-pulse magnetic field facility at Zaragoza

International Nuclear Information System (INIS)

Algarabel, P A; Moral, A del; Martin, C; Serrate, D; Tokarz, W

2006-01-01

The long-pulse magnetic field facility of the Laboratorio de Magnetismo - Instituto de Ciencia de Materiales de Aragon (Universidad de Zaragoza-CSIC) produces magnetic fields up to 31, with a pulse duration of 2.2s. Experimental set-ups for measurements of magnetization, magnetostriction and magnetoresistance are available. The temperature can be controlled between 1.4 and 335 K, being the inner bore of the He cryostat of 22.5 mm. Magnetization is measured using the mutual induction technique, the magnetostriction is determined with the strain-gage and the capacitive cantilever methods, and the magnetoresistance is measured by means of the aclock-in technique in the 4-probes geometry. An overview of the facility will be presented and the presently available experimental techniques will be discussed

A new AMS facility at Inter University Accelerator Centre, New Delhi

Science.gov (United States)

Kumar, Pankaj; Chopra, S.; Pattanaik, J. K.; Ojha, S.; Gargari, S.; Joshi, R.; Kanjilal, D.

2015-10-01

Inter University Accelerator Centre (IUAC), a national facility of government of India, is having a 15UD Pelletron accelerator for multidisciplinary ion beam based research programs. Recently, a new accelerator mass spectrometry (AMS) facility has been developed after incorporating many changes in the existing 15UD Pelletron accelerator. A clean chemistry laboratory for 10Be and 26Al with all the modern facilities has also been developed for the chemical processing of samples. 10Be measurements on sediment samples, inter laboratory comparison results and 26Al measurements on standard samples are presented in this paper. In addition to the 10Be and 26Al AMS facilities, a new 14C AMS facility based on a dedicated 500 kV tandem ion accelerator with two cesium sputter ion sources, is also being setup at IUAC.

A calibration facility for radon fluxmeter

International Nuclear Information System (INIS)

Li Xianjie; Qiu Shoukang; Zhou Jianliang; Liu Chunkui; Pan Jialin; Yang Mingli

1998-01-01

Calibration facilities for radon fluxmeter with three kinds of different emanation medium have been developed. The stability of radon flux is 5%, 9% (RSD) respectively. The uniformity of radon flux is 4.5%, 8.5% (RSD) respectively. These specifications fulfill the calibration requirement for radon fluxmeter. The determination of radon flux of facility takes full account of eliminating the main error source-attenuation effect (including leakage and back diffusion etc.): not only prevent attenuation and make a relevant correction. Therefore the accuracy of determination is assured. The calibration, intercomparison of radon flux meter and the quantitatively evaluation on the measurement method of radon flux are made to be possible by the successful establishment of this facility. (author)

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

STG-ET: DLR electric propulsion test facility

Directory of Open Access Journals (Sweden)

Andreas Neumann

2017-04-01

Full Text Available DLR operates the High Vacuum Plume Test Facility Göttingen – Electric Thrusters (STG-ET. This electric propulsion test facility has now accumulated several years of EP-thruster testing experience. Special features tailored to electric space propulsion testing like a large vacuum chamber mounted on a low vibration foundation, a beam dump target with low sputtering, and a performant pumping system characterize this facility. The vacuum chamber is 12.2m long and has a diameter of 5m. With respect to accurate thruster testing, the design focus is on accurate thrust measurement, plume diagnostics, and plume interaction with spacecraft components. Electric propulsion thrusters have to run for thousands of hours, and with this the facility is prepared for long-term experiments. This paper gives an overview of the facility, and shows some details of the vacuum chamber, pumping system, diagnostics, and experiences with these components.

Radiological characterization of the TAN-IET facility

Energy Technology Data Exchange (ETDEWEB)

Koeppen, L.D.; Rodriguez, S.V.; Wheeler, O.A.; Cadwell, E.D.; Simpson, O.D.

1982-06-01

The Initial Engine Test (IET) facility is located on the Idaho National Engineering Laboratory (INEL) site at the north end of Test Area North (TAN). The IET facility was constructed and used for the Aircraft Nuclear Propulsion Program during the 1950's and was later used for two other programs: the Space Nuclear Auxiliary Power Transient (SNAP-TRAN) and the Hallam Decontamination and Decommissioning Project. The facility is no longer in use, therefore, a complete radiological characterization was conducted at the IET site. The characterization included measurements of beta-gamma dose rates; beta-gamma and alpha surface contamination; concentrations of selected radionuclides in subsurface storage tanks, surface soil, the exhaust duct, stack and test pad; and a walk-over surface survey of the entire facility. The information contained in this report will be of great value as the IET facility goes through the decommissioning and decontamination process.

Working paper on public steering of privately owned sports facilities

DEFF Research Database (Denmark)

Iversen, Evald Bundgård

This short paper discusses how municipalities can steer privately owned sports facilities. Firstly I analyse why steering of privately owned facilities is an interesting subject. Secondly I discuss what the advantages and drawbacks of using different approaches for steering sports facilities are........ Finally I discuss the methodological challenges of measuring activities in sports facilities – and take a closer look at the advantages and drawbacks of using manual and thermal techniques for registering activity.......This short paper discusses how municipalities can steer privately owned sports facilities. Firstly I analyse why steering of privately owned facilities is an interesting subject. Secondly I discuss what the advantages and drawbacks of using different approaches for steering sports facilities are...

Inpatient Psychiatric Facility Follow-Up After Hospitalization for Mental Illness (FUH) Quality Measure Data – National

Data.gov (United States)

U.S. Department of Health & Human Services — Psychiatric facilities that are eligible for the Inpatient Psychiatric Facility Quality Reporting (IPFQR) program are required to meet all program requirements,...

Research Facilities for the Future of Nuclear Energy

International Nuclear Information System (INIS)

Ait Abderrahim, H.

1996-01-01

The proceedings of the ENS Class 1 Topical Meeting on Research facilities for the Future of Nuclear Energy include contributions on large research facilities, designed for tests in the field of nuclear energy production. In particular, issues related to facilities supporting research and development programmes in connection to the operation of nuclear power plants as well as the development of new concepts in material testing, nuclear data measurement, code validation, fuel cycle, reprocessing, and waste disposal are discussed. The proceedings contain 63 papers

Automation in a material processing/storage facility

International Nuclear Information System (INIS)

Peterson, K.; Gordon, J.

1997-01-01

The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements of the facility. Among the functions to be automated are the transport of containers between process and storage areas via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area, the Accountability Measurements (AM) area, the Special Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being automated, but are outside the scope of this paper

New radiation protection calibration facility at CERN.

Science.gov (United States)

Brugger, Markus; Carbonez, Pierre; Pozzi, Fabio; Silari, Marco; Vincke, Helmut

2014-10-01

The CERN radiation protection group has designed a new state-of-the-art calibration laboratory to replace the present facility, which is >20 y old. The new laboratory, presently under construction, will be equipped with neutron and gamma sources, as well as an X-ray generator and a beta irradiator. The present work describes the project to design the facility, including the facility placement criteria, the 'point-zero' measurements and the shielding study performed via FLUKA Monte Carlo simulations. © The Author 2013. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Status report on the Erlangen AMS facility

International Nuclear Information System (INIS)

Scharf, A.; Uhl, T.; Luppold, W.; Rottenbach, A.; Kritzler, K.; Ohneiser, A.; Kretschmer, W.

2007-01-01

The Erlangen AMS facility has been in routine operation since 1995. We present the current status of the facility and recent developments in our laboratory. The main focuses of our research are further improvement and automation of the sample preparation, the development of new sample preparation techniques like the dating of iron artefacts, and the development of an efficient automated gas feeding system for a gas ion source for the measurement of microgram samples for, e.g. environmental or future biomedical applications. The current background level and the long term stability of the facility are presented and discussed

The ISAC facility at TRIUMF

International Nuclear Information System (INIS)

Dilling, J.

2005-01-01

ISAC at TRIUMF, Vancouver is one of the prime radioactive beam facilities worldwide. The isotopes are produced via the isol method and are extracted to typically 30-60 keV beams and subsequently mass selected. The beam can be further accelerated to 1.8 meV/u and with the completion of ISAC II (2005/6) up to 6.5 meV/u. One of the primary motivations at ISAC are nuclear astrophysics experiments. In addition to cross-section determination, Q-values are key parameters. The latter ones are accessible via mass measurements. The TITAN system at ISAC will allow to carry out such measurements with the very high precision (δm/m ≤ x 10 -8 ) on short-lived isotopes (T 1/2 ∼ 10 ms). An introduction to TITAN, together with an overview of the ISAC facility will be given. (author)

Brief description of the Wackersdorf Reprocessing Facility

International Nuclear Information System (INIS)

1986-01-01

The DWK is now planning the construction and operation of a facility for the reprocessing of spent fuel elements and the fabrication of mixed-oxide fuel elements which will initially have an average daily throughput of 2 tons (t) of nuclear fuel. The application required by the Atomic Law was submitted to the Bavarian State Ministry for State Development and Environmental Matters on October 28, 1982. According to Par. 3, Section 1, No. 1 of the Atomic Law Procedural Ordinance such an application for permission in accordance with par. 7 AtL must explicitly be accompanied by a safety report which shall make it possible for third parties to make a judgment whether the impacts associated with the facility and its operation could damage their rights. The safety report is intended to present and explain the concept of the facility, the safety-technological design bases, and the operation of the plant, including its operation and safety systems and the impacts and proposed preventive measures. In addition to the detailed presentations in the safety report, Par. 3 of the Atomic Law Procedural Ordinance also requires a brief description of the plant designed for general public understanding, suitable for the design, which will also explain the expected impacts on the general environment and the surrounding area. Hence the brief description presents and explains the following matters: the site; the technology and state of the art for reprocessing of spent nuclear fuel; the structure and function of the proposed facility; safety provisions of the proposed facility and the management of perturbations in operation; the impacts of the facility and its operation on the environment; measures to be taken for dealing with the radioactive wastes; and provisions for ultimate shut-down of the facility

Four critical facilities: their capabilities and programs

International Nuclear Information System (INIS)

Whitesides, G.E.

1980-01-01

Information is presented on the critical experiments facilities at Babcock and Wilcox, Lynchburg, Virginia; at Battelle Pacific Northwest Laboratory in Hanford, Washington; at Rockwell-International in Rocky Flats, Colorado; and at Los Alamos Scientific Laboratory in New Mexico. It is noted that the critical mass facilities which still exist in this country represent a bare minimum for maintaining a measurement program sufficient for meeting data requirements

Neutron capture cross section measurement of $^{151}Sm$ at the CERN neutron Time of Flight Facility (nTOF)

CERN Document Server

Abbondanno, U; Alvarez-Velarde, F; Alvarez-Pol, H; Andriamonje, Samuel A; Andrzejewski, J; Badurek, G; Baumann, P; Becvar, F; Benlliure, J; Berthoumieux, E; Calviño, F; Cano-Ott, D; Capote, R; Cennini, P; Chepel, V; Chiaveri, Enrico; Colonna, N; Cortés, G; Cortina-Gil, D; Couture, A; Cox, J; Dababneh, S; Dahlfors, M; David, S; Dolfini, R; Domingo-Pardo, C; Durán, I; Embid-Segura, M; Ferrant, L; Ferrari, A; Ferreira-Marques, R; Frais-Kölbl, H; Furman, W; Gonçalves, I; Gallino, R; Gonzalez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martínez, A; Isaev, S; Jericha, E; Kappeler, F; Kadi, Y; Karadimos, D; Kerveno, M; Ketlerov, V; Köhler, P; Konovalov, V; Krticka, M; Lamboudis, C; Leeb, H; Lindote, A; Lopes, I; Lozano, M; Lukic, S; Marganiec, J; Marrone, S; Martinez-Val, J; Mastinu, P; Mengoni, A; Milazzo, P M; Molina-Coballes, A; Moreau, C; Mosconi, M; Neves, F; Oberhummer, Heinz; O'Brien, S; Pancin, J; Papaevangelou, T; Paradela, C; Pavlik, A; Pavlopoulos, P; Perlado, J M; Perrot, L; Pignatari, M; Plag, R; Plompen, A; Plukis, A; Poch, A; Policarpo, Armando; Pretel, C; Quesada, J; Raman, S; Rapp, W; Rauscher, T; Reifarth, R; Rosetti, M; Rubbia, Carlo; Rudolf, G; Rullhusen, P; Salgado, J; Soares, J C; Stéphan, C; Tagliente, G; Taín, J L; Tassan-Got, L; Tavora, L; Terlizzi, R; Vannini, G; Vaz, P; Ventura, A; Villamarín, D; Vincente, M C; Vlachoudis, V; Voss, F; Wendler, H; Wiescher, M; Wissha, K

2004-01-01

The measurement of **1**5**1Sm(n, gamma)**1**5**2Sm (samarium) cross section showed improved performance of the new spallation neutron facility. It covered a wide energy range with good resolution, high neutron flux, low backgrounds and a favourable duty factor. The samarium cross section was found to be of great importance for characterizing neutron capture nucleosynthesis in asymptotic giant stars. The combination of these features provided a promising basis for a broad experimental program directed towards application in astrophysics and advanced nuclear technologies. (Edited abstract)

The DFVLR wind-energy test facility 'Ulrich Huetter' on Schnittlinger Berg

Science.gov (United States)

Kussmann, Alfred

1986-11-01

The DFVLR test facility for wind-energy systems (named after Ulrich Huetter, the designer of the 100-kW GFRP-rotor W 34 wind turbine first manufactured and tested in the 1950s) is described and illustrated with photographs. The history of the facility is traced, and current operations in gathering, archiving, processing, interpreting, and documenting performance-test data are outlined. The facility includes instrumentation for rotor telemetry, gondola motion measurements, and ground measurements and provides testing services to private users on both contract and leasing bases.

Decommissioning of a Radioactive Facility Used for Biomolecule Labeling and Biological Effects

International Nuclear Information System (INIS)

Yagüe, L.; Navarro, N.; Álvarez, A.; Quiñones, J.

2015-01-01

This paper presents the measurement methodology designed for the final status survey of an old radioactive facility, used as radiolabeling lab. Its declassification as radioactive facility required the radiological characterization of all walls, structures and materials at the facility in order to reuse its outbuilding for conventional use. To demonstrate compliance with the declassification criteria, the design of the final status survey was performed applying MARSSIM(1) (Multi-Agency Radiation Survey and Site Investigation Manual) methodology and using different measurement techniques depending on the radioactive isotopes in the inventory of the facility, their half-lives and emission characteristics.

Real-time graphic display system for ROSA-V Large Scale Test Facility

International Nuclear Information System (INIS)

Kondo, Masaya; Anoda, Yoshinari; Osaki, Hideki; Kukita, Yutaka; Takigawa, Yoshio.

1993-11-01

A real-time graphic display system was developed for the ROSA-V Large Scale Test Facility (LSTF) experiments simulating accident management measures for prevention of severe core damage in pressurized water reactors (PWRs). The system works on an IBM workstation (Power Station RS/6000 model 560) and accommodates 512 channels out of about 2500 total measurements in the LSTF. It has three major functions: (a) displaying the coolant inventory distribution in the facility primary and secondary systems; (b) displaying the measured quantities at desired locations in the facility; and (c) displaying the time histories of measured quantities. The coolant inventory distribution is derived from differential pressure measurements along vertical sections and gamma-ray densitometer measurements for horizontal legs. The color display indicates liquid subcooling calculated from pressure and temperature at individual locations. (author)

Initial characterization of the ATR [Advanced Test Reactor] Large Gamma Facility

International Nuclear Information System (INIS)

Schnitzler, B.G.; Rogers, J.W.

1986-05-01

Radiation fields in the ATR Large Gamma Facility test volume are characterized. The preliminary characterization efforts described in this report include total dose rate measurements in the facility, development of a simple methodology for calculating radiation fields from the ATR fuel element power histories, and a comparison of the measured and calculated values

The Sandia transportable triggered lightning instrumentation facility

Science.gov (United States)

Schnetzer, George H.; Fisher, Richard J.

1991-01-01

Development of the Sandia Transportable Triggered Lightning Instrumentation Facility (SATTLIF) was motivated by a requirement for the in situ testing of a munitions storage bunker. Transfer functions relating the incident flash currents to voltages, currents, and electromagnetic field values throughout the structure will be obtained for use in refining and validating a lightning response computer model of this type of structure. A preliminary shakedown trial of the facility under actual operational conditions was performed during summer of 1990 at the Kennedy Space Center's (KSC) rocket-triggered lightning test site. A description is given of the SATTLIF, which is readily transportable on a single flatbed truck of by aircraft, and its instrumentation for measuring incident lightning channel currents and the responses of the systems under test. Measurements of return-stroke current peaks obtained with the SATTLIF are presented. Agreement with data acquired on the same flashes with existing KSC instrumentation is, on average, to within approximately 7 percent. Continuing currents were measured with a resolution of approximately 2.5 A. This field trial demonstrated the practicality of using a transportable triggered lightning facility for specialized test applications.

Legal regime of water management facilities

Directory of Open Access Journals (Sweden)

Salma Jožef

2013-01-01

Full Text Available The paper analyzes the legal regime of water management facilities in the light of Serbian, foreign and European law. Different divisions of water management facilities are carried out (to public and private ones, natural and artificial ones, etc., with determination of their legal relevance. Account is taken of the issue of protection from harmful effects of waters to such facilities, as well. The paper points also to rules on the water management facilities, from acts of planning, to individual administrative acts and measures for maintenance of required qualitative and quantitative condition of waters, depending on their purpose (general use or special, commercial use o waters. Albeit special rules on water management facilities exist, due to the natural interlocking between all the components of the environment (water, air and soil, a comprehensive approach is required. A reference is made to other basic principles of protection of water management facilities as well, such as the principle of prevention, principle of sustainable development and the principle "polluter pays". The last one represents the achievement of contemporary law, which deviates from the idea accepted in the second half of 20th century that supported the socialization of risk from harmful effects of waters.

Rock stress measurements in ONKALO underground characterisation facility at Olkiluoto at depth of 120 m

International Nuclear Information System (INIS)

Fecker, E.

2007-04-01

In November and December 2006 overcoring stress measurements have been conducted in the boreholes ONK-PP74, ONK-PP75 and ONK-PP77 in a niche of the access tunnel of the ONKALO underground characterisation facility at the Olkiluoto site. Measurements have been done using the CSIRO 3D stress measuring cell. This cell is one of the mostly used cells in the whole world for estimation of the state of stress in rock when doing the borehole measurements. The boreholes are at a depth of about 120 m under the ground surface. The rock where the measurements have been conducted is a foliated migmatitic gneiss (subtypes veined and diatexitic gneiss). Parallel to the overcoring measurements a glue test has been conducted in the laboratory to check the quality of the bonding of the stress cells to the rock. The result showed that the glue makes a good contact between the rock and the stress cell, but air bubbles, which have normally been observed within the glue and at the edges, proved this time to be disadvantageous. Normally such air bubbles have dimensions of about one millimetre, but sometimes certain bubbles may become notably bigger. In the ONKALO overcored probes sawn apart such air bubbles were found both in wet and dry probe conditions. In the test series eight stress measurements have been provided, three of them failed for technical reasons. At one of these three tests the glue has extruded too early, at the other two tests the overcoring was not conducted deep enough. At the remaining five tests in spite of the glue test results a calculation of the stress tensor could be made. Four of these five measurements can be seen as relatively successful. The results of these measurements show a major principal stress of 14.8 MPa in average, trending northwest - southeast, and with a dipping of 11 degrees in average. (orig.)

Organisational culture in residential aged care facilities: a cross-sectional observational study.

Science.gov (United States)

Etherton-Beer, Christopher; Venturato, Lorraine; Horner, Barbara

2013-01-01

Organisational culture is increasingly recognised as important for provision of high-quality long-term care. We undertook this study to measure organisational culture in residential aged care facilities in two Australian states. Cross-sectional observational study in 21 residential aged care facilities in Western Australia (n = 14) and Queensland (n = 7), Australia. Staff and next-of-kin of residents participated. Measurement comprised surveys of facility staff and residents' next-of-kin, and structured observation of indicators of care quality. Staff tended to rate organisational culture positively. Some qualitative feedback from staff emphasised negative perceptions of communication, leadership and teamwork. Staffing levels were perceived as a dominant challenge, threatening care quality. Direct observation revealed variability within and between facilities but suggested that most facilities (n = 12) were in the typical range, or were quality facilities (n = 8). There was scope to strengthen organisational culture in participating aged care facilities.

Measurement of concentrations of {gamma}-ray emitters induced in the concrete shield of the JAERI electron linac facility

Energy Technology Data Exchange (ETDEWEB)

Endo, Akira; Kawasaki, Katsuya; Kikuchi, Masamitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Harada, Yasunori

1997-07-01

Measurement has been made to study distributions of {gamma}-ray emitters induced in the concrete shield of the JAERI electron linac facility. Core boring was carried out at seven positions to take samples from the concrete shield, and {gamma}-ray counting rates and {gamma}-ray spectra of these samples were measured with a NaI(Tl) detector and a Ge semiconductor detector, respectively. The following radionuclides were detected in the concrete samples: {sup 60}Co, {sup 134}Cs, {sup 152}Eu and {sup 154}Eu generated through thermal neutron capture reaction, and {sup 22}Na and {sup 54}Mn generated through nuclear reactions by bremsstrahlung and fast neutrons. The relation between the distributions of {gamma}-ray emitters, as a function of the depth of concrete, and the positions of core boring is discussed. (author)

Perceived risk impacts from siting hazardous waste facilities

International Nuclear Information System (INIS)

Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

1992-01-01

This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioecconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts, resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed

Perceived risk impacts from siting hazardous waste facilities

International Nuclear Information System (INIS)

Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

1992-01-01

This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioeconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed

A new AMS facility at Inter University Accelerator Centre, New Delhi

Energy Technology Data Exchange (ETDEWEB)

Kumar, Pankaj, E-mail: pkb@iuac.res.in [Inter-University Accelerator Center (IUAC), New Delhi (India); Chopra, S. [Inter-University Accelerator Center (IUAC), New Delhi (India); Pattanaik, J.K. [Department of Earth Sciences, Indian Institute of Science Education and Research Kolkata, Nadia, WB (India); Ojha, S.; Gargari, S.; Joshi, R.; Kanjilal, D. [Inter-University Accelerator Center (IUAC), New Delhi (India)

2015-10-15

Inter University Accelerator Centre (IUAC), a national facility of government of India, is having a 15UD Pelletron accelerator for multidisciplinary ion beam based research programs. Recently, a new accelerator mass spectrometry (AMS) facility has been developed after incorporating many changes in the existing 15UD Pelletron accelerator. A clean chemistry laboratory for {sup 10}Be and {sup 26}Al with all the modern facilities has also been developed for the chemical processing of samples. {sup 10}Be measurements on sediment samples, inter laboratory comparison results and {sup 26}Al measurements on standard samples are presented in this paper. In addition to the {sup 10}Be and {sup 26}Al AMS facilities, a new {sup 14}C AMS facility based on a dedicated 500 kV tandem ion accelerator with two cesium sputter ion sources, is also being setup at IUAC.

Development of an anthropomorfic simulator for simulation and measurements of neutron dose and flux the facility for BNCT studies

International Nuclear Information System (INIS)