Facilities Performance Indicators Report 2011-12: Tracking Your Facilities Vital Signs

Science.gov (United States)

APPA: Association of Higher Education Facilities Officers, 2013

2013-01-01

This paper provides an expanded Web-based "Facilities Performance Indicators (FPI) Report." The purpose of APPA's Facilities Performance Indicators is to provide a representative set of statistics about facilities in educational institutions. APPA's Information and Research Committee's goal for this year was to enhance the…

Facilities Performance Indicators Report, 2004-05. Facilities Core Data Survey

Science.gov (United States)

Glazner, Steve, Ed.

2006-01-01

The purpose of "Facilities Performance Indicators" is to provide a representative set of statistics about facilities in educational institutions. The second iteration of the web-based Facilities Core Data Survey was posted and available to facilities professionals at more than 3,000 institutions in the Fall of 2005. The website offered a printed…

Fuel Processing Plants - ETHANOL_PRODUCTION_FACILITIES_IN: Ethanol Production Facilities in Indiana (Indiana Geological Survey, Point Shapefile)

Data.gov (United States)

NSGIC State | GIS Inventory — This GIS layer shows the locations of ethanol production facilities in the state of Indiana. Attributes include the name and address of the facility, and information...

Performance of grid-tied PV facilities: A case study based on real data

International Nuclear Information System (INIS)

Díez-Mediavilla, M.; Dieste-Velasco, M.I.; Rodríguez-Amigo, M.C.; García-Calderón, T.; Alonso-Tristán, C.

2013-01-01

Highlights: • A new procedure to analyse the performance of PV facilities is presented. • It only requires limited amounts of data that are easily sourced. • Data sets on production were collected over two complete years. • The transformerless inverter outperforms the isolated inverter. - Abstract: A new procedure is presented to analyse the performance of grid-tied PV facilities. It needs limited amounts of data that are easily sourced and is based on knowledge of the analysed system and its mode of operation. The procedure is applied, in a case study, to compare real PV production at two 100 kW p grid-connected PV installations. Located in the same geographical region, the installation of these two facilities followed the same construction criteria – PV panels, panel support system and wiring – and the facilities were exposed to the same atmospheric temperature and solar radiation. They differ with regard to their inverter technology: one facility uses an inverter with an integrated transformer system and the other uses a transformerless inverter. The results show that the transformerless inverter system performed better than the isolated system by a factor of 1.2%, which, in economic terms, represents more than 2000 €/year

Performance of simulated flexible integrated gasification polygeneration facilities. Part A: A technical-energetic assessment

NARCIS (Netherlands)

Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

2011-01-01

This article investigates technical possibilities and performances of flexible integrated gasification polygeneration (IG-PG) facilities equipped with CO2 capture for the near future. These facilities can produce electricity during peak hours, while switching to the production of chemicals during

Design of GMP compliance radiopharmaceutical production facility in MINT

International Nuclear Information System (INIS)

Anwar Abd Rahman; Shaharum Ramli; M Rizal Mamat Ibrahim; Rosli Darmawan; Yusof Azuddin Ali; Jusnan Hashim

2005-01-01

In 1985, MINT built the only radiopharmaceutical production facility in Malaysia. The facility was designed based on IAEA (International Atomic Energy Agency) standard guidelines which provide radiation safety to the staff and the surrounding environment from radioactive contamination. Since 1999, BPFK (Biro Pengawalan Farmaseutikal Kebangsaan) has used the guidelines from Pharmaceutical Inspection Convention Scheme (PICS) to meet the requirements of the Good Manufacturing Practice (GMP) for Pharmaceutical Products. In the guidelines, the pharmaceutical production facility shall be designed based on clean room environment. In order to design a radiopharmaceutical production facility, it is important to combine the concept of radiation safety and clean room to ensure that both requirements from GMP and IAEA are met. The design requirement is necessary to set up a complete radiopharmaceutical production facility, which is safe, has high production quality and complies with the Malaysian and International standards. (Author)

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

Isotope Production Facility Conceptual Thermal-Hydraulic Design Review and Scoping Calculations

International Nuclear Information System (INIS)

Pasamehmetoglu, K.O.; Shelton, J.D.

1998-01-01

The thermal-hydraulic design of the target for the Isotope Production Facility (IPF) is reviewed. In support of the technical review, scoping calculations are performed. The results of the review and scoping calculations are presented in this report

HTTR hydrogen production system. Structure and main specifications of mock-up test facility (Contract research)

International Nuclear Information System (INIS)

Kato, Michio; Aita, Hideki; Inagaki, Yoshiyuki; Hayashi, Koji; Ohashi, Hirofumi; Sato, Hiroyuki; Iwatsuki, Jin; Takada, Shoji; Inaba, Yoshitomo

2007-03-01

The mock-up test facility was fabricated to investigate performance of the steam generator for mitigation of the temperature fluctuation of helium gas and transient behavior of the hydrogen production system for HTTR and to obtain experimental data for verification of a dynamic analysis code. The test facility has an approximate hydrogen production capacity of 120Nm 3 /h and the steam reforming process of methane; CH 4 +H 2 O=3H 2 +CO, was used for hydrogen production of the test facility. An electric heater was used as a heat source instead of the reactor in order to heat helium gas up to 880degC (4MPa) at the chemical reactor inlet which is the same temperature as the HTTR hydrogen production system. Fabrication of the test facility was completed in February in 2002, and seven cycle operations were carried out from March in 2002 to December in 2004. This report describes the structure and main specifications of the test facility. (author)

Disposal facility data for the interim performance

International Nuclear Information System (INIS)

Eiholzer, C.R.

1995-01-01

The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

Calculation of displacement and helium production at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) irradiation facility

International Nuclear Information System (INIS)

Wechsler, M.S.; Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.

1984-01-01

CT: Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF). The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 20 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Production of medical radioactive isotopes using KIPT electron driven subcritical facility

International Nuclear Information System (INIS)

Talamo, Alberto; Gohar, Yousry

2008-01-01

Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, γ), (n, 2n), (n, p), and (γ, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope

Production of medical radioactive isotopes using KIPT electron driven subcritical facility

Energy Technology Data Exchange (ETDEWEB)

Talamo, Alberto [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)], E-mail: alby@anl.gov; Gohar, Yousry [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

2008-05-15

Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, {gamma}), (n, 2n), (n, p), and ({gamma}, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope.

Production of medical radioactive isotopes using KIPT electron driven subcritical facility.

Science.gov (United States)

Talamo, Alberto; Gohar, Yousry

2008-05-01

Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, gamma), (n, 2n), (n, p), and (gamma, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope.

Production Facility SCADA Design Report

Energy Technology Data Exchange (ETDEWEB)

Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Holloway, Michael Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baily, Scott A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wheat, Robert Mitchell Jr. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-23

The following report covers FY 14 activities to develop supervisory control and data acquisition (SCADA) system for the Northstar Moly99 production facility. The goal of this effort is to provide Northstar with a baseline system design.

Decommissioning of U.S. uranium production facilities

Energy Technology Data Exchange (ETDEWEB)

1995-02-01

From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

Decommissioning of U.S. uranium production facilities

International Nuclear Information System (INIS)

1995-02-01

From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U 3 O 8 to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington

Development of turbopump cavitation performance test facility and the test of inducer performance

International Nuclear Information System (INIS)

Sohn, Dong Kee; Kim, Chun Tak; Yoon, Min Soo; Cha, Bong Jun; Kim, Jin Han; Yang, Soo Seok

2001-01-01

A performance test facility for turbopump inducer cavitation was developed and the inducer cavitation performance tests were performed. Major components of the performance test facility are driving unit, test section, piping, water tank, and data acquisition and control system. The maximum of testing capability of this facility are as follows: flow rate - 30kg/s; pressure - 13 bar, rotational speed - 10,000rpm. This cavitation test facility is characterized by the booster pump installed at the outlet of the pump that extends the flow rate range, and by the pressure control system that makes the line pressure down to vapor pressure. The vacuum pump is used for removing the dissolved air in the water as well as the line pressure. Performance tests were carried out and preliminary data of test model inducer were obtained. The cavitation performance test and cavitation bubble flow visualization were also made. This facility is originally designed for turbopump inducer performance test and cavitation test. However it can be applied to the pump impeller performance test in the future with little modification

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.

Thermodynamic Evaluation of Floating Production Storage and Offloading Facilities with Liquefaction Processes

DEFF Research Database (Denmark)

Nguyen, Tuong-Van; Sánchez, Yamid Alberto Carranza; Junior, Silvio de Oliveira

2016-01-01

Floating, production, storage and offloading (FPSO) plants are facilities used in upstream petroleum processing.They have gained interest because they are more flexible than conventional plants and can be used for producingoil and gas in deep-water fields. In general, gas export is challenging...... because of the lack of infrastructure in remotelocations. The present work investigates the possibility of integrating liquefaction processes on such facilities, consideringfour possible petroleum compositions, which differ in their contents of carbon dioxide, light and heavy hydrocarbons.The performance...

Shielding technology for high energy radiation production facility

International Nuclear Information System (INIS)

Lee, Byung Chul; Kim, Heon Il

2004-06-01

In order to develop shielding technology for high energy radiation production facility, references and data for high energy neutron shielding are searched and collected, and calculations to obtain the characteristics of neutron shield materials are performed. For the evaluation of characteristics of neutron shield material, it is chosen not only general shield materials such as concrete, polyethylene, etc., but also KAERI developed neutron shields of High Density PolyEthylene (HDPE) mixed with boron compound (B 2 O 3 , H 2 BO 3 , Borax). Neutron attenuation coefficients for these materials are obtained for later use in shielding design. The effect of source shape and source angular distribution on the shielding characteristics for several shield materials is examined. This effect can contribute to create shielding concept in case of no detail source information. It is also evaluated the effect of the arrangement of shield materials using current shield materials. With these results, conceptual shielding design for PET cyclotron is performed. The shielding composite using HDPE and concrete is selected to meet the target dose rate outside the composite, and the dose evaluation is performed by configuring the facility room conceptually. From the result, the proper shield configuration for this PET cyclotron is proposed

Facilities for the production and processing of radioisotopes

International Nuclear Information System (INIS)

Fourie, P.J.

1980-01-01

Radioisotopes which are used in South Africa are produced in the nuclear reactor SAFARI 1 of the AEB and the CSIR cyclotron in Pretoria or are being imported from various overseas manufactures. The safe and efficient production and use of radioisotopes is possible when being handled by sufficiently trained personnel using special designed equipment and facilities. The Isotope Production Centre is situated next to the reactor and waste treatment buildings. New production facilities shielded with lead and equipped with remote handling equipment are being erected and will be commissioned early during 1980 [af

Resource-recovery facilities: Production and cost functions, and debt-financing issues

International Nuclear Information System (INIS)

Simonsen, W.S.

1991-01-01

Some of the fiscal questions relating to resource-recovery, or trash-burning, facilities are addressed. Production and cost functions for resource-recovery facilities are estimated using regression analysis. Whether or not there are returns to scale are addressed using the production and cost-function framework. Production functions are also estimated using data envelopment analysis (DEA), and results are compared to the regression results. DEA is a linear-program-based technique that can provide information about the production process. The data used to estimate the production and cost functions were collected from the Resource Recovery Yearbook. Once the decision is made to construct a resource-recovery facility, it needs to be financed. The high cost of these facilities usually prohibits financing construction out of regular operating revenues. Therefore, the issues a government faces when debt is used to finance a resource-recovery facility are analyzed. The most important public policy finding is that increasing economies of scale do not seem to be present for resource-recovery facilities

Optimum operation of a small power production facility

Energy Technology Data Exchange (ETDEWEB)

Capehart, B.L.; Mahoney, J.F.; Sivazlian, B.D.

1983-09-01

To help reduce the U.S.A.'s dependence on imported oil for electrical power generation, the 1978 National Energy Act established regulations to promote construction and operation of cogeneration and small power production facilities. Many of these facilities are presently under construction, with a great number planned. This paper examines the operation of a small power production facility with on-site generation and storage, on-site use, and connection to an electric utility grid system for the purpose of both selling excess power and buying power. It is assumed that the buying and selling price of electricity varies frequently during the day and that the relevant price and demand data may be accurately projected into the near future. With this system description, a mathematical model is formulated and solved by linear programming to obtain a series of periodic buy and sell decisions so as to maximize the profit from operating the small power production facility. Results are presented to illustrate the methodology for determining potential profits.

A cyclotron isotope production facility designed to maximize production and minimize radiation dose

International Nuclear Information System (INIS)

Dickie, W.J.; Stevenson, N.R.; Szlavik, F.F.

1993-01-01

Continuing increases in requirements from the nuclear medicine industry for cyclotron isotopes is increasing the demands being put on an aging stock of machines. In addition, with the 1990 recommendations of the ICRP publication in place, strict dose limits will be required and this will have an effect on the way these machines are being operated. Recent advances in cyclotron design combined with lessons learned from two decades of commercial production mean that new facilities can result in a substantial charge on target, low personnel dose, and minimal residual activation. An optimal facility would utilize a well engineered variable energy/high current H - cyclotron design, multiple beam extraction, and individual target caves. Materials would be selected to minimize activation and absorb neutrons. Equipment would be designed to minimize maintenance activities performed in high radiation fields. (orig.)

Performance specifications for proton medical facility

Energy Technology Data Exchange (ETDEWEB)

Chu, W.T.; Staples, J.W.; Ludewigt, B.A.; Renner, T.R.; Singh, R.P.; Nyman, M.A.; Collier, J.M.; Daftari, I.K.; Petti, P.L.; Alonso, J.R. [Lawrence Berkeley Lab., CA (United States); Kubo, H.; Verhey, L.J. [University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine; Castro, J.R. [Lawrence Berkeley Lab., CA (United States)]|[University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine

1993-03-01

Performance specifications of technical components of a modern proton radiotherapy facility are presented. The technical items specified include: the accelerator; the beam transport system including rotating gantry; the treatment beamline systems including beam scattering, beam scanning, and dosimetric instrumentation; and an integrated treatment and accelerator control system. Also included are treatment ancillary facilities such as diagnostic tools, patient positioning and alignment devices, and treatment planning systems. The facility specified will accommodate beam scanning enabling the three-dimensional conformal therapy deliver .

Appendix E - Sample Production Facility Plan

Science.gov (United States)

This sample Spill Prevention, Control and Countermeasure (SPCC) Plan in Appendix E is intended to provide examples and illustrations of how a production facility could address a variety of scenarios in its SPCC Plan.

Performance test results of helium gas circulator of mock-up test facility with full-scale reaction tube for HTTR hydrogen production system. Contract research

Energy Technology Data Exchange (ETDEWEB)

Shimizu, Akira; Kato, Michio; Hayashi, Koji [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment] [and others

2003-03-01

Hydrogen production system by steam reforming of methane will be connected to the High Temperature Engineering Test Reactor (HTTR) of the Japan Atomic Energy Research Institute (JAERI) against development of nuclear heat utilization system. To obtain design and safety database of the HTTR hydrogen production system, mock-up test facility with full-scale reaction was constructed in FY 2001 and hydrogen of 120m{sup 3}N{sub /}h was successfully produced in overall performance test. This report describes performance test results of a helium gas circulator in this facility. The circulator performance curves regarding to pressure-rise, input power and adiabatic thermal efficiency at standard revolution number were made based on the measured flow-rate, temperature and pressure data in overall performance test. The circulator performance prediction code was made based on these performance curves. The code can calculate revolution number, electric power and temperature-rise of the circulator using flow-rate, inlet temperature, inlet pressure and pressure-rise data. The verification of the code was carried out with the test data in FY 2002. Total pressure loss of the helium gas circulation loop was also evaluated. The circulator should be operated in conditions such as pressure from 2.7MPa to 4.0MPa and flow-rate from 250g/s to 400g/s and at maximum pressure-rise of 250 kPa in test operation. It was confirmed in above verification and evaluations that the circulator had performance to satisfy above conditions within operation limitation of the circulator such as maximum input-power of 150 kW and maximum revolution number of 12,000 rpm. (author)

Stabilization and shutdown of Oak Ridge National Laboratory's Radioisotopes Production Facility

International Nuclear Information System (INIS)

Eversole, R.E.

1992-01-01

The Oak Ridge National Laboratory (ORNL) has been involved in the production and distribution of a variety of radioisotopes for medical, scientific and industrial applications since the late 1940s. Production of these materials was concentrated in a number of facilities primarily built in the 1950s and 1960s. Due to the age and deteriorating condition of these facilities, it was determined in 1989 that it would not be cost effective to upgrade these facilities to bring them into compliance with contemporary environmental, safety and health standards. The US Department of Energy (DOE) instructed ORNL to halt the production of isotopes in these facilities and maintain the facilities in safe standby condition while preparing a stabilization and shutdown plan. The goal was to place the former isotope production facilities in a radiologically and industrially safe condition to allow a 5-year deferral of the initiation of environmental restoration (ER) activities. In response to DOE's instructions, ORNL identified 17 facilities for shutdown, addressed the shutdown requirements for each facility, and prepared and implemented a three-phase, 4-year plan for shutdown of the facilities. The Isotopes Facilities Shutdown Program (IFSP) office was created to execute the stabilization and shutdown plan. The program is entering its third year in which the actual shutdown of the facilities is initiated. Accomplishments to date have included consolidation of all isotopes inventory into one facility, DOE approval of the IFSP Environmental Assessment (EA), and implementation of a detailed management plan for the shutdown of the facilities

Performance assessment of the proposed Monitored Retrievable Storage Facility

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.; Winter, C.

1986-02-01

Pacific Northwest laboratory (PNL) has completed a performance evaluation of the proposed monitored retrievable storage (MRS) facility. This study was undertaken as part of the Department of Energy MRS Program at PNL. The objective of the performance evaluation was to determine whether the conceptual MRS facility would be able to process spent fuel at the specified design rate of 3600 metric tons of uranium (MTU) per year. The performance of the proposed facility was assessed using the computer model COMPACT (Computer Optimization of Processing and Cask Transport) to simulate facility operations. The COMPACT model consisted of three application models each of which addressed a different aspect of the facility's operation: MRS/waste transportation interface; cask handling capability; and disassembly/consolidation (hot cell) operations. Our conclusions, based on the assessment of design criteria for the proposed facility, are as follows: Facilities and equipment throughout the facility have capability beyond the 3600 MTU/y design requirement. This added capability provides a reserve to compensate for unexpected perturbations in shipping or handling of the spent fuel. Calculations indicate that the facility's maximum maintainable processing capability is approximately 4800 MTU/y

Hazard analysis in uranium hexafluoride production facility

International Nuclear Information System (INIS)

Marin, Maristhela Passoni de Araujo

1999-01-01

The present work provides a method for preliminary hazard analysis of nuclear fuel cycle facilities. The proposed method identify both chemical and radiological hazards, as well as the consequences associated with accident scenarios. To illustrate the application of the method, a uranium hexafluoride production facility was selected. The main hazards are identified and the potential consequences are quantified. It was found that, although the facility handles radioactive material, the main hazards as associated with releases of toxic chemical substances such as hydrogen fluoride, anhydrous ammonia and nitric acid. It was shown that a contention bung can effectively reduce the consequences of atmospheric release of toxic materials. (author)

Savannah River Site - Salt-stone Disposal Facility Performance Assessment Update

International Nuclear Information System (INIS)

Newman, J.L.

2009-01-01

The Savannah River Site (SRS) Salt-stone Facility is currently in the midst of a Performance Assessment revision to estimate the effect on human health and the environment of adding new disposal units to the current Salt-stone Disposal Facility (SDF). These disposal units continue the ability to safely process the salt component of the radioactive liquid waste stored in the underground storage tanks at SRS, and is a crucial prerequisite for completion of the overall SRS waste disposition plan. Removal and disposal of low activity salt waste from the SRS liquid waste system is required in order to empty tanks for future tank waste processing and closure operations. The Salt-stone Production Facility (SPF) solidifies a low-activity salt stream into a grout matrix, known as salt-stone, suitable for disposal at the SDF. The ability to dispose of the low-activity salt stream in the SDF required a waste determination pursuant to Section 3116 of the Ronald Reagan National Defense Authorization Act of 2005 and was approved in January 2006. One of the requirements of Section 3116 of the NDAA is to demonstrate compliance with the performance objectives set out in Subpart C of Part 61 of Title 10, Code of Federal Regulations. The PA is the document that is used to ensure ongoing compliance. (authors)

Uranium Production Safety Assessment Team. UPSAT. An international peer review service for uranium production facilities

International Nuclear Information System (INIS)

1996-01-01

The IAEA Uranium Production Safety Assessment Team (UPSAT) programme is designed to assist Member States to improve the safe operation of uranium production facilities. This programme facilitates the exchange of knowledge and experience between team members and industry personnel. An UPSAT mission is an international expert review, conducted outside of any regulatory framework. The programme is implemented in the spirit of voluntary co-operation to contribute to the enhancement of operational safety and practices where it is most effective, at the facility itself. An UPSAT review supplements other facility and regulatory efforts which may have the same objective

Calculation of displacement and helium production at the LAMPF irradiation facility

International Nuclear Information System (INIS)

Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.; Wechsler, M.S.

1984-01-01

Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at LAMPF. The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 40 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Performance assessment for a hypothetical low-level waste disposal facility

International Nuclear Information System (INIS)

Smith, C.S.; Rohe, M.J.; Ritter, P.D.

1997-01-01

Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study

Performance assessment for a hypothetical low-level waste disposal facility

Energy Technology Data Exchange (ETDEWEB)

Smith, C.S.; Rohe, M.J.; Ritter, P.D. [and others

1997-01-01

Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

Facility/equipment performance evaluation using microcomputer simulation analysis

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.

1985-08-01

A computer simulation analysis model was developed at the Pacific Northwest Laboratory to assist in assuring the adequacy of the Monitored Retrievable Storage facility design to meet the specified spent nuclear fuel throughput requirements. The microcomputer-based model was applied to the analysis of material flow, equipment capability and facility layout. The simulation analysis evaluated uncertainties concerning both facility throughput requirements and process duration times as part of the development of a comprehensive estimate of facility performance. The evaluations provided feedback into the design review task to identify areas where design modifications should be considered

Tunisian Rearing facility a first year production constraints and prospects

International Nuclear Information System (INIS)

Guerfali, M.M; Ben Salah, H.; Caceres, C.; Raies, A.

2005-01-01

The Tunisian Medfly rearing facility is located in the north of the country in a small city named Sidi Thabet, near the capital. This facility was designed for rearing the Medfly Genetic Sexing strain (GSS). The facility has been started operations in 2003 in order to release sterile males under 6000 hectares in the north east of the country in the Cap Bon Peninsula. This programme is supported by the Tunisian government, IAEA and FAO. Male only production was not stable for the four first months, due to some constraints. The production is stabilising by the time, after the tune fine off all rearing procedures and adjustment of the environmental control system. Quality control procedures (QC) were put for each procedure of the production from eggs to adult following the procedures established in the International FAO/IAEA/USDA Fruit Flies Quality control Manual

Preliminary design of a production automation framework for a pyroprocessing facility

Directory of Open Access Journals (Sweden)

Moonsoo Shin

2018-04-01

Full Text Available Pyroprocessing technology has been regarded as a promising solution for recycling spent fuel in nuclear power plants. The Korea Atomic Energy Research Institute has been studying the current status of equipment and facilities for pyroprocessing and found that existing facilities are manually operated; therefore, their applications have been limited to laboratory scale because of low productivity and safety concerns. To extend the pyroprocessing technology to a commercial scale, the facility, including all the processing equipment and the material-handling devices, should be enhanced in view of automation. In an automated pyroprocessing facility, a supervised control system is needed to handle and manage material flow and associated operations. This article provides a preliminary design of the supervising system for pyroprocessing. In particular, a manufacturing execution system intended for an automated pyroprocessing facility, named Pyroprocessing Execution System, is proposed, by which the overall production process is automated via systematic collaboration with a planning system and a control system. Moreover, a simulation-based prototype system is presented to illustrate the operability of the proposed Pyroprocessing Execution System, and a simulation study to demonstrate the interoperability of the material-handling equipment with processing equipment is also provided. Keywords: Manufacturing Execution System, Material-handling, Production Automation, Production Planning and Control, Pyroprocessing, Pyroprocessing Execution System

Development of a Medical Cyclotron Production Facility

Science.gov (United States)

Allen, Danny R.

2003-08-01

Development of a Cyclotron manufacturing facility begins with a business plan. Geographics, the size and activity of the medical community, the growth potential of the modality being served, and other business connections are all considered. This business used the customer base established by NuTech, Inc., an independent centralized nuclear pharmacy founded by Danny Allen. With two pharmacies in operation in Tyler and College Station and a customer base of 47 hospitals and clinics the existing delivery system and pharmacist staff is used for the cyclotron facility. We then added cyclotron products to contracts with these customers to guarantee a supply. We partnered with a company in the process of developing PET imaging centers. We then built an independent imaging center attached to the cyclotron facility to allow for the use of short-lived isotopes.

Development of a Medical Cyclotron Production Facility

International Nuclear Information System (INIS)

Allen, Danny R.

2003-01-01

Development of a Cyclotron manufacturing facility begins with a business plan. Geographics, the size and activity of the medical community, the growth potential of the modality being served, and other business connections are all considered. This business used the customer base established by NuTech, Inc., an independent centralized nuclear pharmacy founded by Danny Allen. With two pharmacies in operation in Tyler and College Station and a customer base of 47 hospitals and clinics the existing delivery system and pharmacist staff is used for the cyclotron facility. We then added cyclotron products to contracts with these customers to guarantee a supply. We partnered with a company in the process of developing PET imaging centers. We then built an independent imaging center attached to the cyclotron facility to allow for the use of short-lived isotopes

Control of Listeria species food safety at a poultry food production facility.

Science.gov (United States)

Fox, Edward M; Wall, Patrick G; Fanning, Séamus

2015-10-01

Surveillance and control of food-borne human pathogens, such as Listeria monocytogenes, is a critical aspect of modern food safety programs at food production facilities. This study evaluated contamination patterns of Listeria species at a poultry food production facility, and evaluated the efficacy of procedures to control the contamination and transfer of the bacteria throughout the plant. The presence of Listeria species was studied along the production chain, including raw ingredients, food-contact, non-food-contact surfaces, and finished product. All isolates were sub-typed by pulsed-field gel electrophoresis (PFGE) to identify possible entry points for Listeria species into the production chain, as well as identifying possible transfer routes through the facility. The efficacy of selected in-house sanitizers against a sub-set of the isolates was evaluated. Of the 77 different PFGE-types identified, 10 were found among two or more of the five categories/areas (ingredients, food preparation, cooking and packing, bulk packing, and product), indicating potential transfer routes at the facility. One of the six sanitizers used was identified as unsuitable for control of Listeria species. Combining PFGE data, together with information on isolate location and timeframe, facilitated identification of a persistent Listeria species contamination that had colonized the facility, along with others that were transient. Copyright © 2015 Elsevier Ltd. All rights reserved.

Image processing system performance prediction and product quality evaluation

Science.gov (United States)

Stein, E. K.; Hammill, H. B. (Principal Investigator)

1976-01-01

The author has identified the following significant results. A new technique for image processing system performance prediction and product quality evaluation was developed. It was entirely objective, quantitative, and general, and should prove useful in system design and quality control. The technique and its application to determination of quality control procedures for the Earth Resources Technology Satellite NASA Data Processing Facility are described.

Evaluating building performance in healthcare facilities: an organizational perspective.

Science.gov (United States)

Steinke, Claudia; Webster, Lynn; Fontaine, Marie

2010-01-01

Using the environment as a strategic tool is one of the most cost-effective and enduring approaches for improving public health; however, it is one that requires multiple perspectives. The purpose of this article is to highlight an innovative methodology that has been developed for conducting comprehensive performance evaluations in public sector health facilities in Canada. The building performance evaluation methodology described in this paper is a government initiative. The project team developed a comprehensive building evaluation process for all new capital health projects that would respond to the aforementioned need for stakeholders to be more accountable and to better integrate the larger organizational strategy of facilities. The Balanced Scorecard, which is a multiparadigmatic, performance-based business framework, serves as the underlying theoretical framework for this initiative. It was applied in the development of the conceptual model entitled the Building Performance Evaluation Scorecard, which provides the following benefits: (1) It illustrates a process to link facilities more effectively to the overall mission and goals of an organization; (2) It is both a measurement and a management system that has the ability to link regional facilities to measures of success and larger business goals; (3) It provides a standardized methodology that ensures consistency in assessing building performance; and (4) It is more comprehensive than traditional building evaluations. The methodology presented in this paper is both a measurement and management system that integrates the principles of evidence-based design with the practices of pre- and post-occupancy evaluation. It promotes accountability and continues throughout the life cycle of a project. The advantage of applying this framework is that it engages health organizations in clarifying a vision and strategy for their facilities and helps translate those strategies into action and measurable performance

Required performance to the concrete structure of the accelerator facilities

International Nuclear Information System (INIS)

Irie, Masaaki; Yoshioka, Masakazu; Miyahara, Masanobu

2006-01-01

As for the accelerator facility, there is many a thing which is constructed as underground concrete structure from viewpoint such as cover of radiation and stability of the structure. Required performance to the concrete structure of the accelerator facility is the same as the general social infrastructure, but it has been possessed the feature where target performance differs largely. As for the body sentence, expressing the difference of the performance which is required from the concrete structure of the social infrastructure and the accelerator facility, construction management of the concrete structure which it plans from order of the accelerator engineering works facility, reaches to the design, supervision and operation it is something which expresses the method of thinking. In addition, in the future of material structural analysis of the concrete which uses the neutron accelerator concerning view it showed. (author)

Production Facility Prototype Blower 1000 Hour Test Results II

Energy Technology Data Exchange (ETDEWEB)

Wass, Alexander Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dalmas, Dale Allen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Romero, Frank Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2018-01-08

Long duration tests of the Aerzen GM 12.4 roots style blower in a closed loop configuration provides valuable data and lessons learned for long-term operation at the Mo-99 production facility. The blower was operated in a closed loop configuration with the flow conditions anticipated in plant operation with a Mo-100 target inline. The additional thermal energy generated from beam heating of the Mo-100 disks were not included in these tests. Five 1000 hour tests have been completed since the first test was performed in January of 2016. All five 1000 hour tests have proven successful in exposing preventable issues related to oil and helium leaks. All blower tests to this date have resulted in stable blower performance and consistency. A summary of the results for each test, including a review of the first and second tests, are included in this report.

Performance confirmation operation of water environment control facility

International Nuclear Information System (INIS)

Magome, Hirokatsu; Okada, Yuji; Tomita, Kenji; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Hanawa, Hiroshi; Kanno, Masaru; Sakuta, Yoshiyuki

2015-09-01

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. The material irradiation test facility is used for IASCC study, and consists of mainly three equipments. This report described performance operating test of the water environmental control facilities for IASCC study carried out 2013 fiscal year. (author)

Engineering and technology in the deconstruction of nuclear materials production facilities

International Nuclear Information System (INIS)

Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

1996-01-01

Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

The Copernicus S5P Mission Performance Centre / Validation Data Analysis Facility for TROPOMI operational atmospheric data products

Science.gov (United States)

Compernolle, Steven; Lambert, Jean-Christopher; Langerock, Bavo; Granville, José; Hubert, Daan; Keppens, Arno; Rasson, Olivier; De Mazière, Martine; Fjæraa, Ann Mari; Niemeijer, Sander

2017-04-01

Sentinel-5 Precursor (S5P), to be launched in 2017 as the first atmospheric composition satellite of the Copernicus programme, carries as payload the TROPOspheric Monitoring Instrument (TROPOMI) developed by The Netherlands in close cooperation with ESA. Designed to measure Earth radiance and solar irradiance in the ultraviolet, visible and near infrared, TROPOMI will provide Copernicus with observational data on atmospheric composition at unprecedented geographical resolution. The S5P Mission Performance Center (MPC) provides an operational service-based solution for various QA/QC tasks, including the validation of S5P Level-2 data products and the support to algorithm evolution. Those two tasks are to be accomplished by the MPC Validation Data Analysis Facility (VDAF), one MPC component developed and operated at BIRA-IASB with support from S[&]T and NILU. The routine validation to be ensured by VDAF is complemented by a list of validation AO projects carried out by ESA's S5P Validation Team (S5PVT), with whom interaction is essential. Here we will introduce the general architecture of VDAF, its relation to the other MPC components, the generic and specific validation strategies applied for each of the official TROPOMI data products, and the expected output of the system. The S5P data products to be validated by VDAF are diverse: O3 (vertical profile, total column, tropospheric column), NO2 (total and tropospheric column), HCHO (tropospheric column), SO2 (column), CO (column), CH4 (column), aerosol layer height and clouds (fractional cover, cloud-top pressure and optical thickness). Starting from a generic validation protocol meeting community-agreed standards, a set of specific validation settings is associated with each data product, as well as the appropriate set of Fiducial Reference Measurements (FRM) to which it will be compared. VDAF collects FRMs from ESA's Validation Data Centre (EVDC) and from other sources (e.g., WMO's GAW, NDACC and TCCON). Data

Plutonium production story at the Hanford site: processes and facilities history

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S., Westinghouse Hanford

1996-06-20

This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

Medical Isotope Production With The Accelerator Production of Tritium (APT) Facility

International Nuclear Information System (INIS)

Buckner, M.; Cappiello, M.; Pitcher, E.; O'Brien, H.

1998-01-01

In order to meet US tritium needs to maintain the nuclear weapons deterrent, the Department of Energy (DOE) is pursuing a dual track program to provide a new tritium source. A record of decision is planned for late in 1998 to select either the Accelerator Production of Tritium (APT) or the Commercial Light Water Reactor (CLWR) as the technology for new tritium production in the next century. To support this decision, an APT Project was undertaken to develop an accelerator design capable of producing 3 kg of tritium per year by 2007 (START I requirements). The Los Alamos National Laboratory (LANL) was selected to lead this effort with Burns and Roe Enterprises, Inc. (BREI) / General Atomics (GA) as the prime contractor for design, construction, and commissioning of the facility. If chosen in the downselect, the facility will be built at the Savannah River Site (SRS) and operated by the SRS Maintenance and Operations (M ampersand O) contractor, the Westinghouse Savannah River Company (WSRC), with long-term technology support from LANL. These three organizations (LANL, BREI/GA, and WSRC) are working together under the direction of the APT National Project Office which reports directly to the DOE Office of Accelerator Production which has program authority and responsibility for the APT Project

Issues resulting from separation of production and facilities interests

International Nuclear Information System (INIS)

Park, J. J.

1996-01-01

Traditionally, Canadian oil and gas producers have had full control over the exploration, production, marketing, processing and transportation aspects of their business. The disadvantages and recent changes to this traditional structure were discussed. It was shown how the deregulation of gas markets and prices in the 1980s led to some major changes in the industry. The separation of production interests from the processing and gathering facilities required a new focus by both producers and owners of the facilities. The concerns of both sides (i.e. producers and processors) were outlined. The importance of the Petroleum Joint Venture Agreement (PJVA) in defining obligations in plant expansion and development, and the jurisdictional issues over gathering and processing were described

Improvement works report on mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system (Contract research)

International Nuclear Information System (INIS)

Sakaki, Akihiro; Kato, Michio; Hayashi, Koji; Fujisaki, Katsuo; Aita, Hideki; Ohashi, Hirofumi; Takada, Shoji; Shimizu, Akira; Morisaki, Norihiro; Maeda, Yukimasa; Sato, Hiroyuki; Hanawa, Hiromi; Yonekawa, Hideo; Inagaki, Yoshiyuki

2005-04-01

In order to establish the system integration technology to connect a hydrogen production system to a high temperature gas cooled reactor; the mock-up test facility with a full-scale reaction tube for the steam reforming HTTR hydrogen production system was constructed in fiscal year 2001 and its functional test operation was performed in the year. Seven experimental test operations were performed from fiscal year 2001 to 2004. On a period of each test operation, there happened some troubles. For each trouble, the cause was investigated and the countermeasures and the improvement works were performed to succeed the experiments. The tests were successfully achieved according to plan. This report describes the improvement works on the test facility performed from fiscal year 2001 to 2004. (author)

Asset management: integrated software optimizes production performance

Energy Technology Data Exchange (ETDEWEB)

Polczer, S.

1998-06-01

Two new multi-dimensional databases, which expand the `row and column` concept of spreadsheets into multiple categories of data called dimensions, are described. These integrated software packages provide the foundation for industry players such as Poco Petroleum Ltd and Numac Energy Inc to gain a competitive advantage, by overhauling their respective data collection and retrieval systems to allow for timely cost analysis and financial reporting. Energy Warehouse, an on-line analytical processing product marketed by SysGold Ltd, is one of the software products described. It gathers various sources of information, allows advanced searches and generates reports previously unavailable in other conventional financial accounting systems. The second product discussed - the Canadian Upstream Energy System (CUES) - is an on-line analytical processing system developed by Oracle Corporation and Calgary-based Applied Terravision Systems (ATS) Inc. CUES combines Oracle`s universal data server and software development tools with ATS`s upstream financial, land, geotechnical and production applications. The software also allows for optimization of facilities, analysis of production efficiencies and comparison of performance against industry standards.

Facilities Performance Indicators Report, 2006-07

Science.gov (United States)

Glazner, Steve, Ed.

2008-01-01

The "Facilities Performance Indicators Survey" ("FPI") supersedes and builds upon the two major surveys APPA conducted in the past: the Comparative Costs and Staffing (CCAS) survey and the Strategic Assessment Model (SAM). The "FPI" covers all the materials collected in CCAS and SAM, along with some select new data points and improved survey…

Light ion production for a future radiobiological facility at CERN: preliminary studies.

Science.gov (United States)

Stafford-Haworth, Joshua; Bellodi, Giulia; Küchler, Detlef; Lombardi, Alessandra; Röhrich, Jörg; Scrivens, Richard

2014-02-01

Recent medical applications of ions such as carbon and helium have proved extremely effective for the treatment of human patients. However, before now a comprehensive study of the effects of different light ions on organic targets has not been completed. There is a strong desire for a dedicated facility which can produce ions in the range of protons to neon in order to perform this study. This paper will present the proposal and preliminary investigations into the production of light ions, and the development of a radiobiological research facility at CERN. The aims of this project will be presented along with the modifications required to the existing linear accelerator (Linac3), and the foreseen facility, including the requirements for an ion source in terms of some of the specification parameters and the flexibility of operation for different ion types. Preliminary results from beam transport simulations will be presented, in addition to some planned tests required to produce some of the required light ions (lithium, boron) to be conducted in collaboration with the Helmholtz-Zentrum für Materialien und Energie, Berlin.

RAMI modeling of plant systems for proposed tritium production and extraction facilities

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

The control of life-cycle cost is a primary concern during the development, construction, operation, and decommissioning of DOE systems and facilities. An effective tool that can be used to control these costs, beginning with the design stage, is called a reliability, availability, maintainability, and inspectability analysis or, simply, RAMI for short. In 1997, RAMI technology was introduced to the Savannah River Site with applications at the conceptual design stage beginning with the Accelerator Production of Tritium (APT) Project and later extended to the Commercial Light Water Reactor (CLWR) Tritium Extraction Facility (TEF) Project. More recently it has been applied to the as-build Water Treatment Facilities designed for ground water environmental restoration. This new technology and database was applied to the assessment of balance-of-plant systems for the APT Conceptual Design Report. Initial results from the Heat Removal System Assessment revealed that the system conceptual design would cause the APT to fall short of its annual production goal. Using RAM technology to immediately assess this situation, it was demonstrated that the product loss could be gained back by upgrading the system's chiller unit capacity at a cost of less than $1.3 million. The reclaimed production is worth approximately $100 million. The RAM technology has now been extended to assess the conceptual design for the CLWR-TEF Project. More specifically, this technology and database is being used to translate high level availability goals into lower level system design requirements that will ensure the TEF meets its production goal. Results, from the limited number of system assessments performed to date, have already been used to modify the conceptual design for a remote handling system, improving its availability to the point that a redundant system, with its associated costs of installation and operation may no longer be required. RAMI results were also used to justify the elimination

Study of surface potential contamination in radioisotope and radiopharmaceutical production facilities and alternative solutions

International Nuclear Information System (INIS)

Suhaedi Muhammad; Rimin Sumantri; Farida Tusafariah; Djarwanti Rahayu Pipin Soedjarwo

2013-01-01

Radioisotope and radiopharmaceutical production facilities that exist in their operations around the world in the form of radiological impacts of radiation exposure, contamination of surface and air contamination. Given the number of existing open source in radioisotope and radiopharmaceutical production facility, then the possibility of surface contamination in the work area is quite high. For that to protect the safety and health of both workers, the public and the environment, then the licensee must conduct an inventory of some of the potential that could result in contamination of surfaces in radioisotope and radiopharmaceutical production facilities. Several potential to cause surface contamination in radioisotope and radiopharmaceutical production facilities consist of loss of resources, the VAC system disorders, impaired production facilities, limited resources and lack of work discipline and radioactive waste handling activities. From the study of some potential, there are several alternative solutions that can be implemented by the licensee to address the contamination of the surface so as not to cause adverse radiological impacts for both radiation workers, the public or the environment. (author)

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.

An Integrated Assessment of Location-Dependent Scaling for Microalgae Biofuel Production Facilities

Energy Technology Data Exchange (ETDEWEB)

Coleman, Andre M.; Abodeely, Jared; Skaggs, Richard; Moeglein, William AM; Newby, Deborah T.; Venteris, Erik R.; Wigmosta, Mark S.

2014-06-19

Successful development of a large-scale microalgae-based biofuels industry requires comprehensive analysis and understanding of the feedstock supply chain—from facility siting/design through processing/upgrading of the feedstock to a fuel product. The evolution from pilot-scale production facilities to energy-scale operations presents many multi-disciplinary challenges, including a sustainable supply of water and nutrients, operational and infrastructure logistics, and economic competitiveness with petroleum-based fuels. These challenges are addressed in part by applying the Integrated Assessment Framework (IAF)—an integrated multi-scale modeling, analysis, and data management suite—to address key issues in developing and operating an open-pond facility by analyzing how variability and uncertainty in space and time affect algal feedstock production rates, and determining the site-specific “optimum” facility scale to minimize capital and operational expenses. This approach explicitly and systematically assesses the interdependence of biofuel production potential, associated resource requirements, and production system design trade-offs. The IAF was applied to a set of sites previously identified as having the potential to cumulatively produce 5 billion-gallons/year in the southeastern U.S. and results indicate costs can be reduced by selecting the most effective processing technology pathway and scaling downstream processing capabilities to fit site-specific growing conditions, available resources, and algal strains.

Demonstration of persistent contamination of a cooked egg product production facility with Salmonella enterica serovar Tennessee and characterization of the persistent strain

DEFF Research Database (Denmark)

Jakociune, D.; Bisgaard, M.; Pedersen, Karl

2014-01-01

Aims: The aim of this study was to investigate whether continuous contamination of light pasteurized egg products with Salmonella enterica serovar Tennessee (S. Tennessee) at a large European producer of industrial egg products was caused by persistent contamination of the production facility......, members of the persistent clone were weak producers of H2S in laboratory medium. S. Tennessee isolated from the case was able to grow better in pasteurized egg product compared with other serovars investigated. Conclusions: It was concluded that the contamination was caused by a persistent strain...... in the production facility and that this strain apparently had adapted to grow in the relevant egg product. Significance and Impact of the Study: S. Tennessee has previously been associated with persistence in hatching facilities. This is the first report of persistent contamination of an egg production facility...

Experimental Facilities for Performance Evaluation of Fast Reactor Components

International Nuclear Information System (INIS)

Chandramouli, S.; Kumar, V.A. Suresh; Shanmugavel, M.; Vijayakumar, G.; Vinod, V.; Noushad, I.B.; Babu, B.; Kumar, G. Padma; Nashine, B.K.; Rajan, K.K.

2013-01-01

Brief details about various experimental facilities catering to the testing and performance evaluation requirements of fast reactor components have been brought out. These facilities have been found to be immensely useful to continue research and development activities in the areas of component development and testing, sodium technology, thermal hydraulics and sodium instrumentation for the SFR’s. In addition new facilities which have been planned will be of great importance for the developmental activities related to future SFR’s

Performance assessment for the class L-II disposal facility

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility

International Nuclear Information System (INIS)

Talamo, A.; Gohar, Y.

2007-01-01

Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,γ), (n,2n), (n,p), and (γ,n). In the second part, the parent

Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility.

Energy Technology Data Exchange (ETDEWEB)

Talamo, A.; Gohar, Y.; Nuclear Engineering Division

2007-05-15

Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,{gamma}), (n,2n), (n,p), and ({gamma},n). In the second part

Performing a nuclear facility EMI audit

International Nuclear Information System (INIS)

White, D.R.J.

1993-01-01

This paper addresses several questions which may arise when performing a nuclear facility EMI audit. Among the issues addressed are how a nuclear electrical power plant can ensure that it has taken adequate EMC measures to protect it from hostile electromagnetic ambient environments, means by which these measures can be implemented with sufficient integrity and reliability, and how often an inspection or audit should be performed to assess the EMC measures. Means of assessing EMI hardening and effective control of aging effects are also discussed. 2 figs

Environmental performances of different configurations of a material recovery facility in a life cycle perspective.

Science.gov (United States)

Ardolino, Filomena; Berto, Chiara; Arena, Umberto

2017-10-01

The study evaluated the environmental performances of an integrated material recovery facility (MRF) able to treat 32kt/y of unsorted mixed waste, made of residuals from household source separation and separate collection. The facility includes a mechanical sorting platform for the production of a solid recovered fuel (SRF) utilized in an external waste-to-energy plant, bio-cells for tunnel composting of organic fraction, and a sanitary landfill for the safe disposal of ultimate waste. All the MRF sub-units have been analysed in depth in order to acquire reliable data for a life cycle assessment study, focused on the environmental performances of different configurations of the facility. The study investigated a "past" configuration, including just mechanical sorting, landfilling and biogas combustion in a gas engine, and the "present" one, which includes also a composting unit. Two possible "future" configurations, having a gasifier inside the MRF battery limits, have been also analysed, assessing the performances of two fluidized bed reactors of different size, able to gasify only the residues generated by the sorting platform or the whole amount of produced SRF, respectively. The analysis evaluated the contributions of each unit in the different configurations and allowed a reliable assessment of the technological evolution of the facility. The results quantified the positive effect of the inclusion of an aerobic treatment of the waste organic fraction. The SRF gasification in situ appears to improve the MRF environmental performances in all the impact categories, with the exclusion of that of global warming. Copyright © 2017 Elsevier Ltd. All rights reserved.

Survey of computer codes applicable to waste facility performance evaluations

International Nuclear Information System (INIS)

Alsharif, M.; Pung, D.L.; Rivera, A.L.; Dole, L.R.

1988-01-01

This study is an effort to review existing information that is useful to develop an integrated model for predicting the performance of a radioactive waste facility. A summary description of 162 computer codes is given. The identified computer programs address the performance of waste packages, waste transport and equilibrium geochemistry, hydrological processes in unsaturated and saturated zones, and general waste facility performance assessment. Some programs also deal with thermal analysis, structural analysis, and special purposes. A number of these computer programs are being used by the US Department of Energy, the US Nuclear Regulatory Commission, and their contractors to analyze various aspects of waste package performance. Fifty-five of these codes were identified as being potentially useful on the analysis of low-level radioactive waste facilities located above the water table. The code summaries include authors, identification data, model types, and pertinent references. 14 refs., 5 tabs

Development of post-irradiation test facility for domestic production of 99Mo

International Nuclear Information System (INIS)

Taguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo

2013-01-01

JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of 99 Mo, we have been conducting research and development that can contribute to supply about 25% for 99 Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of 99 Mo: Maintenance of test equipment in the facility in JMTR hot laboratory in preparation for research and development for the production of 99 Mo in JMTR and using MoO 3 pellet irradiated at Kyoto University Research Reactor Institute (KUR). (author)

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

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

Production of U3O8 by uranyl formate precipitation and calcination in a full-scale pilot facility

International Nuclear Information System (INIS)

Kendrick, L.S.; Wilson, W.A.; Mosley, W.C.

1984-08-01

The uranyl formate process for the production of U 3 O 8 with a controlled particle size has been extensively studied on a laboratory scale. Based on this study, a pilot-scale facility (the Uranyl Formate Facility) was built to investigate the key steps of the process on a larger scale. These steps were the precipitation of a uranyl formate monohydrate salt and the calcination of this salt to U 3 O 8 . Tests of the facility and process were conducted at conditions recommended by the laboratory-scale studies for a full-scale production facility. These tests demonstrated that U 3 O 8 of the required particle size for the PM process can be produced on a plant scale by the calcination of uranyl formate crystals. The performance of the U 3 O 8 produced by the uranyl formate process in fuel tube fabrication was also investigated. Small-scale extrusion tests of U 3 O 8 -Al cores which used the U 3 O 8 produced in the Uranyl Formate Facility were conducted. These tests demonstrated that the U 3 O 8 quality was satisfactory for the PM process

A study on building performance analysis for energy retrofit of existing industrial facilities

International Nuclear Information System (INIS)

Gourlis, Georgios; Kovacic, Iva

2016-01-01

Highlights: • Thermal simulation of a historical industrial hall with limited data availability. • Considering waste heat from machinery after measuring production fluctuations. • Test of retrofit alternatives for roof and skylights. • Results indicate a significant reduction in heating energy demand up to 52%. • After retrofit naturally ventilated hall can achieve thermal comfort in summer. - Abstract: Due to the strengthening of regulations and codes on building energy performance, as well as with the application of national legislations regarding energy management and efficiency, existing industrial facilities are using thermal refurbishment and renovation as impetus for increasing their overall energy efficiency. This paper analyzes a building envelope refurbishment for a case study of an existing historical industrial facility. Critical parameters affecting energy performance of industrial buildings were identified by reviewing relevant literate. Two retrofit scenarios were developed and dynamic thermal simulation using EnergyPlus was implemented to evaluate the potential for improvement. Thereby the impact of interior loads was considered, determined by measurements conducted on factory machines, occupancy and lighting operation patterns. However, information regarding constructions of the existing facility and installed technical building services is limited. There is also uncertainty in the quantification of natural ventilation air change rate for such buildings. To overcome these limitations a study of various material databases was carried out, in order to assess data for building envelope composition. Input values for missing data were provided based on literature, allowing a fair comparison between refurbishment alternatives. Simulation results showed that the heating demand of the facility could be reduced up to 52%, indicating a significant potential for energy savings. Beyond that, thermal performance against summer overheating also

E AREA LOW LEVEL WASTE FACILITY DOE 435.1 PERFORMANCE ASSESSMENT

Energy Technology Data Exchange (ETDEWEB)

Wilhite, E

2008-03-31

This Performance Assessment for the Savannah River Site E-Area Low-Level Waste Facility was prepared to meet requirements of Chapter IV of the Department of Energy Order 435.1-1. The Order specifies that a Performance Assessment should provide reasonable assurance that a low-level waste disposal facility will comply with the performance objectives of the Order. The Order also requires assessments of impacts to water resources and to hypothetical inadvertent intruders for purposes of establishing limits on radionuclides that may be disposed near-surface. According to the Order, calculations of potential doses and releases from the facility should address a 1,000-year period after facility closure. The point of compliance for the performance measures relevant to the all pathways and air pathway performance objective, as well as to the impact on water resources assessment requirement, must correspond to the point of highest projected dose or concentration beyond a 100-m buffer zone surrounding the disposed waste following the assumed end of active institutional controls 100 years after facility closure. During the operational and institutional control periods, the point of compliance for the all pathways and air pathway performance measures is the SRS boundary. However, for the water resources impact assessment, the point of compliance remains the point of highest projected dose or concentration beyond a 100-m buffer zone surrounding the disposed waste during the operational and institutional control periods. For performance measures relevant to radon and inadvertent intruders, the points of compliance are the disposal facility surface for all time periods and the disposal facility after the assumed loss of active institutional controls 100 years after facility closure, respectively. The E-Area Low-Level Waste Facility is located in the central region of the SRS known as the General Separations Area. It is an elbow-shaped, cleared area, which curves to the northwest

Heating facility for blanket and performance test

Energy Technology Data Exchange (ETDEWEB)

Furuya, Kazuyuki; Kuroda, Toshimasa; Enoeda, Mikio; Sato, Satoshi; Hatano, Toshihisa; Takatsu, Hideyuki; Ohara, Yoshihiro [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment; Hara, Shigemitsu

1999-03-01

A design and a fabrication of heating test facility for a mock-up of the blanket module to be installed in International Thermonuclear Experimental Reactor (ITER) have been conducted to evaluate/demonstrate its heat removal performance and structural soundness under cyclic heat loads. To simulate surface heat flux to the blanket module, infrared heating method is adopted so as to heat large surface area uniformly. The infrared heater is used in vacuum environment (10{sup -4} Torr{approx}), and the lamps are cooled by air flowing through an annulus between the lamp and a cover tube made of quartz glass. Elastomer O rings (available to be used up to {approx}300degC) and used for vacuum seal at outer surface of the cover tube. To prevent excessive heating of the O ring, the end part of the cover tube is specially designed including the tube shape, flow path of air and gold coating on the surface of the cover tube to protect the O ring against thermal radiation from glowing tungsten filament. To examine the performance of the facility, steady state and cyclic operation of the infrared heater were conducted using a small-scaled shielding blanket mock-up as a test specimen. The important results are as follows: (1) Heat flux at the surface of the small-scaled mock-up measured by a calorimeter was {approx}0.2 MW/m{sup 2}. (2) A comparison of thermal analysis results and measured temperature responses showed that the small-scaled mock-up had good heat removal performance. (3) Steady state operation and cyclic operation with step response between the rated and zero powers of the infrared heater were successfully performed, and it was confirmed that this heating facility was well-prepared and available for the thermal cyclic test of a blanket module. (author)

Analysis of federal and state policies and environmental issues for bioethanol production facilities.

Science.gov (United States)

McGee, Chandra; Chan Hilton, Amy B

2011-03-01

The purpose of this work was to investigate incentives and barriers to fuel ethanol production from biomass in the U.S. during the past decade (2000-2010). In particular, we examine the results of policies and economic conditions during this period by way of cellulosic ethanol activity in four selected states with the potential to produce different types of feedstocks (i.e., sugar, starch, and cellulosic crops) for ethanol production (Florida, California, Hawaii, and Iowa). Two of the four states, Iowa and California, currently have commercial ethanol production facilities in operation using corn feedstocks. While several companies have proposed commercial scale facilities in Florida and Hawaii, none are operating to date. Federal and state policies and incentives, potential for feedstock production and conversion to ethanol and associated potential environmental impacts, and environmental regulatory conditions among the states were investigated. Additionally, an analysis of proposed and operational ethanol production facilities provided evidence that a combination of these policies and incentives along with the ability to address environmental issues and regulatory environment and positive economic conditions all impact ethanol production. The 2000-2010 decade saw the rise of the promise of cellulosic ethanol. Federal and state policies were enacted to increase ethanol production. Since the initial push for development, expansion of cellulosic ethanol production has not happened as quickly as predicted. Government and private funding supported the development of ethanol production facilities, which peaked and then declined by the end of the decade. Although there are technical issues that remain to be solved to more efficiently convert cellulosic material to ethanol while reducing environmental impacts, the largest barriers to increasing ethanol production appear to be related to government policies, economics, and logistical issues. The numerous federal and state

Performance indicator program for U.S. Department of Energy reactors and facilities

International Nuclear Information System (INIS)

Sastry, R.; Fielding, J.R.; Snyder, B.J.; Usher, J.; Boccio, J.

1990-01-01

The U.S. Department of Energy (DOE) is developing a Performance Indicator (PI) Program for all facilities. The objective is to periodically collect, statistically analyze and present performance-related information in a concise and consistent format for DOE and safety of facility operations. A set of 14 DOE-Hq. defined PI's has been established after review of programs used by other organizations. Since July 1989, these PI's have been used in a trial program for eight diverse DOE facilities. Electronic reporting is directly to the DOE Safety Performance Measurement System computer. This paper reports on results demonstrated for the feasibility and usefulness of a DOE-wide PI Program and steps being taken to include all DOE facilities

Hyperpolarized 3-helium MR imaging of the lungs: testing the concept of a central production facility

International Nuclear Information System (INIS)

Beek, E.J.R. van; Schmiedeskamp, J.; Filbir, F.; Heil, W.; Wolf, M.; Otten, E.; Wild, J.M.; Paley, M.N.J.; Fichele, S.; Woodhouse, N.; Swift, A.; Knitz, F.; Mills, G.H.

2003-01-01

The aim of this study was to test the feasibility of a central production facility with distribution network for implementation of hyperpolarized 3-helium MRI. The 3-helium was hyperpolarized to 50-65% using a large-scale production facility based at a university in Germany. Using a specially designed transport box, containing a permanent low-field shielded magnet and dedicated iron-free glass cells, the hyperpolarized 3-helium gas was transported via airfreight to a university in the UK. At this location, the gas was used to perform in vivo MR experiments in normal volunteers and patients with chronic obstructive lung diseases. Following initial tests, the transport (road-air-road cargo) was successfully arranged on six occasions (approximately once per month). The duration of transport to imaging averaged 18 h (range 16-20 h), which was due mainly to organizational issues such as working times and flight connections. During the course of the project, polarization at imaging increased from 20% to more than 30%. A total of 4 healthy volunteers and 8 patients with chronic obstructive pulmonary disease were imaged. The feasibility of a central production facility for hyperpolarized 3-helium was demonstrated. This should enable a wider distribution of gas for this novel technology without the need for local start-up costs. (orig.)

ALARA implementation in 131I therapeutic capsule production facility

International Nuclear Information System (INIS)

Kumawat, Lalit; Swaminathan, N.; Sudheer, T.S.; Sachdev, S.S.; Arora, S.S.; Vairalkar, K.G.

2005-01-01

Sodium iodide 131 I solution had been invariably administered to patients for both diagnosis and therapy of thyrotoxicosis. The undue exposure to non-target organs has been over come by introducing NaI ( 131 I) in a gelatin capsule. BRIT has set up experimental facility for the preparation and the production volume has augmented into four fold due to increase in demand and the same facility is being used to cater the need. However, the adequately shielded facility (fume hood) used for (manual) dispensing activity in capsules, capsules and product vial capping, transfer of the vials into lead pots and activity measurement of each vial has resulted in significant increase in the personnel exposure. The sources had been identified and efforts were made to reduce the exposure in these operations. An annular shield was introduced around the dispenser, resulted in the reduction of radiation field at wrist level by a factor of three. Introduction of shielded automated dispenser and usage of longer tools for transfer and capping of vials has effected in two times reduction of collective wrist dose. Currently, the relocated capping station two meters away from the source certainly will bring down further exposure. (author)

Evaluation of syngas production unit cost of bio-gasification facility using regression analysis techniques

Energy Technology Data Exchange (ETDEWEB)

Deng, Yangyang; Parajuli, Prem B.

2011-08-10

Evaluation of economic feasibility of a bio-gasification facility needs understanding of its unit cost under different production capacities. The objective of this study was to evaluate the unit cost of syngas production at capacities from 60 through 1800Nm 3/h using an economic model with three regression analysis techniques (simple regression, reciprocal regression, and log-log regression). The preliminary result of this study showed that reciprocal regression analysis technique had the best fit curve between per unit cost and production capacity, with sum of error squares (SES) lower than 0.001 and coefficient of determination of (R 2) 0.996. The regression analysis techniques determined the minimum unit cost of syngas production for micro-scale bio-gasification facilities of $0.052/Nm 3, under the capacity of 2,880 Nm 3/h. The results of this study suggest that to reduce cost, facilities should run at a high production capacity. In addition, the contribution of this technique could be the new categorical criterion to evaluate micro-scale bio-gasification facility from the perspective of economic analysis.

Radioisotope handling facilities and automation of radioisotope production

International Nuclear Information System (INIS)

2004-12-01

If a survey is made of the advances in radioisotope handling facilities, as well as the technical conditions and equipment used for radioisotope production, it can be observed that no fundamental changes in the design principles and technical conditions of conventional manufacture have happened over the last several years. Recent developments are mainly based on previous experience aimed at providing safer and more reliable operations, more sophisticated maintenance technology and radioactive waste disposal. In addition to the above observation, significant improvements have been made in the production conditions of radioisotopes intended for medical use, by establishing aseptic conditions with clean areas and isolators, as well as by introducing quality assurance as governing principle in the production of pharmaceutical grade radioactive products. Requirements of the good manufacturing practice (GMP) are increasingly complied with by improving the technical and organizational conditions, as well as data registration and documentation. Technical conditions required for the aseptic production of pharmaceuticals and those required for radioactive materials conflicting in some aspects are because of the contrasting contamination mechanisms and due consideration of the radiation safety. These can be resolved by combining protection methods developed for pharmaceuticals and radioactive materials, with the necessary compromise in some cases. Automation serves to decrease the radiation dose to the operator and environment as well as to ensure more reliable and precise radiochemical processing. Automation has mainly been introduced in the production of sealed sources and PET radiopharmaceuticals. PC controlled technologies ensure high reliability for the production and product quality, whilst providing automatic data acquisition and registration required by quality assurance. PC control is also useful in the operation of measuring instruments and in devices used for

Production facility for ATLAS new small wheel drift panels at JGU Mainz

Energy Technology Data Exchange (ETDEWEB)

Duedder, Andreas; Lin, Tai-Hua; Schott, Matthias [Johannes Gutenberg-Universitaet Mainz (Germany)

2016-07-01

The ATLAS Phase-I Upgrade in 2018 includes the replacement of the ATLAS Muon Small Wheel by the so-called New Small Wheel (NSW). Large-scale Micromegas detectors will serve as tracking detectors in the NSW. Parts of these detectors will be constructed at the Johannes Gutenberg University Mainz (JGU). In order to fulfill the requirements of the envisioned detector performance, a high precision detector construction is crucial. Especially the surface planarity of the produced detector panels has to better than 30 μm over an area of 2 m{sup 2}. Methods for the quality control of the raw material and the constructed parts have been developed and implemented. This talk gives an overview of the production facility at JGU Mainz which is used during the mass production of NSW components in coming years.

Iodine-129 Dose in LLW Disposal Facility Performance Assessments

International Nuclear Information System (INIS)

Wilhite, E.L.

1999-01-01

Iodine-129 has the lowest Performance Assessment derived inventory limit in SRS disposal facilities. Because iodine is concentrated in the body to one organ, the thyroid, it has been thought that dilution with stable iodine would reduce the dose effects of 129I.Examination of the dose model used to establish the Dose conversion factor for 129I shows that, at the levels considered in performance assessments of low-level waste disposal facilities, the calculated 129I dose already accounts for ingestion of stable iodine. At higher than normal iodine ingestion rates, the uptake of iodine by the thyroid itself decrease, which effectively cancels out the isotopic dilution effect

A preliminary analysis of floating production storage and offloading facilities with gas liquefaction processes

DEFF Research Database (Denmark)

Nguyen, Tuong-Van; Carranza-Sánchez, Yamid Alberto; Junior, Silvio de Oliveira

2016-01-01

Floating, production, storage and offloading (FPSO) plants are facilities used in upstream petroleum processing. They have gained interest because they are more flexible than conventional plants and can be used for producing oil and gas in deep-water fields. In general, gas export is challenging...... because of the lack of infrastructure in remote locations. The present work investigates the possibility of integrating liquefaction processes on such facilities, considering two mixed-refrigerant and two expansion-based processes suitable for offshore applications. Two FPSO configurations are considered...... in this work, and they were suggested by Brazilian operators for fields processing natural gas with moderate to high content of carbon dioxide. The performance of the combined systems is analysed by conducting energy and exergy analyses. The integration of gas liquefaction results in greater power consumption...

Development of Design Concept and Applied Technology for RCP Performance Test Facility

International Nuclear Information System (INIS)

Park, Sang Jin; Lee, Jung Ho; Yoon, Seok Ho

2010-02-01

Performance test facility for RCP (reactor coolant pump) is essential to verify the performance and reliability of RCP before installation in the nuclear power plant. The development of RCP for new-type reactor and the performance verification of hydraulic revolving body also needs the RCP test facility. The design concept of test loop and the technology of flow rate measurement are investigated in this research

Impacts of facility size and location decisions on ethanol production cost

International Nuclear Information System (INIS)

Kocoloski, Matt; Michael Griffin, W.; Scott Matthews, H.

2011-01-01

Cellulosic ethanol has been identified as a promising alternative to fossil fuels to provide energy for the transportation sector. One of the obstacles cellulosic ethanol must overcome in order to contribute to transportation energy demand is the infrastructure required to produce and distribute the fuel. Given a nascent cellulosic ethanol industry, locating cellulosic ethanol refineries and creating the accompanying infrastructure is essentially a greenfield problem that may benefit greatly from quantitative analysis. This study models cellulosic ethanol infrastructure investment using a mixed integer program (MIP) that locates ethanol refineries and connects these refineries to the biomass supplies and ethanol demands in a way that minimizes the total cost. For the single- and multi-state regions examined in this study, larger facilities can decrease ethanol costs by $0.20-0.30 per gallon, and placing these facilities in locations that minimize feedstock and product transportation costs can decrease ethanol costs by up to $0.25 per gallon compared to uninformed placement that could result from influences such as local subsidies to encourage economic development. To best benefit society, policies should allow for incentives that encourage these low-cost production scenarios and avoid politically motivated siting of plants. - Research highlights: → Mixed-integer programming can be used to model ethanol infrastructure investment. → Large cellulosic ethanol facilities can decrease production cost by $0.20/gallon. → Optimized facility placement can save $0.25/gallon.

Framework for Certification of Fish Propagation, Protection and Monitoring Facilities. Final Report.

Energy Technology Data Exchange (ETDEWEB)

Carlson, Thomas J.; Costello, Ronald J.

1997-06-01

A conceptual framework for certification of fish production and monitoring facilities including software templates to expedite implementation of the framework are presented. The framework is based on well established and widely utilized project management techniques. The implementation templates are overlays for Microsoft Professional Office software products: Excel, Word, and Project. Use of the software templates requires Microsoft Professional Office. The certification framework integrates two classical project management processes with a third process for facility certification. These processes are: (1) organization and definition of the project, (2) acquisition and organization of project documentation, and (3) facility certification. The certification process consists of systematic review of the production processes and the characteristics of the produced product. The criteria for certification review are the plans and specifications for the products and production processes that guided development of the facility. The facility is certified when the production processes are operating as designed and the product produced meets specifications. Within this framework, certification is a performance based process, not dissimilar from that practiced in many professions and required for many process, or a product meets professional/industry standards of performance. In the case of fish production facilities, the certifying authority may be diffuse, consisting of many entities acting through a process such as NEPA. A cornerstone of certification is accountability, over the long term, for the operation and products of a facility. This is particularly important for fish production facilities where the overall goal of the facility may require decades to accomplish.

18 CFR 292.208 - Special requirements for hydroelectric small power production facilities located at a new dam or...

Science.gov (United States)

2010-04-01

... for hydroelectric small power production facilities located at a new dam or diversion. 292.208 Section... requirements for hydroelectric small power production facilities located at a new dam or diversion. (a) A hydroelectric small power production facility that impounds or diverts the water of a natural watercourse by...

Subsides for optimization of transfer of radioactive liquid waste from 99MO production plant to the waste treatment facility

International Nuclear Information System (INIS)

Rego, Maria Eugenia de Melo; Vicente, Roberto; Hiromoto, Goro

2013-01-01

The increasing need for radioisotopes lead Brazil to consider the domestic production of 99 Mo from fission of low enriched uranium targets. In order to meet the present demand of 99m Tc generators the planned 'end of irradiation' activity of 99 Mo is about 170 TBq per week. The radioactive waste from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the waste were predicted based on the fission yield and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production process and schedule, already established by the project management. The transfer of the waste from the production plant to the treatment facility will be done by means of special shielded packages. In the present study, the commercially available code Scale 6.0 was used to simulate the irradiation of the targets and the decay of radioactive products, assuming that an alkaline dissolution process would be performed on the targets before the removal and purification of 99 Mo. The assessment of the shielding required for the packages containing liquid waste was done using MicroShield 9 code. The results presented here are part of a project that aims at contributing to the design of the waste management system for the 99 Mo production facility. (author)

Performance of the RI exhaust filter at Chosun university cyclotron facility and {sup 18}F emission reduction

Energy Technology Data Exchange (ETDEWEB)

Jeong, Cheol Ki; Jang, Han; Lee, Goung Jin [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)

2017-03-15

Recently, the number of PET cyclotrons has increased in Korea. A cyclotron mainly produces {sup 18}F, which is used for the production of [{sup 18}F]FDG, a cancer diagnostic radiopharmaceutical. For radiation protection, the discharge control standard under the Nuclear Safety Act limits the radioactive concentration of {sup 18}F in the exhaust discharged from a nuclear power utilization facility to below 2,000 Bq m-3. However, the radioactive concentration of 18F discharged during [18F]FDG production at the cyclotron facility at Chosun University is maintained at about 1,500 Bq m{sup -3} on average, which is 75% of the concentration limit of the discharge control standard, and temporarily exceeds the standard as per the real-time monitoring results. This study evaluated the performance of the exhaust flter unit of the cyclotron facility at Chosun University by assessing the concentration of {sup 18}F in the exhaust, and an experiment was conducted on the discharge reduction, where {sup 18}F is discharged without reacting with the FDG precursors during [{sup 18}F]FDG synthesis and is immediately captured by the [{sup 18}F]FDG automatic synthesis unit. Based on the performance evaluation results of the exhaust flter at the cyclotron facility of Chosun University, the measured capture effciency before and after the flter was found to be 92%. Furthermore, the results of the discharge reduction experiment, where the exhaust {sup 18}F was immediately captured by the [{sup 18}F]FDG synthesizer, showed a very satisfactory 94.3% reduction in the concentration of discharge compared to the existing discharge concentration.

Performance of smokeless gasoline fire test facility

International Nuclear Information System (INIS)

Griffin, J.F.; Watkins, R.A.

1978-01-01

Packaging for radioactive materials must perform satisfactorily when subjected to temperatures simulating an accident involving a fire. The new thermal test facility has proved to be a reliable method for satisfactorily performing the required test. The flame provides sufficient heat to assure that the test is valid, and the temperature can be controlled satisfactorily. Also, the air and water mist systems virtually eliminate any smoke and thereby exceed the local EPA requirements. The combination of the two systems provides an inexpensive, low maintenance technique for elimination of the smoke plume

Evaluation of performance indicators applied to a material recovery facility fed by mixed packaging waste.

Science.gov (United States)

Mastellone, Maria Laura; Cremiato, Raffaele; Zaccariello, Lucio; Lotito, Roberta

2017-06-01

Most of the integrated systems for municipal solid waste management aim to increase the recycling of secondary materials by means of physical processes including sorting, shredding and reprocessing. Several restrictions prevent from reaching a very high material recycling efficiency: the variability of the composition of new-marketed materials used for packaging production and its shape and complexity are critical issues. The packaging goods are in fact made of different materials (aluminium, polymers, paper, etc.), possibly assembled, having different shape (flat, cylindrical, one-dimensional, etc.), density, colours, optical properties and so on. These aspects limit the effectiveness and efficiency of the sorting and reprocessing plants. The scope of this study was to evaluate the performance of a large scale Material Recovery Facility (MRF) by utilizing data collected during a long period of monitoring. The database resulted from the measured data has been organized in four sections: (1) data related to the amount and type of inlet waste; (2) amount and composition of output products and waste; (3) operating data (such as worked hours for shift, planned and unscheduled maintenance time, setting parameters of the equipment, and energy consumption for shift); (4) economic data (value of each product, disposal price for the produced waste, penalty for non-compliance of products and waste, etc.). A part of this database has been utilized to build an executive dashboard composed by a set of performance indicators suitable to measure the effectiveness and the efficiency of the MRF operations. The dashboard revealed itself as a powerful tool to support managers and engineers in their decisions in respect to the market demand or compliance regulation variation as well as in the designing of the lay-out improvements. The results indicated that the 40% of the input waste was recovered as valuable products and that a large part of these (88%) complied with the standards of

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)

Annual report on experimental operations and maintenances of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system in 2002 fiscal year (Contract research)

International Nuclear Information System (INIS)

Hayashi, Koji; Ohashi, Hirofumi; Inaba, Yoshitomo; Kato, Michio; Aita, Hideki; Morisaki, Norihiro; Takeda, Tetsuaki; Nishihara, Tetsuo; Takada, Shoji; Inagaki, Yoshiyuki

2006-03-01

This report describes 2002 fiscal-year experimental test operations of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system. The improvement works were performed in May 2002. The second experimental test operation was performed from June 2002 and the performances of the improved parts were confirmed. Periodic inspections on boiler equipment and high-pressure gas production facilities were performed from end of July 2002. The third experimental test operation was performed, from October 2002, for (a) start-up and shutdown test, (b) process change test, (c) chemical reaction shutdown test and (d) characteristics test on steam reformer. It was confirmed that the changes of helium gas temperature, caused at steam reformer, could be mitigated into the target range by the steam generator. Maintenance works of high-pressure gas production facilities were also performed in February 2003. This report is summarized with the outline and the results of the test, maintenance works and inspections, and operation records in mentioned above. (author)

Pathways to high and low performance: factors differentiating primary care facilities under performance-based financing in Nigeria

Science.gov (United States)

Mabuchi, Shunsuke; Sesan, Temilade; Bennett, Sara C

2018-01-01

Abstract The determinants of primary health facility performance in developing countries have not been well studied. One of the most under-researched areas is health facility management. This study investigated health facilities under the pilot performance-based financing (PBF) scheme in Nigeria, and aimed to understand which factors differentiated primary health care centres (PHCCs) which had performed well, vs those which had not, with a focus on health facility management practices. We used a multiple case study where we compared two high-performing PHCCs and two low-performing PHCCs for each of the two PBF target states. Two teams of two trained local researchers spent 1 week at each PHCC and collected semi-structured interview, observation and documentary data. Data from interviews were transcribed, translated and coded using a framework approach. The data for each PHCC were synthesized to understand dynamic interactions of different elements in each case. We then compared the characteristics of high and low performers. The areas in which critical differences between high and low-performers emerged were: community engagement and support; and performance and staff management. We also found that (i) contextual and health system factors particularly staffing, access and competition with other providers; (ii) health centre management including community engagement, performance management and staff management; and (iii) community leader support interacted and drove performance improvement among the PHCCs. Among them, we found that good health centre management can overcome some contextual and health system barriers and enhance community leader support. This study findings suggest a strong need to select capable and motivated health centre managers, provide long-term coaching in managerial skills, and motivate them to improve their practices. The study also highlights the need to position engagement with community leaders as a key management practice and a central

Geochemical Data Package for the 2005 Hanford Integrated Disposal Facility Performance Assessment

Energy Technology Data Exchange (ETDEWEB)

Krupka, Kenneth M.; Serne, R JEFFREY.; Kaplan, D I.

2004-09-30

CH2M HILL Hanford Group, Inc. (CH2M HILL) is designing and assessing the performance of an integrated disposal facility (IDF) to receive low-level waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and failed or decommissioned melters. The CH2M HILL project to assess the performance of this disposal facility is the Hanford IDF Performance Assessment (PA) activity. The goal of the Hanford IDF PA activity is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the vadose zone to groundwater where contaminants may be re-introduced to receptors via drinking water wells or mixing in the Columbia River. Pacific Northwest National Laboratory (PNNL) assists CH2M HILL in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the IDF, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (Kd) and the thermodynamic solubility product (Ksp), respectively. In this data package, we approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. The Kd values and

Operation status and prospect of radioisotope production facility in HANARO

International Nuclear Information System (INIS)

Kim, Minjin; Jung, H.S.

2012-01-01

At the RIPF at HANARO, Radioisotopes for industrial and medical purpose are produced and research and development for various radioisotopes are carried out. Major products include Ir-192 for NDT, I-131 for treatment and diagnosis of thyroid cancer, Mo-99/Tc-99m Generator for imaging diagnosis of cancer. Production of radioisotope and radiopharmaceutical is being increased every year. Due to world-wide unstableness in the supply of Mo-99, a technology to produce (n,γ)Mo-99 generator at HANARO had been developed as a short term countermeasure. It will be available by the end of 2012. As a long term countermeasure, we are trying to build a new fully dedicated isotope reactor that will produce Fission Mo-99. At present, utilization of RIPF at HANARO is being increased. However when the construction of a new dedicated isotope reactor is completed in 2016, the role of the existing facility and new facility should be established accordingly so that none of the facilities are idling. In the near future, when the prospect of a utilization plan is completed, we expect an opportunity to present the result. (author)

Manufacturing and test of a low cost polypropylene bag to reduce the radioactive gas released by a radiopharmaceutical production facility

Energy Technology Data Exchange (ETDEWEB)

Tavares, Jose Carlos Freitas; Lacerda, Marco Aurelio de Sousa, E-mail: jcft@cdtn.b, E-mail: masl@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (SEPRA/ CDTN/CNEN-MG) Belo Horizonte, MG (Brazil). Servico de Protecao Radiologica; Nascimento, Leonardo Tafas Constantino do; Silva, Juliana Batista da, E-mail: ltcn@cdtn.b, E-mail: silvajb@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (SECPRA/ CDTN/CNEN-MG) Belo Horizonte, MG (Brazil). Secao de Producao de Radiofarmacos

2011-07-01

The main objective of this work was to evaluate the efficiency of a plastic gas storage bag to reduce the radioactive gas released by the chimney of a radiopharmaceutical production facility during the 2-[{sup 18}F]fluoro-2- deoxy-D-glucose ({sup 18}FDG) synthesis. The studied facility was the Development Centre of Nuclear Technology (CDTN/CNEN) in Belo Horizonte, Brazil. The bag was manufactured utilizing foils of polypropylene of 360 x 550 x 0.16 mm and disposable components of the cassette of the synthesizer. Two synthesis of {sup 18}FDG were done using the same hot cell and synthesizer to evaluate the efficiency of the bag. The manufactured bag was put in the gas exit of the synthesizer and the activity reported by the online radiation monitoring system in the first synthesis. These results were compared to the activity released in a synthesis performed without the bag. We observed when the bag was used the amount released was about 0.2% in 270 minutes. The second synthesis was performed without the bag, about 7,1% of the input activity was released by the exhaust of the facility in the same time interval. The bag presented a very good efficiency in the reducing of the radioactive gas released by the chimney of the radiopharmaceutical production facility. (author)

Manufacturing and test of a low cost polypropylene bag to reduce the radioactive gas released by a radiopharmaceutical production facility

International Nuclear Information System (INIS)

Tavares, Jose Carlos Freitas; Lacerda, Marco Aurelio de Sousa; Nascimento, Leonardo Tafas Constantino do; Silva, Juliana Batista da

2011-01-01

The main objective of this work was to evaluate the efficiency of a plastic gas storage bag to reduce the radioactive gas released by the chimney of a radiopharmaceutical production facility during the 2-[ 18 F]fluoro-2- deoxy-D-glucose ( 18 FDG) synthesis. The studied facility was the Development Centre of Nuclear Technology (CDTN/CNEN) in Belo Horizonte, Brazil. The bag was manufactured utilizing foils of polypropylene of 360 x 550 x 0.16 mm and disposable components of the cassette of the synthesizer. Two synthesis of 18 FDG were done using the same hot cell and synthesizer to evaluate the efficiency of the bag. The manufactured bag was put in the gas exit of the synthesizer and the activity reported by the online radiation monitoring system in the first synthesis. These results were compared to the activity released in a synthesis performed without the bag. We observed when the bag was used the amount released was about 0.2% in 270 minutes. The second synthesis was performed without the bag, about 7,1% of the input activity was released by the exhaust of the facility in the same time interval. The bag presented a very good efficiency in the reducing of the radioactive gas released by the chimney of the radiopharmaceutical production facility. (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

Radiocesium Discharges and Subsequent Environmental Transport at the Major U.S. Weapons Production Facilities

Energy Technology Data Exchange (ETDEWEB)

Garten, Jr. C.T.; Hamby, D.M.; Schreckhise, R.G.

1999-11-14

Radiocesium is one of the more prevalent radionuclides in the environment as a result of weapons production related atomic projects in the United States and the former Soviet Union. Radiocesium discharges during the 1950's account for a large fraction of the historical releases from U.S. weapons production facilities. Releases of radiocesium to terrestrial and aquatic ecosystems during the early ,years of nuclear weapons production provided the opportunity to conduct multidisciplinary studies on the transport mechanisms of this potentially hazardous radionuclide. The major U.S. Department of Energy facilities (Oak Ridge Reservation in Tennessee, Hanford Site near Richland, Washington, and Savannah River Site near Aiken, South Carolina) are located in regions of the country that have different geographical characteristics. The facility siting provided diverse backgrounds for the development of an understanding of environmental factors contributing to the fate and transport of radiocesium. In this paper, we summarize the significant environmental releases of radiocesium in the early -years of weapons production and then discuss the historically significant transport mechanisms for r37Cs at the three facilities that were part of the U.S. nuclear weapons complex.

HUMPF [Heterogeneous Unix Montecarlo Production Facility] users guide

International Nuclear Information System (INIS)

Cahill, P.; Edgecock, R.; Fisher, S.M.; Gee, C.N.P.; Gordon, J.C.; Kidd, T.; Leake, J.; Rigby, D.J.; Roberts, J.H.C.

1992-11-01

The Heterogenous Unix Monte Carlo Production Facility (HUMPF) simplifies the running of particle physics simulation programs on Unix workstations. Monte Carlo is the largest consumer of IBM (CPU) capacity within the Atlas centre at Rutherford Appleton Laboratory (RAL). It is likely that the future computing requirements of the LEP and HERA experiments cannot be satisfied by the IBM 3090 system. HUMPF adds extra capacity, and can be expanded with minimal effort. Monte Carlo programs are CPU-bound, and make little use of the vector or the input/output capacity of the IBM 3090. Such programs are therefore excellent candidates to use the spare capacity of powerful workstations. The main data storage is still handled centrally by the IBM 3090 and its peripherals. The HUMPF facility is suitable for any program with a similar profile. (author)

Productivity and Performance Measurement

DEFF Research Database (Denmark)

Hald, Kim Sundtoft; Spring, Martin

This study explores conceptually how performance measurement as discussed in the literature, enables or constrains the ability to manage and improve productivity. It uses an inter-disciplinary literature review to identify five areas of concern relating productivity accounting to the ability...... to improve productivity: “Productivity representation”; “productivity incentives”, “productivity intervention”; “productivity trade-off or synergy” and “productivity strategy and context”. The paper discusses these areas of concern and expands our knowledge of how productivity and performance measurement...

Good Manufacturing Practices (GMP) manufacturing of advanced therapy medicinal products: a novel tailored model for optimizing performance and estimating costs.

Science.gov (United States)

Abou-El-Enein, Mohamed; Römhild, Andy; Kaiser, Daniel; Beier, Carola; Bauer, Gerhard; Volk, Hans-Dieter; Reinke, Petra

2013-03-01

Advanced therapy medicinal products (ATMP) have gained considerable attention in academia due to their therapeutic potential. Good Manufacturing Practice (GMP) principles ensure the quality and sterility of manufacturing these products. We developed a model for estimating the manufacturing costs of cell therapy products and optimizing the performance of academic GMP-facilities. The "Clean-Room Technology Assessment Technique" (CTAT) was tested prospectively in the GMP facility of BCRT, Berlin, Germany, then retrospectively in the GMP facility of the University of California-Davis, California, USA. CTAT is a two-level model: level one identifies operational (core) processes and measures their fixed costs; level two identifies production (supporting) processes and measures their variable costs. The model comprises several tools to measure and optimize performance of these processes. Manufacturing costs were itemized using adjusted micro-costing system. CTAT identified GMP activities with strong correlation to the manufacturing process of cell-based products. Building best practice standards allowed for performance improvement and elimination of human errors. The model also demonstrated the unidirectional dependencies that may exist among the core GMP activities. When compared to traditional business models, the CTAT assessment resulted in a more accurate allocation of annual expenses. The estimated expenses were used to set a fee structure for both GMP facilities. A mathematical equation was also developed to provide the final product cost. CTAT can be a useful tool in estimating accurate costs for the ATMPs manufactured in an optimized GMP process. These estimates are useful when analyzing the cost-effectiveness of these novel interventions. Copyright © 2013 International Society for Cellular Therapy. Published by Elsevier Inc. All rights reserved.

Special report. New products that improve officer performance, safety.

Science.gov (United States)

1991-12-01

The need for products that improve performance of security officers is counterbalanced these days by budgetary constraints. While this may limit major investments in security systems and personnel, less costly improvements or innovations might be worth considering. In this report, we will discuss four advances that may be valuable not only in hospital security, but in other industries as well. One of them, a smoke filter, was originally developed for the hotel industry. Another, a drug detection device, may replace the use of undercover agents or drug-sniffing' dogs in certain circumstances. The third new product is an economical patrol vehicle for parking facilities which might replace more costly vehicles such as golf carts or cars. The fourth product, a roving CCTV camera, is actually being tested at a Midwest medical center and may allow you to monitor areas of parking garages with cameras instead of officers on patrol.

Cyclotron Produced Radionuclides: Guidance on Facility Design and Production of [18F]Fluorodeoxyglucose (FDG)

International Nuclear Information System (INIS)

2012-01-01

Positron emission tomography (PET) has advanced rapidly in recent years and is becoming an indispensable imaging modality for the evaluation and staging of cancer patients. A key component of the successful operation of a PET centre is the on-demand availability of radiotracers (radiopharmaceuticals) labelled with suitable positron emitting radioisotopes. Of the hundreds of positron labelled radiotracers, 2-[ 18 F]-fluoro-2-deoxy-D-glucose (FDG) is the most successful and widely used imaging agent in PET today. While FDG is utilized largely in oncology for the management of cancer patients, its applications in neurology and cardiology are also steadily growing. A large number of PET facilities have been established in Member States over the past few years, and more are being planned. The design and operation of a facility for the production of FDG requires attention to detail, in particular the application of good manufacturing practices (GMP) guidelines and quality assurance. The product must conform to the required quality specifications and must be safe for human use. This book is intended to be a resource manual with practical information for planning and operating an FDG production facility, including design and implementation of the laboratories, facility layout, equipment, personnel and FDG quality assessment. GMP and quality management are discussed only briefly, since these topics are covered extensively in the IAEA publication Cyclotron Produced Radionuclides: Guidelines for Setting up a Facility (Technical Reports Series No. 471). It should be noted that manufacturing processes and quality specifications for FDG are not currently globally harmonized, and these do vary to some extent. However, there is no disagreement over the need to ensure that the product is manufactured in a controlled manner, that it conforms to applicable quality specifications and that it is safe for human use. Administrators, managers, radiopharmaceutical scientists, production

Microcomputer simulation model for facility performance assessment: a case study of nuclear spent fuel handling facility operations

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.; Otis, P.T.

1985-10-01

A microcomputer based simulation model was recently developed at the Pacific Northwest Laboratory (PNL) to assist in the evaluation of design alternatives for a proposed facility to receive, consolidate and store nuclear spent fuel from US commercial power plants. Previous performance assessments were limited to deterministic calculations and Gantt chart representations of the facility operations. To insure that the design of the facility will be adequate to meet the specified throughput requirements, the simulation model was used to analyze such factors as material flow, equipment capability and the interface between the MRS facility and the nuclear waste transportation system. The simulation analysis model was based on commercially available software and application programs designed to represent the MRS waste handling facility operations. The results of the evaluation were used by the design review team at PNL to identify areas where design modifications should be considered. 4 figs

Product Platform Performance

DEFF Research Database (Denmark)

Munk, Lone

The aim of this research is to improve understanding of platform-based product development by studying platform performance in relation to internal effects in companies. Platform-based product development makes it possible to deliver product variety and at the same time reduce the needed resources...... engaging in platform-based product development. Similarly platform assessment criteria lack empirical verification regarding relevance and sufficiency. The thesis focuses on • the process of identifying and estimating internal effects, • verification of performance of product platforms, (i...... experienced representatives from the different life systems phase systems of the platform products. The effects are estimated and modeled within different scenarios, taking into account financial and real option aspects. The model illustrates and supports estimation and quantification of internal platform...

A national biomedical tracer facility (NBTF)

International Nuclear Information System (INIS)

Erb, D.E.; Moody, D.; Peterson, E.; Mausner, L.; Atcher, R.

1991-01-01

The production, supply, and sale of isotopes and related services originating in Department of Energy production and research facilities has been a long-standing activity of DOE and predecessor organizations (AEC and ERDA). The authority for this activity is derived from the Atomic Energy Act of 1954, as amended. Stable isotopes and radioisotopes, together with related services, are now being produced in many DOE production and research facilities at several DOE installations which presently include: Argonne National Laboratory (ANL), Brookhaven National Laboratory (BNL), EG ampersand G Mound Laboratories (Mound), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Westinghouse Hanford Company (WHC), and the Pacific Northwest Laboratories (PNL) at Richland, Washington. The products and services are, in many instances, unique in that their production and processing can be performed only in production and research facilities owned by, and operated for, DOE. In some instances, DOE is the sole supplier of such isotope products and services in the Western World

Construction and performance of the magnetic bunch compressor for the THz facility at Chiang Mai University

International Nuclear Information System (INIS)

Saisut, J.; Kusoljariyakul, K.; Rimjaem, S.; Kangrang, N.; Wichaisirimongkol, P.; Thamboon, P.; Rhodes, M.W.; Thongbai, C.

2011-01-01

The Plasma and Beam Physics Research Facility at Chiang Mai University has established a THz facility to focus on the study of ultra-short electron pulses. Short electron bunches can be generated from a system that consists of a radio-frequency (RF) gun with a thermionic cathode, an alpha magnet as a magnetic bunch compressor, and a linear accelerator as a post-acceleration section. The alpha magnet is a conventional and simple instrument for low-energy electron bunch compression. With the alpha magnet constructed in-house, several hundred femtosecond electron bunches for THz radiation production can be generated from the thermionic RF gun. The construction and performance of the alpha magnet, as well as some experimental results, are presented in this paper.

Construction and performance of the magnetic bunch compressor for the THz facility at Chiang Mai University

Science.gov (United States)

Saisut, J.; Kusoljariyakul, K.; Rimjaem, S.; Kangrang, N.; Wichaisirimongkol, P.; Thamboon, P.; Rhodes, M. W.; Thongbai, C.

2011-05-01

The Plasma and Beam Physics Research Facility at Chiang Mai University has established a THz facility to focus on the study of ultra-short electron pulses. Short electron bunches can be generated from a system that consists of a radio-frequency (RF) gun with a thermionic cathode, an alpha magnet as a magnetic bunch compressor, and a linear accelerator as a post-acceleration section. The alpha magnet is a conventional and simple instrument for low-energy electron bunch compression. With the alpha magnet constructed in-house, several hundred femtosecond electron bunches for THz radiation production can be generated from the thermionic RF gun. The construction and performance of the alpha magnet, as well as some experimental results, are presented in this paper.

Branch technical position for performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Campbell, A.C.; Abramson, L.; Byrne, R.M.

1994-01-01

The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

Targetry at the LANL 100 MeV isotope production facility: lessons learned from facility commissioning

Energy Technology Data Exchange (ETDEWEB)

Nortier, F. M. (Francois M.); Fassbender, M. E. (Michael E.); DeJohn, M.; Hamilton, V. T. (Virginia T.); Heaton, R. C. (Richard C.); Jamriska, David J.; Kitten, J. J. (Jason J.); Lenz, J. W.; Lowe, C. E.; Moddrell, C. F.; McCurdy, L. M. (Lisa M.); Peterson, E. J. (Eugene J.); Pitt, L. R. (Lawrence R.); Phillips, D. R. (Dennis R.); Salazar, L. L. (Louie L.); Smith, P. A. (Paul A.); Valdez, Frank O.

2004-01-01

The new Isotope Production Facility (IPF) at Los Alamos National Laboratory has been commissioned during the spring of 2004. Commissioning activities focused on the establishment of a radionuclide database, the review and approval of two specific target stack designs, and four trial runs with subsequent chemical processing and data analyses. This paper highlights some aspects of the facility and the targetry of the two approved target stacks used during the commissioning process. Since one niobium encapsulated gallium target developed a blister after the extended irradiation of 4 days, a further evaluation of the gallium targets is required. Beside this gallium target, no other target showed any sign of thermal failure. Considering the uncertainties involved, the production yields obtained for targets irradiated in the same energy slot are consistent for all three 'Prototype' stacks. A careful analysis of the temperature profile in the RbCl targets shows that energy shifts occur in the RbCl and Ga targets. Energy shifts are a result of density variations in the RbCl disk under bombardment. Thickness adjustments of targets in the prototype stack are required to ensure maximum production yields of {sup 82}Sr and {sup 68}Ge in the design energy windows. The {sup 68}Ge yields obtained are still consistently lower than the predicted yield value, which requires further investigation. After recalculation of the energy windows for the RbCl and Ga targets, the measured {sup 82}Sr production yields compare rather well with values predicted on the basis of evaluated experimental excitation function data.

AMS data production facilities at science operations center at CERN

Science.gov (United States)

Choutko, V.; Egorov, A.; Eline, A.; Shan, B.

2017-10-01

The Alpha Magnetic Spectrometer (AMS) is a high energy physics experiment on the board of the International Space Station (ISS). This paper presents the hardware and software facilities of Science Operation Center (SOC) at CERN. Data Production is built around production server - a scalable distributed service which links together a set of different programming modules for science data transformation and reconstruction. The server has the capacity to manage 1000 paralleled job producers, i.e. up to 32K logical processors. Monitoring and management tool with Production GUI is also described.

Subsides for optimization of transfer of radioactive liquid waste from {sup 99}MO production plant to the waste treatment facility

Energy Technology Data Exchange (ETDEWEB)

Rego, Maria Eugenia de Melo; Vicente, Roberto; Hiromoto, Goro, E-mail: maria.eugenia@ipen.br, E-mail: rvicente@ipen.br, E-mail: hiromoto@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

The increasing need for radioisotopes lead Brazil to consider the domestic production of {sup 99}Mo from fission of low enriched uranium targets. In order to meet the present demand of {sup 99m}Tc generators the planned 'end of irradiation' activity of {sup 99}Mo is about 170 TBq per week. The radioactive waste from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the waste were predicted based on the fission yield and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production process and schedule, already established by the project management. The transfer of the waste from the production plant to the treatment facility will be done by means of special shielded packages. In the present study, the commercially available code Scale 6.0 was used to simulate the irradiation of the targets and the decay of radioactive products, assuming that an alkaline dissolution process would be performed on the targets before the removal and purification of {sup 99}Mo. The assessment of the shielding required for the packages containing liquid waste was done using MicroShield 9 code. The results presented here are part of a project that aims at contributing to the design of the waste management system for the {sup 99}Mo production facility. (author)

Demonstration of persistent contamination of a cooked egg product production facility with Salmonella enterica serovar Tennessee and characterization of the persistent strain.

Science.gov (United States)

Jakočiūnė, D; Bisgaard, M; Pedersen, K; Olsen, J E

2014-08-01

The aim of this study was to investigate whether continuous contamination of light pasteurized egg products with Salmonella enterica serovar Tennessee (S. Tennessee) at a large European producer of industrial egg products was caused by persistent contamination of the production facility and to characterize the persistent strains. Seventy-three S. Tennessee isolates collected from products over a 3-year period with intermittent contamination, and 15 control strains were compared by pulsed field gel electrophoresis (PFGE) using two enzymes. Forty-five case isolates distributed throughout the full period were shown to belong to one profile type. Isolates representing different PFGE profiles were all assigned to ST 319 by multilocus sequence typing (MLST). The case isolates did not show a higher ability to form biofilm on a plastic surface than noncase isolates. Characteristically, members of the persistent clone were weak producers of H2 S in laboratory medium. S. Tennessee isolated from the case was able to grow better in pasteurized egg product compared with other serovars investigated. It was concluded that the contamination was caused by a persistent strain in the production facility and that this strain apparently had adapted to grow in the relevant egg product. S. Tennessee has previously been associated with persistence in hatching facilities. This is the first report of persistent contamination of an egg production facility with this serovar. © 2014 The Society for Applied Microbiology.

Facility design consideration for continuous mix production of class 1.3 propellant

Science.gov (United States)

Williamson, K. L.; Schirk, P. G.

1994-01-01

In November of 1989, NASA awarded the Advanced Solid Rocket Motor (ASRM) contract to Lockheed Missiles and Space Company (LMSC) for production of advanced solid rocket motors using the continuous mix process. Aerojet ASRM division (AAD) was selected as the facility operator and RUST International Corporation provided the engineering, procurement, and construction management services. The continuous mix process mandates that the mix and cast facilities be 'close-coupled' along with the premix facilities, creating unique and challenging requirements for the facility designer. The classical approach to handling energetic materials-division into manageable quantities, segregation, and isolation-was not available due to these process requirements and quantities involved. This paper provides a description of the physical facilities, the continuous mix process, and discusses the monitoring and detection techniques used to mitigate hazards and prevent an incident.

Fast Flux Test Facility core restraint system performance

International Nuclear Information System (INIS)

Hecht, S.L.; Trenchard, R.G.

1990-02-01

Characterizing Fast Flux Test Facility (FFTF) core restraint system performance has been ongoing since the first operating cycle. Characterization consists of prerun analysis for each core load, in-reactor and postirradiation measurements of subassembly withdrawal loads and deformations, and using measurement data to fine tune predictive models. Monitoring FFTF operations and performing trend analysis has made it possible to gain insight into core restraint system performance and head off refueling difficulties while maximizing component lifetimes. Additionally, valuable information for improved designs and operating methods has been obtained. Focus is on past operating experience, emphasizing performance improvements and avoidance of potential problems. 4 refs., 12 figs., 2 tabs

A Strategic Framework for the Establishment of International Production Facilities

DEFF Research Database (Denmark)

Nielsen, A.P.; Riis, Jens Ove

2000-01-01

Departing from the empirical observation that there often is a weak link between the corporate internationalisation strategies and the actual establishment of international production facilities. This paper describes a framework to overcome this problem. The basic idea in the framework is the dis...

Factors Affecting Slot Machine Performance in an Electronic Gaming Machine Facility

OpenAIRE

Etienne Provencal; David L. St-Pierre

2017-01-01

A facility exploiting only electronic gambling machines (EGMs) opened in 2007 in Quebec City, Canada under the name of Salons de Jeux du Québec (SdjQ). This facility is one of the first worldwide to rely on that business model. This paper models the performance of such EGMs. The interest from a managerial point of view is to identify the variables that can be controlled or influenced so that a comprehensive model can help improve the overall performance of the business. The EGM individual per...

Current Status and Performance Tests of Korea Heat Load Test Facility KoHLT-EB

Energy Technology Data Exchange (ETDEWEB)

Kim, Sukkwon; Jin, Hyunggon; Shin, Kyuin; Choi, Boguen; Lee, Eohwak; Yoon, Jaesung; Lee, Dongwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Duckhoi; Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

2013-05-15

A commissioning test has been scheduled to establish the installation and preliminary performance experiments of the copper hypervapotron mockups. And a qualification test will be performed to evaluate the CuCrZr duct liner in the ITER neutral beam injection facility and the ITER first wall small-scale mockups of the semi-prototype, at up to 1.5 and 5 MW/m{sup 2} high heat flux. Also, this system will be used to test other PFCs for ITER and materials for tokamak reactors. Korean high heat flux test facility(KoHLT-EB; Korea Heat Load Test facility - Electron Beam) by using an electron beam system has been constructed in KAERI to perform the qualification test for ITER blanket FW semi-prototype mockups, hypervapotron cooling devices in fusion devices, and other ITER plasma facing components. The commissioning and performance tests with the supplier of e-gun system have been performed on November 2012. The high heat flux test for hypervapotron cooling device and calorimetry were performed to measure the surface heat flux, the temperature profile and cooling performance. Korean high heat flux test facility for the plasma facing components of nuclear fusion machines will be constructed to evaluate the performance of each component. This facility for the plasma facing materials will be equipped with an electron beam system with a 60 kV acceleration gun.

Experimental Breeder Reactor II (EBR-II) Fuel-Performance Test Facility (FPTF)

International Nuclear Information System (INIS)

Pardini, J.A.; Brubaker, R.C.; Veith, D.J.; Giorgis, G.C.; Walker, D.E.; Seim, O.S.

1982-01-01

The Fuel-Performance Test Facility (FPTF) is the latest in a series of special EBR-II instrumented in-core test facilities. A flow control valve in the facility is programmed to vary the coolant flow, and thus the temperature, in an experimental-irradiation subassembly beneath it and coupled to it. In this way, thermal transients can be simulated in that subassembly without changing the temperatures in surrounding subassemblies. The FPTF also monitors sodium flow and temperature, and detects delayed neutrons in the sodium effluent from the experimental-irradiation subassembly beneath it. This facility also has an acoustical detector (high-temperature microphone) for detecting sodium boiling

Performance evaluation of the Solar Building Test Facility

Science.gov (United States)

Jensen, R. N.

1981-01-01

The general performance of the NASA Solar Building Test Facility (SBTF) and its subsystems and components over a four year operational period is discussed, and data are provided for a typical one year period. The facility consists of a 4645 sq office building modified to accept solar heated water for operation of an absorption air conditioner and a baseboard heating system. An adjoining 1176 sq solar flat plate collector field with a 114 cu tank provides the solar heated water. The solar system provided 57 percent of the energy required for heating and cooling on an annual basis. The average efficiency of the solar collectors was 26 percent over a one year period.

Evaluation of a Low-Cost Salmon Production Facility; 1988 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Hill, James M.; Olson, Todd

1989-05-01

This fiscal year 1988 study sponsored by the Bonneville Power Administration evaluates an existing, small-scale salmon production facility operated and maintained by the Clatsop County Economic Development Committee's Fisheries Project.

Pinellas Plant facts. [Products, processes, laboratory facilities

Energy Technology Data Exchange (ETDEWEB)

1986-09-01

This plant was built in 1956 in response to a need for the manufacture of neutron generators, a principal component in nuclear weapons. The neutron generators consist of a miniaturized linear ion accelerator assembled with the pulsed electrical power supplies required for its operation. The ion accelerator, or neutron tube, requires ultra clean, high vacuum technology: hermetic seals between glass, ceramic, glass-ceramic, and metal materials: plus high voltage generation and measurement technology. The existence of these capabilities at the Pinellas Plant has led directly to the assignment of the lightning arrester connector, specialty capacitor, vacuum switch, and crystal resonator. Active and reserve batteries and the radioisotopically-powered thermoelectric generator draw on the materials measurement and controls technologies which are required to ensure neutron generator life. A product development and production capability in alumina ceramics, cermet (electrical) feedthroughs, and glass ceramics has become a specialty of the plant; the laboratories monitor the materials and processes used by the plant's commercial suppliers of ferroelectric ceramics. In addition to the manufacturing facility, a production development capability is maintained at the Pinellas Plant.

A Study on Methodology of Assessment for Hydrogen Explosion in Hydrogen Production Facility

International Nuclear Information System (INIS)

Jung, Gun Hyo

2007-02-01

Due to the exhaustion of fossil fuel as energy sources and international situation insecurity for political factor, unstability of world energy market is rising, consequently, a substitute energy development have been required. Among substitute energy to be discussed, producing hydrogen from water by nuclear energy which does not release carbon is a very promising technology. Very high temperature gas cooled reactor is expected to be utilized since the procedure of producing hydrogen requires high temperature over 1000 .deg. C. Hydrogen production facility using very high temperature gas cooled reactor lies in situation of high temperature and corrosion which makes hydrogen release easily. In case of hydrogen release, there lies a danger of explosion. Moreover explosion not only has a bad influence upon facility itself but very high temperature gas cooled reactor which also result in unsafe situation that might cause serious damage. However, from point of thermal-hydraulics view, long distance makes low efficiency result. In this study, therefore, outlines of hydrogen production using nuclear energy is researched. Several methods for analyzing the effects of hydrogen explosion upon high temperature gas cooled reactor are reviewed. Reliability physics model which is appropriate for assessment is used. Using this model, leakage probability, rupture probability and structure failure probability of very high temperature gas cooled reactor is evaluated classified by detonation volume and distance. Also based on standard safety criteria which is a value of 1x10 -6 , the safety distance between very high temperature and hydrogen production facility is calculated. In the future, assessment for characteristic of very high temperature gas cooled reactor, capacity to resist pressure from outside hydrogen explosion and overpressure for large amount of detonation volume in detail is expected to identify more precise distance using reliability physics model in this paper. This

ESOL facility for the generation and radiochemical separation of short half-life fission products

International Nuclear Information System (INIS)

Gehrke, R.J.; Meikrantz, D.H.; Baker, J.D.; Anderl, R.A.; Novick, V.J.; Greenwood, R.C.

1988-01-01

A facility has been developed at the Idaho National Engineering Laboratory (INEL) for the generation and rapid radiochemical separation of short half-life mixed fission products. This facility, referred to as the Idaho Elemental Separation On Line (ESOL), consists of electro-plated sources of spontaneously fissioning 252 Cf with a helium jet transport arrangement to continuously deliver short half-life, mixed fission products to the radiochemistry laboratory for rapid, computer controlled, radiochemical separations. 18 refs., 13 figs

Efficiency and cost advantages of an advanced-technology nuclear electrolytic hydrogen-energy production facility

Science.gov (United States)

Donakowski, T. D.; Escher, W. J. D.; Gregory, D. P.

1977-01-01

The concept of an advanced-technology (viz., 1985 technology) nuclear-electrolytic water electrolysis facility was assessed for hydrogen production cost and efficiency expectations. The facility integrates (1) a high-temperature gas-cooled nuclear reactor (HTGR) operating a binary work cycle, (2) direct-current (d-c) electricity generation via acyclic generators, and (3) high-current-density, high-pressure electrolyzers using a solid polymer electrolyte (SPE). All subsystems are close-coupled and optimally interfaced for hydrogen production alone (i.e., without separate production of electrical power). Pipeline-pressure hydrogen and oxygen are produced at 6900 kPa (1000 psi). We found that this advanced facility would produce hydrogen at costs that were approximately half those associated with contemporary-technology nuclear electrolysis: $5.36 versus $10.86/million Btu, respectively. The nuclear-heat-to-hydrogen-energy conversion efficiency for the advanced system was estimated as 43%, versus 25% for the contemporary system.

Annual report on experimental operations and maintenances of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system in 2003 fiscal year (Contract research)

International Nuclear Information System (INIS)

Hayashi, Koji; Morisaki, Norihiro; Ohashi, Hirofumi; Kato, Michio; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Takada, Shoji; Inagaki, Yoshiyuki

2006-03-01

This is a report on the experimental operations and maintenances of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system in 2003 fiscal year. The fourth and fifth experimental test operations were performed, from May to July and from October to December in 2003, for the following tests; (a) start-up and shutdown operation test, (b) process change test, (c) continuous hydrogen-production test and (d) chemical reaction shutdown test. From the results, a long time-range stability of the hydrogen production system was confirmed, a behavior of the helium-gas cooling system, consists of steam generator and radiator; during chemical reaction shutdown, was understood, and so on. Periodic inspections on boiler equipment and high-pressure gas production facilities were performed from end of July 2003. This report is summarized on outlines and results of the tests, outlines and results of the periodic inspections, and operation records of the mock-up test facility. (author)

Cyclotron Produced Radionuclides: Guidance on Facility Design and Production of [{sup 18}F]Fluorodeoxyglucose (FDG)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-01-15

Positron emission tomography (PET) has advanced rapidly in recent years and is becoming an indispensable imaging modality for the evaluation and staging of cancer patients. A key component of the successful operation of a PET centre is the on-demand availability of radiotracers (radiopharmaceuticals) labelled with suitable positron emitting radioisotopes. Of the hundreds of positron labelled radiotracers, 2-[{sup 18}F]-fluoro-2-deoxy-D-glucose (FDG) is the most successful and widely used imaging agent in PET today. While FDG is utilized largely in oncology for the management of cancer patients, its applications in neurology and cardiology are also steadily growing. A large number of PET facilities have been established in Member States over the past few years, and more are being planned. The design and operation of a facility for the production of FDG requires attention to detail, in particular the application of good manufacturing practices (GMP) guidelines and quality assurance. The product must conform to the required quality specifications and must be safe for human use. This book is intended to be a resource manual with practical information for planning and operating an FDG production facility, including design and implementation of the laboratories, facility layout, equipment, personnel and FDG quality assessment. GMP and quality management are discussed only briefly, since these topics are covered extensively in the IAEA publication Cyclotron Produced Radionuclides: Guidelines for Setting up a Facility (Technical Reports Series No. 471). It should be noted that manufacturing processes and quality specifications for FDG are not currently globally harmonized, and these do vary to some extent. However, there is no disagreement over the need to ensure that the product is manufactured in a controlled manner, that it conforms to applicable quality specifications and that it is safe for human use. Administrators, managers, radiopharmaceutical scientists

Computerized radionuclidic analysis in production facilities

International Nuclear Information System (INIS)

Gibbs, A.

1978-03-01

The Savannah River Plant Laboratories Department has been using a dual computer system to control all radionuclidic pulse height analyses since 1971. This computerized system analyzes 7000 to 8000 samples per month and has allowed the counting room staff to be reduced from three persons to one person. More reliable process information is being returned to the production facilities and for environmental evaluations and being returned faster, even though the sample load has more than tripled. This information is now more easily retrievable for other evaluations. The computer is also used for mass spectrometer data reduction and for quality control data analysis. The basic system is being expanded by interfacing microcomputers which provide data input from all of the laboratory modules for quality assurance programs

A performance goal-based seismic design philosophy for waste repository facilities

International Nuclear Information System (INIS)

Hossain, Q.A.

1994-02-01

A performance goal-based seismic design philosophy, compatible with DOE's present natural phenomena hazards mitigation and ''graded approach'' philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed

Gamma and X-rays Production for Experiments at ELSA Facility

CERN Document Server

Lemaire, J

2004-01-01

The ELSA facility is a high brightness 18 MeV electron source dedicated to electron radiation, gamma-rays and picosecond hard and soft X-rays. It consists of a 144 MHz RF photoinjector producing short bunches which are further accelerated to a final energy varying from 2 to 18 MeV thanks to three 433 MHz RF cavities. Former beam compression design used a half turn magnet compressor system. It has been recently replaced by a double alpha magnet compressor. Electron beams are now delivered to a new experimental room. We present the new panel of interests offered by this facility in term of gamma-ray and X-ray production.

High Performance Computing Facility Operational Assessment, CY 2011 Oak Ridge Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Baker, Ann E [ORNL; Barker, Ashley D [ORNL; Bland, Arthur S Buddy [ORNL; Boudwin, Kathlyn J. [ORNL; Hack, James J [ORNL; Kendall, Ricky A [ORNL; Messer, Bronson [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL; Wells, Jack C [ORNL; White, Julia C [ORNL; Hudson, Douglas L [ORNL

2012-02-01

Oak Ridge National Laboratory's Leadership Computing Facility (OLCF) continues to deliver the most powerful resources in the U.S. for open science. At 2.33 petaflops peak performance, the Cray XT Jaguar delivered more than 1.4 billion core hours in calendar year (CY) 2011 to researchers around the world for computational simulations relevant to national and energy security; advancing the frontiers of knowledge in physical sciences and areas of biological, medical, environmental, and computer sciences; and providing world-class research facilities for the nation's science enterprise. Users reported more than 670 publications this year arising from their use of OLCF resources. Of these we report the 300 in this review that are consistent with guidance provided. Scientific achievements by OLCF users cut across all range scales from atomic to molecular to large-scale structures. At the atomic scale, researchers discovered that the anomalously long half-life of Carbon-14 can be explained by calculating, for the first time, the very complex three-body interactions between all the neutrons and protons in the nucleus. At the molecular scale, researchers combined experimental results from LBL's light source and simulations on Jaguar to discover how DNA replication continues past a damaged site so a mutation can be repaired later. Other researchers combined experimental results from ORNL's Spallation Neutron Source and simulations on Jaguar to reveal the molecular structure of ligno-cellulosic material used in bioethanol production. This year, Jaguar has been used to do billion-cell CFD calculations to develop shock wave compression turbo machinery as a means to meet DOE goals for reducing carbon sequestration costs. General Electric used Jaguar to calculate the unsteady flow through turbo machinery to learn what efficiencies the traditional steady flow assumption is hiding from designers. Even a 1% improvement in turbine design can save the nation

The ETH Zurich AMS facilities: Performance parameters and reference materials

Energy Technology Data Exchange (ETDEWEB)

Christl, M., E-mail: mchristl@phys.ethz.ch [Laboratory of Ion Beam Physics, ETH Zurich, 8093 Zurich (Switzerland); Vockenhuber, C.; Kubik, P.W.; Wacker, L.; Lachner, J.; Alfimov, V.; Synal, H.-A. [Laboratory of Ion Beam Physics, ETH Zurich, 8093 Zurich (Switzerland)

2013-01-15

The current performance of all three AMS systems in operation at ETH Zurich, the 6 MV HVEC EN-Tandem facility 'TANDEM', the 0.5 MV NEC Pelletron 'TANDY', and the 0.2 MV system 'MICADAS' is summarized. Radionuclides routinely measured with these AMS systems include {sup 10}Be, {sup 14}C, {sup 26}Al, {sup 36}Cl, {sup 41}Ca, {sup 129}I and the actinides. The reference materials used for the normalization of the AMS measurements at the ETH Zurich AMS facilities are presented. This paper therefore is a comprehensive status report of all three AMS systems currently operated by the Laboratory of Ion Beam Physics (LIP) at ETH Zurich and documents their performance and operation parameters.

Annual Summary of the Integrated Disposal Facility Performance Assessment 2012

Energy Technology Data Exchange (ETDEWEB)

Khaleel, R. [INTERA, Austin, TX (United States); Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2012-12-27

An annual summary of the adequacy of the Hanford Immobilized Low-Activity Waste (ILAW) Performance Assessment (PA) is required each year (DOE O 435.1 Chg 1,1 DOE M 435.1-1 Chg 1;2 and DOE/ORP-2000-013). The most recently approved PA is DOE/ORP-2000-24.4 The ILAW PA evaluated the adequacy of the ILAW disposal facility, now referred to as the Integrated Disposal Facility (IDF), for the safe disposal of vitrified Hanford Site tank waste.

Commissioning of indigenous microwave test facility for development and pilot production of 2 MW S-band magnetrons

International Nuclear Information System (INIS)

Shrivastava, Purushottam; Wanmode, Y.D.; Hannurkar, P.R.; Prasad, Sharda

2005-01-01

To have self reliance in the field of microwave devices and to have consistent supply of pulsed magnetrons for the Indian accelerator programme. CAT initiated development of 2 MW S-Band pulsed magnetrons in collaboration with CEERI, Pilani. The design, development and testing of the microwave test facilities for ageing. conditioning and performance testing of Indian magnetrons, was successfully done by CAT indigenously. After the rigorous testing. the test facility was shifted, installed and commissioned at CEERI, Pilani by CAT. Over a period of 10 years, nine prototypes were aged and tested, two magnetrons were life tested and five magnetrons under production programme have been successfully conditioned and tested. Testing of more numbers is underway. The system details. commissioning aspects are discussed, results are shown. (author)

Calibrating the radiation detector of the ventilation of a PET radiopharmaceutical production facility

International Nuclear Information System (INIS)

Lacerda, Marco Aurelio de Sousa; Tavares, Jose Carlos Freitas; Silva, Juliana Batista da

2011-01-01

The aim of this work is to demonstrate a new methodology of estimating the calibration factor of the ventilation duct of a PET radiopharmaceutical facility. The proposed methodology was studied to minimize contamination risks for the workers, as well as the uncertainties attributed to the gas sampling. The studied facility was the Development Centre of Nuclear Technology (CDTN/CNEN) in Belo Horizonte, Brazil. It was performed 3 consecutive irradiations with normal water (H 2 16 O) for production of nitrogen-13 to estimate the calibration factor of the detector located in the chimney of the facility. The readings of the detector were registered by the online radiation monitoring system (MEDISMARTS) during the transfer of the irradiated liquid until the count rate decreased for the background (BG) levels. The remaining activity of the water from the vial was measured and the decay corrected to the beginning of the transfer of the activity. The mean calibration factor estimated was (3.6 +- 0.5) kBq . m -3 . cps -1 . The maximum activities registered in the three irradiations were, respectively, 278 s, 370 s and 366 s after transferring of the activity to the hot cell. The conservative assumptions adopted and the values found for the calibration factor, which were close to the manufacturer published data, permit to estimate, safely, the discharges of radioactive gases in the installation. (author)

A performance goal-based seismic design philosophy for waste repository facilities

International Nuclear Information System (INIS)

Hossain, Q.A.

1994-01-01

A performance goal-based seismic design philosophy, compatible with DOE's present natural phenomena hazards mitigation and open-quotes graded approachclose quotes philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed

Process for decontamination of surfaces in an facility of natural uranium hexafluoride production (UF6)

International Nuclear Information System (INIS)

Almeida, Claudio C. de; Silva, Teresinha M.; Rodrigues, Demerval L.; Carneiro, Janete C.G.G.

2017-01-01

The experience acquired in the actions taken during the decontamination process of an IPEN-CNEN / SP Nuclear and Energy Research Institute facility, for the purpose of making the site unrestricted, is reported. The steps of this operation involved: planning, training of facility operators, workplace analysis and radiometric measurements. The facility had several types of equipment from the natural uranium hexafluoride (UF 6 ) production tower and other facility materials. Rules for the transportation of radioactive materials were established, both inside and outside the facility and release of materials and installation

18 CFR 292.209 - Exceptions from requirements for hydroelectric small power production facilities located at a new...

Science.gov (United States)

2010-04-01

... requirements for hydroelectric small power production facilities located at a new dam or diversion. 292.209... Exceptions from requirements for hydroelectric small power production facilities located at a new dam or... the Federal Power Act, at which non-Federal hydroelectric development is permissible; or (2) An...

77 FR 64999 - Guidance for Industry: Necessity of the Use of Food Product Categories in Food Facility...

Science.gov (United States)

2012-10-24

...] Guidance for Industry: Necessity of the Use of Food Product Categories in Food Facility Registrations and... industry entitled ``Necessity of the Use of Food Product Categories in Food Facility Registrations and... made available a draft guidance entitled ``Guidance for Industry: Necessity of the Use of Food [[Page...

Radiological performance assessment for the Z-Area Saltstone Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Cook, J.R.; Fowler, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-12-18

This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements.

Radiological performance assessment for the Z-Area Saltstone Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.; Fowler, J.R.

1992-01-01

This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements

Improvement of irradiation facilities performance in JMTR

International Nuclear Information System (INIS)

Kanno, Masaru; Sakurai, Susumu; Honma, Kenzo; Sagawa, Hisashi; Nakazaki, Chousaburo

1999-01-01

Various kinds of irradiation facilities are installed in the JMTR for the purpose of irradiation tests on fuels and materials and of producing radioisotopes. The irradiation facilities have been improved so far at every opportunity of new irradiation requirements and of renewing them which reached the design lifetime. Of these irradiation facilities, improvements of the power ramping test facility (BOCA/OSF-1 facility) and the hydraulic rabbit No.2 (HR-2 facility) are described here. (author)

Radiological performance assessment for the E-Area Vaults Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.

2000-01-01

This report is the first revision to ''Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0

10 CFR 170.21 - Schedule of fees for production and utilization facilities, review of standard referenced design...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Schedule of fees for production and utilization facilities, review of standard referenced design approvals, special projects, inspections and import and export... AMENDED Schedule of Fees § 170.21 Schedule of fees for production and utilization facilities, review of...

Design of a Production Process to Enhance Optical Performance of 3(omega) Optics

International Nuclear Information System (INIS)

Prasad, R.R.; Bruere, J.R.; Halpin, J.; Lucero, P.; Mills, S.; Bernacil, M.; Hackel, R.P.

2003-01-01

Using the Phoenix pre-production conditioning facility we have shown that raster scanning of 3ω optics using a XeF excimer laser and mitigation of the resultant damage sites with a CO 2 laser can enhance their optical damage resistance. Several large-scale (43 cm x 43 cm) optics have been processed in this facility. A production facility capable of processing several large optics a week has been designed based on our experience in the pre-production facility. The facility will be equipped with UV conditioning lasers--351-nm XeF excimer lasers operating at 100 Hz and 23 ns. The facility will also include a CO 2 laser for damage mitigation, an optics stage for raster scanning large-scale optics, a damage mapping system (DMS) that images large-scale optics and can detect damage sites or precursors as small as ∼ 15 (micro)m, and two microscopes to image damage sites with ∼ 5 (micro)m resolution. The optics will be handled in a class 100 clean room, within the facility that will be maintained at class 1000

ARM Climate Research Facility Quarterly Value-Added Product Report

Energy Technology Data Exchange (ETDEWEB)

Sivaraman, Chitra

2014-01-14

The purpose of this report is to provide a concise status update for value-added products (VAP) implemented by the Atmospheric Radiation Measurement Climate Research Facility. The report is divided into the following sections: (1) new VAPs for which development has begun, (2) progress on existing VAPs, (3) future VAPs that have been recently approved, (4) other work that leads to a VAP, and (5) top requested VAPs from the archive.

FOAM FORMATION IN THE SALTSTONE PRODUCTION FACILITY: EVALUATION OF SOURCES AND MITIGATION

Energy Technology Data Exchange (ETDEWEB)

Cozzi, A.

2011-01-18

The Saltstone Production Facility receives waste from Tank 50H for treatment. Influents into Tank 50H include the Effluent Treatment Project waste concentrate, H-Canyon low activity waste and General Purpose Evaporator bottoms, Modular Caustic Side Solvent Extraction Unit decontaminated salt solution, and salt solution from the Deliquification, Dissolution and Adjust campaign. Using the Waste Characterization System (WCS), this study tracks the relative amounts of each influent into Tank 50H, as well as the total content of Tank 50H, in an attempt to identify the source of foaming observed in the Saltstone Production Facility hopper. Saltstone has been using antifoam as part of routine processing with the restart of the facility in December 2006. It was determined that the maximum admix usage in the Saltstone Production Facility, both antifoam and set retarder, corresponded with the maximum concentration of H-Canyon low activity waste in Tank 50H. This paper also evaluates archived salt solutions from Waste Acceptance Criteria analysis for propensity to foam and the antifoam dosage required to mitigate foaming. It was determined that Effluent Treatment Project contributed to the expansion factor (foam formation) and General Purpose Evaporator contributed to foaminess (persistence). It was also determined that undissolved solids contribute to foam persistence. It was shown that additions of Dow Corning Q2-1383a antifoam reduced both the expansion factor and foaminess of salt solutions. The evaluation of foaming in the grout hopper during the transition from water to salt solution indicated that higher water-to-premix ratios tended to produce increased foaming. It was also shown that additions of Dow Corning Q2-1383a antifoam reduced foam formation and persistence.

Validation of the cleaning and sanitization method for radiopharmaceutical production facilities

International Nuclear Information System (INIS)

Robles, Anita; Morote, Mario; Moore, Mariel; Castro, Delcy; Paragulla, Wilson; Novoa, Carlos; Otero, Manuel; Miranda, Jesus; Herrera, Jorge; Gonzales, Luis

2014-01-01

A protocol for the cleaning and sanitization method for radiopharmaceutical production facilities has been designed and developed for the inner surface of the hot cells for the production of Sodium Pertechnetate Tc-99m and Sm-153 EDTMP, considering an extreme situation for each hot cell. Cleaning is performed with double-distilled water and sanitation with two disinfectant solutions, 70 % isopropyl alcohol and 3 % hydrogen peroxide in alternate weeks. Microbiological analysis of sanitized surfaces were made after 20 minutes and 48 hours for the hot cell of Tc-99m and 72 hours for the hot cell of EDTMP Sm-153 in 3 consecutive tests by the method of direct contact with plates containing culture medium, made for each sampling point (6 in the first and five in the second). The results showed that the microbial load on surfaces sanitized was below acceptable limits and that the lifetime of cleaning and sanitization is 48 hours for the hot cell of Tc-99m and 72 hours for the one of EDTMP-Sm-153. As a conclusion, the method of cleaning and sanitization is effective to reduce or eliminate microbial contamination therefore, the process is validated. (authors).

The national ignition facility performance status

Energy Technology Data Exchange (ETDEWEB)

Haynam, C.; Auerbach, J.; Bowers, M.; Di-Nicola, J.M.; Dixit, S.; Erbert, G.; Heestand, G.; Henesian, M.; Jancaitis, K.; Manes, K.; Marshall, C.; Mehta, N.; Nostrand, M.; Orth, C.; Sacks, R.; Shaw, M.; Sutton, S.; Wegner, P.; Williams, W.; Widmayer, C.; White, R.; Yang, S.; Van Wonterghem, B. [Lawrence Livermore National Laboratory, Livermore, CA (United States)

2006-06-15

The National Ignition Facility (NIF) laser has been designed to support high energy density science, including the demonstration of fusion ignition through Inertial Confinement. NIF operated a single 'quad' of 4 beams from December 2002 through October 2004 in order to gain laser operations experience, support target experiments, and demonstrate laser performance consistent with NIF's design requirement. During this two-year period, over 400 Main Laser shots were delivered at 1{omega} to calorimeters for diagnostic calibration purposes, at 3{omega} to the Target Chamber, and at 1{omega}, 2{omega}, and 3{omega} to the precision diagnostic system (PDS). The PDS includes its own independent single beam transport system, NIF design frequency conversion hardware and optics, and laser sampling optics that deliver light to a broad range of laser diagnostics. Highlights of NIF laser performance will be discussed including the results of high energy 2{omega} and 3{omega} experiments, the use of multiple focal spot beam conditioning techniques, the reproducibility of laser performance on multiple shots, the generation on a single beam of a 3{omega} temporally shaped ignition pulse at full energy and power, and recent results on full bundle (8 beamline) performance. NIF's first quad laser performance meets or exceeds NIF's design requirements. (authors)

The National Ignition Facility Performance Status

Energy Technology Data Exchange (ETDEWEB)

Haynam, C; Auerbach, J; Nicola, J D; Dixit, S; Heestand, G; Henesian, M; Jancaitis, K; Manes, K; Marshall, C; Mehta, N; Nostrand, M; Orth, C; Sacks, R; Shaw, M; Sutton, S; Wegner, P; Williams, W; Widmayer, C; White, R; Yang, S; Van Wonterghem, B

2005-08-30

The National Ignition Facility (NIF) laser has been designed to support high energy density science (HEDS), including the demonstration of fusion ignition through Inertial Confinement. NIF operated a single ''quad'' of 4 beams from December 2002 through October 2004 in order to gain laser operations experience, support target experiments, and demonstrate laser performance consistent with NIF's design requirement. During this two-year period, over 400 Main Laser shots were delivered at 1{omega} to calorimeters for diagnostic calibration purposes, at 3{omega} to the Target Chamber, and at 1{omega}, 2{omega}, and 3{omega} to the Precision Diagnostics System (PDS). The PDS includes its own independent single beam transport system, NIF design frequency conversion hardware and optics, and laser sampling optics that deliver light to a broad range of laser diagnostics. Highlights of NIF laser performance will be discussed including the results of high energy 2{omega} and 3{omega} experiments, the use of multiple focal spot beam conditioning techniques, the reproducibility of laser performance on multiple shots, the generation on a single beam of a 3{omega} temporally shaped ignition pulse at full energy and power, and recent results on full bundle (8 beamline) performance. NIF's first quad laser performance meets or exceeds NIF's design requirements.

Emulation and Control of Slugging Flows in a Gas-Lifted Offshore Oil Production Well Through a Lab-sized Facility

DEFF Research Database (Denmark)

Jepsen, Kasper Lund; Hansen, Leif; Mai, Christian

2013-01-01

flow and pressures in the production well system, which is referred to as the slugging flow problem. This instability is mainly due to the casing-heading mechanism. This work investigates the possibility to use a feedback control for stabilizing the production operation without sacrificing...... the production capability. A labsized production well system is constructed in an economic manner. Afterwards, a simple nonlinear model is derived according to physical principles and then verified with the experimental facility. A observer-based state feedback control is designed to handle the potential...... slugging problem. The developed controller manipulates the openness degree of the production choke based on feedback a number of pressure measurements. The current simulation results showed satisfactory control performances by stabilizing the system operation at some relatively large production rate which...

Environmental aspects based on operation performance of nuclear fuel fabrication facilities

International Nuclear Information System (INIS)

2001-07-01

This publication was prepared within the framework of the IAEA Project entitled Development and Upgrading of Guidelines, Databases and Tools for Integrating Comparative Assessment into Energy System Analysis and Policy Making, which included the collection, review and input of data into a database on health and environmental impacts related to operation of nuclear fuel cycle facilities. The objectives of the report included assembling environmental data on operational performance of nuclear fabrication facilities in each country; compiling and arranging the data in a database, which will be easily available to experts and the public; and presenting data that may be of value for future environmental assessment of nuclear fabrication facilities

CERN n_TOF Facility: Performance Report

CERN Document Server

n_TOF, Collaboration

2003-01-01

This report describes the basic characteristics and the performances of the new neutron time-of-flight facility, n_TOF, recently set in operation at CERN. The report is divided into three parts. In the first part, a description of the characteristics of the installation, up to the experimental area (EAR-1) is presented. This includes the proton extraction line from the PS, the spallation module (the lead target and its cooling and moderation systems) and the neutron beam window. A description of the neutron time-of-flight line with the vacuum system, shielding and collimation is also included in this part. In the second part, matters related to safety issues, including radiation and dose estimates and measurements in the target area are discussed. In the third part, a description of the experimental set up in EAR-1 is presented. This includes the data acquisition systems, the beam monitoring systems and the detectors for capture and for fission measurements. The measurements performed in order to derive the m...

Development of the radioisotope production facility for the HANARO

International Nuclear Information System (INIS)

Lee, Ji Bok; Wu, J. S.; Baik, S. T.

1998-06-01

Hot cell and related facilities were developed in the RI production building of the HANARO. 1. development of concrete H/C and related components 2. development of lead H/C and related components 3. development of the hydraulic transfer system 4. development of radiation monitoring system 5. development of purification system for Co-60 storage pool 6. development of the fire fighting system for H/C 7. development of the experimental equipment. (author). 15 figs

One year's experience of the WA medical cyclotron and radiopharmaceutical production facility

International Nuclear Information System (INIS)

DeRoach, J.; Tuchyna, T.; Jones, C.; Price, R.

2004-01-01

Full text: The WA PET Centre Medical Cyclotron, a facility novel in Western Australia, produced its first bolus of FDG for patient injection for PET scanning in August 2003. This paper describes the methodology and practices employed during the past 12 months for ensuring that reliable routine provision of FDG is maintained, in parallel with facilitating the development and production of achievable new radiopharmaceuticals. An FDG production team of six staff and, a maintenance and development team of 4 staff were created from the 3.4 staff specifically recruited for this service and from incumbent staff. Teams were also set up to carry out development projects related to the service. Training procedures were created under the department's ISO9001:2000 accreditation system for the certification of production and maintenance staff. Practices and documentation systems were put in place in anticipation of a pending cGMP audit. Several unplanned major changes to equipment and infrastructure were necessary post commissioning. These changes included purchase of a different FDG synthesis module from that originally supplied, and modifications to engineering services, including changes to air conditioning, changes to supply of vacuum and upgrading of drainage in the laboratory area. A device for the measurement of end of bombardment yield was built, so that the efficiencies of the various synthesis modules could be accurately determined. Strict radiation protection procedures were put in place. All staff were provided with luxels and finger TLDs for monthly reporting of their radiation levels, as well as electronic monitors for real-time monitoring. From August 2003 to June 2004 (11 months) 2229 FDG patient doses were produced and dispensed by this facility. An average of 8.0 patient doses per available working day were dispensed during the 2003 period, rising to 11.1 patient doses per day in 2004. Several 11 NH3 doses were also delivered. The cyclotron was unavailable for

ARM Climate Research Facility Quarterly Value-Added Product Report

Energy Technology Data Exchange (ETDEWEB)

Sivaraman, C. [DOE ARM Climate Research Facility, Washington, DC (United States)

2016-10-01

The purpose of this report is to provide a concise status update for Value-Added Products (VAPs) implemented by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new VAPs for which development has begun; (2) progress on existing VAPs; (3) future VAPs that have been recently approved; (4) other work that leads to a VAP; (5) top requested VAPs from the ARM Data Archive; and (6) a summary of VAP and data releases to production and evaluation. New information is highlighted in blue text. New information about processed data by the developer is highlighted in red text. The upcoming milestones and dates are highlighted in green.

A combined approach of simulation and analytic hierarchy process in assessing production facility layouts

Science.gov (United States)

Ramli, Razamin; Cheng, Kok-Min

2014-07-01

One of the important areas of concern in order to obtain a competitive level of productivity in a manufacturing system is the layout design and material transportation system (conveyor system). However, changes in customers' requirements have triggered the need to design other alternatives of the manufacturing layout for existing production floor. Hence, this paper discusses effective alternatives of the process layout specifically, the conveyor system layout. Subsequently, two alternative designs for the conveyor system were proposed with the aims to increase the production output and minimize space allocation. The first proposed layout design includes the installation of conveyor oven in the particular manufacturing room based on priority, and the second one is the one without the conveyor oven in the layout. Simulation technique was employed to design the new facility layout. Eventually, simulation experiments were conducted to understand the performance of each conveyor layout design based on operational characteristics, which include predicting the output of layouts. Utilizing the Analytic Hierarchy Process (AHP), the newly and improved layout designs were assessed before the final selection was done. As a comparison, the existing conveyor system layout was included in the assessment process. Relevant criteria involved in this layout design problem were identified as (i) usage of space of each design, (ii) operator's utilization rates, (iii) return of investment (ROI) of the layout, and (iv) output of the layout. In the final stage of AHP analysis, the overall priority of each alternative layout was obtained and thus, a selection for final use by the management was made based on the highest priority value. This efficient planning and designing of facility layout in a particular manufacturing setting is able to minimize material handling cost, minimize overall production time, minimize investment in equipment, and optimize utilization of space.

NUMERICAL FLOW AND TRANSPORT SIMULATIONS SUPPORTING THE SALTSTONE FACILITY PERFORMANCE ASSESSMENT

Energy Technology Data Exchange (ETDEWEB)

Flach, G.

2009-02-28

The Saltstone Disposal Facility Performance Assessment (PA) is being revised to incorporate requirements of Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), and updated data and understanding of vault performance since the 1992 PA (Cook and Fowler 1992) and related Special Analyses. A hybrid approach was chosen for modeling contaminant transport from vaults and future disposal cells to exposure points. A higher resolution, largely deterministic, analysis is performed on a best-estimate Base Case scenario using the PORFLOW numerical analysis code. a few additional sensitivity cases are simulated to examine alternative scenarios and parameter settings. Stochastic analysis is performed on a simpler representation of the SDF system using the GoldSim code to estimate uncertainty and sensitivity about the Base Case. This report describes development of PORFLOW models supporting the SDF PA, and presents sample results to illustrate model behaviors and define impacts relative to key facility performance objectives. The SDF PA document, when issued, should be consulted for a comprehensive presentation of results.

Recent performance of the TRIUMF cyclotron and status of the facility

International Nuclear Information System (INIS)

Dutto, G.; Blackmore, E.W.; Carey, J.

1995-09-01

In December 1994, TRIUMF celebrated 20 years of operation. The peak intensity has been increased over the years to the present level of approximately 200 μA on beam line 1A. Polarized beam currents in excess of 20 μA are available although most users prefer lower intensity, higher quality slit-tailored polarized beams. The cyclotron simultaneously extracts three beams: one at 500 MeV for meson production, a lower intensity beam on beam line 4 for nuclear physics, nuclear chemistry, or astrophysics experiments, and a low energy beam (65-120 MeV, from a few nA up to 100 μA) on beam line 2C for isotope production or proton therapy. The yearly total integrated extracted beam current is now in the order of 600 mAh per year. Beam delivery is in excess of 5000 hours per year with beam availability consistently around 90%, serving as many as 8 experimental stations simultaneously. An additional simultaneous extraction line is planned for the new ISAC facility. With the present polarized beam current capability, the operation of polarized beams for the beam line 4 experiments will be possible simultaneously with the operation of the ISAC facility up to levels of 20 μA, 500 MeV, on target. Recent facility developments will also be reported. (author)

performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Tavares, Renato L. A.; Filho, Josélio S. M., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear. Divisão de Normas e Segurança Física; Fontes, Gladson S.; Fiel, J.C.B., E-mail: gsfontes@hotmail.com, E-mail: fiel@ime.eb.br [Instituto Militar de Engenharia (SE-7/IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

2017-07-01

This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

International Nuclear Information System (INIS)

Tavares, Renato L. A.; Filho, Josélio S. M.; Fontes, Gladson S.; Fiel, J.C.B.

2017-01-01

This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

Lean coding machine. Facilities target productivity and job satisfaction with coding automation.

Science.gov (United States)

Rollins, Genna

2010-07-01

Facilities are turning to coding automation to help manage the volume of electronic documentation, streamlining workflow, boosting productivity, and increasing job satisfaction. As EHR adoption increases, computer-assisted coding may become a necessity, not an option.

Evaluation of rubber seal products for gamma facilities

International Nuclear Information System (INIS)

Sobhy, M.S.; Shafy, M.A.; Shahin, F.

2005-01-01

Ageing behavior by employing the prolonged exposures of high-energy radiation such as gamma-rays on the physicomechanical properties of some rubber seal products are studied. The proposed binary-rubber blends, SBR/NBR, EPDM/NBR and EPDM/EPM. have overcome their problem of inhomogeneity and incompatibility between the two rubber phases. Such enhancements are acquired by either the replacement of part of NBR by SBR during mastication, or the incorporation of maleic anhydride. Results show that the EPDM/EPM rubber blend has possessed the radiation resistance property towards the deterioration due to higher gamma-irradiation dose. The SEM images have c early observed the role of the used antioxidant, where a thin film is usually produced, degraded; with the appearance of surface cracks, and repaired with further gamma-irradiation up to high doses. Such enhancement is necessary for the definition of the requirements to be put on rubber seal materials. Finally, these products ought to assure the quality control in production and evaluate their application suitability that may employ in the pneumatic system in gamma facility

Ethanol production in small- to medium-size facilities

Science.gov (United States)

Hiler, E. A.; Coble, C. G.; Oneal, H. P.; Sweeten, J. M.; Reidenbach, V. G.; Schelling, G. T.; Lawhon, J. T.; Kay, R. D.; Lepori, W. A.; Aldred, W. H.

1982-04-01

In early 1980 system design criteria were developed for a small-scale ethanol production plant. The plant was eventually installed on November 1, 1980. It has a production capacity of 30 liters per hour; this can be increased easily (if desired) to 60 liters per hour with additional fermentation tanks. Sixty-six test runs were conducted to date in the alcohol production facility. Feedstocks evaluated in these tests include: corn (28 runs); grain sorghum (33 runs); grain sorghum grits (1 run); half corn/half sorghum (1 run); and sugarcane juice (3 runs). In addition, a small bench-scale fermentation and distillation system was used to evaluate sugarcane and sweet sorghum feedstocks prior to their evaluation in the larger unit. In each of these tests, evaluation of the following items was conducted: preprocessing requirements; operational problems; conversion efficiency (for example, liters of alcohol produced per kilogram of feedstock); energy balance and efficiency; nutritional recovery from stillage; solids separation by screw press; chemical characterization of stillage including liquid and solids fractions; wastewater requirements; and air pollution potential.

THAI test facility for experimental research on hydrogen and fission product behaviour in light water reactor containments

Energy Technology Data Exchange (ETDEWEB)

Gupta, S., E-mail: gupta@becker-technologies.com [Becker Technologies GmbH, Koelner Strasse 6, 65760 Eschborn (Germany); Schmidt, E.; Laufenberg, B. von; Freitag, M.; Poss, G. [Becker Technologies GmbH, Koelner Strasse 6, 65760 Eschborn (Germany); Funke, F. [AREVA GmbH, P.O. Box 1109, 91001 Erlangen (Germany); Weber, G. [Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Forschungszentrum, Boltzmannstraße 14, 85748 Garching (Germany)

2015-12-01

hydraulics, gas distribution) and ISP-49 (hydrogen combustion), EU-SARNET/SARNET2 code-benchmark exercises involving THAI data on iodine/surface interactions, iodine mass transfer, passive autocatalytic recombiner performance, iodine oxide behaviour and iodine transport in multi-compartment behaviour. The present paper provides an overview of the THAI experiments related to hydrogen and fission products issues performed in the frame of national and international projects. From the comprehensive THAI experimental database, a selection of typical results is presented to illustrate the multi-functionality of the THAI facility and the broad variety of the experimental investigations.

Effects of facility backpressure on the performance and plume of a Hall thruster

Science.gov (United States)

Walker, Mitchell Louis Ronald

2005-07-01

This dissertation presents research aimed at understanding the relationship between facility background pressure, Hall thruster performance, and plume characteristics. Due to the wide range of facilities used in Hall thruster testing, it is difficult for researchers to make adequate comparisons between data sets because of both dissimilar instrumentation and backpressures. The differences in the data sets are due to the ingestion of background gas into the Hall thruster discharge channel and charge-exchange collisions in the plume. Thus, this research aims to understand facility effects and to develop the tools needed to allow researchers to obtain relevant plume and performance data for a variety of chambers and backpressures. The first portion of this work develops a technique for calibrating a vacuum chamber in terms of pressure to account for elevated backpressures while testing Hall thrusters. Neutral gas background pressure maps of the Large Vacuum Test Facility are created at a series of cold anode flow rates and one hot flow rate at two UM/AFRL P5 5 kW Hall thruster operating conditions. These data show that a cold flow pressure map can be used to approximate the neutral background pressure in the chamber with the thruster in operation. In addition, the data are used to calibrate a numerical model that accurately predicts facility backpressure within a vacuum chamber of specified geometry and pumping speed. The second portion of this work investigates how facility backpressure influences the plume, plume diagnostics, and performance of the P5 Hall thruster. Measurements of the plume and performance characteristics over a wide range of pressures show that ingestion, a decrease in the downstream plasma potential, and broadening of the ion energy distribution function cause the increase in thrust with backpressure. Furthermore, a magnetically-filtered Faraday probe accurately measures ion current density at elevated operating pressures. The third portion of

Investigation of the radionuclide inventory and the production yields of the target stacks at the PEFP radioisotope production facility

International Nuclear Information System (INIS)

Yoon, Sang-Pil; Hong, In-Seok; Cho, Yong-Sub

2010-01-01

The Proton Engineering Frontier Project (PEFP) will construct a radioisotope production facility by using the nuclear reaction between the 100-MeV proton beam and the solid target. For investigating the radionuclide inventory and the production yield of the radioisotope production facility, we have optimized the thickness of the prototype target stacks by using a SRIM calculation. The target stacks consist of RbCl encapsulated in inconel alloy, Zn metal, and Ga metal encapsulated in niobium. Typical beam parameters were 300 μA and 95 hours. An inventory of all generated radionuclide activities is mandatory in order to prepare the operation scenario and design the hot cell. The Monte Carlo code MCNPX was used to investigate what radionuclide is generated. The obtained radionuclide inventory indicated that about 100 radionuclides were generated and that the total radioactivity of the irradiated target stacks was 1324.1 Ci at the end of the bombardment. The production yields of Sr-82, Cu-67, and Ge-68 were 3.79 Ci, 2.74 Ci, and 1.23 Ci at the end of the bombardment.

Experiments on injection performance of SMART ECC facility using SWAT

Energy Technology Data Exchange (ETDEWEB)

Cho, Young Il; Cho, Seok; Ko, Yung Joo; Min, Kyoung Ho; Shin, Yong Cheol; Kwon, Tae Soon; Yi, Sung Jae; Lee, Won Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

SMART (System-integrated Modular Advanced ReacTor), an advanced integrated PWR is now in the under developing stages by KAERI. Such integral PWR excludes large-size piping of the primary system of conventional PWR and incorporates the SGs into RPV, which means no LBLOCA could occur in SMART. Therefore, the SBLOCA is considered as a major DBA (Design Basis Accident) in SMART and it is mainly analyzed by using TASS/SMR computer code. The TASS/SMR code should be validated using experimental data from both Integral Effect Test and Separate Effect Test facilities. To investigate injection performance of the ECC system, on SET facility, named as SWAT (SMART ECC Water Asymmetric Two-phase choking test facility), has been constructed at KAERI. The SWAT simulates the geometric configurations of the SG-side upper downcomer annulus and ECCSs of those of SMART. It is designed based on the modified linear scaling method with a scaling ratio of 1/5, to preserve the geometrical similarity and minimize gravitational distortion. The purpose of the SWAT tests is to investigate the safety injection performance, such as the ECC bypass in the downcomer and the penetration rate in the core during the SBLOCA, and hence to produce experimental data to validate and the prediction capability of safety analysis codes, TASS/SMR

Comparing the dynamic performance of wastewater treatment systems: A metafrontier Malmquist productivity index approach.

Science.gov (United States)

Molinos-Senante, María; Hernández-Sancho, Francesc; Sala-Garrido, Ramón

2015-09-15

The assessment of productivity change of wastewater treatment plants (WWTPs) is essential to improve the performance over time of the facilities evaluated. This study assessed and compared the productivity growth of WWTPs operating with non-homogeneous technologies. The metafrontier Malmquist productivity index (MMPI) was computed for a sample of 99 WWTPs encompassing 4 alternative technologies: activated sludge (AS), aerated lagoon (AL), trickling filter (TF) and rotating biological contactor (BD). The results indicated that, on average, WWTPs with AS and BD exhibited better performance over time than WWTPs with AL and TF. The MMPI indicates that, over the period 2007-2009, the productivity rose by 0.9% and 0.3% for AS and BD technologies, respectively, whilst for the AL and TF processes, the productivity decreased by 0.5% and 2.2%, respectively. The decomposition of the MMPI into efficiency change (EC) and technical change (TC) illustrated that EC was a positive driver of productivity change for WWTPs that use AS, whilst TC contributed positively to the productivity growth of WWTPs using AL and BD. Several policy implications to help managers make informed decisions were drawn from our empirical analysis. Copyright © 2015 Elsevier Ltd. All rights reserved.

W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance

International Nuclear Information System (INIS)

Meyers, S.C.; Henderson, J.M.

1980-05-01

The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses their development, fabrication, and performance in the W-1 experiment

Preliminary scoping safety analyses of the limiting design basis protected accidents for the Fast Flux Test Facility tritium production core

International Nuclear Information System (INIS)

Heard, F.J.

1997-01-01

The SAS4A/SASSYS-l computer code is used to perform a series of analyses for the limiting protected design basis transient events given a representative tritium and medical isotope production core design proposed for the Fast Flux Test Facility. The FFTF tritium and isotope production mission will require a different core loading which features higher enrichment fuel, tritium targets, and medical isotope production assemblies. Changes in several key core parameters, such as the Doppler coefficient and delayed neutron fraction will affect the transient response of the reactor. Both reactivity insertion and reduction of heat removal events were analyzed. The analysis methods and modeling assumptions are described. Results of the analyses and comparison against fuel pin performance criteria are presented to provide quantification that the plant protection system is adequate to maintain the necessary safety margins and assure cladding integrity

Breathing new life into your production irradiator the case for reinvesting in your facility

International Nuclear Information System (INIS)

Aube, Robert; Wynnyk, Mike

2002-01-01

This paper focuses on one of the important technology issues facing the gamma processing industry today: that of strategically planning for extending the useful life of a production irradiator. Production irradiator owners are typically faced with the difficult question of whether or not to significantly reinvest in their facilities after 15-20 years of service. At this point in time the irradiator has likely provided many years of safe, reliable service and has paid for itself many times over. As the equipment ages, it may become less reliable, due to wear and maintenance practices, and more costly to operate. The cost of refurbishing the equipment may be significant and the downtime required to complete the refurbishment is also likely to be a challenge. This makes it essential to present a clear and rational justification for reinvesting in the facility. There has been a growing trend in recent years for irradiator owners to refurbish or upgrade their facilities. This trend is driven by the need to keep the facilities operating efficiently and safely as well as by the desire to take advantage of advancements that have occurred in the technology over the years. These advancements can enhance equipment efficiency, improve operational effectiveness and maintain or exceed quality assurance requirements. This paper illustrates the value of reinvesting in irradiator facilities, and highlights the significant benefits derived

Future technological and economic performance of IGCC and FT production facilities with and without CO2 capture: Combining component based learning curve and bottom-up analysis

NARCIS (Netherlands)

Knoope, M.M.J.; Meerman, J.C.; Ramirez, C.A.; Faaij, A.P.C.

2013-01-01

This study aims to investigate the technological and economic prospects of integrated gasification facilities for power (IGCC) and Fischer–Tropsch (FT) liquid production with and without CCS over time. For this purpose, a component based experience curve was constructed and applied to identify the

Production facility site selection factors for Texas value-added wood producers

Science.gov (United States)

Judd H. Michael; Joanna Teitel; James E. Granskog

1998-01-01

Value-added wood products manufacturers serve an important role in the economies of many U.S. regions and are therefore sought after by entities such as economic development agencies. The reasons why certain locations for a prospective prodution facility would be more attractive to secondary wood industry producers are not clearly understood. Therefore, this research...

75 FR 47592 - Final Test Guideline; Product Performance of Skin-applied Insect Repellents of Insect and Other...

Science.gov (United States)

2010-08-06

.... Crystal Dr., Arlington, VA. The hours of operation of this Docket Facility are from 8:30 a.m. to 4 p.m... has been working to revise this Product Performance Test Guideline since it was published as a... further strengthening the scientific and ethical conduct of this kind of research; these have been...

Performance assessment handbook for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Seitz, R.R.; Garcia, R.S.; Kostelnik, K.M.; Starmer, R.J.

1992-02-01

Performance assessments of proposed low-level radioactive waste disposal facilities must be conducted to support licensing. This handbook provides a reference document that can be used as a resource by management and staff responsible for performance assessments. Brief discussions describe the performance assessment process and emphasize selected critical aspects of the process. References are also provided for additional information on many aspects of the performance assessment process. The user's manual for the National Low-Level Waste Management Program's Performance Assessment Center (PAC) on the Idaho National Engineering Laboratory Cray computer is included as Appendix A. The PAC provides users an opportunity to experiment with a number of performance assessment computer codes on a Cray computer. Appendix B describes input data required for 22 performance assessment codes

Annual report on experimental operations and maintenance of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system in 2004 fiscal year (Contract research)

International Nuclear Information System (INIS)

Hayashi, Koji; Ohashi, Hirofumi; Morisaki, Norihiro; Kato, Michio; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Takada, Shoji; Inagaki, Yoshiyuki

2006-03-01

This is annual report on the experimental test operations and maintenances of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system in 2004 fiscal year. The improvement work of catalyst dust filter in combustion system was performed in May 2004, and the performance was confirmed. The sixth experimental test operation was performed from June to July 2004. Periodic inspections on boiler equipment and high-pressure gas production facilities were performed from end of July to September 2004. The seventh experimental test operation was performed from October to December 2004 for chemical reaction shutdown test. From the results, a behavior of the helium-gas cooling system, consists of steam generator and radiator, during chemical reaction shutdown was confirmed. This report is summarized with the outline and the results of the test, maintenance works and inspections, and operation records in mentioned above. (author)

Model business plan for a sterile insect production facility

International Nuclear Information System (INIS)

2008-01-01

For over 50 years the sterile insect technique (SIT) is a pest control strategy which has been used for eradication, and more recently for suppression, containment and prevention, of unwanted insect pest populations. Examples of successful applications of SIT, almost always applied in conjunction with other control methods in an area-wide integrated approach, are available from around the world. The development and application of SIT has relied overwhelmingly on public or donor initiative and funding throughout its history, although the private sector has always been involved as participants, cooperators or partners in funding. The demand for SIT, and therefore the market for sterile insects, has increased in recent years. This increase coincides with the introduction of new pests through the expansion of global trade and, at the same time, widespread pressure to find alternatives to pesticides. Recent improvements in the technology supporting SIT facilitate its application and suggest lower costs can be achieved. The conditions are therefore met for a greater commercialization of the technique to bring it in line with other pest control approaches that are fully integrated into a market approach. Several challenges arise, however, in pursuing sterile insect production as a commercial venture, ranging from intellectual property protection to pricing of the product. Routine insurance requirements, for instance, are complicated by the biological aspects of the business. This report is aimed at facilitating private sector involvement in the production of sterile insects for use in pest control. It provides guidelines and tools to support the development of specific business plans for a new SIT venture. By providing an international perspective on such issues as initial capital costs and recurring operational expenditures for a sterile insect facility, it may be used to evaluate the feasibility of proceeding with the construction or expansion of a sterile insect

Meeting performance objectives for Low-Level Radioactive Disposal Waste Facility at the Savannah River Site

International Nuclear Information System (INIS)

Taylor, G.E.

1992-01-01

A new Low-Level Radioactive Waste (LLW) disposal facility at the Savannah River Site is presently being constructed. The facility was designed to meet specific performance objectives (derived from DOE Order 5820.2A and proposed EPA Regulation 40CFR 193) in the disposal of containerized Class A and B wastes. The disposal units have been designed as below-grade concrete vaults. These vaults will be constructed using uniquely designed blast furnace slag + fly as concrete mix, surrounded by a highly permeable drainage layer, and covered with an engineered clay cap to provide the necessary environmental isolation of the waste form to meet the stated performance objectives. The concrete mix used in this facility, is the first such application in the United States. These vaults become operational in September 1992 and will become the first active facility of its kind, several years ahead of those planned in the commercial theater. This paper will discuss the selection of the performance objectives and conceptual design

Compendium of Low-Cost Pacific Salmon and Steelhead Trout Production Facilities and Practices in the Pacific Northwest.

Energy Technology Data Exchange (ETDEWEB)

Senn, Harry G.

1984-09-01

The purpose was to research low capital cost salmon and steelhead trout production facilities and identify those that conform with management goals for the Columbia Basin. The species considered were chinook salmon (Oncorhynchus tshawytscha), coho salmon (O. kisutch), sockeye salmon (O. nerka), and steelhead trout (Salmo gairdneri). This report provides a comprehensive listing of the facilities, techniques, and equipment used in artificial production in the Pacific Northwest. (ACR)

Impact of Facilities on Academic Performance of Students with Special Needs in Mainstreamed Public Schools in Southwestern Nigeria

Science.gov (United States)

Fareo, Dorcas Oluremi; Ojo, Olakunbi Olubukola

2013-01-01

Facilities have a great impact on academic performances of students, and inadequate facilities translate to poor performance. The study examined the availability and convenience of the facilities that were provided to students with special educational needs in mainstreamed schools. It ascertained the qualifications of teachers teaching in…

Product, Organizational and Performance Effects of Product Modularity

DEFF Research Database (Denmark)

Boer, Henrike Engele Elisabeth

2014-01-01

beyond these industries. To be able to establish whether firms not part of these industries would experience the same performance effects, survey research will be needed. To support future survey research, this paper proposes an operationalization of product modularity and details the link between...... product modularity and firm performance, to support the future development of measures and hypotheses....

A conversion development program to LEU targets for medical isotope production in the MAPLE Facilities

International Nuclear Information System (INIS)

Malkoske, G.R.

2000-01-01

Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). The molybdenum extraction process from the HEU targets provided predictable, consistent yields for our high-volume molybdenum production process. A reliable supply of HEU for the NRU research reactor targets has enabled MDS Nordion to develop a secure chain of medical isotope supply for the international nuclear medicine community. Each link of the isotope supply chain, from isotope production to patient application, has been established on a proven method of HEU target irradiation and processing. To ensure a continued reliable and timely supply of medical isotopes, the design of the MAPLE facilities was based on our established process - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a program to convert the MAPLE facilities to LEU targets. An initial feasibility study was initiated to identify the technical issues to convert the MAPLE targets from HEU to LEU. This paper will present the results of the feasibility study. It will also describe future challenges and opportunities in converting the MAPLE facilities to LEU targets for large scale, commercial medical isotope production. (author)

Asset management -- Integrated software optimizes production performance

International Nuclear Information System (INIS)

Polczer, S.

1998-01-01

Developments in data collection and retrieval systems to allow timely cost analysis, financial reporting and production management are discussed. One of the most important new OLAP (on-line analytical processing) products is Energy Warehouse which gathers field information from various sources, allows advanced searches, and generates reports previously unavailable in other conventional financial accounting systems. Another OLAP-based system, the Canadian Upstream Energy System (CUES), was developed by the Oracle Corporation and the Calgary-based Applied Terravision Systems (ATS) Inc. CUES combines Oracle's universal data server software development tools with ATS's upstream financial, land, geotechnical and production applications. ATS also developed a product called IDPMARS (Integrated Daily Production Management Accounting Reporting System). It interfaces with CUES to link working interests, government royalties, administration, facility charges, lifting costs, transportation tooling, and customers by integrating field data collection systems with financial accounting

Asset management -- Integrated software optimizes production performance

Energy Technology Data Exchange (ETDEWEB)

Polczer, S.

1998-10-01

Developments in data collection and retrieval systems to allow timely cost analysis, financial reporting and production management are discussed. One of the most important new OLAP (on-line analytical processing) products is Energy Warehouse which gathers field information from various sources, allows advanced searches, and generates reports previously unavailable in other conventional financial accounting systems. Another OLAP-based system, the Canadian Upstream Energy System (CUES), was developed by the Oracle Corporation and the Calgary-based Applied Terravision Systems (ATS) Inc. CUES combines Oracle`s universal data server software development tools with ATS`s upstream financial, land, geotechnical and production applications. ATS also developed a product called IDPMARS (Integrated Daily Production Management Accounting Reporting System). It interfaces with CUES to link working interests, government royalties, administration, facility charges, lifting costs, transportation tooling, and customers by integrating field data collection systems with financial accounting.

Comparison of facility-level methane emission rates from natural gas production well pads in the Marcellus, Denver-Julesburg, and Uintah Basins

Science.gov (United States)

Omara, M.; Li, X.; Sullivan, M.; Subramanian, R.; Robinson, A. L.; Presto, A. A.

2015-12-01

The boom in shale natural gas (NG) production, brought about by advances in horizontal drilling and hydraulic fracturing, has yielded both economic benefits and concerns about environmental and climate impacts. In particular, leakages of methane from the NG supply chain could substantially increase the carbon footprint of NG, diminishing its potential role as a transition fuel between carbon intensive fossil fuels and renewable energy systems. Recent research has demonstrated significant variability in measured methane emission rates from NG production facilities within a given shale gas basin. This variability often reflect facility-specific differences in NG production capacity, facility age, utilization of emissions capture and control, and/or the level of facility inspection and maintenance. Across NG production basins, these differences in facility-level methane emission rates are likely amplified, especially if significant variability in NG composition and state emissions regulations are present. In this study, we measured methane emission rates from the NG production sector in the Marcellus Shale Basin (Pennsylvania and West Virginia), currently the largest NG production basin in the U.S., and contrast these results with those of the Denver-Julesburg (Colorado) and Uintah (Utah) shale basins. Facility-level methane emission rates were measured at 106 NG production facilities using the dual tracer flux (nitrous oxide and acetylene), Gaussian dispersion simulations, and the OTM 33A techniques. The distribution of facility-level average methane emission rate for each NG basin will be discussed, with emphasis on how variability in NG composition (i.e., ethane-to-methane ratios) and state emissions regulations impact measured methane leak rates. While the focus of this presentation will be on the comparison of methane leak rates among NG basins, the use of three complimentary top-down methane measurement techniques provides a unique opportunity to explore the

Guidelines for Risk-Based Changeover of Biopharma Multi-Product Facilities.

Science.gov (United States)

Lynch, Rob; Barabani, David; Bellorado, Kathy; Canisius, Peter; Heathcote, Doug; Johnson, Alan; Wyman, Ned; Parry, Derek Willison

2018-01-01

In multi-product biopharma facilities, the protection from product contamination due to the manufacture of multiple products simultaneously is paramount to assure product quality. To that end, the use of traditional changeover methods (elastomer change-out, full sampling, etc.) have been widely used within the industry and have been accepted by regulatory agencies. However, with the endorsement of Quality Risk Management (1), the use of risk-based approaches may be applied to assess and continuously improve established changeover processes. All processes, including changeover, can be improved with investment (money/resources), parallel activities, equipment design improvements, and standardization. However, processes can also be improved by eliminating waste. For product changeover, waste is any activity not needed for the new process or that does not provide added assurance of the quality of the subsequent product. The application of a risk-based approach to changeover aligns with the principles of Quality Risk Management. Through the use of risk assessments, the appropriate changeover controls can be identified and controlled to assure product quality is maintained. Likewise, the use of risk assessments and risk-based approaches may be used to improve operational efficiency, reduce waste, and permit concurrent manufacturing of products. © PDA, Inc. 2018.

Vector Production in an Academic Environment: A Tool to Assess Production Costs

Science.gov (United States)

Boeke, Aaron; Doumas, Patrick; Reeves, Lilith; McClurg, Kyle; Bischof, Daniela; Sego, Lina; Auberry, Alisha; Tatikonda, Mohan

2013-01-01

Abstract Generating gene and cell therapy products under good manufacturing practices is a complex process. When determining the cost of these products, researchers must consider the large number of supplies used for manufacturing and the personnel and facility costs to generate vector and maintain a cleanroom facility. To facilitate cost estimates, the Indiana University Vector Production Facility teamed with the Indiana University Kelley School of Business to develop a costing tool that, in turn, provides pricing. The tool is designed in Microsoft Excel and is customizable to meet the needs of other core facilities. It is available from the National Gene Vector Biorepository. The tool allows cost determinations using three different costing methods and was developed in an effort to meet the A21 circular requirements for U.S. core facilities performing work for federally funded projects. The costing tool analysis reveals that the cost of vector production does not have a linear relationship with batch size. For example, increasing the production from 9 to18 liters of a retroviral vector product increases total costs a modest 1.2-fold rather than doubling in total cost. The analysis discussed in this article will help core facilities and investigators plan a cost-effective strategy for gene and cell therapy production. PMID:23360377

VHTR-based Nuclear Hydrogen Plant Analysis for Hydrogen Production with SI, HyS, and HTSE Facilities

International Nuclear Information System (INIS)

Shin, Youngjoon; Lee, Taehoon; Lee, Kiyoung; Kim, Minhwan

2016-01-01

In this paper, analyses of material and heat balances on the SI, HyS, and HTSE processes coupled to a Very High Temperature gas-cooled Reactor (VHTR) were performed. The hydrogen production efficiency including the thermal to electric energy ratio demanded from each process is found and the normalized evaluation results obtained from three processes are compared to each other. The currently technological issues to maintain the long term continuous operation of each process will be discussed at the conference site. VHTR-based nuclear hydrogen plant analysis for hydrogen production with SI, HyS, and HTSE facilities has been carried out to determine the thermal efficiency. It is evident that the thermal to electrical energy ratio demanded from each hydrogen production process is an important parameter to select the adequate process for hydrogen production. To improve the hydrogen production efficiency in the SI process coupled to the VHTR without electrical power generation, the demand of electrical energy in the SI process should be minimized by eliminating an electrodialysis step to break through the azeotrope of the HI/I_2/H_2O ternary aqueous solution

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

2012-05-01

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

40 CFR 63.5795 - How do I know if my reinforced plastic composites production facility is a new affected source or...

Science.gov (United States)

2010-07-01

... for Hazardous Air Pollutants: Reinforced Plastic Composites Production What This Subpart Covers § 63.5795 How do I know if my reinforced plastic composites production facility is a new affected source or an existing affected source? (a) A reinforced plastic composites production facility is a new...

Qualification of academic facilities for small-scale automated manufacture of autologous cell-based products.

Science.gov (United States)

Hourd, Paul; Chandra, Amit; Alvey, David; Ginty, Patrick; McCall, Mark; Ratcliffe, Elizabeth; Rayment, Erin; Williams, David J

2014-01-01

Academic centers, hospitals and small companies, as typical development settings for UK regenerative medicine assets, are significant contributors to the development of autologous cell-based therapies. Often lacking the appropriate funding, quality assurance heritage or specialist regulatory expertise, qualifying aseptic cell processing facilities for GMP compliance is a significant challenge. The qualification of a new Cell Therapy Manufacturing Facility with automated processing capability, the first of its kind in a UK academic setting, provides a unique demonstrator for the qualification of small-scale, automated facilities for GMP-compliant manufacture of autologous cell-based products in these settings. This paper shares our experiences in qualifying the Cell Therapy Manufacturing Facility, focusing on our approach to streamlining the qualification effort, the challenges, project delays and inefficiencies we encountered, and the subsequent lessons learned.

Greening Federal Facilities: An Energy, Environmental, and Economic Resource Guide for Federal Facility Managers and Designers; Second Edition

Energy Technology Data Exchange (ETDEWEB)

Wilson, A.

2001-05-16

Greening Federal Facilities, Second Edition, is a nuts-and-bolts resource guide compiled to increase energy and resource efficiency, cut waste, and improve the performance of Federal buildings and facilities. The guide highlights practical actions that facility managers, design and construction staff, procurement officials, and facility planners can take to save energy and money, improve the comfort and productivity of employees, and benefit the environment. It supports a national effort to promote energy and environmental efficiency in the nation's 500,000 Federal buildings and facilities. Topics covered include current Federal regulations; environmental and energy decision-making; site and landscape issues; building design; energy systems; water and wastewater; materials; waste management, and recycling; indoor environmental quality; and managing buildings.

Lessons learned: the effect of increased production rate on operation and maintenance of OPG's Western Used Fuel Dry Storage Facility

Energy Technology Data Exchange (ETDEWEB)

Morton, L.; Smith, N. [Ontario Power Generation, Tiverton, ON (Canada)

2011-07-01

In 2010, the Western Used Fuel Dry Storage Facility (WUFDSF) located at Ontario Power Generation's (OPG's) Western Waste Management Facility in Tiverton, ON, transferred, processed and stored a record-high number of Dry Storage Containers (DSC's) from Bruce Power's nuclear generating stations. The WUFDSF has been in operation since 2002. The facility transfers, processes, and stores the used fuel from the Bruce Power generating stations located in Tiverton, Ontario. As per a contractual agreement between OPG and Bruce Power, an annual DSC production and transfer schedule is agreed to between the two parties. In 2010, an increased annual production rate of 130 DSC's was agreed to between OPG and Bruce Power. Throughout 2007, 2008 and 2009, several facility modifications had been completed in anticipation of the increased production rate. These modifications included: Installation and commissioning of a second set of welding consoles; Addition of a second vacuum drying system; Procurement of a second transfer vehicle; and, Installation of a bulk gas system for welding cover gas. In 2010, the increased production rate of 130 DSC's/year came into effect. Throughout 2010, significant lessons learned were gained related to the impact of such a high production rate on the operation and maintenance of the facility. This paper presents the challenges and successes of that operation. The facility successfully achieved its production target with no safety incidents. This high rate of production is planned to continue for several years at the facility. Some challenges continue and these are being assessed and incorporated into the facility's business plan. In order to continue being successful, the facility must look to the future for opportunities for improvement and efficiencies to be gained. (author)

Lessons learned: the effect of increased production rate on operation and maintenance of OPG's Western Used Fuel Dry Storage Facility

International Nuclear Information System (INIS)

Morton, L.; Smith, N.

2011-01-01

In 2010, the Western Used Fuel Dry Storage Facility (WUFDSF) located at Ontario Power Generation's (OPG's) Western Waste Management Facility in Tiverton, ON, transferred, processed and stored a record-high number of Dry Storage Containers (DSC's) from Bruce Power's nuclear generating stations. The WUFDSF has been in operation since 2002. The facility transfers, processes, and stores the used fuel from the Bruce Power generating stations located in Tiverton, Ontario. As per a contractual agreement between OPG and Bruce Power, an annual DSC production and transfer schedule is agreed to between the two parties. In 2010, an increased annual production rate of 130 DSC's was agreed to between OPG and Bruce Power. Throughout 2007, 2008 and 2009, several facility modifications had been completed in anticipation of the increased production rate. These modifications included: Installation and commissioning of a second set of welding consoles; Addition of a second vacuum drying system; Procurement of a second transfer vehicle; and, Installation of a bulk gas system for welding cover gas. In 2010, the increased production rate of 130 DSC's/year came into effect. Throughout 2010, significant lessons learned were gained related to the impact of such a high production rate on the operation and maintenance of the facility. This paper presents the challenges and successes of that operation. The facility successfully achieved its production target with no safety incidents. This high rate of production is planned to continue for several years at the facility. Some challenges continue and these are being assessed and incorporated into the facility's business plan. In order to continue being successful, the facility must look to the future for opportunities for improvement and efficiencies to be gained. (author)

Hot Cell Facility modifications at Sandia National Laboratories to support 99Mo production

International Nuclear Information System (INIS)

Vernon, M.; Philbin, J.; Berry, D.

1997-01-01

In September, 1996, following the completion of an extensive Environmental Impact Statement (EIS), a record of decision (ROD) was issued by DOE selecting Sandia as the facility to take on the 99 Mo production mission. 99 Mo is the precursor to 99m Tc which is used in 36,000 medical procedures per day in the US. to meet US 99 Mo medical demands, 20 kCi of 99 Mo must be delivered to the pharmaceutical companies each week. This could be accomplished by the processing of twenty-five targets (total fission product of 15 kCi/target) each week within the SNL Hot Cell Facility (HCF). To accomplish this new mission, significant modifications to the HCF will have to be undertaken. This paper presents a brief history of the HCF, and describes modifications necessary to achieve DOE directives

Radon gas in oil and natural gas production facilities

International Nuclear Information System (INIS)

Chandler, W.P.

1994-01-01

Radon gas is a naturally occurring radionuclide that can be found in some oil and natural gas production facilities, either as a contaminant in a natural gas stream or derived from Radium dissolved in formation waters. The gas itself is not normally a health hazard, but it's decay products, which can be concentrated by plate-out or deposition as a scale in process equipment, can be a health hazard for maintenance personnel. To evaluate possible health hazards, it is necessary to monitor for naturally occurring radioactive materials (NORM) in the gas stream and in the formation water. If Radon and/or Radium is found, a monitoring programme should be initiated to comply with National or State requirements. In some instances, it has been found necessary to dispose of silt and scale materials as low level radioactive waste. 8 refs

Novel Biocontrol Methods for Listeria monocytogenes Biofilms in Food Production Facilities.

Science.gov (United States)

Gray, Jessica A; Chandry, P Scott; Kaur, Mandeep; Kocharunchitt, Chawalit; Bowman, John P; Fox, Edward M

2018-01-01

High mortality and hospitalization rates have seen Listeria monocytogenes as a foodborne pathogen of public health importance for many years and of particular concern for high-risk population groups. Food manufactures face an ongoing challenge in preventing the entry of L. monocytogenes into food production environments (FPEs) due to its ubiquitous nature. In addition to this, the capacity of L. monocytogenes strains to colonize FPEs can lead to repeated identification of L. monocytogenes in FPE surveillance. The contamination of food products requiring product recall presents large economic burden to industry and is further exacerbated by damage to the brand. Poor equipment design, facility layout, and worn or damaged equipment can result in Listeria hotspots and biofilms where traditional cleaning and disinfecting procedures may be inadequate. Novel biocontrol methods may offer FPEs effective means to help improve control of L. monocytogenes and decrease cross contamination of food. Bacteriophages have been used as a medical treatment for many years for their ability to infect and lyse specific bacteria. Endolysins, the hydrolytic enzymes of bacteriophages responsible for breaking the cell wall of Gram-positive bacteria, are being explored as a biocontrol method for food preservation and in nanotechnology and medical applications. Antibacterial proteins known as bacteriocins have been used as alternatives to antibiotics for biopreservation and food product shelf life extension. Essential oils are natural antimicrobials formed by plants and have been used as food additives and preservatives for many years and more recently as a method to prevent food spoilage by microorganisms. Competitive exclusion occurs naturally among bacteria in the environment. However, intentionally selecting and applying bacteria to effect competitive exclusion of food borne pathogens has potential as a biocontrol application. This review discusses these novel biocontrol methods and their

Licensing of digital Instrumentation and Control in Radioisotope Production Facility

International Nuclear Information System (INIS)

Abdel-Aziz, L.Kh.; Lashin, R.; Mostafa, W.

2012-01-01

In spite of the rapid development of digital I and C systems in all major industries, it has for several reasons been slower in nuclear power plants. The most important reason is that only a few new plants have been ordered worldwide during the last ten years. A second reason is connected to the efforts needed in providing adequate evidence that the digital I and C system can be used in safety and safety related applications. This issue is connected to the effort needed in obtaining adequate assurance that the digital I and C will fulfill its intended function and contain no unintended function in all possible operational states during its entire life cycle. This paper presents an acceptance criteria for licensing a digital instrumentation and control system in a Radioisotope Production Facility(1), which is under commissioning. The acceptance criteria ensure that the I and C systems are designed to reach the highest degree of reliability with respect to the function they perform, operators will have clear and accessible availability to data on every plant parameter, and also ensure that the safety objectives have been covered

Fiscal 1997 survey report. Basic survey on trends of waste use type production facilities and waste fuel production facilities; 1997 nendo chosa hokokusho. Haikibutsu riyogata seizo shisetsu oyobi haikibutsu nenryo seizo shisetsu doko kiso chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

This survey was made to obtain the basic data for future spread and promotion of No.6 type (waste use type production facilities) and No.7 type (waste fuel production facilities) which were added to the objects having been subsidized since fiscal 1997 under `the environmental harmony type energy community project.` In the former, the kiln in the cement industry and the blast furnace in the steel industry can be extremely large places to receive waste plastic since the facilities are distributed in every area and the treatment capacity is large. However, the effective collection, transportation and sorting of large quantity of waste plastic, especially the problem of removal of vinyl chloride, is a big bottleneck. As to the use of waste plastic using gasification technology, there are no actual results on the commercial basis. That is, however, appropriate for treatment of the waste difficult in treatment, and can be expected of the usage in the chemical industry. In the latter, in the facilities using industrial waste raw materials as fuel, solidification and liquefaction are both operated on a commercial basis. In relation to the solidification and use as fuel of general waste, the treatment of combustion ash is preventing the expansion of use of waste in the industrial field because of a large quantity of chlorine included in the products. 92 refs., 54 figs., 35 tabs.

An integrated prediction and optimization model of biogas production system at a wastewater treatment facility.

Science.gov (United States)

Akbaş, Halil; Bilgen, Bilge; Turhan, Aykut Melih

2015-11-01

This study proposes an integrated prediction and optimization model by using multi-layer perceptron neural network and particle swarm optimization techniques. Three different objective functions are formulated. The first one is the maximization of methane percentage with single output. The second one is the maximization of biogas production with single output. The last one is the maximization of biogas quality and biogas production with two outputs. Methane percentage, carbon dioxide percentage, and other contents' percentage are used as the biogas quality criteria. Based on the formulated models and data from a wastewater treatment facility, optimal values of input variables and their corresponding maximum output values are found out for each model. It is expected that the application of the integrated prediction and optimization models increases the biogas production and biogas quality, and contributes to the quantity of electricity production at the wastewater treatment facility. Copyright © 2015 Elsevier Ltd. All rights reserved.

Nuclear data for the production of radioisotopes in fusion materials irradiation facility

International Nuclear Information System (INIS)

Cheng, E.T.; Schenter, R.E.; Mann, F.M.; Ikeda, Y.

1991-01-01

The fusion materials irradiation facility (FMIF) is a neutron source generator that will produce a high-intensity 14-MeV neutron field for testing candidate fusion materials under reactor irradiation conditions. The construction of such a facility is one of the very important development stages toward realization of fusion energy as a practical energy source for electricity production. As a result of the high-intensity neutron field, 10 MW/m 2 or more equivalent neutron wall loading, and the relatively high-energy (10- to 20-MeV) neutrons, the FMIF, as future fusion reactors, also bears the potential capability of producing a significant quantity of radioisotopes. A study is being conducted to identify the potential capability of the FMIF to produce radioisotopes for medical and industrial applications. Two types of radioisotopes are involved: one is already available; the second might not be readily available using conventional production methods. For those radioisotopes that are not readily available, the FMIF could develop significant benefits for future generations as a result of the availability of such radioisotopes for medical or industrial applications. The current production of radioisotopes could help finance the operation of the FMIF for irradiating the candidate fusion materials; thus this concept is attractive. In any case, nuclear data are needed for calculating the neutron flux and spectrum in the FMIF and the potential production rates of these isotopes. In this paper, the authors report the result of a preliminary investigation on the production of 99 Mo, the parent radioisotope for 99m Tc

Conceptual design report -- Gasification Product Improvement Facility (GPIF)

Energy Technology Data Exchange (ETDEWEB)

Sadowski, R.S.; Skinner, W.H.; House, L.S.; Duck, R.R. [CRS Sirrine Engineers, Inc., Greenville, SC (United States); Lisauskas, R.A.; Dixit, V.J. [Riley Stoker Corp., Worcester, MA (United States); Morgan, M.E.; Johnson, S.A. [PSI Technology Co., Andover, MA (United States). PowerServe Div.; Boni, A.A. [PSI-Environmental Instruments Corp., Andover, MA (United States)

1994-09-01

The problems heretofore with coal gasification and IGCC concepts have been their high cost and historical poor performance of fixed-bed gasifiers, particularly on caking coals. The Gasification Product Improvement Facility (GPIF) project is being developed to solve these problems through the development of a novel coal gasification invention which incorporates pyrolysis (carbonization) with gasification (fixed-bed). It employs a pyrolyzer (carbonizer) to avoid sticky coal agglomeration caused in the conventional process of gradually heating coal through the 400 F to 900 F range. In so doing, the coal is rapidly heated sufficiently such that the coal tar exists in gaseous form rather than as a liquid. Gaseous tars are then thermally cracked prior to the completion of the gasification process. During the subsequent endothermic gasification reactions, volatilized alkali can become chemically bound to aluminosilicates in (or added to) the ash. To reduce NH{sub 3} and HCN from fuel born nitrogen, steam injection is minimized, and residual nitrogen compounds are partially chemically reduced in the cracking stage in the upper gasifier region. Assuming testing confirms successful deployment of all these integrated processes, future IGCC applications will be much simplified, require significantly less mechanical components, and will likely achieve the $1,000/kWe commercialized system cost goal of the GPIF project. This report describes the process and its operation, design of the plant and equipment, site requirements, and the cost and schedule. 23 refs., 45 figs., 23 tabs.

Occurrence of pharmaceuticals in Taiwan's surface waters: impact of waste streams from hospitals and pharmaceutical production facilities.

Science.gov (United States)

Lin, Angela Yu-Chen; Tsai, Yu-Ting

2009-06-01

We investigated the occurrence and distribution of pharmaceuticals (including antibiotics, estrogens, non-steroidal anti-inflammatory drugs (NSAIDs), beta-blockers, and lipid regulators) in three rivers and in the waste streams of six hospitals and four pharmaceutical production facilities in Taiwan. The most frequently detected pharmaceuticals were acetaminophen, erythromycin-H(2)O, sulfamethoxazole, and gemfibrozil. NSAIDs were the next most-often detected compounds, with a detection frequency >60%. The other analytes were not detected or were seen in only a few samples at trace concentrations. The present study demonstrates a significant discharge of human medications from hospital and drug production facilities into surface waters in the Taipei district. The high concentrations of pharmaceuticals found in the Sindian and Dahan rivers demonstrate the alarming degree to which they have been impacted by urban drainage (waste effluents from hospitals, households, and pharmaceutical production facilities). The ubiquitous occurrence at extremely high concentrations of acetaminophen and erythromycin-H(2)O in both rivers (up to 15.7 and 75.5 microg/L) and in wastewater from hospitals and pharmaceutical production facilities (up to 417.5 and 7.84 microg/L) was unique. This finding, in combination with acetaminophen's status as the drug most often prescribed by Taiwan's dominant clinical institute, suggests the potential use of acetaminophen as a molecular indicator of contamination of Taiwan's aqueous environments with untreated urban drainage.

Scoping assessment on medical isotope production at the Fast Flux Test Facility

International Nuclear Information System (INIS)

Scott, S.W.

1997-01-01

The Scoping Assessment addresses the need for medical isotope production and the capability of the Fast Flux Test Facility to provide such isotopes. Included in the discussion are types of isotopes used in radiopharmaceuticals, which types of cancers are targets, and in what way isotopes provide treatment and/or pain relief for patients

Scoping assessment on medical isotope production at the Fast Flux Test Facility

Energy Technology Data Exchange (ETDEWEB)

Scott, S.W.

1997-08-29

The Scoping Assessment addresses the need for medical isotope production and the capability of the Fast Flux Test Facility to provide such isotopes. Included in the discussion are types of isotopes used in radiopharmaceuticals, which types of cancers are targets, and in what way isotopes provide treatment and/or pain relief for patients.

Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

Science.gov (United States)

Gencer, A.; Demirköz, B.; Efthymiopoulos, I.; Yiğitoğlu, M.

2016-07-01

Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between 10 μA and 1.2 mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam flux. The DBL is designed to provide fluxes between 107 p /cm2 / s and 109 p /cm2 / s for performing irradiation tests in an area of 15.4 cm × 21.5 cm. The facility will be the first irradiation facility of its kind in Turkey.

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.)

Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities

International Nuclear Information System (INIS)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-09-01

This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km 2 (570-mi 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 (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation

Innovations to increase throughput of the multipurpose irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Cabalfin, Estelita G; Lanuza, Luvimina G; Maningas, Aurelio L; Solomon, Haydee M [Irradiation Services Unit, Nuclear Services and Training Division, Philippine Nuclear Research Institute, Quezon City (Philippines)

1998-07-01

With the installation and operation of the PNRI [Philippine Nuclear Research Institute] multipurpose irradiation facility, several local industries are now aware of, and in fact using gamma radiation for sterilization or decontamination of medical and pharmaceutical products, packaging materials and for food preservation. However, the multipurpose irradiation facility has limited capacity and capability, since this was designed as a pilot scale irradiator for research and development. To meet the increasing demand of gamma irradiation service, a new product handling system was locally designed, fabricated and installed. Performance, in terms of total loading and more importantly, radiation dose distribution of the new product handling system, was evaluated. An increase in product throughput was realized effectively with the new product handling system. (Author)

Innovations to increase throughput of the multipurpose irradiation facility

International Nuclear Information System (INIS)

Cabalfin, Estelita G.; Lanuza, Luvimina G.; Maningas, Aurelio L.; Solomon, Haydee M.

1998-01-01

With the installation and operation of the PNRI [Philippine Nuclear Research Institute] multipurpose irradiation facility, several local industries are now aware of, and in fact using gamma radiation for sterilization or decontamination of medical and pharmaceutical products, packaging materials and for food preservation. However, the multipurpose irradiation facility has limited capacity and capability, since this was designed as a pilot scale irradiator for research and development. To meet the increasing demand of gamma irradiation service, a new product handling system was locally designed, fabricated and installed. Performance, in terms of total loading and more importantly, radiation dose distribution of the new product handling system, was evaluated. An increase in product throughput was realized effectively with the new product handling system. (Author)

Vitrification Facility integrated system performance testing report

International Nuclear Information System (INIS)

Elliott, D.

1997-01-01

This report provides a summary of component and system performance testing associated with the Vitrification Facility (VF) following construction turnover. The VF at the West Valley Demonstration Project (WVDP) was designed to convert stored radioactive waste into a stable glass form for eventual disposal in a federal repository. Following an initial Functional and Checkout Testing of Systems (FACTS) Program and subsequent conversion of test stand equipment into the final VF, a testing program was executed to demonstrate successful performance of the components, subsystems, and systems that make up the vitrification process. Systems were started up and brought on line as construction was completed, until integrated system operation could be demonstrated to produce borosilicate glass using nonradioactive waste simulant. Integrated system testing and operation culminated with a successful Operational Readiness Review (ORR) and Department of Energy (DOE) approval to initiate vitrification of high-level waste (HLW) on June 19, 1996. Performance and integrated operational test runs conducted during the test program provided a means for critical examination, observation, and evaluation of the vitrification system. Test data taken for each Test Instruction Procedure (TIP) was used to evaluate component performance against system design and acceptance criteria, while test observations were used to correct, modify, or improve system operation. This process was critical in establishing operating conditions for the entire vitrification process

Research studies performed using the Cairo Fourier Diffractometer Facility

International Nuclear Information System (INIS)

Maayouf, R.M.A.; Ridikas, D.

2009-12-01

This report represents the results of the research studies performed using the Cairo Fourier Diffractometer Facility (CFDF), within 10 years after it was installed and put into operation at the beginning of 1996. The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022 'Upgrading of Research Reactor Utilization'. The present report is the second published INDC report, while the first one, published at the beginning of 1997, was about the performance of the CFDF and its main characteristic parameters. Plenty of measurements were performed since then, yielding several publications both in local and international scientific periodicals and resulting in 8 M.Sc. and Ph.D. degrees from Egyptian Universities. In addition, a new approach for the analysis of the neutron spectra was implemented using the CFDF. Specially designed interface card with proper software program was applied instead of the reverse time of flight (RTOF) and Finnish made analyzer originally attached to the facility. It has been verified that the new approach can successfully replace the RTOF analyzer, significantly decreasing the time of measurement and saving the reactor's operation time. Besides, a special fault diagnostic system program was developed and tested for caring and handling the possible failures of the CFDF. Moreover, measurements were carried out for the diffraction spectra emitted at different points of one of the samples. The latter was scanned across the neutron beam of the CFDF, for studying the stress after welding; used in industrial applications. (author)

The Proposal of Key Performance Indicators in Facility Management and Determination the Weights of Significance

Science.gov (United States)

Rimbalová, Jarmila; Vilčeková, Silvia

2013-11-01

The practice of facilities management is rapidly evolving with the increasing interest in the discourse of sustainable development. The industry and its market are forecasted to develop to include non-core functions, activities traditionally not associated with this profession, but which are increasingly being addressed by facilities managers. The scale of growth in the built environment and the consequential growth of the facility management sector is anticipated to be enormous. Key Performance Indicators (KPI) are measure that provides essential information about performance of facility services delivery. In selecting KPI, it is critical to limit them to those factors that are essential to the organization reaching its goals. It is also important to keep the number of KPI small just to keep everyone's attention focused on achieving the same KPIs. This paper deals with the determination of weights of KPI of FM in terms of the design and use of sustainable buildings.

Performance of the CNEN MHD Blow-Down Loop Facility

Energy Technology Data Exchange (ETDEWEB)

Bertolini, E.; Brown, R.; Gasparotto, M.; Gay, P.; Toschi, R. [Laboratorio Conversione Diretta, CNEN, Frascati (Italy)

1968-11-15

The CNEN facility has been designed, manufactured and used for alkali-seeded noble gas MHD energy conversion research, as the major experimental effort during the first five-year CNEN Research Programme on MHD. The main specifications and the general arrangement with information on preliminary commissioning tests of some components were given at the Salzburg Symposium. Since then the facility has been successfully commissioned and from March 1967 has been working on MHD experiments. Efforts were made to reduce any adverse effects on the experimental MHD results that were due to inherent limitations of an experimental apparatus (particularly under open-circuit conditions). Great emphasis was placed on problems of caesium vaporization and the mixing with helium, the purity level of the mixture, measurements and the control system. The insulation of the plasma from ground was carefully treated, increasing the ratio between insulator resistance and typical plasma resistance as much as possible. Fluidynamic tests at room and high temperatures have shown that stability in the gas parameters (temperature, pressure and mass flow) can be maintained within few per cent for tens of seconds after a transient, giving a behaviour similar to a continuously running system. The high- temperature, alumina pebble-bed heater has successfully operated, bringing the helium-caesium mixtures up to 2000 Degree-Sign K and up to 4 atm abs pressure, and undergoing seven thermal cycles, for a total of more than 2000 hours operation at top temperature. Preheated generator ducts using alumina as insulator and tantalum for electrodes performed satisfactorily, very much attention having been given in the design to reduction of thermal shocks and to obviating possible paths for caesium leakage and short-circuiting of electrode leads. The pulsed liquid nitrogen precooled magnet has been run for about 50 pulses at high field ( Asymptotically-Equal-To 4.5 tesla) with an operating time of about 10

Design features of isotope production facility at Inshas cyclotron complex. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Comsan, M N [Nuclear Research Center, Atomic Energy Aurhority, Cairo, (Egypt)

1996-03-01

The nuclear research center, AEA, Egypt is erecting at its Inshas campus cyclotron complex for multidisciplinary use for research and application. The complex is to utilize a russian made AVF cyclotron accelerator of the type MGC-20 with MeV protons. Among its applications, the accelerator will be used for the production of short lived cyclotron isotopes. This article presents a concise description of the design features of isotope production facility to be annexed to the complex layout, schemes for radio waste, ventilation, and air conditioning systems. 2 figs., 2 tabs.

Techniques and results of examination of fission product release from VVER fuel rods with artificial defects and a burnup of ∼60 MWd/kgU at the MIR loop facility

International Nuclear Information System (INIS)

Burukin, A.; Goryachev, A.; Ilyenko, S.; Izhutov, A.; Konyashov, V.; Shishin, V.; Shulimov, V.; Luzanova, L.; Miglo, V.

2009-01-01

Complex of equipment and several techniques for examination of radioactive fission product release from defective fuel rods were developed, prepared and tested at the PV-1 loop facility of the MIR reactor. During the first test, which was conducted at the PV-1 loop facility and aimed at testing of developed equipment and techniques, measurement of radioactive fission product release from an experimental re-fabricated fuel rod with a burnup of ∼60 MWd/kgU and an artificial defect was performed under design-basis steady-state operating conditions of the VVER-1000 reactor. PIE of all main parameters of the experimental defective fuel rod did not reveal any state peculiarities which could be caused by the artificial defect, i.e. fuel and cladding characteristics in the defect area did not differ from the initial ones (before testing) as well as their characteristics in areas distant from the defect; they are typical for fuel rods with a similar irradiation history in the VVER NPP. The gap in the experimental fuel rod was bridged due to close contact between fuel and cladding at increased fuel burnup; it can appreciable reduce release of radioactive fission products into the PV-1 primary coolant. This suggestion and quantitative characteristics of effect of gap bridging in a high-burnup fuel rod on radioactive fission product release should be investigated during the next tests performed at the PV-1 loop facility. Values of radioactive fission product release measured during the first test at the PV-1 loop facility in the MIR reactor will be used for development of an empirical engineering model in order to take into account high burnup effects and their impact on fission product release from fuel and defective fuel rods

Metal Exposures at three U.S. electronic scrap recycling facilities.

Science.gov (United States)

Ceballos, Diana; Beaucham, Catherine; Page, Elena

2017-06-01

Many metals found in electronic scrap are known to cause serious health effects, including but not limited to cancer and respiratory, neurologic, renal, and reproductive damage. The National Institute for Occupational Safety and Health, Centers for Disease Control and Prevention performed three health hazard evaluations at electronic scrap recycling facilities in the U.S. to characterize employee exposure to metals and recommend control strategies to reduce these exposures. We performed air, surface, and biological monitoring for metals. We found one overexposure to lead and two overexposures to cadmium. We found metals on non-production surfaces, and the skin and clothing of workers before they left work in all of the facilities. We also found some elevated blood lead levels (above 10 micrograms per deciliter), however no employees at any facility had detectable mercury in their urine or exceeded 34% of the OELs for blood or urine cadmium. This article focuses on sampling results for lead, cadmium, mercury, and indium. We provided recommendations for improving local exhaust ventilation, reducing the recirculation of potentially contaminated air, using respirators until exposures are controlled, and reducing the migration of contaminants from production to non-production areas. We also recommended ways for employees to prevent taking home metal dust by using work uniforms laundered on-site, storing personal and work items in separate lockers, and using washing facilities equipped with lead-removing cleaning products.

Workshop on Seismic Performance of Underground Facilities: proceedings

International Nuclear Information System (INIS)

Marine, I.W.

1982-01-01

A workshop entitled Seismic Performance of Underground Facilities was held in Augusta, GA, February 11-13, 1981. The Workshop was organized and conducted by The Savannah River Laboratory of E.I. du Pont de Nemours and Co. and was sponsored by The Department of Energy and The Office of Nuclear Waste Isolation of Battelle. The objective of the Workshop was to review and assess the state of the science of determining and predicting damage to underground facilities from earthquakes, with particular emphasis on the ultimate goal of developing criteria for siting and design of mined geologic nuclear waste repositories. The Workshop consisted of a day of presentations in the categories of Introduction, Data Collection and Analysis, Modeling, and Design. The second day consisted of assessments of the science by subgroups in the subjects of Seismology; Rock Mechanics and Hydrology; Modeling; Licensing, Siting, and Tectonics; and Design. Most Scientists in attendance believed that enough was known of the subsurface effects of earthquakes to proceed with site selection, design, and licensing of a waste repository. There was, however, recognition of several items of research that would enhance the understanding of the subsurface effects of seismicity

Biannular Airbreathing Nozzle Rig (BANR) facility checkout and plug nozzle performance test data

Science.gov (United States)

Cummings, Chase B.

2010-09-01

The motivation for development of a supersonic business jet (SSBJ) platform lies in its ability to create a paradigm shift in the speed and reach of commercial, private, and government travel. A full understanding of the performance capabilities of exhaust nozzle configurations intended for use in potential SSBJ propulsion systems is critical to the design of an aircraft of this type. Purdue University's newly operational Biannular Airbreathing Nozzle Rig (BANR) is a highly capable facility devoted to the testing of subscale nozzles of this type. The high accuracy, six-axis force measurement system and complementary mass flowrate measurement capabilities of the BANR facility make it rather ideally suited for exhaust nozzle performance appraisal. Detailed accounts pertaining to methods utilized in the proper checkout of these diagnostic capabilities are contained herein. Efforts to quantify uncertainties associated with critical BANR test measurements are recounted, as well. Results of a second hot-fire test campaign of a subscale Gulfstream Aerospace Corporation (GAC) axisymmetric, shrouded plug nozzle are presented. Determined test article performance parameters (nozzle thrust efficiencies and discharge coefficients) are compared to those of a previous test campaign and numerical simulations of the experimental set-up. Recently acquired data is compared to published findings pertaining to plug nozzle experiments of similar scale and operating range. Suggestions relating to the future advancement and improvement of the BANR facility are provided. Lessons learned with regards to test operations and calibration procedures are divulged in an attempt to aid future facility users, as well.

Overview of power plant and industrial facility performance in earthquakes in 1985 through 1987

International Nuclear Information System (INIS)

Horstman, N.G.; Yanev, P.I.; McCormick, D.L.

1987-01-01

This paper briefly documents the performance of power and industrial facilities during five destructive earthquakes in 1985 and 1986. These earthquakes represent varying levels of intensity, duration, frequency content, epicentral distance and construction practice. All of the earthquakes reinforce the findings of earlier earthquake investigations. Damage to equipment in power and industrial facilities is rare, as long as the equipment is adequately anchored. The ceramic components of switchyard equipment and the actuation of electro-mechanical relays remain concerns in the design of facilities which must remain operational during and following strong motion earthquakes. (orig.)

Combustion and environmental performance of clean coal end products

Energy Technology Data Exchange (ETDEWEB)

Skodras, G.; Sakellaropoulos, G. [Centre for Research and Technology, Hellas, Ptolemaidas-Kozanis, Ptolemaida (Greece). Inst. for Solid Fuel Technolgy and Applications]|[Aristotle Univ. of Thessaloniki, Thessaloniki (Greece). Dept. of Chemical Engineering, Chemical Process Engineering Lab]|[Chemical Process Engineering Research Inst., Thessaloniki (Greece). Lab. of Solid Fuels and Environment; Someus, E. [Thermal Desorption Technology Group (Greece); Grammelis, P.; Amarantos, P.S. [Centre for Research and Technology, Hellas, Ptolemaidas-Kozanis, Ptolemaida (Greece). Inst. for Solid Fuel Technolgy and Applications; Palladas, A.; Basinas, P.; Natas, P.; Prokopidou, M.; Diamantopoulou, I.; Sakellaropoulos, G. [Aristotle Univ. of Thessaloniki, Thessaloniki (Greece). Dept. of Chemical Engineering, Chemical Process Engineering Lab

2006-07-01

Clean and affordable power production is needed in order to achieve sustainable economic development. This paper focused on clean coal technologies in which coal-fired power plants are used in conjunction with large amounts of renewable energy sources to offer a high level of process safety and long term management of all residual operation streams. Thermal Desorption Recycle-Reduce-Reuse Technology (TDT-3R) was described as being a promising solid fuel pretreatment process for clean energy production up to 300 MWe capacities. TDT-3R is based on low temperature carbonisation fuel pre-treatment principles, which produce cleansed anthracite type fuels from coal and other carbonaceous material such as biomass and organic wastes. The combustion efficiency of such clean coals and the environmental performance of the TDT-3R process were investigated in this study via pilot scale tests of clean fuel production. Tests included flue gas emissions monitoring, raw fuel and product characterisation and thermogravimetric tests, polychlorinated dibenzo-p-dioxins and dibenzo-furans, and heavy metals analyses, and toxicity tests. Raw material included coal and biomass, such as willow, straw and demolition wood. The fuels were heated in a rotary kiln operating at 550 degrees C under slightly vacuum conditions. Clean coals were tested either alone or in conjunction with biomass fuels in a pilot scale combustion facility at Dresden, Germany. The clean coal samples were shown to have higher fixed carbon and ash content and lower volatiles compared to the respective raw coal samples. The major advantage of the TDT-3R process is the production of fuels with much lower pollutants content. Low nitrogen, sulphur, chlorine and heavy metal contents result in produced fuels that have excellent environmental performance, allow boiler operation in higher temperatures and overall better efficiency. Moreover, the use of clean fuels reduces deposition problems in the combustion chamber due to the

A commercial multipurpose radiation processing facility for Hawaii

International Nuclear Information System (INIS)

Welt, M.A.

1985-01-01

The State of Hawaii offers a unique challenge for the designer of an economically feasible radiation processing system. Based on the prevailing agricultural export requirements, the radiation facility must be capable for handling a variety of bulky fruit and vegetable products for insect disinfestation purposes and, yet, provide proper economies for the users of the facility. A capability must exist for irradiating other types of products requiring higher doses, e.g., fish and shellfish products for shelf-life extension, which might require a dose approximately eight times higher than the disinfestation dose, or even medical product or a food sterilization dose, which would be approximately twelve times higher than the required shelf-life extension dose. The Radiation Technology Model RT 4l0l-4048 radiation processing facility provides the necessary versatility and operational reliability to meet the challenge. The technical features and economic analyses demonstrate the advantages of this computer-operated pallet irradiation system. Actual performance data from the Radiation Technology subsidiary operations in West Memphis, Arkasas, and Burlilngton, North Carolina, are presented along with photographs of the proposed system for Hawaii

Application of an experimental irradiation facility type K-120 for the radiation treatment of agricultural products in large quantity

International Nuclear Information System (INIS)

Stenger, V.; Foeldiak, G.; Horvath, I.; Hargittai, P.; Bartfai, Cs.

1979-01-01

During experimental and pilot irradiation carried out by the 60 Co irradiation facility type K-120 of the Institute of Isotopes of the Hungarian Academy of Sciences an irradiation technology for the treatment of agricultural and food products of considerable density has been developed. Applying transport containers of commercial size the intermittent radiation treatment of great quantity products was made possible with homogeneous dose distribution. The radiation technical characteristics, the utilization coefficient and the capacity of the facility for every agricultural product were calculated. (author)

Projected Salt Waste Production from a Commercial Pyroprocessing Facility

Directory of Open Access Journals (Sweden)

Michael F. Simpson

2013-01-01

Full Text Available Pyroprocessing of used nuclear fuel inevitably produces salt waste from electrorefining and/or oxide reduction unit operations. Various process design characteristics can affect the actual mass of such waste produced. This paper examines both oxide and metal fuel treatment, estimates the amount of salt waste generated, and assesses potential benefit of process options to mitigate the generation of salt waste. For reference purposes, a facility is considered in which 100 MT/year of fuel is processed. Salt waste estimates range from 8 to 20 MT/year from considering numerous scenarios. It appears that some benefit may be derived from advanced processes for separating fission products from molten salt waste, but the degree of improvement is limited. Waste form production is also considered but appears to be economically unfavorable. Direct disposal of salt into a salt basin type repository is found to be the most promising with respect to minimizing the impact of waste generation on the economic feasibility and sustainability of pyroprocessing.

Welding and Production Metallurgy Facility

Data.gov (United States)

Federal Laboratory Consortium — This 6000 square foot facility represents the only welding laboratory of its kind within DA. It is capable of conducting investigations associated with solid state...

Managing Human Performance to Improve Nuclear Facility Operation

International Nuclear Information System (INIS)

2013-01-01

. It describes how human performance can be managed within an overall performance improvement model. The need for IAEA involvement in this area and to address key issues highlighted in IAEA Nuclear Energy Series No. NG-G-2.1 were reinforced during the meetings of the Technical Working Group on Managing Human Resources in the Field of Nuclear Energy (TWG-MHR) in 2008 and 2010. The importance of human performance in the safe operation of any nuclear facility is no longer in doubt. The contribution of human performance to the occurrence of significant events and, consequently, to overall performance in the nuclear field has been well documented. Monitoring and continually improving human performance has now become one of the key challenges in the management of human resources for nuclear facilities. To facilitate meeting the challenge of improving human performance, a model of performance improvement is presented that provides a framework which can be used to improve individual, process and organizational performance. It is generally postulated that without human performance improvement, a safe working environment is impossible to maintain. While there are many different perspectives from which safety issues might be addressed, there are several factors significant for human performance improvement that are consistent, useful and necessary to understand. This publication is not intended as an all encompassing guide to managing human performance, but, rather, provides a summary of concepts and good practices for organizations to consider in their design of various programmes and in the performance of activities. In addition, tools that are helpful for managing human performance are discussed, and references for more detailed information on these concepts and tools are provided

A national study of efficiency for dialysis centers: an examination of market competition and facility characteristics for production of multiple dialysis outputs.

Science.gov (United States)

Ozgen, Hacer; Ozcan, Yasar A

2002-06-01

To examine market competition and facility characteristics that can be related to technical efficiency in the production of multiple dialysis outputs from the perspective of the industrial organization model. Freestanding dialysis facilities that operated in 1997 submitted cost report fonns to the Health Care Financing Administration (HCFA), and offered all three outputs--outpatient dialysis, dialysis training, and home program dialysis. The Independent Renal Facility Cost Report Data file (IRFCRD) from HCFA was utilized to obtain information on output and input variables and market and facility features for 791 multiple-output facilities. Information regarding population characteristics was obtained from the Area Resources File. Cross-sectional data for the year 1997 were utilized to obtain facility-specific technical efficiency scores estimated through Data Envelopment Analysis (DEA). A binary variable of efficiency status was then regressed against its market and facility characteristics and control factors in a multivariate logistic regression analysis. The majority of the facilities in the sample are functioning technically inefficiently. Neither the intensity of market competition nor a policy of dialyzer reuse has a significant effect on the facilities' efficiency. Technical efficiency is significantly associated, however, with type of ownership, with the interaction between the market concentration of for-profits and ownership type, and with affiliations with chains of different sizes. Nonprofit and government-owned Facilities are more likely than their for-profit counterparts to become inefficient producers of renal dialysis outputs. On the other hand, that relationship between ownership form and efficiency is reversed as the market concentration of for-profits in a given market increases. Facilities that are members of large chains are more likely to be technically inefficient. Facilities do not appear to benefit from joint production of a variety of

Facilities for Research and Development of Medical Radioisotopes

International Nuclear Information System (INIS)

Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

2003-03-01

This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value

Improving and extending performance at synchrotron radiation facilities

International Nuclear Information System (INIS)

Jackson, A.

1997-05-01

Synchrotron radiation facilities around the world have now matured through three generations. The latest facilities have all met or exceeded their design specifications and are learning how to cope with the ever more demanding requests of the user community, especially concerning beam stability. The older facilities remain competitive by extending the unique features of their design, and by developing novel insertion devices. In this paper we survey the beam characteristics achieved at third-generation sources and explore the improvements made at earlier generation facilities

Reliability of eye lens dosimetry in workers of a positron emission tomography radiopharmaceutical production facility

International Nuclear Information System (INIS)

Silva, Teógenes A. da; Guimarães, Margarete C.; Meireles, Leonardo S.; Teles, Luciana L.D.; Lacerda, Marco Aurélio S.

2016-01-01

A new regulatory statement was issued concerning the eye lens radiation protection of persons in planned exposures. A debate was raised on the adequacy of the dosimetric quantity and on its method of measurement. The aim of this work was to establish the individual monitoring procedure with the EYE-D™ holder and a MCP-N LiF:Mg,Cu,P thermoluminescent chip detector for measuring the personal dose equivalent H_p(3) in workers of a Positron Emission Tomography Radiopharmaceutical Production Facility. - Highlights: • New regulatory statement was issued concerning eye lens radiation protection. • The calibration procedure of dosimeters for measuring H_p(3) was studied on a slab and cylindrical phantoms. • H_p(3) measurements in workers in a radiopharmaceutical production facility were done.

Cleaning and disinfection programs against Campylobacter jejuni for broiler chickens: productive performance, microbiological assessment and characterization1

Science.gov (United States)

Deliberali Lelis, Karoline; Granghelli, Carlos Alexandre; Carão de Pinho, Agatha Cristina; Ribeiro Almeida Queiroz, Sabrina; Fernandes, Andrezza Maria; Moro de Souza, Ricardo Luiz; Gaglianone Moro, Maria Estela; de Andrade Bordin, Roberto; de Albuquerque, Ricardo

2017-01-01

Abstract Detailed cleaning and disinfection programs aims to reduce infection pressure from microorganisms from one flock to the next. However, studies evaluating the benefits to poultry performance, the sanitary status of the facilities, and the sanitary quality of the meat are rarely found. Thus, this study was designed to evaluate 2 cleaning and disinfecting programs regarding their influence on productive performance, elimination of Campylobacter, and characterization of Campylobacter jejuni strains when applied to broiler chickens’ facilities. Two subsequent flocks with 960 birds each were distributed into 32 pens containing 30 birds each. In the first, the whole flock was inoculated with a known strain of Campylobacter jejuni in order to contaminate the environment. In the second flock, performance and microbiological evaluations were done, characterizing an observational study between 2 cleaning and disinfection programs, regular and proposed. The regular program consisted of sweeping facilities, washing equipment and environment with water and neutral detergent. The proposed cleaning program consisted of dry and wet cleaning, application of 2 detergents (one acid and one basic) and 2 disinfectants (250 g/L glutaraldehyde and 185 g/L formaldehyde at 0.5% and 210 g/L para-chloro-meta-cresol at 4%). Total microorganism count in the environment and Campylobacter spp. identification were done for the microbiological assessment of the environment and carcasses. The positive samples were submitted to molecular identification of Campylobacter spp. and posterior genetic sequencing of the species identified as Campylobacter jejuni. The birds housed in the facilities and submitted to the proposed treatment had better performance when compared to the ones in the regular treatment, most likely because there was a smaller total microorganism count on the floor, walls, feeders and drinkers. The proposed program also resulted in a reduction of Campylobacter spp. on

Novel Biocontrol Methods for Listeria monocytogenes Biofilms in Food Production Facilities

Directory of Open Access Journals (Sweden)

Jessica A. Gray

2018-04-01

Full Text Available High mortality and hospitalization rates have seen Listeria monocytogenes as a foodborne pathogen of public health importance for many years and of particular concern for high-risk population groups. Food manufactures face an ongoing challenge in preventing the entry of L. monocytogenes into food production environments (FPEs due to its ubiquitous nature. In addition to this, the capacity of L. monocytogenes strains to colonize FPEs can lead to repeated identification of L. monocytogenes in FPE surveillance. The contamination of food products requiring product recall presents large economic burden to industry and is further exacerbated by damage to the brand. Poor equipment design, facility layout, and worn or damaged equipment can result in Listeria hotspots and biofilms where traditional cleaning and disinfecting procedures may be inadequate. Novel biocontrol methods may offer FPEs effective means to help improve control of L. monocytogenes and decrease cross contamination of food. Bacteriophages have been used as a medical treatment for many years for their ability to infect and lyse specific bacteria. Endolysins, the hydrolytic enzymes of bacteriophages responsible for breaking the cell wall of Gram-positive bacteria, are being explored as a biocontrol method for food preservation and in nanotechnology and medical applications. Antibacterial proteins known as bacteriocins have been used as alternatives to antibiotics for biopreservation and food product shelf life extension. Essential oils are natural antimicrobials formed by plants and have been used as food additives and preservatives for many years and more recently as a method to prevent food spoilage by microorganisms. Competitive exclusion occurs naturally among bacteria in the environment. However, intentionally selecting and applying bacteria to effect competitive exclusion of food borne pathogens has potential as a biocontrol application. This review discusses these novel biocontrol

Novel Biocontrol Methods for Listeria monocytogenes Biofilms in Food Production Facilities

Science.gov (United States)

Gray, Jessica A.; Chandry, P. Scott; Kaur, Mandeep; Kocharunchitt, Chawalit; Bowman, John P.; Fox, Edward M.

2018-01-01

High mortality and hospitalization rates have seen Listeria monocytogenes as a foodborne pathogen of public health importance for many years and of particular concern for high-risk population groups. Food manufactures face an ongoing challenge in preventing the entry of L. monocytogenes into food production environments (FPEs) due to its ubiquitous nature. In addition to this, the capacity of L. monocytogenes strains to colonize FPEs can lead to repeated identification of L. monocytogenes in FPE surveillance. The contamination of food products requiring product recall presents large economic burden to industry and is further exacerbated by damage to the brand. Poor equipment design, facility layout, and worn or damaged equipment can result in Listeria hotspots and biofilms where traditional cleaning and disinfecting procedures may be inadequate. Novel biocontrol methods may offer FPEs effective means to help improve control of L. monocytogenes and decrease cross contamination of food. Bacteriophages have been used as a medical treatment for many years for their ability to infect and lyse specific bacteria. Endolysins, the hydrolytic enzymes of bacteriophages responsible for breaking the cell wall of Gram-positive bacteria, are being explored as a biocontrol method for food preservation and in nanotechnology and medical applications. Antibacterial proteins known as bacteriocins have been used as alternatives to antibiotics for biopreservation and food product shelf life extension. Essential oils are natural antimicrobials formed by plants and have been used as food additives and preservatives for many years and more recently as a method to prevent food spoilage by microorganisms. Competitive exclusion occurs naturally among bacteria in the environment. However, intentionally selecting and applying bacteria to effect competitive exclusion of food borne pathogens has potential as a biocontrol application. This review discusses these novel biocontrol methods and their

Veterans Affairs facility performance on Washington Circle indicators and casemix-adjusted effectiveness.

Science.gov (United States)

Harris, Alex H S; Humphreys, Keith; Finney, John W

2007-12-01

Self-administered Addiction Severity Index (ASI) data were collected on 5,723 patients who received substance abuse treatment in 1 of 110 programs located at 73 Veterans Affairs facilities. The associations between each of three Washington Circle (WC) performance indicator scores (identification, initiation, and engagement) and their casemix-adjusted facility-level improvement in ASI drug and alcohol composites 7 months after intake were estimated. Higher initiation rates were not associated with facility-level improvement in ASI alcohol composite scores but were modestly associated with greater improvements in ASI drug composite scores. Identification and engagement rates were unrelated to 7-month outcomes. WC indicators focused on the early stages of treatment may tap necessary but insufficient processes for patients with substance use disorder to achieve good posttreatment outcomes. Ideally, the WC indicators would be supplemented with other measures of treatment quality.

New electron beam facility for R&D and production at acsion industries

Science.gov (United States)

Lopata, V. J.; Barnard, J. W.; Saunders, C. B.; Stepanik, T. M.

2003-08-01

Since its incorporation in 1998, Acsion Industries Inc. has been working with clients to develop industrial uses of electron processing for improving products and manufacturing processes. Acsion has promoted this technology for sterilizing medical devices and pharmaceuticals, for treating wood pulp in the viscose/rayon process, for reducing pathogens in food and animal feed, and for curing advanced composites for the aerospace industry. As a result of significant developments in its composite curing programs, Acsion has recently made major modifications to its facility to increase its production and R&D capabilities. These modifications are described in this paper.

Improving primary health care facility performance in Ghana: efficiency analysis and fiscal space implications.

Science.gov (United States)

Novignon, Jacob; Nonvignon, Justice

2017-06-12

and public facilities. There is need for primary health facility managers to improve productivity via effective and efficient resource use. Efforts to improve efficiency should focus on training health workers and improving facility environment alongside effective monitoring and evaluation exercises.

Need to use probabilistic risk approach in performance assessment of waste disposal facilities

International Nuclear Information System (INIS)

Bonano, E.J.; Gallegos, D.P.

1991-01-01

Regulations governing the disposal of radioactive, hazardous, and/or mixed wastes will likely require, either directly or indirectly, that the performance of disposal facilities be assessed quantitatively. Such analyses, commonly called ''performance assessments,'' rely on the use of predictive models to arrive at a quantitative estimate of the potential impact of disposal on the environment and the safety and health of the public. It has been recognized that a suite of uncertainties affect the results of a performance assessment. These uncertainties are conventionally categorized as (1) uncertainty in the future state of the disposal system (facility and surrounding medium), (2) uncertainty in models (including conceptual models, mathematical models, and computer codes), and (3) uncertainty in data and parameters. Decisions regarding the suitability of a waste disposal facility must be made in light of these uncertainties. Hence, an approach is needed that would allow the explicit consideration of these uncertainties so that their impact on the estimated consequences of disposal can be evaluated. While most regulations for waste disposal do not prescribe the consideration of uncertainties, it is proposed that, even in such cases, a meaningful decision regarding the suitability of a waste disposal facility cannot be made without considering the impact of the attendant uncertainties. A probabilistic risk assessment (PRA) approach provides the formalism for considering the uncertainties and the technical basis that the decision makers can use in discharging their duties. A PRA methodology developed and demonstrated for the disposal of high-level radioactive waste provides a general framework for assessing the disposal of all types of wastes (radioactive, hazardous, and mixed). 15 refs., 1 fig., 1 tab

Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-09-01

This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{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 (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.

Summary of the last step of active test at separation facility and purification facility in Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Kuroishi, Yuuki; Iseki, Tadahiro; Mitani, Akira; Takahashi, Naoki; Tsujimura, Akino; Sato, Nobuharu; Inaba, Makoto; Itagaki, Takashi

2008-01-01

During the last step of Active Test (AT) at Rokkasho Reprocessing Plant (RRP), the performance of the Separation Facility, mainly for pulsed columns and mixer-settlers were tested; Diluent washing efficiency, Plutonium extraction and stripping efficiency, Decontamination factors of fission products and Uranium and plutonium losses into wastes. Also, those of the Plutonium purification unit in the Purification Facility have been checked; Diluent washing efficiency, Plutonium extraction and stripping efficiency and Plutonium losses into wastes. Test results were equivalent to or better than expected values. (author)

Radiological performance assessment for the E-Area Vaults Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Cook, J.R.; Hunt, P.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-04-15

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

Radiological performance assessment for the E-Area Vaults Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.; Hunt, P.D.

1994-01-01

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type

Design and selection criteria of a commercial irradiation facility for spices and dry products

International Nuclear Information System (INIS)

Aggarwal, K.S.

1990-01-01

Apart from cost considerations, various factors which should be taken into consideration in design of a commercial irradiation facility for spices and dry products and the factors which a user should consider for selecting a food irradiator are discussed in brief. (author)

A Tool for the Design of Facilities for the Sustainable Production of Knowledge

NARCIS (Netherlands)

Wu, J.

2005-01-01

The aim of the study is to develop a ‘design tool’, that is a method to enhance the design and planning of facilities for the sustainable production of new knowledge. More precisely, the objective is to identify a method to support the conception of building complexes related to the long-term

Cleaning and disinfection programs against Campylobacter jejuni for broiler chickens: productive performance, microbiological assessment and characterization.

Science.gov (United States)

Castro Burbarelli, Maria Fernanda de; do Valle Polycarpo, Gustavo; Deliberali Lelis, Karoline; Granghelli, Carlos Alexandre; Carão de Pinho, Agatha Cristina; Ribeiro Almeida Queiroz, Sabrina; Fernandes, Andrezza Maria; Moro de Souza, Ricardo Luiz; Gaglianone Moro, Maria Estela; de Andrade Bordin, Roberto; de Albuquerque, Ricardo

2017-09-01

Detailed cleaning and disinfection programs aims to reduce infection pressure from microorganisms from one flock to the next. However, studies evaluating the benefits to poultry performance, the sanitary status of the facilities, and the sanitary quality of the meat are rarely found. Thus, this study was designed to evaluate 2 cleaning and disinfecting programs regarding their influence on productive performance, elimination of Campylobacter, and characterization of Campylobacter jejuni strains when applied to broiler chickens' facilities. Two subsequent flocks with 960 birds each were distributed into 32 pens containing 30 birds each. In the first, the whole flock was inoculated with a known strain of Campylobacter jejuni in order to contaminate the environment. In the second flock, performance and microbiological evaluations were done, characterizing an observational study between 2 cleaning and disinfection programs, regular and proposed. The regular program consisted of sweeping facilities, washing equipment and environment with water and neutral detergent. The proposed cleaning program consisted of dry and wet cleaning, application of 2 detergents (one acid and one basic) and 2 disinfectants (250 g/L glutaraldehyde and 185 g/L formaldehyde at 0.5% and 210 g/L para-chloro-meta-cresol at 4%). Total microorganism count in the environment and Campylobacter spp. identification were done for the microbiological assessment of the environment and carcasses. The positive samples were submitted to molecular identification of Campylobacter spp. and posterior genetic sequencing of the species identified as Campylobacter jejuni. The birds housed in the facilities and submitted to the proposed treatment had better performance when compared to the ones in the regular treatment, most likely because there was a smaller total microorganism count on the floor, walls, feeders and drinkers. The proposed program also resulted in a reduction of Campylobacter spp. on floors

PLASMA ELECTRODE POCKELS CELL SUBSYSTEM PERFORMANCE IN THE NATIONAL IGNITION FACILITY

International Nuclear Information System (INIS)

Barbosa, F; Arnold, P; Hinz, A; Zacharias, R; Ollis, C; Fulkerson, E; Mchale, B; Runtal, A; Bishop, C

2007-01-01

The Plasma Electrode Pockels Cell (PEPC) subsystem is a key component of the National Ignition Facility, enabling the laser to employ an efficient four-pass main amplifier architecture. PEPC relies on a pulsed power technology to initiate and maintain plasma within the cells and to provide the necessary high voltage bias to the cells nonlinear crystals. Ultimately, nearly 300 high-voltage, high-current pulse generators will be deployed in the NIF in support of PEPC. Production of solid-state plasma pulse generators and thyratron-switched pulse generators is now complete, with the majority of the hardware deployed in the facility. An entire cluster (one-fourth of a complete NIF) has been commissioned and is operating on a routine basis, supporting laser shot operations. Another cluster has been deployed, awaiting final commissioning. Activation and commissioning of new hardware continues to progress in parallel, driving toward a goal of completing the PEPC subsystem in late 2007

UNC Nuclear Industries reactor and fuels production facilities 1985 effluent release report

International Nuclear Information System (INIS)

Rokkan, D.J.

1986-01-01

Analyses of routine samples from radioactive liquid and airborne streams were performed using UNC's Radioanalytical Laboratory and the analytical services of US Testing Company. All significant effluent discharges from UNC facilities to the environment during CY 1985 are reported in this document

The Precipitation Products Generation Chain for the EUMETSAT Hydrological Satellite Application Facility at C.N.M.C.A.

Science.gov (United States)

Zauli, Francesco; Biron, Daniele; Melfi, Davide

2009-11-01

The EUMETSA T Satellite Application Facility in support to Hydrology (H-SAF) focuses on the development of new geophysical products on precipitation, soil moisture and snow parameters and the utilisation of these parameters in hydrological models, NWP models and water management. The development phase of the H-SAF started in September 2005 under the leadership of Italian Meteorological Service.The Centro Nazionale di Meteorologia e Climatologia Aeronautica (C.N.M.C.A.), the Italian National Weather Centre, that physically hosts the generation chain of precipitation products, developed activities to reach the final target: development of algorithms, validation of results, implementation of operative procedure to supply the service and to monitor the service performances.The paper shows the recent architectural review of H- SAF precipitation group, stressing components of operation for high sustainability, full redundancy, absolute continuity of service.

Performance of Shiva as a laser fusion irradiation facility

International Nuclear Information System (INIS)

Speck, D.R.; Bliss, E.S.; Glaze, J.A.; Johnson, B.C.; Manes, K.R.; Ozarski, R.G.; Rupert, P.R.; Simmons, W.W.; Swift, C.D.; Thompson, C.E.

1979-01-01

Shiva is a 20 beam Nd:Glass Laser and Target Irradiation Facility at the Lawrence Livermore Laboratory. The laser system and integrated target facility evolved during the last year from a large, untested, experimental laser system to a target irradiation facility which has provided significant laser driven inertial confinement fusion data. The operation of the facility is discussed

Human reliability assessment in a 99Mo/99mTc generator production facility using the standardized plant analysis risk-human (SPAR-H) technique.

Science.gov (United States)

Eyvazlou, Meysam; Dadashpour Ahangar, Ali; Rahimi, Azin; Davarpanah, Mohammad Reza; Sayyahi, Seyed Soheil; Mohebali, Mehdi

2018-02-13

Reducing human error is an important factor for enhancing safety protocols in various industries. Hence, analysis of the likelihood of human error in nuclear industries such as radiopharmaceutical production facilities has become more essential. This cross-sectional descriptive study was conducted to quantify the probability of human errors in a 99 Mo/ 99m Tc generator production facility in Iran. First, through expert interviews, the production process of the 99 Mo/ 99m Tc generator was analyzed using hierarchical task analysis (HTA). The standardized plant analysis risk-human (SPAR-H) method was then applied in order to calculate the probability of human error. Twenty tasks were determined using HTA. All of the eight performance shaping factors (PSF S ) were evaluated for the tasks. The mean probability of human error was 0.320. The highest and the lowest probability of human error in the 99 Mo/ 99m Tc generator production process, related to the 'loading the generator with the molybdenum solution' task and the 'generator elution' task, were 0.858 and 0.059, respectively. Required measures for reducing the human error probability (HEP) were suggested. These measures were derived from the level of PSF S that were evaluated in this study.

Source term model evaluations for the low-level waste facility performance assessment

Energy Technology Data Exchange (ETDEWEB)

Yim, M.S.; Su, S.I. [North Carolina State Univ., Raleigh, NC (United States)

1995-12-31

The estimation of release of radionuclides from various waste forms to the bottom boundary of the waste disposal facility (source term) is one of the most important aspects of LLW facility performance assessment. In this work, several currently used source term models are comparatively evaluated for the release of carbon-14 based on a test case problem. The models compared include PRESTO-EPA-CPG, IMPACTS, DUST and NEFTRAN-II. Major differences in assumptions and approaches between the models are described and key parameters are identified through sensitivity analysis. The source term results from different models are compared and other concerns or suggestions are discussed.

Demonstration test operation of Feed Materials Production Center Biodenitrification Facility

International Nuclear Information System (INIS)

Benear, A.K.; Patton, J.B.

1987-01-01

A fluidized-bed biological denitrification (BDN) system was used to treat high-nitrate wastewater streams from a DOE owned uranium processing plant. A two-column system was used to demonstrate BDN operation on a production scale. In a continuous 200 hour rate determination period, the BDN processed over 1.6 million gallons that contained over 4700 kilograms of nitrate and nitrite nitrogen. The BDN removed an average 97% of the incoming nitrate and nitrite. The BDN effluent was discharged to the FMPC sewage treatment plant where it caused increased levels of TOD, TSS and fecal coliforms in the STP discharge. This indicated the BDN effluent will require treatment prior to discharge to the environment. Preliminary chemical consumption rates and associated costs of operation were determined. Several modifications and additions to the system were identified as necessary for the permanent production facility. 3 refs., 11 figs., 2 tabs

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.

Performance Measurement in Global Product Development

DEFF Research Database (Denmark)

Taylor, Thomas Paul; Ahmed-Kristensen, Saeema

2013-01-01

there is a requirement for the process to be monitored and measured relative to the business strategy of an organisation. It was found that performance measurement is a process that helps achieve sustainable business success, encouraging a learning culture within organisations. To this day, much of the research into how...... performance is measured has focussed on the process of product development. However, exploration of performance measurement related to global product development is relatively unexplored and a need for further research is evident. This paper contributes towards understanding how performance is measured...

Performance investigation of a salt gradient solar pond coupled with desalination facility near the Dead Sea

International Nuclear Information System (INIS)

Saleh, A.; Qudeiri, J.A.; Al-Nimr, M.A.

2011-01-01

Solar ponds provide the most convenient and least expensive option for heat storage for daily and seasonal cycles. This is particularly important for a desalination facility, if steady and constant water production is required. If, in addition to high storage capacity, other favorable conditions exist, the salt gradient solar ponds (SGSPs) are expected to be able to carry the entire load of a large-scale flash desalination plants without dependence upon supplementary sources. This paper presents a performance investigation of a SGSP coupled with desalination plant under Jordanian climatic conditions. This is particularly convenient in the Dead Sea region characterized by high solar radiation intensities, high ambient temperature most of the year, and by the availability of high concentration brine. It was found that a 3000 m 2 solar pond installed near the Dead Sea is able to provide an annual average production rate of 4.3 L min -1 distilled water compared with 3.3 L min -1 that would be produced by El Paso solar pond, which has the same surface area. Based on this study, solar ponds appear to be a feasible and an appropriate technology for water desalination near the Dead Sea in Jordan. -- Research highlights: → A performance investigation of a solar pond coupled with desalination plant. → Dead Sea area is characterized by availability of high solar radiation and brine. → The Dead Sea solar pond can provide production rate of 4.3 L min -1 . → El Paso solar pond has production rate of 3.32 L min -1 . The improvement is about 30%. → The solar pond with desalination investigated showed to be a feasible technology.

ESO Catalogue Facility Design and Performance

Science.gov (United States)

Moins, C.; Retzlaff, J.; Arnaboldi, M.; Zampieri, S.; Delmotte, N.; Forchí, V.; Klein Gebbinck, M.; Lockhart, J.; Micol, A.; Vera Sequeiros, I.; Bierwirth, T.; Peron, M.; Romaniello, M.; Suchar, D.

2013-10-01

The ESO Phase 3 Catalogue Facility provides investigators with the possibility to ingest catalogues resulting from ESO public surveys and large programs and to query and download their content according to positional and non-positional criteria. It relies on a chain of tools that covers the complete workflow from submission to validation and ingestion into the ESO archive and catalogue repository and a web application to browse and query catalogues. This repository consists of two components. One is a Sybase ASE relational database where catalogue meta-data are stored. The second one is a Sybase IQ data warehouse where the content of each catalogue is ingested in a specific table that returns all records matching a user's query. Spatial indexing has been implemented in Sybase IQ to speed up positional queries and relies on the Spherical Geometry Toolkit from the Johns Hopkins University which implements the Hierarchical Triangular Mesh (HTM) algorithm. It is based on a recursive decomposition of the celestial sphere in spherical triangles and the assignment of an index to each of them. It has been complemented with the use of optimized indexes on the non-positional columns that are likely to be frequently used as query constraints. First tests performed on catalogues such as 2MASS have confirmed that this approach provides a very good level of performance and a smooth user experience that are likely to facilitate the scientific exploitation of catalogues.

Characterization of uranium corrosion products involved in the March 13, 1998 fuel manufacturing facility pyrophoric event

International Nuclear Information System (INIS)

Totemeier, T.C.

1999-01-01

Uranium metal corrosion products from ZPPR fuel plates involved in the March 13, 1998 pyrophoric event in the Fuel Manufacturing Facility at Argonne National Laboratory-West were characterized using thermo-gravimetric analysis, X-ray diffraction, and BET gas sorption techniques. Characterization was performed on corrosion products in several different conditions: immediately after separation from the source metal, after low-temperature passivation, after passivation and extended vault storage, and after burning in the pyrophoric event. The ignition temperatures and hydride fractions of the corrosion product were strongly dependent on corrosion extent. Corrosion products from plates with corrosion extents less than 0.7% did not ignite in TGA testing, while products from plates with corrosion extents greater than 1.2% consistently ignited. Corrosion extent is defined as mass of corrosion products divided by the total mass of uranium. The hydride fraction increased with corrosion extent. There was little change in corrosion product properties after low-temperature passivation or vault storage. The burned products were not reactive and contained no hydride; the principal constituents were UO 2 and U 3 O 7 . The source of the event was a considerable quantity of reactive hydride present in the corrosion products. No specific ignition mechanism could be conclusively identified. The most likely initiator was a static discharge in the corrosion product from the 14th can as it was poured into the consolidation can. The available evidence does not support scenarios in which the powder in the consolidation can slowly self-heated to the ignition point, or in which the powder in the 14th can was improperly passivated

Characterization of uranium corrosion products involved in the March 13, 1998 fuel manufacturing facility pyrophoric event.

Energy Technology Data Exchange (ETDEWEB)

Totemeier, T.C.

1999-04-26

Uranium metal corrosion products from ZPPR fuel plates involved in the March 13, 1998 pyrophoric event in the Fuel Manufacturing Facility at Argonne National Laboratory-West were characterized using thermo-gravimetric analysis, X-ray diffraction, and BET gas sorption techniques. Characterization was performed on corrosion products in several different conditions: immediately after separation from the source metal, after low-temperature passivation, after passivation and extended vault storage, and after burning in the pyrophoric event. The ignition temperatures and hydride fractions of the corrosion product were strongly dependent on corrosion extent. Corrosion products from plates with corrosion extents less than 0.7% did not ignite in TGA testing, while products from plates with corrosion extents greater than 1.2% consistently ignited. Corrosion extent is defined as mass of corrosion products divided by the total mass of uranium. The hydride fraction increased with corrosion extent. There was little change in corrosion product properties after low-temperature passivation or vault storage. The burned products were not reactive and contained no hydride; the principal constituents were UO{sub 2} and U{sub 3}O{sub 7}. The source of the event was a considerable quantity of reactive hydride present in the corrosion products. No specific ignition mechanism could be conclusively identified. The most likely initiator was a static discharge in the corrosion product from the 14th can as it was poured into the consolidation can. The available evidence does not support scenarios in which the powder in the consolidation can slowly self-heated to the ignition point, or in which the powder in the 14th can was improperly passivated.

Lambdastation: a forwarding and admission control service to interface production network facilities with advanced research network paths

Energy Technology Data Exchange (ETDEWEB)

DeMar, Philip; Petravick, Don; /Fermilab

2004-12-01

Over the past several years, there has been a great deal of research effort and funding put into the deployment of optical-based, advanced technology wide-area networks. Fermilab and CalTech have initiated a project to enable our production network facilities to exploit these advanced research network facilities. Our objective is to forward designated data transfers across these advanced wide area networks on a per-flow basis, making use our capacious production-use storage systems connected to the local campus network. To accomplish this, we intend to develop a dynamically provisioned forwarding service that would provide alternate path forwarding onto available wide area advanced research networks. The service would dynamically reconfigure forwarding of specific flows within our local production-use network facilities, as well as provide an interface to enable applications to utilize the service. We call this service LambdaStation. If one envisions wide area optical network paths as high bandwidth data railways, then LambdaStation would functionally be the railroad terminal that regulates which flows at the local site get directed onto the high bandwidth data railways. LambdaStation is a DOE-funded SciDac research project in its very early stage of development.

Performance assessment studies for the long-term safety evaluation of radioactive waste disposal facility

International Nuclear Information System (INIS)

Bujoreanu, D.; Olteanu, M.; Bujoreanu, L.

2008-01-01

Especially during the last ten years, a part of Romanian research program 'Management of Radioactive Waste and Spent Fuel' was focused mainly on applicative research for the design of near-surface disposal facility, which intends to accommodate the low and intermediate radioactive waste generated from Cernavoda NPP. In this frame, our contribution was at the acquisition of technical data for the characterization of the future disposal facility. In the present, the project of the disposal facility, located on the Saligny site, near Cernavoda NPP, must be licensed. As regards to the safe disposal, the location of final disposal, the Saligny site, has been characterized through the five geological formations which contain potential routes for transport of radionuclide released from disposal facility, in the receiving zones(potential receiving zones), into liquid and gaseous phases. The technical characteristics of the disposal facility were adapted at the Romanian disposal concept using the reference data from IAEA technical report (IAEA,1999). Input parameters which characterized from physical and chemical point of view the disposal system, were partially taken from literature. The performance assessment studies, which follows the preliminary design development phases and the selection, describes how the source term is affected by the infiltration of water through the disposal facility, degradation process of engineering barriers (reflected in the distribution coefficient values) and solubility limit. The studies regard the evaluation of the source term, sensitivity and uncertainty analysis provide the information on 'how' and 'why' were evaluated, following: (i) radiological safety assessment of near-surface disposal facility on Saligny site; (ii) complexity standard assessment of the Engineering Barriers Systems (EBS); (iii) identification of the elements which must be elaborated for the increase of the disposal safety and the necessity for new technical data for

Facility overview for commercial application of selected Rocky Flats facilities

International Nuclear Information System (INIS)

1996-11-01

The purpose of this Facility Overview is to support the Rocky Flats Local Impacts Initiative's Request for Interest, to solicit interest from commercial corporations for utilizing buildings 865 and 883, and the equipment contained within each building, for a commercial venture. In the following sections, this document describes the Rocky Flats Site, the buildings available for lease, the equipment within these buildings, the site services available to a tenant, the human resources available to support operations in buildings 865 and 883, and the environmental condition of the buildings and property. In addition, a brief description is provided of the work performed to date to explore the potential products that might be manufactured in Buildings 865 and 883, and the markets for these products

Antifoam Degradation Products in Off Gas and Condensate of Sludge Batch 9 Simulant Nitric-Formic Flowsheet Testing for the Defense Waste Processing Facility

Energy Technology Data Exchange (ETDEWEB)

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

2016-04-14

Ten chemical processing cell (CPC) experiments were performed using simulant to evaluate Sludge Batch 9 for sludge-only and coupled processing using the nitric-formic flowsheet in the Defense Waste Processing Facility (DWPF). Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) cycles were performed on eight of the ten. The other two were SRAT cycles only. Samples of the condensate, sludge, and off gas were taken to monitor the chemistry of the CPC experiments. The Savannah River National Laboratory (SRNL) has previously shown antifoam decomposes to form flammable organic products, (hexamethyldisiloxane (HMDSO), trimethylsilanol (TMS), and propanal), that are present in the vapor phase and condensate of the CPC vessels. To minimize antifoam degradation product formation, a new antifoam addition strategy was implemented at SRNL and DWPF to add antifoam undiluted.

Strategic interaction among hospitals and nursing facilities: the efficiency effects of payment systems and vertical integration.

Science.gov (United States)

Banks, D; Parker, E; Wendel, J

2001-03-01

Rising post-acute care expenditures for Medicare transfer patients and increasing vertical integration between hospitals and nursing facilities raise questions about the links between payment system structure, the incentive for vertical integration and the impact on efficiency. In the United States, policy-makers are responding to these concerns by initiating prospective payments to nursing facilities, and are exploring the bundling of payments to hospitals. This paper develops a static profit-maximization model of the strategic interaction between the transferring hospital and a receiving nursing facility. This model suggests that the post-1984 system of prospective payment for hospital care, coupled with nursing facility payments that reimburse for services performed, induces inefficient under-provision of hospital services and encourages vertical integration. It further indicates that the extension of prospective payment to nursing facilities will not eliminate the incentive to vertically integrate, and will not result in efficient production unless such integration takes place. Bundling prospective payments for hospitals and nursing facilities will neither remove the incentive for vertical integration nor induce production efficiency without such vertical integration. However, bundled payment will induce efficient production, with or without vertical integration, if nursing facilities are reimbursed for services performed. Copyright 2001 John Wiley & Sons, Ltd.

Performance assessment review for DOE LLW disposal facilities

International Nuclear Information System (INIS)

Wilhite, Elmer L.

1992-01-01

The United States Department of Energy (US DOE) disposes of low-level radioactive waste in near-surface disposal facilities. Safety of the disposal operations is evaluated for operational safety as well as long-term safety. Operational safety is evaluated based on the perceived level of hazard of the operation and may vary from a simple safety assessment to a safety analysis report. Long-term safety of all low-level waste disposal systems is evaluated through the conduct of a radiological performance assessment. The US DOE has established radiological performance objectives for disposal of low-level waste. They are to protect a member of the general public from receiving over 25 mrem/y, and an inadvertent intruder into the waste from receiving over 100 mrem/y continuous exposure or 500 mrem from a single exposure. For a disposal system to be acceptable, a performance assessment must be prepared which must be technically accurate and provide reasonable assurance that these performance objectives are met. Technical quality of the performance assessments is reviewed by a panel of experts. The panel of experts is used in two ways to assure the technical quality of performance assessment. A preliminary (generally 2 day) review by the panel is employed in the late stages of development to provide guidance on finalizing the performance assessment. The comments from this review are communicated to the personnel responsible for the performance assessment for consideration and incorporation. After finalizing the performance assessment, it is submitted for a formal review. The formal review is accomplished by a much more thorough analysis of the performance assessment over a multi-week time period. The panel then formally reports their recommendations to the US DOE waste management senior staff who make the final determination on acceptability of the performance assessment. A number of lessons have been learned from conducting several preliminary reviews of performance

Performance evaluation on aquatic product cold-chain logistics

Directory of Open Access Journals (Sweden)

Wenbing Wu

2015-11-01

Full Text Available Purpose: The requirements for high quality and diversification aquatic products are increasing with the improvement of Chinese living standard. However, the distribution between place of production and place of consumption are uneven, which results in large cold-chain logistics demand for aquatic products. At present, the low-level development of cold chain logistics has a bad impact on the circulation of aquatic products in China. So it is very urgent to develop cold-chain logistics in China. Design/methodology/approach: In order to do this, we apply performance evaluation, a well-known management tool, to study Chinese aquatic product cold-chain logistics. In this paper we first propose SISP(Subjects, Indexes, Standards, and Phases of performance evaluation model and ACSSN model(Aquatic product, Customer, Supply Chain, Society, and Node enterprises of supply chain for aquatic products cold-chain logistics performance evaluation. Then an ANP-Fuzzy method is proposed to evaluate the operational performance of Shandong Oriental Ocean Sci-Tech Co., Ltd. Furthermore, a system dynamic model is built to simulate the impact of temperature on the profits in aquatic products cold-chain sales section. Findings: We find out within a reasonable temperature range, lower temperature brings higher profit level. Also, performance improvement methods are proposed and the simulation of performance evaluation system is developed. Practical implications: Our findings can help to improve the level of aquatic product cold-chain logistics in China. Originality/value: The paper proposes the SISP (Subjects, Indexes, Standards, and Phases of performance evaluation model and ACSSN model (Aquatic product, Customer, Supply Chain, Society, and Node enterprises of supply chain for aquatic products cold-chain logistics performance evaluation.

Study of In-Pile test facility for fast reactor safety research: performance requirements and design features

Energy Technology Data Exchange (ETDEWEB)

Nonaka, N.; Kawatta, N.; Niwa, H.; Kondo, S.; Maeda, K

1996-12-31

This paper describes a program and the main design features of a new in-pile safety facility SERAPH planned for future fast reactor safety research. The current status of R and D on technical developments in relation to the research objectives and performance requirements to the facility design is given.

Activation of air and concrete in medical isotope production facilities

Science.gov (United States)

Dodd, Adam C.; Shackelton, R. J.; Carr, D. A.; Ismail, A.

2017-05-01

Medical isotope facilities operating in the 10 to 25 MeV proton energy range have long been used to generate radioisotopes for medical diagnostic imaging. In the last few years the beam currents available in commercially available cyclotrons have increased dramatically, and so the activation of the materials within cyclotron vaults may now pose more serious radiological hazards. This will impact the regulatory oversight of cyclotron operations, cyclotron servicing and future decommissioning activities. Air activation could pose a hazard to cyclotron staff. With the increased cyclotron beam currents it was necessary to examine the issue more carefully. Therefore the ways in which radioactivity may be induced in air by neutron reactions and neutron captures were considered and it was found that the dominant mechanism is neutron capture on Ar-40. A study of the activation of the air by neutron capture on Ar-40 within a cyclotron vault was performed using the MCNP Monte Carlo code. The neutron source energy spectrum used was from the production of the widely used F-18 PET isotope. The results showed that the activation of the air within a cyclotron vault does not pose a significant radiological hazard at the beam intensities currently in use and shows how ventilation affects the results. A second MCNP study on the activation of ordinary concrete in cyclotron vaults by neutron capture was made with a view to determining the optimum thickness of borated polyethylene to reduce neutron activation on both the inner surfaces of the vault and around production targets. This is of importance in decommissioning cyclotrons and therefore in the design of new cyclotron vaults. The distribution of activation on the walls as a function of the source position was also studied. Results are presented for both borated and regular polyethylene, and F-18 and Tc-99 neutron spectra.

Characteristics and performance of a superconducting bumpy-torus magnet facility for plasma research

Science.gov (United States)

Roth, J. R.; Holmes, A. D.; Keller, T. A.; Krawczonek, W. M.

1973-01-01

The NASA Lewis bumpy-torus facility consists of 12 superconducting coils, each 19 cm i.d. and capable of 3.0 T on its axis. The coils are equally spaced around a toroidal array with a major diameter of 1.52 m; they are mounted with the major axis of the torus vertical in a single vacuum tank 2.6 m in diameter. Tests of the facility mapped out its magnetic, cryogenic, vacuum, mechanical, and electrical performance. The design value of the maximum magnetic field on the magnetic axis, 3.0 T, was reached and exceeded. A maximum magnetic field of 3.23 T was held for a period of 60 minutes. When the coils were charged to a maximum magnetic field of 3.35 T, the coil system went normal without apparent damage or degradation of performance.

PNRI Pioneering the Establishment and Operation of the Tc-99m Generator Production Facility for Nuclear Medicine Applications

International Nuclear Information System (INIS)

Bulos, Adelina DM.; Borras, Ma. Teresa L.; Ciocson, Gregory R.; Mascariñas, Rommel D.C.; Nuñez, Ivy Angelica A.; Dela Rosa, Alumanda M.

2015-01-01

In response to the increasing demand in the nuclear medicine sector in the Philippines, the Philippine Nuclear Research Institute (PNRI) initiated the establishment of a radioisotope production facility. To date, the most commonly used radioisotope in nuclear medicine, Technetium-99m or Tc-99m has been successfully produced in the new laboratory, the PNRI facility has already obtained a license to operate from the Philippine FDA. The new facility is envisioned to meet the country’s requirements for all the major medical radioisotope starting with the local production of Tc-99m and the most commonly used Tc-99m radiopharmaceuticals. At present, all radioisotope supplies in the country are sourced overseas at price that varies accordingly. With the establishment of the PNRI’s laboratories, we now have a GMP-grade Tc-99m generator facility capable of producing 50 Tc-99m generators per batch. Instead of Tc-99m being imported, it will be the parent Mo-99m that will be transferred to PNRI facility from Mo-99 processing facilities overseas, contained in specialized transport containers and via airfreight arrangements so it can be processed locally to make Tc-99m generators. But, to make radiopharmaceuticals, the other non-radioactive components are needed to be sourced from abroad. Thus, it has become imperative to also locally produce these non-radioactive components. All of these components, radioactive and non-radioactive, from the radiopharmaceutical finished products which are utilized in nuclear medicine caters for the diagnosis and detection of critical and non-critical human illnesses. The completion of this program is foreseen as another concrete validation on the capacity of the Philippine as a country that is at par with advanced nations on competency and expertise in the research and development of nuclear medicine application for better healthcare delivery and management. (author)

Fluidized column biodenitrification demonstration facility at the FMPC [Feed Materials Production Center

International Nuclear Information System (INIS)

Patton, J.B.

1987-02-01

The mission of the Fernald Ohio Feed Materials Production Center, owned by DOE and operated by Westinghouse Materials Company of Ohio, is to produce uranium metal primarily for fuel in production reactors at Hanford, Washington, and Savannah River, South Carolina. Several waste streams result from production that are combined in the plant general sump and processed through settling basins prior to discharge. Individual streams have varying nitrate concentrations which, when combined, may range up to about 10,000 milligrams/liter. A fluidized-bed technology has been operated to demonstrate nitrate reduction by bacteriological denitrification on production scale. The system consists of two columns operating in series. The demonstration run will be considering: rate of biodenitrification; methyl alcohol consumption (bacterial substrate); sulfuric acid requirement (pH adjustment); accommodation of the biomass by the plant sewage treatment facility; flexibility of the system to receive a waste stream which varies in both volume and nitrate concentration; and modification and/or additions needed in the system to function as a permanent production operation. 8 figs

Predictive analytics tools to adjust and monitor performance metrics for the ATLAS Production System

CERN Document Server

Titov, Mikhail; The ATLAS collaboration

2017-01-01

Every scientific workflow involves an organizational part which purpose is to plan an analysis process thoroughly according to defined schedule, thus to keep work progress efficient. Having such information as an estimation of the processing time or possibility of system outage (abnormal behaviour) will improve the planning process, provide an assistance to monitor system performance and predict its next state. The ATLAS Production System is an automated scheduling system that is responsible for central production of Monte-Carlo data, highly specialized production for physics groups, as well as data pre-processing and analysis using such facilities as grid infrastructures, clouds and supercomputers. With its next generation (ProdSys2) the processing rate is around 2M tasks per year that is more than 365M jobs per year. ProdSys2 evolves to accommodate a growing number of users and new requirements from the ATLAS Collaboration, physics groups and individual users. ATLAS Distributed Computing in its current stat...

Lignocellulosic ethanol production from woody biomass: The impact of facility siting on competitiveness

International Nuclear Information System (INIS)

Stephen, James D.; Mabee, Warren E.; Saddler, Jack N.

2013-01-01

Just as temperate region pulp and paper companies need to compete with Brazilian eucalyptus pulp producers, lignocellulosic biofuel producers in North America and Europe, in the absence of protectionist trade policies, will need to be competitive with tropical and sub-tropical biofuel producers. This work sought to determine the impact of lignocellulosic ethanol biorefinery siting on economic performance and minimum ethanol selling price (MESP) for both east and west coast North American fuel markets. Facility sites included the pine-dominated Pacific Northwest Interior, the mixed deciduous forest of Ontario and New York, and the Brazilian state of Espírito Santo. Feedstock scenarios included both plantation (poplar, willow, and eucalyptus, respectively) and managed forest harvest. Site specific variables in the techno-economic model included delivered feedstock cost, ethanol delivery cost, cost of capital, construction cost, labour cost, electricity revenues (and co-product credits), and taxes, insurance, and permits. Despite the long shipping distance from Brazil to North American east and west coast markets, the MESP for Brazilian-produced eucalyptus lignocellulosic ethanol, modelled at $0.74 L −1 , was notably lower than that of all North American-produced cases at $0.83–1.02 L −1 . - Highlights: • Lignocellulosic ethanol production costs vary notably by region. • Feedstock cost is the primary site-specific production cost variable. • Woody feedstocks in North America have a higher cost than those in Brazil. • Use of Brazilian eucalyptus resulted in the lowest MESP for considered feedstocks. • MESP ranged from −1 to >$1.00 L −1

Independent Review of Siesmic Performance Assessments for the Plutonium Facility PF-4

Energy Technology Data Exchange (ETDEWEB)

Whittaker, Andrew [State Univ. of New York (SUNY), Buffalo, NY (United States); Goen, Lawrence Kenneth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kennedy, Robert [RPK Structural Mechanics, San Diego, CA (United States); McDonald, Brian [Exponent, Los Angeles, CA (United States); Morgan, Troy [Exponent, Los Angeles, CA (United States); Wyllie, Loring [Degenkolb Engineers, San Francisco, CA (United States)

2015-11-25

The Plutonium Facility, designated PF-4, is located in Technical Area 55 at the Los Alamos National Laboratory (LANL). The facility is a one-story rectangular structure above a complete basement; the building was constructed of cast-in-place reinforced concrete, with small interior frames of structural steel. The plan dimensions of the building are 265’×284’. The overall height of the building varies between 39’-0” at the north and south ends, and 40’-6” at the center ridge. The programmatic work performed in the building is vital to our national security and its functions and storage purposes are not replicated elsewhere in the United States Department of Energy (DOE).

A Long-Pulse Spallation Source at Los Alamos: Facility description and preliminary neutronic performance for cold neutrons

International Nuclear Information System (INIS)

Russell, G.J.; Weinacht, D.J.; Pitcher, E.J.; Ferguson, P.D.

1998-03-01

The Los Alamos National Laboratory has discussed installing a new 1-MW spallation neutron target station in an existing building at the end of its 800-MeV proton linear accelerator. Because the accelerator provides pulses of protons each about 1 msec in duration, the new source would be a Long Pulse Spallation Source (LPSS). The facility would employ vertical extraction of moderators and reflectors, and horizontal extraction of the spallation target. An LPSS uses coupled moderators rather than decoupled ones. There are potential gains of about a factor of 6 to 7 in the time-averaged neutron brightness for cold-neutron production from a coupled liquid H 2 moderator compared to a decoupled one. However, these gains come at the expense of putting ''tails'' on the neutron pulses. The particulars of the neutron pulses from a moderator (e.g., energy-dependent rise times, peak intensities, pulse widths, and decay constant(s) of the tails) are crucial parameters for designing instruments and estimating their performance at an LPSS. Tungsten is the reference target material. Inconel 718 is the reference target canister and proton beam window material, with Al-6061 being the choice for the liquid H 2 moderator canister and vacuum container. A 1-MW LPSS would have world-class neutronic performance. The authors describe the proposed Los Alamos LPSS facility, and show that, for cold neutrons, the calculated time-averaged neutronic performance of a liquid H 2 moderator at the 1-MW LPSS is equivalent to about 1/4th the calculated neutronic performance of the best liquid D 2 moderator at the Institute Laue-Langevin reactor. They show that the time-averaged moderator neutronic brightness increases as the size of the moderator gets smaller

New electron beam facility for R and D and production at acsion industries

Energy Technology Data Exchange (ETDEWEB)

Lopata, V.J.; Barnard, J.W.; Saunders, C.B.; Stepanik, T.M. E-mail: stepanik@acsion.com

2003-08-01

Since its incorporation in 1998, Acsion Industries Inc. has been working with clients to develop industrial uses of electron processing for improving products and manufacturing processes. Acsion has promoted this technology for sterilizing medical devices and pharmaceuticals, for treating wood pulp in the viscose/rayon process, for reducing pathogens in food and animal feed, and for curing advanced composites for the aerospace industry. As a result of significant developments in its composite curing programs, Acsion has recently made major modifications to its facility to increase its production and R and D capabilities. These modifications are described in this paper.

Moly99 Production Facility: Report on Beamline Components, Requirements, Costs

Energy Technology Data Exchange (ETDEWEB)

Bishofberger, Kip A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-23

In FY14 we completed the design of the beam line for the linear accelerator production design concept. This design included a set of three bending magnets, quadrupole focusing magnets, and octopoles to flatten the beam on target. This design was generic and applicable to multiple different accelerators if necessary. In FY15 we built on that work to create specifications for the individual beam optic elements, including power supply requirements. This report captures the specification of beam line components with initial cost estimates for the NorthStar production facility.This report is organized as follows: The motivation of the beamline design is introduced briefly, along with renderings of the design. After that, a specific list is provided, which accounts for each beamline component, including part numbers and costs, to construct the beamline. After that, this report details the important sections of the beamline and individual components. A final summary and list of follow-on activities completes this report.

Money for Research, Not for Energy Bills: Finding Energy and Cost Savings in High Performance Computer Facility Designs

Energy Technology Data Exchange (ETDEWEB)

Drewmark Communications; Sartor, Dale; Wilson, Mark

2010-07-01

High-performance computing facilities in the United States consume an enormous amount of electricity, cutting into research budgets and challenging public- and private-sector efforts to reduce energy consumption and meet environmental goals. However, these facilities can greatly reduce their energy demand through energy-efficient design of the facility itself. Using a case study of a facility under design, this article discusses strategies and technologies that can be used to help achieve energy reductions.

Performance Evaluation Facility for Fire Fighting Thermal Imager

International Nuclear Information System (INIS)

Kim, Sung Chan; Amon, Francine; Hamins, Anthony

2007-01-01

The present study investigates the characteristics of obscuring media inside an optical smoke cell, which is a bench-scale testing facility for the evaluation of thermal imaging cameras used by fire fighters. Light extinction coefficient and visibility through the smoke cell is characterized by the measured laser transmittance. The laser transmittance along the axial direction of the smoke cell is relatively uniform at upper and lower part for various air/fuel volume flow rate. Contrast level based image quality of visible CCD camera through the smoke cell is compared with that of thermal imaging camera. The optical smoke cell can be used as well-controlled and effective laboratory-scale test apparatus to evaluate the performance of thermal imaging camera for fire fighting application

Current developments of fuel fabrication technologies at the plutonium fuel production facility, PFPF

International Nuclear Information System (INIS)

Asakura, K.; Aono, S.; Yamaguchi, T.; Deguchi, M.

2000-01-01

The Japan Nuclear Cycle Development Institute, JNC, designed, constructed and has operated the Plutonium Fuel Production Facility, PFPF, at the JNC Tokai Works to supply MOX fuels to the proto-type Fast Breeder Reactor, FBR, 'MONJU' and the experimental FBR 'JOYO' with 5 tonMOX/year of fabrication capability. Reduction of personal radiation exposure to a large amount of plutonium is one of the most important subjects in the development of MOX fabrication facility on a large scale. As the solution of this issue, the PFPF has introduced automated and/or remote controlled equipment in conjunction with computer controlled operation scheme. The PFPF started its operation in 1988 with JOYO reload fuel fabrication and has demonstrated MOX fuel fabrication on a large scale through JOYO and MONJU fuel fabrication for this decade. Through these operations, it has become obvious that several numbers of equipment initially installed in the PFPF need improvements in their performance and maintenance for commercial utilization of plutonium in the future. Furthermore, fuel fabrication of low density MOX pellets adopted in the MONJU fuel required a complete inspection because of difficulties in pellet fabrication compared with high density pellet for JOYO. This paper describes new pressing equipment with a powder recovery system, and pellet finishing and inspection equipment which has multiple functions, such as grinding measurements of outer diameter and density, and inspection of appearance to improve efficiency in the pellet finishing and inspection steps. Another development of technology concerning an annular pellet and an innovative process for MOX fuel fabrication are also described in this paper. (author)

A facile production of microporous carbon spheres and their electrochemical performance in EDLC

Science.gov (United States)

Xia, Xiaohong; Shi, Lei; Liu, Hongbo; Yang, Li; He, Yuede

2012-03-01

In the absence of activation process, we prepared a series of carbon particles from saccharine, in which hydrothermal carbonization method was used. These particles have spherical or near-spherical morphology, controllable monodisperse particle size from the analyses of SEM. Raman and XRD results show that they are nongraphitizable. The BET surface area of these carbon spherules is around 400-500 m2 g-1 and the microporosity is about 84%, suggesting that the carbon particles are rich in micropores. The electrochemical behaviors were characterized by means of galvanostatic charging/discharging, cycle voltammetry and impedance spectroscopy. The results show that the specific capacitance of sucrose-based carbon spherule reached 164 F g-1 in 30% KOH electrolyte and a high volumetric capacitance over 170 F cm-3 was obtained. These carbon spherules could be promising materials for EDLC according to their facile preparation way, low cost and high packing density.

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

Energy Technology Data Exchange (ETDEWEB)

Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

International Nuclear Information System (INIS)

Rosenberger, Kent H.

2013-01-01

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling

Accelerator-driven subcritical facility:Conceptual design development

Science.gov (United States)

Gohar, Yousry; Bolshinsky, Igor; Naberezhnev, Dmitry; Duo, Jose; Belch, Henry; Bailey, James

2006-06-01

A conceptual design development of an accelerator-driven subcritical facility has been carried out in the preparation of a joint activity with Kharkov Institute of Physics and Technology of Ukraine. The main functions of the facility are the medical isotope production and the support of the Ukraine nuclear industry. An electron accelerator is considered to drive the subcritical assembly. The neutron source intensity and spectrum have been studied. The energy deposition, spatial neutron generation, neutron utilization fraction, and target dimensions have been quantified to define the main target performance parameters, and to select the target material and beam parameters. Different target conceptual designs have been developed based the engineering requirements including heat transfer, thermal hydraulics, structure, and material issues. The subcritical assembly is designed to obtain the highest possible neutron flux level with a Keff of 0.98. Different fuel materials, uranium enrichments, and reflector materials are considered in the design process. The possibility of using low enrichment uranium without penalizing the facility performance is carefully evaluated. The mechanical design of the facility has been developed to maximize its utility and minimize the time for replacing the target and the fuel assemblies. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements, upgrades, and new missions. In addition, it has large design margins to accommodate different operating conditions and parameters. In this paper, the conceptual design and the design analyses of the facility will be presented.

Study on control characteristics for HTTR hydrogen production system with mock-up test facility

International Nuclear Information System (INIS)

Inaba, Yoshitomo; Ohashi, Hirofumi; Nishihara, Tetsuo; Sato, Hiroyuki; Inagaki, Yoshiyuki; Takeda, Tetsuaki; Hayashi, Koji; Takada, Shoji

2005-01-01

The Japan Atomic Energy Research Institute has a demonstration test plan of a hydrogen production system by steam reforming of methane coupling with the High-Temperature Engineering Test Reactor (HTTR). Prior to the coupling of a hydrogen production plant with the HTTR, simulation tests with a mock-up test facility of the HTTR hydrogen production system (HTTR-H2) is underway. The test facility is a 1/30-scale of the HTTR-H2 and simulates key components downstream from an intermediate heat exchanger of the HTTR. The main objective of the simulation tests is the establishment and demonstration of control technology, focusing on the mitigation of a thermal disturbance to the reactor by a steam generator (SG) and on the controllability of the pressure difference between the helium and process gases at the reaction tube in a steam reformer (SR). It was confirmed that the fluctuation of the outlet helium gas temperature at the SG and the pressure difference in the SR can be controlled within the allowable range for the HTTR-H2 in the case of the system controllability test for the fluctuation of chemical reaction. In addition, a dynamic simulation code for the HTTR-H2 was verified with the obtained test data

New Ideas on Facilities Management.

Science.gov (United States)

Grimm, James C.

1986-01-01

Examines trends in facilities management relating to products and people. Reviews new trends in products, including processes, techniques, and programs that are being expounded by business and industry. Discusses the "people factors" involved in facilities management. (ABB)

Capacity optimization and scheduling of a multiproduct manufacturing facility for biotech products.

Science.gov (United States)

Shaik, Munawar A; Dhakre, Ankita; Rathore, Anurag S; Patil, Nitin

2014-01-01

A general mathematical framework has been proposed in this work for scheduling of a multiproduct and multipurpose facility involving manufacturing of biotech products. The specific problem involves several batch operations occurring in multiple units involving fixed processing time, unlimited storage policy, transition times, shared units, and deterministic and fixed data in the given time horizon. The different batch operations are modeled using state-task network representation. Two different mathematical formulations are proposed based on discrete- and continuous-time representations leading to a mixed-integer linear programming model which is solved using General Algebraic Modeling System software. A case study based on a real facility is presented to illustrate the potential and applicability of the proposed models. The continuous-time model required less number of events and has a smaller problem size compared to the discrete-time model. © 2014 American Institute of Chemical Engineers.

Minnesota's Nursing Facility Performance-Based Incentive Payment Program: An Innovative Model for Promoting Care Quality

Science.gov (United States)

Cooke, Valerie; Arling, Greg; Lewis, Teresa; Abrahamson, Kathleen A.; Mueller, Christine; Edstrom, Lisa

2010-01-01

Purpose: Minnesota's Nursing Facility Performance-Based Incentive Payment Program (PIPP) supports provider-initiated projects aimed at improving care quality and efficiency. PIPP moves beyond conventional pay for performance. It seeks to promote implementation of evidence-based practices, encourage innovation and risk taking, foster collaboration…

Safety performance assessment of food industry facilities using a fuzzy approach

Directory of Open Access Journals (Sweden)

F. Barreca

2013-09-01

Full Text Available The latest EU policies focus on the issue of food safety with a view to assuring adequate and standard quality levels for the food produced and/or consumed within the EC. To that purpose, the environment where agricultural products are manufactured and processed plays a crucial role in achieving food hygiene. As a consequence, it is of the utmost importance to adopt proper building solutions which meet health and hygiene requirements and to use suitable tools to measure the levels achieved. Similarly, it is necessary to verify and evaluate the level of safety and welfare of the workers in their working environment. The safety of the workers has not only an ethical and social value but also an economic implication, since possible accidents or environmental stressors are the major causes of the lower efficiency and productivity of workers. However, the technical solutions adopted in the manufacturing facilities in order to achieve adequate levels of safety and welfare of the workers are not always consistent with the solutions aimed at achieving adequate levels of food hygiene, even if both of them comply with sectoral rules which are often unconnected with each other. Therefore, it is fundamental to design suitable models of analysis that allow assessing buildings as a whole, taking into account both health and hygiene safety as well as the safety and welfare of workers. Hence, this paper proposes an evaluation model that, based on an established study protocol and on the application of a fuzzy logic procedure, allows evaluating the global safety level of a building. The proposed model allows to obtain a synthetic and global value of the building performance in terms of food hygiene and safety and welfare of the workers as well as to highlight possible weaknesses. Though the model may be applied in either the design or the operational phase of a building, this paper focuses on its application to certain buildings already operational in a specific

Consideration of In-Growth of Radionuclides for Facility Hazard Categorization

International Nuclear Information System (INIS)

Mr. Robert E. Miller

2007-01-01

This paper addresses issues associated with the effects of daughter product in-growth on the hazard categorization of facilities in accordance with DOE-STD-1027-92, 'Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports'. There is a list of issues that occur when performing facility hazard categorizations at DOE facilities. The first issue is when radionuclides are concentrated outside of their natural decay schemes, and the resulting daughter products exceed the hazard category three threshold quantity values (HC3 TQVs) while their parents do not. The second issue is if a parent nuclide is evaluated for the inhalation pathway, and the daughter product is evaluated using a different pathway and methodology. The third issue is when the parent and daughter are evaluated using the same pathway for exposure, but the daughter is significantly more radiotoxic than the parent. Lastly, when the TQVs were derived for hazard categorization, the methodology used involved a 24 hour exposure period during which, for the sake of simplicity, no consideration was given to decay and the subsequent in-growth of daughter products. Facility hazard categorization is a snapshot in time and does not provide an accurate inventory for long term operations and/or storage

9 CFR 117.2 - Animal facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Animal facilities. 117.2 Section 117.2 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE VIRUSES... Animal facilities. Animal facilities shall comply with the requirements provided in part 108 of this...

9 CFR 590.538 - Defrosting facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Defrosting facilities. 590.538 Section 590.538 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG..., and Facility Requirements § 590.538 Defrosting facilities. (a) Approved metal defrosting tanks or vats...

9 CFR 590.534 - Freezing facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Freezing facilities. 590.534 Section 590.534 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG..., and Facility Requirements § 590.534 Freezing facilities. (a) Freezing rooms, either on or off the...

Analysis and results of a hydrogen-moderated isotope production assembly in the Fast Flux Test Facility

International Nuclear Information System (INIS)

Wootan, D.W.; Rawlins, J.A.; Carter, L.L.; Brager, H.R.; Schenter, R.E.

1989-01-01

This paper reports on a cobalt test assembly containing yttrium hydride pins for neutron moderation irradiated in the Fast Flux Test Facility (FFTF) during cycle 9A for 137.7 equivalent full-power days at a power level of 291 MW. The 36 test pins consisted of a batch of 32 pins containing cobalt metal used to produce 60 Co and a set of four pins with europium oxide to produce 153 Gd, a radioisotope used in detection of the bone disease osteoporosis. Postirradiation examination of the cobalt pins determined the 60 Co production to be predictable to an accuracy of ∼ 5%. The measured 60 Co spatially distributed concentrations were within 20% of the calculated concentrations. The assembly average 60 Co measured activity was 4% less than the calculated value. The europium oxide pins were gamma scanned for the europium isotopes 152 Eu and 154 Eu to an absolute accuracy of ≅ 10%. The measured europium radioisotope and 153 Gd concentrations were within 20% of calculated values. The hydride assembly performed well and is an excellent vehicle for many FFTF isotope production applications. The results also demonstrate the accuracy of the calculational methods developed by the Westinghouse Hanford Company for predicting isotope production rates in this type of assembly

7 CFR Appendix C to Subpart E of... - Guidelines for Loan Guarantees for Alcohol Fuel Production Facilities

Science.gov (United States)

2010-01-01

... beverage purposes, is manufactured from biomass. (2) The alcohol production facility includes all... studies are very important and required and will be prepared by competent and knowledgeable independent...

Carbon Capture and Sequestration from a Hydrogen Production Facility in an Oil Refinery

Energy Technology Data Exchange (ETDEWEB)

Engels, Cheryl; Williams, Bryan, Valluri, Kiranmal; Watwe, Ramchandra; Kumar, Ravi; Mehlman, Stewart

2010-06-21

The project proposed a commercial demonstration of advanced technologies that would capture and sequester CO2 emissions from an existing hydrogen production facility in an oil refinery into underground formations in combination with Enhanced Oil Recovery (EOR). The project is led by Praxair, Inc., with other project participants: BP Products North America Inc., Denbury Onshore, LLC (Denbury), and Gulf Coast Carbon Center (GCCC) at the Bureau of Economic Geology of The University of Texas at Austin. The project is located at the BP Refinery at Texas City, Texas. Praxair owns and operates a large hydrogen production facility within the refinery. As part of the project, Praxair would construct a CO2 capture and compression facility. The project aimed at demonstrating a novel vacuum pressure swing adsorption (VPSA) based technology to remove CO2 from the Steam Methane Reformers (SMR) process gas. The captured CO2 would be purified using refrigerated partial condensation separation (i.e., cold box). Denbury would purchase the CO2 from the project and inject the CO2 as part of its independent commercial EOR projects. The Gulf Coast Carbon Center at the Bureau of Economic Geology, a unit of University of Texas at Austin, would manage the research monitoring, verification and accounting (MVA) project for the sequestered CO2, in conjunction with Denbury. The sequestration and associated MVA activities would be carried out in the Hastings field at Brazoria County, TX. The project would exceed DOE?s target of capturing one million tons of CO2 per year (MTPY) by 2015. Phase 1 of the project (Project Definition) is being completed. The key objective of Phase 1 is to define the project in sufficient detail to enable an economic decision with regard to proceeding with Phase 2. This topical report summarizes the administrative, programmatic and technical accomplishments completed in Phase 1 of the project. It describes the work relative to project technical and design activities

The simulation of stationary and non-stationary regime operation of heavy water production facilities

International Nuclear Information System (INIS)

Peculea, M.; Beca, T.; Constantinescu, D.M.; Dumitrescu, M.; Dimulescu, A.; Isbasescu, G.; Stefanescu, I.; Mihai, M.; Dogaru, C.; Marinescu, M.; Olariu, S.; Constantin, T.; Necula, A.

1995-01-01

This paper refers to testing procedures of the production capacity of heavy water production pilot, industrial scale plants and of heavy water reconcentration facilities. Simulation codes taking into account the mass and heat transfers inside the exchange columns were developed. These codes provided valuable insight about the isotope build-up of the installation which allowed estimating the time of reaching the stationary regime. Also transient regimes following perturbations in the operating parameters (i.e. temperature, pressure, fluid rates) of the installation were simulated and an optimal rate of routine inspections and adjustments was thus established

Installation of Tc-99m generator manufacturing facilities

International Nuclear Information System (INIS)

Shin, B. C.; Choung, W. M.; Park, J. H.; Park, S. H.; Kim, S. J.; Park, K. B.

2004-01-01

For the characteristics of radiopharmaceuticals, the manufacturing facility should be complied with the radiation safety standards for operators as well as GMP (Good Manufacturing Practice) cleanness standards for production. We intensively modified the existing Radioisotope production facilities, which were installed only in radiation safety points of view, to meet cleanness criteria. And the concept of multi-barrier buffer zones was introduced to apply negative air pressure for hot cell with first priority and to continue relative positive air pressure for clean room. The manufacturing area for Tc-99m Generator can be entered only through a second change. The doors of each change area are interlocked to maintain air pressure differentials. The pass box for material transfer are also interlocked so that only one side may be opened at any one time to keep cleanness. Two door-type autoclave was installed crossing the wall between preparing room and aseptic room to keep cleanness after sterilization. Three lead hot cells were installed and final inspection including gamma survey test were performed. The clean room was installed and TAB for this facility was performed in order to acquire the necessary air flow. The filter bank for filtration of exhausted radiation air was installed and its efficiency test was performed. In this facility, radiation shielding utilities and manufacturing instruments were set up and their operating manuals were documented. Efficiency tests for every utilities and instruments were satisfied and the approval for use of the facilities was achieved from MOST (Ministry of Science and Technology). The Sam Young Unitech, the lessee of the facilities set up the equipment in the hot cell, which is needed to produce Tc-99m Generator, supported by IPPE in Russia. They are composing the systems complied with the guidelines and the regulations, and keep in contact to KFDA for acquiring its approval. It is expected to produce Tc-99m Generator within

Accident sequences and causes analysis in a hydrogen production process

Energy Technology Data Exchange (ETDEWEB)

Jae, Moo Sung; Hwang, Seok Won; Kang, Kyong Min; Ryu, Jung Hyun; Kim, Min Soo; Cho, Nam Chul; Jeon, Ho Jun; Jung, Gun Hyo; Han, Kyu Min; Lee, Seng Woo [Hanyang Univ., Seoul (Korea, Republic of)

2006-03-15

Since hydrogen production facility using IS process requires high temperature of nuclear power plant, safety assessment should be performed to guarantee the safety of facility. First of all, accident cases of hydrogen production and utilization has been surveyed. Based on the results, risk factors which can be derived from hydrogen production facility were identified. Besides the correlation between risk factors are schematized using influence diagram. Also initiating events of hydrogen production facility were identified and accident scenario development and quantification were performed. PSA methodology was used for identification of initiating event and master logic diagram was used for selection method of initiating event. Event tree analysis was used for quantification of accident scenario. The sum of all the leakage frequencies is 1.22x10{sup -4} which is similar value (1.0x10{sup -4}) for core damage frequency that International Nuclear Safety Advisory Group of IAEA suggested as a criteria.

40 CFR 60.30d - Designated facilities.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Designated facilities. 60.30d Section... Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

Performance of the first Japanese large-scale facility for radon inhalation experiments with small animals

International Nuclear Information System (INIS)

Ishimori, Y.; Mitsunobu, F.; Yamaoka, K.; Tanaka, H.; Kataoka, T.; Sakoda, A.

2011-01-01

A radon test facility for small animals was developed in order to increase the statistical validity of differences of the biological response in various radon environments. This paper illustrates the performances of that facility, the first large-scale facility of its kind in Japan. The facility has a capability to conduct approximately 150 mouse-scale tests at the same time. The apparatus for exposing small animals to radon has six animal chamber groups with five independent cages each. Different radon concentrations in each animal chamber group are available. Because the first target of this study is to examine the in vivo behaviour of radon and its effects, the major functions to control radon and to eliminate thoron were examined experimentally. Additionally, radon progeny concentrations and their particle size distributions in the cages were also examined experimentally to be considered in future projects. (authors)

DOE High Performance Computing Operational Review (HPCOR): Enabling Data-Driven Scientific Discovery at HPC Facilities

Energy Technology Data Exchange (ETDEWEB)

Gerber, Richard; Allcock, William; Beggio, Chris; Campbell, Stuart; Cherry, Andrew; Cholia, Shreyas; Dart, Eli; England, Clay; Fahey, Tim; Foertter, Fernanda; Goldstone, Robin; Hick, Jason; Karelitz, David; Kelly, Kaki; Monroe, Laura; Prabhat,; Skinner, David; White, Julia

2014-10-17

U.S. Department of Energy (DOE) High Performance Computing (HPC) facilities are on the verge of a paradigm shift in the way they deliver systems and services to science and engineering teams. Research projects are producing a wide variety of data at unprecedented scale and level of complexity, with community-specific services that are part of the data collection and analysis workflow. On June 18-19, 2014 representatives from six DOE HPC centers met in Oakland, CA at the DOE High Performance Operational Review (HPCOR) to discuss how they can best provide facilities and services to enable large-scale data-driven scientific discovery at the DOE national laboratories. The report contains findings from that review.

Maximizing Production Capacity from an Ultrafiltration Process at the Hanford Department of Waste Treatment Facility

International Nuclear Information System (INIS)

Foust, Henry C.; Holton, Langdon K.; Demick, Laurence E.

2005-01-01

The Department of Energy has contracted Bechtel National, Inc. to design, construct and commission a Waste Treatment and Immobilization Plant (WTP) to treat radioactive slurry currently stored in underground waste storage tanks. A critical element of the waste treatment capacity for the WTP is the proper operation of an ultrafiltration process (UFP). The UFP separates supernate solution from radioactive solids. The solution and solid phases are separately immobilized. An oversight review of the UFP design and operation has identified several methods to improve the capacity of the ultrafiltration process, which will also improve the capacity of the WTP. Areas explored were the basis of design, an analysis of the WTP capacity, process chemistry within the UFP, and UFP process control. This article discusses some of the findings of this oversight review in terms of sodium and solid production, which supports the treatment of low activity waste (LAW) associated with the facility, and solid production, which supports the treatment of high level waste (HLW) associated with the facility

Conceptual design report for Central Waste Disposal Facility

International Nuclear Information System (INIS)

1984-01-01

The permanent facilities are defined, and cost estimates are provided for the disposal of Low-Level Radioactive Wastes (LLW) at the Central Waste Disposal Facility (CWDF). The waste designated for the Central Waste Disposal Facility will be generated by the Y-12 Plant, the Oak Ridge Gaseous Diffusion Plant, and the Oak Ridge National Laboratory. The facility will be operated by ORNL for the Office of Defense Waste and By-Products Management of the Deparment of Energy. The CWDF will be located on the Department of Energy's Oak Ridge Reservation, west of Highway 95 and south of Bear Creek Road. The body of this Conceptual Design Report (CDR) describes the permanent facilities required for the operation of the CWDF. Initial facilities, trenches, and minimal operating equipment will be provided in earlier projects. The disposal of LLW will be by shallow land burial in engineered trenches. DOE Order 5820 was used as the performance standard for the proper disposal of radioactive waste. The permanent facilities are intended for beneficial occupancy during the first quarter of fiscal year 1989. 3 references, 9 figures, 7 tables

Performance Related Pay and Labor Productivity

NARCIS (Netherlands)

Gielen, A. C.; Kerkhofs, M.J.M.; van Ours, J.C.

2006-01-01

This paper uses information from a panel of Dutch firms to investigate the labor productivity effects of performance related pay (PRP).We find that PRP increases labor productivity at the firm level with about 9%.

Performance Related Pay and Labour Productivity

OpenAIRE

Gielen, Anne; Kerkhofs, Marcel J M; van Ours, Jan C

2006-01-01

This paper uses information from a panel of Dutch firms to investigate the labour productivity effects of performance related pay (PRP). We find that PRP increases labour productivity at the firm level with about 9%.

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.

Laser performance upgrade for precise ICF experiment in SG-Ⅲ laser facility

Directory of Open Access Journals (Sweden)

Wanguo Zheng

2017-09-01

Full Text Available The SG-Ⅲ laser facility (SG-Ⅲ is the largest laser driver for inertial confinement fusion (ICF researches in China, which has 48 beamlines and can deliver 180 kJ ultraviolet laser energy in 3 ns. In order to meet the requirements of precise physics experiments, some new functionalities need to be added to SG-Ⅲ and some intrinsic laser performances need upgrade. So at the end of SG-Ⅲ's engineering construction, the 2-year laser performance upgrade project started. This paper will introduce the newly added functionalities and the latest laser performance of SG-Ⅲ. With these function extensions and performance upgrade, SG-Ⅲ is now fully prepared for precise ICF experiments and solidly paves the way towards fusion ignition.

The neutronic design and performance of the Indiana University Cyclotron Facility (IUCF) Low Energy Neutron Source (LENS)

Science.gov (United States)

Lavelle, Christopher M.

Neutron scattering research is performed primarily at large-scale facilities. However, history has shown that smaller scale neutron scattering facilities can play a useful role in education and innovation while performing valuable materials research. This dissertation details the design and experimental validation of the LENS TMR as an example for a small scale accelerator driven neutron source. LENS achieves competitive long wavelength neutron intensities by employing a novel long pulse mode of operation, where the neutron production target is irradiated on a time scale comparable to the emission time of neutrons from the system. Monte Carlo methods have been employed to develop a design for optimal production of long wavelength neutrons from the 9Be(p,n) reaction at proton energies ranging from 7 to 13 MeV proton energy. The neutron spectrum was experimentally measured using time of flight, where it is found that the impact of the long pulse mode on energy resolution can be eliminated at sub-eV neutron energies if the emission time distribution of neutron from the system is known. The emission time distribution from the TMR system is measured using a time focussed crystal analyzer. Emission time of the fundamental cold neutron mode is found to be consistent with Monte Carlo results. The measured thermal neutron spectrum from the water reflector is found to be in agreement with Monte Carlo predictions if the scattering kernels employed are well established. It was found that the scattering kernels currently employed for cryogenic methane are inadequate for accurate prediction of the cold neutron intensity from the system. The TMR and neutronic modeling have been well characterized and the source design is flexible, such that it is possible for LENS to serve as an effective test bed for future work in neutronic development. Suggestions for improvements to the design that would allow increased neutron flux into the instruments are provided.

75 FR 18572 - Facility Control Numbers

Science.gov (United States)

2010-04-12

...), biodiesel production facilities (BCN), or ethanol production facilities (ECN). A taxable fuel registrant... -CB-) will be issued a BCN for each biodiesel production physical location that a registrant in good... approved terminal. Each TCN identifies a unique physical location in the bulk transport/delivery system and...

Agriculture products as source of radionuclides and some monitoring principles of agriculture near nuclear facilities

International Nuclear Information System (INIS)

Aleksakhin, R.M.; Korneev, N.A.; Panteleev, L.I.; Shukhovtsev, B.I.

1985-01-01

Migration of radionuclides into agriculture products in regions adjoining the nuclear facilities depends on a large number of factors. Among them is the complex of ecological conditions: meteorological factors, type of soils etc., as well as biological peculiarities of agriculture plants and animals. It is possible to control the radionuclide content administered to man's organism with agriculture products changing large branches of agriculture and varying within the range of seprate branches of industry, taking into account the most effective ways of radionuclide pathways

Upgrade of the facility EXOTIC for the in-flight production of light Radioactive Ion Beams

Energy Technology Data Exchange (ETDEWEB)

Mazzocco, M., E-mail: marco.mazzocco@pd.infn.it [Dipartimento di Fisica e Astronomia, Universitá di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); INFN-Sezione di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); Torresi, D.; Strano, E. [Dipartimento di Fisica e Astronomia, Universitá di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); INFN-Sezione di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); Boiano, A. [INFN-Sezione di Napoli, Via Cinthia, I-80126 Napoli (Italy); Boiano, C. [INFN-Sezione di Milano, Via Celoria 16, I-20133 Milano (Italy); Costa, L. [INFN-LNL, Viale dell’Università 2, I-35020 Legnaro, PD (Italy); Glodariu, T. [NIPNE, 407 Atomistilor Street, 077125 Magurele (Romania); Guglielmetti, A. [INFN-Sezione di Milano, Via Celoria 16, I-20133 Milano (Italy); Dipartimento di Fisica,Università di Milano, Via Celoria 16, I-20133 Milano (Italy); La Commara, M. [INFN-Sezione di Napoli, Via Cinthia, I-80126 Napoli (Italy); Dipartimento di Scienze Fisiche, Università di Napoli, Via Cinthia, I-80126 Napoli (Italy); Parascandolo, C. [Dipartimento di Fisica e Astronomia, Universitá di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); INFN-Sezione di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); Pierroutsakou, D. [INFN-Sezione di Napoli, Via Cinthia, I-80126 Napoli (Italy); Signorini, C.; Soramel, F. [Dipartimento di Fisica e Astronomia, Universitá di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); INFN-Sezione di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); Stroe, L. [NIPNE, 407 Atomistilor Street, 077125 Magurele (Romania)

2013-12-15

Highlights: • Production of in-flight Radioactive Ion Beams via two-body reactions. • Development of a cryogenic gas target. • Event-by-event tracking via Parallel Plate Avalanche Counters (PPACs). -- Abstract: The facility EXOTIC for the in-flight production of light weakly-bound Radioactive Ion Beams (RIBs) has been operating at INFN-LNL since 2004. RIBs are produced via two-body reactions induced by high intensity heavy-ion beams impinging on light gas targets and selected by means of a 30°-dipole bending magnet and a 1-m long Wien filter. The facility has been recently upgraded (i) by developing a cryogenic gas target, (ii) by replacing the power supplies of the middle lenses of the two quadrupole triplets, (iii) by installing two y-steerers and (iv) by placing two Parallel Plate Avalanche Counters upstream the secondary target to provide an event-by-event reconstruction of the position hit on the target. So far, RIBs of {sup 7}Be, {sup 8}B and {sup 17}F in the energy range 3–5 MeV/u have been produced with intensities about 3 × 10{sup 5}, 1.6 × 10{sup 3} and 10{sup 5} pps, respectively. Possible light RIBs (up to Z = 10) deliverable by the facility EXOTIC are also reviewed.

High-Performance Na-O2 Batteries Enabled by Oriented NaO2 Nanowires as Discharge Products.

Science.gov (United States)

Khajehbashi, S Mohammad B; Xu, Lin; Zhang, Guobin; Tan, Shuangshuang; Zhao, Yan; Wang, Lai-Sen; Li, Jiantao; Luo, Wen; Peng, Dong-Liang; Mai, Liqiang

2018-06-13

Na-O 2 batteries are emerging rechargeable batteries due to their high theoretical energy density and abundant resources, but they suffer from sluggish kinetics due to the formation of large-size discharge products with cubic or irregular particle shapes. Here, we report the unique growth of discharge products of NaO 2 nanowires inside Na-O 2 batteries that significantly boosts the performance of Na-O 2 batteries. For this purpose, a high-spin Co 3 O 4 electrocatalyst was synthesized via the high-temperature oxidation of pure cobalt nanoparticles in an external magnetic field. The discharge products of NaO 2 nanowires are 10-20 nm in diameter and ∼10 μm in length, characteristics that provide facile pathways for electron and ion transfer. With these nanowires, Na-O 2 batteries have surpassed 400 cycles with a fixed capacity of 1000 mA h g -1 , an ultra-low over-potential of ∼60 mV during charging, and near-zero over-potential during discharging. This strategy not only provides a unique way to control the morphology of discharge products to achieve high-performance Na-O 2 batteries but also opens up the opportunity to explore growing nanowires in novel conditions.

Overview of a performance assessment methodology for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Kozak, M.W.; Chu, M.S.Y.

1991-01-01

A performance assessment methodology has been developed for use by the US Nuclear Regulatory Commission in evaluating license applications for low-level waste disposal facilities. This paper provides a summary and an overview of the modeling approaches selected for the methodology. The overview includes discussions of the philosophy and structure of the methodology. This performance assessment methodology is designed to provide the NRC with a tool for performing confirmatory analyses in support of license reviews related to postclosure performance. The methodology allows analyses of dose to individuals from off-site releases under normal conditions as well as on-site doses to inadvertent intruders. 24 refs., 1 tab

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

Green facility location

NARCIS (Netherlands)

Velázquez Martínez, J.C.; Fransoo, J.C.; Bouchery, Y.; Corbett, C.J.; Fransoo, J.C.; Tan, T.

2017-01-01

Transportation is one of the main contributing factors of global carbon emissions, and thus, when dealing with facility location models in a distribution context, transportation emissions may be substantially higher than the emissions due to production or storage. Because facility location models

Cross-sectional relationship between physical fitness components and functional performance in older persons living in long-term care facilities

Directory of Open Access Journals (Sweden)

van Mechelen Willem

2006-02-01

Full Text Available Abstract Background The age-related deterioration of physiological capacities such as muscle strength and balance is associated with increased dependence. Understanding the contribution of physical fitness components to functional performance facilitates the development of adequate exercise interventions aiming at preservation of function and independence of older people. The aim of the study was to investigate the relationship between physical fitness components and functional performance in older people living in long-term care facilities. Methods Design cross-sectional study Subjects 226 persons living in long-term care facilities (mean age: 81.6 ± 5.6. Outcome measures Physical fitness and functional performance were measured by performance-based tests. Results Knee and elbow extension strength were significantly higher in men (difference = 44.5 and 50.0 N, respectively, whereas women were more flexible (difference sit & reach test = 7.2 cm. Functional performance was not significantly different between the genders. In men, motor coordination (eye-hand coordination and measures of strength were the main contributors to functional performance, whereas in women flexibility (sit and reach test and motor coordination (tandem stance and eye-hand coordination played a major role. Conclusion The results of this study show that besides muscle strength, fitness components such as coordination and flexibility are associated with functional performance of older people living in long-term care facilities. This suggests that men and women living in long-term care facilities, differ considerably concerning the fitness factors contributing to functional performance. Women and men may, therefore, need exercise programs emphasizing different fitness aspects in order to improve functional performance.

9 CFR 351.10 - Facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Facilities. 351.10 Section 351.10... CERTIFICATION CERTIFICATION OF TECHNICAL ANIMAL FATS FOR EXPORT Facilities and Operations § 351.10 Facilities. (a) Facilities for the preparation, identification, and storage of the technical animal fat to be...

SNL/CA Facilities Management Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

Rabb, David [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Clark, Eva [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

2014-12-01

At Sandia National Laboratories in California (SNL/CA), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/CA applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule.

International technology exchange in support of the Defense Waste Processing Facility wasteform production

International Nuclear Information System (INIS)

Kitchen, B.G.

1989-01-01

The nearly completed Defense Waste Processing Facility (DWPF) is a Department of Energy (DOE) facility at the Savannah River Site that is designed to immobilize defense high level radioactive waste (HLW) by vitrification in borosilicate glass and containment in stainless steel canisters suitable for storage in the future DOE HLW repository. The DWPF is expected to start cold operation later this year (1990), and will be the first full scale vitrification facility operating in the United States, and the largest in the world. The DOE has been coordinating technology transfer and exchange on issues relating to HLW treatment and disposal through bi-lateral agreements with several nations. For the nearly fifteen years of the vitrification program at Savannah River Laboratory, over two hundred exchanges have been conducted with a dozen international agencies involving about five-hundred foreign national specialists. These international exchanges have been beneficial to the DOE's waste management efforts through confirmation of the choice of the waste form, enhanced understanding of melter operating phenomena, support for paths forward in political/regulatory arenas, confirmation of costs for waste form compliance programs, and establishing the need for enhancements of melter facility designs. This paper will compare designs and schedules of the international vitrification programs, and will discuss technical areas where the exchanges have provided data that have confirmed and aided US research and development efforts, impacted the design of the DWPF and guided the planning for regulatory interaction and product acceptance

UNC Nuclear Industries reactor and fuels production facilities. 1984 effluent release report

International Nuclear Information System (INIS)

Rokkan, D.J.

1985-01-01

This document has been prepared to fulfill the annual reporting requirements of DOE 5484.1, ''Environmental Protection, Safety, and Health Protection Information Reporting Requirements.'' Radioanalyses performed on routine samples of liquid and airborne streams were evaluated using UNC's Environmental Release Summary computer program. All identified significant discharges from UNC facilities to the environment during CY 1984 are reported in this document

Geothermal source heat pumps under energy services companies finance scheme to increase energy efficiency and production in stockbreeding facilities

International Nuclear Information System (INIS)

Borge-Diez, David; Colmenar-Santos, Antonio; Pérez-Molina, Clara; López-Rey, África

2015-01-01

In Europe energy services are underutilized in terms of their potential to improve energy efficiency and reduce external energy dependence. Agricultural and stockbreeding sectors have high potential to improve their energy efficiency. This paper presents an energy model for geothermal source heat pumps in stockbreeding facilities and an analysis of an energy services business case. The proposed solution combines both energy cost reduction and productivity increases and improves energy services company financing scheme. CO 2 emissions drop by 89%, reducing carbon footprint and improving added value for the product. For the two different evaluated scenarios, one including winter heating and one including heating and cooling, high IRR (internal return rate) values are obtained. A sensitivity analysis reveals that the IRR ranges from 10.25% to 22.02%, making the investment attractive. To make the research highly extensible, a sensitivity analysis for different locations and climatic conditions is presented, showing a direct relationship between financial parameters and climatic conditions. A Monte Carlo simulation is performed showing that initial fuel cost and initial investment are the most decisive in the financial results. This work proves that energy services based on geothermal energy can be profitable in these sectors and can increase sustainability, reduce CO 2 emissions and improve carbon footprint. - Highlights: • Geothermal heat pumps are studied to promote industrial energy services. • Geothermal energy in farming facilities improves global competitiveness. • Research shows profitability of low enthalpy geothermal energy services. • Climatic conditions sensitivity analysis reveals IRR ranges from 10.25% to 22.02%. • Added market value for the product as carbon footprint reduction, are achieved

The definition of and drivers of new product performance

DEFF Research Database (Denmark)

Jespersen, Kristina Risom; Juhl, Hans Jørn

In the last three decades academic research on new product development has tried to identify the drivers of new product development performance. This body of research is characterised by a vast amount of different definitions of both the drivers of new product performance and the performance...

Product variety, product complexity and manufacturing operational performance: A systematic literature review

DEFF Research Database (Denmark)

Trattner, Alexandria Lee; Hvam, Lars; Herbert-Hansen, Zaza Nadja Lee

Manufacturing in the twenty-first century has been wrought with the struggle to satisfy the rising demand for greater product variety and more complex products while still maintaining efficient manufacturing operations. However, the literature lacks an overview of which operational performance...... measures are most affected by increased variety and complexity. This study presents a systematic literature review of the recent scholarly literature on variety, complexity and manufacturing operational performance (MOP). Results show that product variety has a consistently negative relationship with MOP...... across different time, cost, quality and flexibility measures while product complexity lacks evidence of strong relationships with MOP measures....

Sustainable data policy for a data production facility: a work in (continual) progress

Science.gov (United States)

Ketcham, R. A.

2017-12-01

The University of Texas High-Resolution X-Ray Computed Tomography Facility (UTCT) has been producing volumetric data and data products of geological and other scientific specimens and engineering materials for over 20 years. Data volumes, both in terms of the size of individual data sets and overall facility production, have progressively grown and fluctuated near the upper boundary of what can be managed by contemporary workstations and lab-scale servers and network infrastructure, making data policy a preoccupation for our entire history. Although all projects have been archived since our first day of operation, policies on which data to keep (raw, reconstructed after corrections, processed) have varied, and been periodically revisited in consideration of the cost of curation and the likelihood of revisiting and reprocessing data when better techniques become available, such as improved artifact corrections or iterative tomographic reconstruction. Advances in instrumentation regularly make old data obsolete and more advantageous to reacquire, but the simple act of getting a sample to a scanning facility is a practical barrier that cannot be overlooked. In our experience, the main times that raw data have been revisited using improved processing to improve image quality were predictable, high-impact charismatic projects (e.g., Archaeopteryx, A. Afarensis "Lucy"). These cases actually provided the impetus for development of the new techniques (ring and beam hardening artifact reduction), which were subsequently incorporated into our data processing pipeline going forward but were rarely if ever retroactively applied to earlier data sets. The only other times raw data have been reprocessed were when reconstruction parameters were inappropriate, due to unnoticed sample features or human error, which are usually recognized fairly quickly. The optimal data retention policy thus remains an open question, although erring on the side of caution remains the default

BALU: Largest autoclave research facility in the world

Directory of Open Access Journals (Sweden)

Hakan Ucan

2016-03-01

Full Text Available Among the large-scale facilities operated at the Center for Lightweight-Production-Technology of the German Aerospace Center in Stade BALU is the world's largest research autoclave. With a loading length of 20m and a loading diameter of 5.8 m the main objective of the facility is the optimization of the curing process operated by components made of carbon fiber on an industrial scale. For this reason, a novel dynamic autoclaving control has been developed that is characterized by peripheral devices to expend the performance of the facility for differential applications, by sensing systems to detect the component state throughout the curing process and by a feedback system, which is capable to intervene into the running autoclave process.

Overview of SNS Cryomodule Performance

CERN Document Server

Drury, Michael A; Davis, Kirk; Delayen, Jean R; Grenoble, Christiana; Hicks, William R; King, Larry; Plawski, Tomasz; Powers, Tom; Preble, Joseph P; Wang, Haipeng; Wiseman, Mark

2005-01-01

Thomas Jefferson National Accelerating Facility (Jefferson Lab) has completed production of 24 Superconducting Radio Frequency (SRF) cryomodules for the Spallation Neutron Source (SNS) superconducting linac. This includes one medium-beta (0.61) prototype, eleven medium-beta and twelve high-beta (0.81) production cryomodules. Ten medium-beta cryomodules as well as two high beta cryomodules have undergone complete operational performance testing in the Cryomodule Test Facility at Jefferson Lab. The set of tests includes measurements of maximum gradient, unloaded Q (Q0), microphonics, and response to Lorentz forces. The Qext's of the various couplers are measured and the behavior of the higher order mode couplers is examined. The mechanical and piezo tuners are also characterized. The results of these performance tests will be discussed in this paper.

Adjustment of automatic control systems of production facilities at coal processing plants using multivariant physico- mathematical models

Science.gov (United States)

Evtushenko, V. F.; Myshlyaev, L. P.; Makarov, G. V.; Ivushkin, K. A.; Burkova, E. V.

2016-10-01

The structure of multi-variant physical and mathematical models of control system is offered as well as its application for adjustment of automatic control system (ACS) of production facilities on the example of coal processing plant.

Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

Energy Technology Data Exchange (ETDEWEB)

Bargalló, Enric, E-mail: enric.bargallo@esss.se [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Arroyo, Jose Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain); Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Moya, Joaquin; Ibarra, Angel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain)

2015-10-15

Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

International Nuclear Information System (INIS)

Bargalló, Enric; Arroyo, Jose Manuel; Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos; Moya, Joaquin; Ibarra, Angel

2015-01-01

Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

Characterization of Spatial Impact of Particles Emitted from a Cement Material Production Facility on Outdoor Particle Deposition in the Surrounding Community.

Science.gov (United States)

Yu, Chang Ho; Fan, Zhihua Tina; McCandlish, Elizabeth; Stern, Alan H; Lioy, Paul J

2011-10-01

The objective of this study was to estimate the contribution of a facility that processes steel production slag into raw material for cement production to local outdoor particle deposition in Camden, NJ. A dry deposition sampler that can house four 37-mm quartz fiber filters was developed and used for the collection of atmospheric particle deposits. Two rounds of particle collection (3-4 weeks each) were conducted in 8-11 locations 200-800 m downwind of the facility. Background samples were concurrently collected in a remote area located ∼2 km upwind from the facility. In addition, duplicate surface wipe samples were collected side-by-side from each of the 13 locations within the same sampling area during the first deposition sampling period. One composite source material sample was also collected from a pile stored in the facility. Both the bulk of the source material and the particle deposition flux in the study area was higher (24-83 mg/m 2 ·day) than at the background sites (13-17 mg/m 2 ·day). The concentration of Ca, a major element in the cement source production material, was found to exponentially decrease with increasing downwind distance from the facility (P particle deposition. The contribution of the facility to outdoor deposited particle mass was further estimated by three independent models using the measurements obtained from this study. The estimated contributions to particle deposition in the study area were 1.8-7.4% from the regression analysis of the Ca concentration in particle deposition samples against the distance from the facility, 0-11% from the U.S. Environmental Protection Agency (EPA) Chemical Mass Balance (CMB) source-receptor model, and 7.6-13% from the EPA Industrial Source Complex Short Term (ISCST3) dispersion model using the particle-size-adjusted permit-based emissions estimates. [Box: see text].

Fuel elements and fuel element materials. Experimental facilities for fission products lift-off tests

International Nuclear Information System (INIS)

Blanchard, R.J.; Veyrat, J.F.

1978-01-01

One of the hypothetical accidents on the HTGR primary cooling circuits is the failure of a circuit resulting in a depressurization in the primary loops of the reactor. There is a risk of release of fission products in relation to the size of the failure. Experimental facilities for HTGR tests were developed: an in pile helium loop Comedie and an out of pile helium loop

Performance assessment and licensing issues for United States commercial near-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, S.M.

1997-10-01

The final objective of performance assessment for a near-surface LLW disposal facility is to demonstrate that potential radiological impacts for each of the human exposure pathways will not violate applicable standards. This involves determining potential pathways and specific receptor locations for human exposure to radionuclides; developing appropriate scenarios for each of the institutional phases of a disposal facility; and maintaining quality assurance and control of all data, computer codes, and documentation. The results of a performance assessment should be used to demonstrate that the expected impacts are expected to be less than the applicable standards. The results should not be used to try to predict the actual impact. This is an important distinction that results from the uncertainties inherent in performance assessment calculations. The paper discusses performance objectives; performance assessment phases; scenario selection; mathematical modeling and computer programs; final results of performance assessments submitted for license application; institutional control period; licensing issues; and related research and development activities

Practice for dosimetry in gamma irradiation facilities for radiation processing. 2. ed.

International Nuclear Information System (INIS)

2004-01-01

This practice outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance quali- fication, and routine processing in facilities that process product with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to installation qualification, operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory absorbed-dose limits is not within the scope of this practice

Team engineering for successful reuse and mission enhancement of a former DOE Weapons Material Production Facility

International Nuclear Information System (INIS)

Blackford, L.T.; Mizner, J.H. Jr.

1994-11-01

This paper describes the team engineering approach used to resolve issues associated with converting a 50-year-old fuel processing facility into a decontamination facility. In only nine months, the multi-disciplinary team formed for this task has made significant progress toward both long-term and short-term goals, including conceptual design of two decontamination modules. The team's accomplishments are even more notable in light of frequent changes in scope and mission. Today, the team serves as a venue for troubleshooting operational issues, sharing vendor information, developing long-range strategies, and addressing integration issues within the facility's organizational structure. The team's approach could serve as a useful model to address the many issues surrounding the transition of the U.S. Department of Energy (DOE) and commercial complexes from a production and supply role to one of cleanup and environmental remediation

The materials production and processing facility at the Spanish National Centre for fusion technologies (TechnoFusion)

International Nuclear Information System (INIS)

Munoz, A.; Monge, M.A.; Pareja, R.; Hernandez, M.T.; Jimenez-Rey, D.; Roman, R.; Gonzalez, M.; Garcia-Cortes, I.; Perlado, M.; Ibarra, A.

2011-01-01

In response to the urgent request from the EU Fusion Program, a new facility (TechnoFusion) for research and development of fusion materials has been planned with support from the Regional Government of Madrid and the Ministry of Science and Innovation of Spain. TechnoFusion, the National Centre for Fusion Technologies, aims screening different technologies relevant for ITER and DEMO environments while promoting the contribution of international companies and research groups into the Fusion Programme. For this purpose, the centre will be provided with a large number of unique facilities for the manufacture, testing (a triple-beam multi-ion irradiation, a plasma-wall interaction device, a remote handling for under ionizing radiation testing) and analysis of critical fusion materials. Particularly, the objectives, semi-industrial scale capabilities and present status of the TechnoFusion Materials Production and Processing (MPP) facility are presented. Previous studies revealed that the MPP facility will be a very promising infrastructure for the development of new materials and prototypes demanded by the fusion technology and therefore some of them will be here briefly summarized.

The materials production and processing facility at the Spanish National Centre for fusion technologies (TechnoFusion)

Energy Technology Data Exchange (ETDEWEB)

Munoz, A., E-mail: rpp@fis.uc3m.es [Departamento de Fisica, UC3M, Avda de la Universidad 30, 28911 Leganes, Madrid (Spain); Monge, M.A.; Pareja, R. [Departamento de Fisica, UC3M, Avda de la Universidad 30, 28911 Leganes, Madrid (Spain); Hernandez, M.T. [LNF-CIEMAT, Avda, Complutense, 22, 28040 Madrid (Spain); Jimenez-Rey, D. [CMAM, UAM, C/Faraday 3, 28049, Madrid (Spain); Roman, R.; Gonzalez, M.; Garcia-Cortes, I. [LNF-CIEMAT, Avda, Complutense, 22, 28040 Madrid (Spain); Perlado, M. [IFN, ETSII, UPM, C/Jose Gutierrez Abascal, 2, 28006 Madrid (Spain); Ibarra, A. [LNF-CIEMAT, Avda, Complutense, 22, 28040 Madrid (Spain)

2011-10-15

In response to the urgent request from the EU Fusion Program, a new facility (TechnoFusion) for research and development of fusion materials has been planned with support from the Regional Government of Madrid and the Ministry of Science and Innovation of Spain. TechnoFusion, the National Centre for Fusion Technologies, aims screening different technologies relevant for ITER and DEMO environments while promoting the contribution of international companies and research groups into the Fusion Programme. For this purpose, the centre will be provided with a large number of unique facilities for the manufacture, testing (a triple-beam multi-ion irradiation, a plasma-wall interaction device, a remote handling for under ionizing radiation testing) and analysis of critical fusion materials. Particularly, the objectives, semi-industrial scale capabilities and present status of the TechnoFusion Materials Production and Processing (MPP) facility are presented. Previous studies revealed that the MPP facility will be a very promising infrastructure for the development of new materials and prototypes demanded by the fusion technology and therefore some of them will be here briefly summarized.

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)

Production and setting of fractional elution facility for recovery of useful rare metals from seawater

International Nuclear Information System (INIS)

Seko, Noriaki; Kasai, Noboru; Tamada, Masao; Hasegawa, Shin; Katakai, Akio

2005-01-01

In September 1999, we have soaked 200 kg of fibrous amidoxime absorbents, synthesized by radiation-induced graft polymerization, into seawater to evaluate their performance. Fractional elution facility was set effectively to elute the rare metals on adsorbents in Mutsu-Establishment. This facility consists of two parts of pre-washing and elution. The present report dealt with planning, manufacture and setting of fractional facility. Marine organism and slime on adsorbent cassette (290 x 295 x 160 mm) were washed out and every 72 cassettes were set in elution unit (1210 x 1210 x H1460 mm) with nonwoven materials as a packing to avoid elution loss. In the elution process alkaline and alkaline earth metals were eluted with low concentration hydrochloric acid (0.01M) and rare metals were eluted with high concentration (0.5 M) after the packing of elution unit into fractional elution facility. Adsorbent cassettes were regenerated with alkaline solution after elution procedure. (author)

Energy Systems Integration Facility (ESIF) Facility Stewardship Plan: Revision 2.1

Energy Technology Data Exchange (ETDEWEB)

Torres, Juan [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Anderson, Art [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

2018-01-02

The U.S. Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy (EERE), has established the Energy Systems Integration Facility (ESIF) on the campus of the National Renewable Energy Laboratory (NREL) and has designated it as a DOE user facility. This 182,500-ft2 research facility provides state-of-the-art laboratory and support infrastructure to optimize the design and performance of electrical, thermal, fuel, and information technologies and systems at scale. This Facility Stewardship Plan provides DOE and other decision makers with information about the existing and expected capabilities of the ESIF and the expected performance metrics to be applied to ESIF operations. This plan is a living document that will be updated and refined throughout the lifetime of the facility.

Assessment of Loads and Performance of a Containment in a Hypothetical Accident (ALPHA). Facility design report

International Nuclear Information System (INIS)

Yamano, Norihiro; Maruyama, Yu; Kudo, Tamotsu; Moriyama, Kiyofumi; Ito, Hideo; Komori, Keiichi; Sonobe, Hisao; Sugimoto, Jun

1998-06-01

In the ALPHA (Assessment of Loads and Performance of Containment in Hypothetical Accident) program, several tests have been performed to quantitatively evaluate loads to and performance of a containment vessel during a severe accident of a light water reactor. The ALPHA program focuses on investigating leak behavior through the containment vessel, fuel-coolant interaction, molten core-concrete interaction and FP aerosol behavior, which are generally recognized as significant phenomena considered to occur in the containment. In designing the experimental facility, it was considered to simulate appropriately the phenomena mentioned above, and to cover experimental conditions not covered by previous works involving high pressure and temperature. Experiments from the viewpoint of accident management were also included in the scope. The present report describes design specifications, dimensions, instrumentation of the ALPHA facility based on the specific test objectives and procedures. (author)

The first DC performance test and analysis of CC conductor short sample at ASIPP conductor test facility

International Nuclear Information System (INIS)

Shi Yi; Wu Yu; Liu Huajun; Long Feng; Qian Li; Ren Zhibin; Li Shaolei; Liu Bo; Chen Jinglin

2012-01-01

Highlights: ► In this study the first DC performance experiments of ITER correction coil conductor short sample have been carried out in ASIPP test facility. ► A CC conductor short sample was fabricated and tested to confirm the capability of this test facility for qualification tests of CC conductors. ► There is no obvious impact of cycling on DC performance measurement. ► Those measured results of current sharing temperature are in agreement with the expected results from strand scaling - Abstract: The first DC performance experiments of ITER correction coil (CC) conductor short sample have been carried out in the conductor test facility of Institute of Plasma Physics, CAS (ASIPP) in January this year. Those experiments aim to investigate the DC performance of ITER CC conductor. The tested conductor short sample is bended as a half circle with the diameter of 270 mm to meet the background magnetic field shape. The half circle part of sample is longer than the final twist pitch. The current sharing temperature (T cs ) in the 3.86 T external magnetic field (B ex ), ≤12 kA could be measured including the critical current (I c ) run. There is no obvious impact of 1000 cycles on DC performance. Those measured T cs results are in agreement with the expected results from strand scaling.

Overview of high intensity proton accelerator facility, J-PARC

International Nuclear Information System (INIS)

Ikeda, Y.

2010-01-01

The J-PARC project of high intensity proton accelerator research complex, conducted jointly by JAERI and KEK, has been completed with demonstration of all beam productions in 2009 as the facility construction phase, and the operation started to offer the secondary beams of neutron, muon, kaon, and neutrino, to the advanced scientific experimental research aiming at making breakthroughs in materials and life science, nuclear and elementary physics, etc. This text describes the overview of the J-PARC present status with emphasis of a performance toward to 1MW power as user facilities. (author)

Facilities and procedures used for the performance testing of DOE personnel dosimetry systems

Energy Technology Data Exchange (ETDEWEB)

Roberson, P.L.; Fox, R.A.; Hogan, R.T.; Holbrook, K.L.; Hooker, C.D.; Yoder, R.C.

1983-04-01

Radiological calibration facilities for personnel dosimeter testing were developed at the Pacific Northwest Laboratory (PNL) for the Department of Energy (DOE) to provide a capability for evaluating the performance of DOE personnel dosimetry systems. This report includes the testing methodology used. The informational presented here meets requirements specified in draft ANSI N13.11 for the testing laboratory. The capabilities of these facilities include sealed source irradiations for /sup 137/Cs, several beta-particle emitters, /sup 252/Cf, and machine-generated x-ray beams. The x-ray beam capabilities include filtered techniques maintained by the National Bureau of Standards (NBS) and K-fluorescent techniques. The calibration techniques, dosimeter irradiation procedures, and dose-equivalent calculation methods follow techniques specified by draft ANSI N13.11 where appropriate.

Facilities and procedures used for the performance testing of DOE personnel-dosimetry systems

International Nuclear Information System (INIS)

Roberson, P.L.; Fox, R.A.; Hogan, R.T.; Holbrook, K.L.; Hooker, C.D.; Yoder, R.C.

1983-04-01

Radiological calibration facilities for personnel dosimeter testing were developed at the Pacific Northwest Laboratory (PNL) for the Department of Energy (DOE) to provide a capability for evaluating the performance of DOE personnel dosimetry systems. This report includes the testing methodology used. The informational presented here meets requirements specified in draft ANSI N13.11 for the testing laboratory. The capabilities of these facilities include sealed source irradiations for 137 Cs, several beta-particle emitters, 252 Cf, and machine-generated x-ray beams. The x-ray beam capabilities include filtered techniques maintained by the National Bureau of Standards (NBS) and K-fluorescent techniques. The calibration techniques, dosimeter irradiation procedures, and dose-equivalent calculation methods follow techniques specified by draft ANSI N13.11 where appropriate

Manufacturing lines under surplus-based control : multiple products and bounded buffers

NARCIS (Netherlands)

Starkov, K.; Pogromskiy, A.Y.; Adan, I.J.B.F.

2015-01-01

Challenged by the scheduling complexity for production flow processes in industrial facilities, we study the performance of multi-product producing lines. We analyse the performance of multi-product lines that consist a number of machines and bounded buffers with preselected base stock levels. It is

9 CFR 3.27 - Facilities, outdoor.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Facilities, outdoor. 3.27 Section 3.27... Pigs and Hamsters Facilities and Operating Standards § 3.27 Facilities, outdoor. (a) Hamsters shall not be housed in outdoor facilities. (b) Guinea pigs shall not be housed in outdoor facilities unless...

An overview of technical requirements on durable concrete production for near surface disposal facilities for radioactive wastes

International Nuclear Information System (INIS)

Tolentino, Evandro; Tello, Cledola Cassia Oliveira de

2013-01-01

Radioactive waste can be generated by a wide range of activities varying from activities in hospitals to nuclear power plants, to mines and mineral processing facilities. General public have devoted nowadays considerable attention to the subject of radioactive waste management due to heightened awareness of environmental protection. The preferred strategy for the management of all radioactive waste is to contain it and to isolate it from the accessible biosphere. The Federal Government of Brazil has announced the construction for the year of 2014 and operation for the year of 2016 of a near surface disposal facility for low and intermediate level radioactive waste. The objective of this paper is to provide an overview of technical requirements related to production of durable concrete to be used in near surface disposal facilities for radioactive waste concrete structures. These requirements have been considered by researchers dealing with ongoing designing effort of the Brazilian near surface disposal facility. (author)

Site maps and facilities listings

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities.

Site maps and facilities listings

International Nuclear Information System (INIS)

1993-11-01

In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities

Experimental results of the SMART ECC injection performance with reduced scale of test facility

Energy Technology Data Exchange (ETDEWEB)

Cho, Young Il; Cho, Seok; Ko, Yung Joo; Shin, Yong Cheol; Kwon, Tae Soon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

SMART pressurized water reactor type is different from the existing integral NSSS commercial pressurized water reactor system which is equipped with the main features. In addition, RCS piping is removed and the feature of the SBLOCA is a major design break accident. SWAT (SMART ECC Water Asymmetric Two-phase choking test facility) test facility is to simulate the 2 inch SBLOCA of the SMART using with reduced scale. The Test was performed to produce experimental data for the validation of the TASS/SMR-S thermal hydraulic analysis code, and to investigate the related thermal hydraulic phenomena in the down-comer region during the 2 inch SBLOCA of the safety inject line. The particular phenomena for the observation are ECC bypass and multi-dimensional flow characteristics to verify the effectiveness and performance of the safety injection system. In this paper, the corresponding steady state test conditions, including initial and boundary conditions along with major measuring parameters, and related experimental results were described

Annual report on experimental operation of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system in 2001 fiscal year (Contract research)

International Nuclear Information System (INIS)

Hayashi, Koji; Inagaki, Yoshiyuki; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; Takada, Shoji; Shimizu, Akira; Morisaki, Norihiro; Sakaki, Akihiro; Maeda, Yukimasa; Sato, Hiroyuki

2005-06-01

This is an annual report on the experimental operation of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system in 2001 fiscal year. The first experimental operation was performed during two weeks from March 1, 2002 to March 13, 2002 to test on the thermal hydraulic performance of the steam reformer and also to train the operators. The thermal hydraulic performance test of the steam reformer was performed to evaluate the heat transfer characteristics between helium gas and process gas in the steam reformer. This report is summarized with an overview of the test, the results and its operation records. (author)

Performance Test of Korea Heat Load Test Facility (KoHLT-EB) for the Plasma Facing Components of Fusion Reactor

International Nuclear Information System (INIS)

Kim, Suk-Kwon; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae-Sung; Lee, Dong Won; Cho, Seungyon

2014-01-01

The main components of the plasma facing components (PFCs) in the tokamak are the blanket first wall and divertor, which include the armour materials, the heat sink with the cooling mechanism, and the diagnostics devices for the temperature measurement. The Korea Heat Load Test facility by using electron beam (KoHLT-EB) has been operating for the plasma facing components to develop fusion engineering. This electron beam facility was constructed using a 300 kW electron gun and a cylindrical vacuum chamber. Performance tests were carried out for the calorimetric calibrations with Cu dummy mockup and for the heat load test of large Cu module. For the simulation of the heat load test of each mockup, the preliminary thermal-hydraulic analyses with ANSYS-CFX were performed. For the development of the plasma facing components in the fusion reactors, test mockups were fabricated and tested in the high heat flux test facility. To perform a beam profile test, an assessment of the possibility of electron beam Gaussian power density profile and the results of the absorbed power for that profile before the test starts are needed. To assess the possibility of a Gaussian profile, for the qualification test of the Gaussian heat load profile, a calorimeter mockup and large Cu module were manufactured to simulate real heat. For this high-heat flux test, the Korean high-heat flux test facility using an electron beam system was constructed. In this facility, a cyclic heat flux test will be performed to measure the surface heat flux, surface temperature profile, and cooling capacity

Performance Test of Korea Heat Load Test Facility (KoHLT-EB) for the Plasma Facing Components of Fusion Reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk-Kwon; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae-Sung; Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

2014-10-15

The main components of the plasma facing components (PFCs) in the tokamak are the blanket first wall and divertor, which include the armour materials, the heat sink with the cooling mechanism, and the diagnostics devices for the temperature measurement. The Korea Heat Load Test facility by using electron beam (KoHLT-EB) has been operating for the plasma facing components to develop fusion engineering. This electron beam facility was constructed using a 300 kW electron gun and a cylindrical vacuum chamber. Performance tests were carried out for the calorimetric calibrations with Cu dummy mockup and for the heat load test of large Cu module. For the simulation of the heat load test of each mockup, the preliminary thermal-hydraulic analyses with ANSYS-CFX were performed. For the development of the plasma facing components in the fusion reactors, test mockups were fabricated and tested in the high heat flux test facility. To perform a beam profile test, an assessment of the possibility of electron beam Gaussian power density profile and the results of the absorbed power for that profile before the test starts are needed. To assess the possibility of a Gaussian profile, for the qualification test of the Gaussian heat load profile, a calorimeter mockup and large Cu module were manufactured to simulate real heat. For this high-heat flux test, the Korean high-heat flux test facility using an electron beam system was constructed. In this facility, a cyclic heat flux test will be performed to measure the surface heat flux, surface temperature profile, and cooling capacity.

Understanding new product project performance : A meta-analysis

NARCIS (Netherlands)

Commandeur, H.R.; Pattikawa, L.H.; Verwaal, E.

2006-01-01

Purpose: The purpose of this paper is to summarize the accumulated body of knowledge on the performance of new product projects and provide directions for further research. Design/methodology/approach: Using a refined classification of antecedents of new product project performance the research

Performance test of personal RF monitor for area monitoring at magnetic confinement fusion facility

International Nuclear Information System (INIS)

Tanaka, M.; Uda, T.; Wang, J.; Fujiwara, O.

2012-01-01

For safety management at a magnetic confinement fusion-test facility, protection from not only ionising radiation, but also non-ionising radiation such as the leakage of static magnetic and electromagnetic fields is an important issue. Accordingly, the use of a commercially available personal RF monitor for multipoint area monitoring is proposed. In this study, the performance of both fast- and slow-type personal RF monitors was investigated by using a transverse electromagnetic cell system. The range of target frequencies was between 10 and 300 MHz, corresponding to the ion cyclotron range of frequency in a fusion device. The personal RF monitor was found to have good linearity, frequency dependence and isotropic response. However, the time constant for the electric field sensor of the slow-type monitor was much longer than that for the fast-type monitor. Considering the time-varying field at the facility, it is found that the fast-type monitor is suitable for multipoint monitoring at magnetic confinement fusion test facilities. (authors)

System-theoretic analysis of due-time performance in production systems

Directory of Open Access Journals (Sweden)

David Jacobs

1995-01-01

Full Text Available Along with the average production rate, the due-time performance is an important characteristic of manufacturing systems. Unlike the production rate, the due-time performance has received relatively little attention in the literature, especially in the context of large volume production. This paper is devoted to this topic. Specifically, the notion of due-time performance is formalized as the probability that the number of parts produced during the shipping period reaches the required shipment size. This performance index is analyzed for both lean and mass manufacturing environments. In particular, it is shown that, to achieve a high due-time performance in a lean environment, the production system should be scheduled for a sufficiently small fraction of its average production rate. In mass production, due-time performance arbitrarily close to one can be achieved for any scheduling practice, up to the average production rate.

Description of the blowdown test facility COG program on in-reactor fission product release, transport, and deposition under severe accident conditions

International Nuclear Information System (INIS)

Fehrenbach, P.J.; Wood, J.C.

1987-06-01

Loss-of-coolant accidents with additional impairment of emergency cooling would probably result in high fuel temperatures leading to severe fuel damage (SFD) and significant fission product activity would then be transported along the PHTS to the break where a fraction of it would be released and transport under such conditions, there are many interacting and sometimes competing phenomena to consider. Laboratory simulations are being used to provide data on these individual phenomena, such as UO 2 oxidation and Zr-UO 2 interaction, from which mathematical models can be constructed. These are then combined into computer codes to include the interaction effects and assess the overall releases. In addition, in-reactor tests are the only source of data on release and transport of short-lived fission product nuclides, which are important in the consequence analysis of CANDU reactor accidents. Post-test decontamination of an in-reactor test facility also provides a unique opportunity to demonstrate techniques and obtain decontamination data relevant to post-accident rehabilitation of CANDU power reactors. Specialized facilities are required for in-reactor testing because of the extensive release of radioactive fission products and the high temperatures involved (up to 2500 degrees Celsius). To meet this need for the Canadian program, the Blowdown Test Facility (BTF) has been built in the NRU reactor at Chalk River. Between completion of construction in mid-1987 and the first Zircaloy-sheathed fuel test in fiscal year 1987/88, several commissioning tests are being performed. Similarly, extensive development work has been completed to permit application of instrumentation to irradiated fuel elements, and in support of post-test fuel assembly examination. A program of decontamination studies has also been developed to generate information relevant to post-accident decontamination of power reactors. The BTF shared cost test program funded by the COG High Temperature

University of Wisconsin Oshkosh Anaerobic Dry Digestion Facility

Energy Technology Data Exchange (ETDEWEB)

Koker, John [Univ. of Wisconsin, Oshkosh, WI (United States); Lizotte, Michael [Univ. of Wisconsin, Oshkosh, WI (United States)

2017-02-08

The University of Wisconsin Oshkosh Anaerobic Dry Digestion Facility is a demonstration project that supported the first commercial-scale use in the United States of high solids, static pile technology for anaerobic digestion of organic waste to generate biogas for use in generating electricity and heat. The research adds to the understanding of startup, operation and supply chain issues for anaerobic digester technology. Issues and performance were documented for equipment installation and modifications, feedstock availability and quality, weekly loading and unloading of digestion chambers, chemical composition of biogas produced, and energy production. This facility also demonstrated an urban industrial ecology approach to siting such facilities near sewage treatment plants (to capture and use excess biogas generated by the plants) and organic yard waste collection sites (a source of feedstock).

Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

CERN Document Server

Gencer, A.; Efthymiopoulos, I.; Yiğitoğlu, M.

2016-01-01

Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between View the MathML source10μA and View the MathML source1.2mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam ...

Hybrid gas turbine–organic Rankine cycle for seawater desalination by reverse osmosis in a hydrocarbon production facility

International Nuclear Information System (INIS)

Eveloy, Valérie; Rodgers, Peter; Qiu, Linyue

2015-01-01

Highlights: • Seawater reverse osmosis driven by hybrid gas turbine–organic Rankine power cycle. • High ambient air and seawater temperatures, and high seawater salinity. • Energy–exergy analysis of power and desalination systems for six organic fluids. • Economic viability of waste heat recovery in subsidized utility pricing context. - Abstract: Despite water scarcity, the use of industrial waste heat for seawater desalination has been limited in the Middle East to date. This study evaluates the technical and economic feasibility of integrating on-site gas turbine power generation and reverse osmosis equipment for the production of both electricity and fresh water in a coastal hydrocarbon production facility. Gas turbine exhaust gas waste heat is recovered using an intermediate heat transfer fluid and fed to an organic Rankine cycle evaporator, to generate mechanical power to drive the reverse osmosis high pressure pump. Six candidate organic working fluids are evaluated, namely toluene, benzene, cyclohexane, cyclopentane, n-pentane and R245fa. Thermodynamic and desalination performance are assessed in the harsh climatic and salinity conditions of the Arabian Gulf. The performance metrics considered incorporate electric power and permeate production, thermal and exergy efficiency, specific energy consumption, system size, and permeate quality. Using toluene in the bottoming power cycle, a gain in power generation efficiency of approximately 12% is achieved relative to the existing gas turbine cycle, with an annual average of 2260 m"3/h of fresh water produced. Depending upon the projected evolution of local water prices, the investment becomes profitable after two to four years, with an end-of-life net present value of 220–380 million USD, and internal rate of return of 26–48%.

The GreenLab Research Facility: A Micro-Grid Integrating Production, Consumption and Storage of Clean Energy

Science.gov (United States)

McDowell Bomani, Bilal Mark; Elbuluk, Malik; Fain, Henry; Kankam, Mark D.

2012-01-01

There is a large gap between the production and demand for energy from alternative fuel and alternative renewable energy sources. The NASA Glenn Research Center (GRC) has initiated a laboratory-pilot study that concentrates on using biofuels as viable alternative fuel resources for the field of aviation, as well as, utilizing wind and solar technologies as alternative renewable energy resources, and in addition, the use of pumped water for storage of energy that can be retrieved through hydroelectric generation. This paper describes the GreenLab Research Facility and its power and energy sources with .recommendations for worldwide expansion and adoption of the concept of such a facility

Overview of SNS Cryomodule Performance

International Nuclear Information System (INIS)

Michael Drury; Edward Daly; Christiana Grenoble; William Hicks; Lawrence King; Tomasz Plawski; Thomas Powers; Joseph Preble; Haipeng Wang; Mark Wiseman; G. Davis; Jean Delayen

2005-01-01

Thomas Jefferson National Accelerating Facility (Jefferson Lab) has completed production of 24 Superconducting Radio Frequency (SRF) cryomodules for the Spallation Neutron Source (SNS) superconducting linac. This includes one medium-β (0.61) prototype, eleven medium-β and twelve high-β (0.81) production cryomodules. Nine medium-β cryomodules as well as two high-β cryomodules have undergone complete operational performance testing in the Cryomodule Test Facility at Jefferson Lab. The set of tests includes measurements of maximum gradient, unloaded Q (Q 0 ), microphonics, and response to Lorentz forces. The Q ext 's of the various couplers are measured and the behavior of the higher order mode couplers is examined. The mechanical and piezo tuners are also characterized. The results of these performance tests will be discussed in this paper

SNS Cryomodule Performance

International Nuclear Information System (INIS)

Isidoro Campisi; Edward Daly; G. Davis; Jean Delayen; Michael Drury; Christiana Grenoble; John Hogan; Lawrence King; Peter Kneisel; John Mammosser; Thomas Powers; Joseph Preble; Mircia Stirbet; Haipeng Wang; Tim Whitlatch; Mark Wiseman

2003-01-01

Thomas Jefferson National Accelerating Facility, Jefferson Lab, is producing 24 Superconducting Radio FR-equency (SRF) cryomodules for the Spallation Neutron Source (SNS) cold linac. This includes one medium beta (0.61) prototype, 11 medium beta production, and 12 high beta (0.81) production cryomodules. After testing [ ], the medium beta prototype cryomodule was shipped to Oak Ridge National Laboratory (ORNL) and acceptance check out has been completed. All production orders for cavities and cryomodule components are being received at this time and the medium beta cryomodule production run has started. Each of the medium beta cryomodules is scheduled to undergo complete operational performance testing at Jefferson Laboratory before shipment to ORNL. The performance results of cryomodules to date will be discussed

Optimizing clinical drug product performance

DEFF Research Database (Denmark)

Dickinson, Paul A.; Kesisoglou, Filippos; Flanagan, Talia

2016-01-01

The aim of Biopharmaceutics Risk Assessment Roadmap (BioRAM) and the BioRAM Scoring Grid is to facilitate optimization of clinical performance of drug products. BioRAM strategy relies on therapy-driven drug delivery and follows an integrated systems approach for formulating and addressing critical...... questions and decision-making (J Pharm Sci. 2014,103(11): 3777-97). In BioRAM, risk is defined as not achieving the intended in vivo drug product performance, and success is assessed by time to decision-making and action. Emphasis on time to decision-making and time to action highlights the value of well....... Application of the BioRAM Scoring Grid is illustrated using published literature. Organizational considerations for implementing BioRAM strategy, including the interactions, function, and skillsets of the BioRAM group members, are also reviewed. As a creative and innovative systems approach, we believe...

Self-imposed self-assessment program at a DOE Nuclear Facility

International Nuclear Information System (INIS)

Geoffrion, R.R.; Loud, J.J.; Walter, E.C.

1996-01-01

The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL's internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES ampersand H, conduct of operations, and other functional area requirements

A Facile Approach to Evaluate Thermal Insulation Performance of Paper Cups

Directory of Open Access Journals (Sweden)

Yudi Kuang

2015-01-01

Full Text Available Paper cups are ubiquitous in daily life for serving water, soup, coffee, tea, and milk due to their convenience, biodegradability, recyclability, and sustainability. The thermal insulation performance of paper cups is of significance because they are used to supply hot food or drinks. Using an effective thermal conductivity to accurately evaluate the thermal insulation performance of paper cups is complex due to the inclusion of complicated components and a multilayer structure. Moreover, an effective thermal conductivity is unsuitable for evaluating thermal insulation performance of paper cups in the case of fluctuating temperature. In this work, we propose a facile approach to precisely analyze the thermal insulation performance of paper cups in a particular range of temperature by using an evaluation model based on the MISO (Multiple-Input Single-Output technical theory, which includes a characterization parameter (temperature factor and a measurement apparatus. A series of experiments was conducted according to this evaluation model, and the results show that this evaluation model enables accurate characterization of the thermal insulation performance of paper cups and provides an efficient theoretical basis for selecting paper materials for paper cups.

9 CFR 3.102 - Facilities, indoor.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Facilities, indoor. 3.102 Section 3... Marine Mammals Facilities and Operating Standards § 3.102 Facilities, indoor. (a) Ambient temperature. The air and water temperatures in indoor facilities shall be sufficiently regulated by heating or...

Annual Status Report (FY2016) Performance Assessment for the Environmental Restoration Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Casbon, M. A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2017-03-15

DOE O 435.1, Radioactive Waste Management, and DOE M 435.1-1, Radioactive Waste Management Manual, require that a determination of continued adequacy of the performance assessment (PA), composite analysis (CA), and disposal authorization statement (DAS) be made on an annual basis, and it must consider the results of data collection and analysis from research, field studies, and monitoring. Annual summaries of low-level waste (LLW) disposal operations must be prepared with respect to the conclusions and recommendations of the PA and CA, and a determination of the need to revise the PA or CA must be made. The annual summary requirement provides a structured approach for demonstrating the continued adequacy of the PA and CA in demonstrating a reasonable expectation that the performance objectives will be met. This annual summary addresses only the status of the Environmental Restoration Disposal Facility (ERDF) PA (CP-60089, Performance Assessment for the Environmental Restoration Disposal Facility, Hanford Site, Washington, formerly WCH-520 Rev. 1)1. The CA for ERDF is supported by DOE/RL-2016-62, Annual Status Report (FY 2016): Composite Analysis of Low Level Waste Disposal in the Central Plateau at the Hanford Site. The ERDF PA portion of the CA document is found in Section 3.1.4, and the ERDF operations portion is found in Section 3.3.3.2 of that document.

Investigation of the Effects of Facility Background Pressure on the Performance and Voltage-Current Characteristics of the High Voltage Hall Accelerator

Science.gov (United States)

Kamhawi, Hani; Huang, Wensheng; Haag, Thomas; Spektor, Rostislav

2014-01-01

The National Aeronautics and Space Administration (NASA) Science Mission Directorate In-Space Propulsion Technology office is sponsoring NASA Glenn Research Center to develop a 4 kW-class Hall thruster propulsion system for implementation in NASA science missions. A study was conducted to assess the impact of varying the facility background pressure on the High Voltage Hall Accelerator (HiVHAc) thruster performance and voltage-current characteristics. This present study evaluated the HiVHAc thruster performance in the lowest attainable background pressure condition at NASA GRC Vacuum Facility 5 to best simulate space-like conditions. Additional tests were performed at selected thruster operating conditions to investigate and elucidate the underlying physics that change during thruster operation at elevated facility background pressure. Tests were performed at background pressure conditions that are three and ten times higher than the lowest realized background pressure. Results indicated that the thruster discharge specific impulse and efficiency increased with elevated facility background pressure. The voltage-current profiles indicated a narrower stable operating region with increased background pressure. Experimental observations of the thruster operation indicated that increasing the facility background pressure shifted the ionization and acceleration zones upstream towards the thruster's anode. Future tests of the HiVHAc thruster are planned at background pressure conditions that are expected to be two to three times lower than what was achieved during this test campaign. These tests will not only assess the impact of reduced facility background pressure on thruster performance, voltage-current characteristics, and plume properties; but will also attempt to quantify the magnitude of the ionization and acceleration zones upstream shifting as a function of increased background pressure.

Social networks of nursing staff and organizational performance. A study in long-term care facilities

NARCIS (Netherlands)

Beek, A.P.A van

2013-01-01

Over the years, there has been increasing attention for the role of social networks in explaining performance differences between organizations. Yet, research on social networks within healthcare organizations in general and long-term care facilities specifically has been rare, despite growing

Long-term performance of structural component of intermediate- and low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Hwang, Joo Ho; Kim, Seong Soo; Lee, Jae Min; Kang, Dong Koo; Yu, Jeong Beom; Lim, Goon Taek

1998-03-01

Domestic and foreign requirements with regard to the selection criteria and the performance criteria for structural components of disposal facility were surveyed. Characteristics of presently available cements were studied. Types and characteristics of high performance concrete and construction methods similar to disposal facility are also included in the study. Definitions of the term durability and the limit of the term were surveyed. Literature survey for the important factors affecting the durability and modeling methods to assess durability was performed. Deterioration and crack forming mechanisms were studied. Characteristics of domestic ground water were collected from KAERI data. Experiments were carried out with synthetic ground water to study the reactions between cement and constituents in the ground water. Experiments lasted up to 130 days and penetration of cations and anions was investigated. Ions of importance were Ca 2- . Mg 2- , SO 4 2+ , Cl - . Changes of ionic concentrations and compressive strength after 110 to 130 days of soaking in synthetic ground water with accelerated conditions were measured. Based upon ASTM's standard for accelerated testing, procedures to assess the durability of cement concrete were suggested

Nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

1991-01-01

The information brochure is a survey of installed nuclear facilities in Germany, presenting on one page each a picture of a nuclear power plant together with the main relevant data, or of other type of nuclear facilities belonging to the nuclear fuel cycle (such as fuel production plant, fuel production plant, fuel element storage facilities, and facilities for spent fuel and waste management). (UA) [de

Laser performance operations model (LPOM): a computational system that automates the setup and performance analysis of the national ignition facility

Energy Technology Data Exchange (ETDEWEB)

Shaw, M; House, R; Williams, W; Haynam, C; White, R; Orth, C; Sacks, R [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, CA, 94550 (United States)], E-mail: shaw7@llnl.gov

2008-05-15

The National Ignition Facility (NIF) is a stadium-sized facility containing a 192-beam, 1.8 MJ, 500-TW, 351-nm laser system together with a 10-m diameter target chamber with room for many target diagnostics. NIF will be the world's largest laser experimental system, providing a national center to study inertial confinement fusion and the physics of matter at extreme energy densities and pressures. A computational system, the Laser Performance Operations Model (LPOM) has been developed and deployed that automates the laser setup process, and accurately predict laser energetics. LPOM determines the settings of the injection laser system required to achieve the desired main laser output, provides equipment protection, determines the diagnostic setup, and supplies post shot data analysis and reporting.

Lean Production Practices to Enhance Organisational Performance

Directory of Open Access Journals (Sweden)

Shah Satya

2017-01-01

Full Text Available Service sector organisations are constantly overcoming the challenges facing the over-production and waste reduction within their environments. Industries are also becoming very competitive thus forcing them to seek suitable production organisation strategies with the aim towards enhancing their competitiveness and efficiency. The aim of this research study is to investigate the impact of lean production practices on the performance of service based businesses through the case study of a local baked goods supplier. The research framework adopted consists of questionnaire survey method implemented with different end users, thus covering the overall production – retail – customer cycle. The research results and analysis justify the objective of the research that lean production practices enhance the performance of the supplier company and the common tool identified were JIT (Just in Time, Value Steam Mapping (VSP and the 5S methods. The results also suggest that JIT method has a higher impact towards improvement on performance relating to quality, speed, dependability, flexibility and cost of the supplier. However, the research study also identifies that one of the major challenges faced by the organisation while adopting lean practices was the lack of commitment from top management, continuous training and employee engagement measures.

9 CFR 3.25 - Facilities, general.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Facilities, general. 3.25 Section 3.25... Pigs and Hamsters Facilities and Operating Standards § 3.25 Facilities, general. (a) Structural strength. Indoor and outdoor housing facilities for guinea pigs or hamsters shall be structurally sound and...

High performance capsule implosions on the OMEGA Laser facility with rugby hohlraums

International Nuclear Information System (INIS)

Robey, H. F.; Amendt, P.; Park, H.-S.; Town, R. P. J.; Milovich, J. L.; Doeppner, T.; Hinkel, D. E.; Wallace, R.; Sorce, C.; Strozzi, D. J.; Philippe, F.; Casner, A.; Caillaud, T.; Landoas, O.; Liberatore, S.; Monteil, M.-C.; Seguin, F.; Rosenberg, M.; Li, C. K.; Petrasso, R.

2010-01-01

Rugby-shaped hohlraums have been proposed as a method for x-ray drive enhancement for indirectly driven capsule implosions. This concept has recently been tested in a series of shots on the OMEGA laser facility [T. R. Boehly, D. L. Brown, R. S. Craxton et al., Opt. Commun. 133, 495 (1997)]. In this paper, experimental results are presented comparing the performance of D 2 -filled capsules between standard cylindrical Au hohlraums and rugby-shaped hohlraums. The rugby hohlraums demonstrated 18% more x-ray drive energy as compared with the cylinders, and the high-performance design of these implosions (both cylinder and rugby) also provided ≅20x more deuterium (DD) neutrons than any previous indirectly driven campaign on OMEGA and ≅3x more than ever achieved on NOVA [E. M. Campbell, Laser Part. Beams 9, 209 (1991)] implosions driven with nearly twice the laser energy. This increase in performance enables, for the first time, a measurement of the neutron burn history and imaging of the neutron core shapes in an indirectly driven implosion. Previous DD neutron yields had been too low to register this key measurement of capsule performance and the effects of dynamic mix. A wealth of additional data on the fuel areal density from the suite of charged particle diagnostics was obtained on a subset of the shots that used D 3 He rather than D 2 fuel. Comparisons of the experimental results with numerical simulations are shown to be in very good agreement. The design techniques employed in this campaign, e.g., smaller laser entrance holes and hohlraum case-to-capsule ratios, provide added confidence in the pursuit of ignition on the National Ignition Facility [J. D. Lindl, P. Amendt, R. L. Berger et al., Phys. Plasmas 11, 339 (2004)].

High performance capsule implosions on the OMEGA Laser facility with rugby hohlraumsa)

Science.gov (United States)

Robey, H. F.; Amendt, P.; Park, H.-S.; Town, R. P. J.; Milovich, J. L.; Döppner, T.; Hinkel, D. E.; Wallace, R.; Sorce, C.; Strozzi, D. J.; Philippe, F.; Casner, A.; Caillaud, T.; Landoas, O.; Liberatore, S.; Monteil, M.-C.; Séguin, F.; Rosenberg, M.; Li, C. K.; Petrasso, R.; Glebov, V.; Stoeckl, C.; Nikroo, A.; Giraldez, E.

2010-05-01

Rugby-shaped hohlraums have been proposed as a method for x-ray drive enhancement for indirectly driven capsule implosions. This concept has recently been tested in a series of shots on the OMEGA laser facility [T. R. Boehly, D. L. Brown, R. S. Craxton et al., Opt. Commun. 133, 495 (1997)]. In this paper, experimental results are presented comparing the performance of D2-filled capsules between standard cylindrical Au hohlraums and rugby-shaped hohlraums. The rugby hohlraums demonstrated 18% more x-ray drive energy as compared with the cylinders, and the high-performance design of these implosions (both cylinder and rugby) also provided ≈20× more deuterium (DD) neutrons than any previous indirectly driven campaign on OMEGA and ≈3× more than ever achieved on NOVA [E. M. Campbell, Laser Part. Beams 9, 209 (1991)] implosions driven with nearly twice the laser energy. This increase in performance enables, for the first time, a measurement of the neutron burn history and imaging of the neutron core shapes in an indirectly driven implosion. Previous DD neutron yields had been too low to register this key measurement of capsule performance and the effects of dynamic mix. A wealth of additional data on the fuel areal density from the suite of charged particle diagnostics was obtained on a subset of the shots that used D H3e rather than D2 fuel. Comparisons of the experimental results with numerical simulations are shown to be in very good agreement. The design techniques employed in this campaign, e.g., smaller laser entrance holes and hohlraum case-to-capsule ratios, provide added confidence in the pursuit of ignition on the National Ignition Facility [J. D. Lindl, P. Amendt, R. L. Berger et al., Phys. Plasmas 11, 339 (2004)].

High Performance Capsule Implosions on the Omega Laser Facility with Rugby Hohlraums

Science.gov (United States)

Robey, Harry F.

2009-11-01

Rugby-shaped hohlraums have been proposed as a method for x-ray drive enhancement for indirectly-driven capsule implosions [1]. This concept has recently been tested in a series of shots on the OMEGA laser facility at the Laboratory for Laser Energetics at the University of Rochester. In this talk, experimental results are presented comparing the performance of D2-filled capsules between standard cylindrical Au hohlraums and rugby-shaped hohlraums. Not only did the rugby hohlraums demonstrate 18% more x-ray drive energy as compared with the cylinders, but the high-performance design of these implosions (both cylinder and rugby) also provided 20X more DD neutrons than any previous indirectly-driven campaign on Omega (and 3X more than ever achieved on Nova implosions driven with nearly twice the laser energy). This increase in performance enables, for the first time, a measurement of the neutron burn history of an indirectly-driven implosion. Previous DD neutron yields had been too low to register this key measurement of capsule performance and the effects of dynamic mix. A wealth of additional data on the fuel areal density from the suite of charged particle diagnostics was obtained on a subset of the shots that used D^3He rather than D2 fuel. Comparisons of the experimental results with numerical simulations are shown to be in excellent agreement. The design techniques employed in this campaign, e.g., smaller NIF-like laser entrance holes and hohlraum case-to-capsule ratios, provide added confidence in the pursuit of ignition on the National Ignition Facility. [4pt] [1] P. Amendt, C. Cerjan, D. E. Hinkel, J. L. Milovich, H.-S. Park, and H. F. Robey, ``Rugby-like hohlraum experimental designs for demonstrating x-ray drive enhancement'', Phys. Plasmas 15, 012702 (2008).

Study of the pyritized surfaces of the carbon steel components in heavy water production facilities

International Nuclear Information System (INIS)

Radulescu, Maria; Parvan, Ioana; Lucan, Dumitra; Fulger, Manuela; Dinu, Alice; Blanatui, A.

1998-01-01

The components used in the Girldler Sulfide (GS) process of heavy water production are made of carbon steel covered by iron sulfide layers of different compositions (mackinawite, troilite, pyrrhotite or pyrite) of variable thicknesses. The most protective layers which provide an acceptable corrosion resistance of the subjacent metal are the mixtures of pyrrhotite and pyrite. In the present work, the corrosion resistance of carbon steel samples covered by different types of sulfides was investigated by the following methods: X ray diffraction, metallography and electrochemical methods (potential-dynamical and electrochemical impedance). In order to carry out the electrochemical measurements in the same conditions as those of the operation of carbon steel components in D 2 O production facilities, the experiments were performed with Na 2 S solutions, at pH=4 - 13 and S 2- concentration value between 1 and 1000 mg/l. The dependence of corrosion rate kinetics on pH and S 2- concentration of the testing solution was investigated for sulfide covered samples comparatively with the uncovered ones. Corrosion rates determined gravimetrically were compared with those determined by electrochemical measurements. The uniformity and thickness of the sulfide layers were checked by metallographic methods. The composition of the sulfides formed in various environment conditions was established by X-ray diffraction. Reaction mechanisms specific for sulfide formation environments have been proposed. (authors)

Production of exotic, short lived carbon isotopes in ISOL-type facilities

CERN Document Server

Franberg, Hanna; Köster, Ulli; Ammann, Markus

2008-01-01

The beam intensities of short-lived carbon isotopes at Isotope Separation On-Line (ISOL) facilities have been limited in the past for technical reasons. The production of radioactive ion beams of carbon isotopes is currently of high interest for fundamental nuclear physics research. To produce radioactive ions a target station consisting of a target in a container connected to an ion source via a transfer line is commonly used. The target is heated to vaporize the product for transport. Carbon in elementary form is a very reactive element and react strongly with hot metal surfaces. Due to the strong chemisorption interaction, in the target and ion source unit, the atoms undergo significant retention on their way from the target to the ion source. Due to this the short lived isotopes decays and are lost leading to low ion yields. A first approach to tackle these limitations consists of incorporating the carbon atoms into less reactive molecules and to use materials for the target housing and the transfer line ...

Screening Study for Utilizing Feedstocks Grown on CRP Lands in a Biomass to Ethanol Production Facility: Final Subcontract Report; July 1998

Energy Technology Data Exchange (ETDEWEB)

American Coalition for Ethanol; Wu, L.

2004-02-01

Feasibility study for a cellulosic ethanol plant using grasses grown on Conservation Reserve Program lands in three counties of South Dakota, with several subcomponent appendices. In 1994, there were over 1.8 million acres of CRP lands in South Dakota. This represented approximately 5 percent of the total U.S. cropland enrolled in the CRP. Nearly 200,000 acres of CRP lands were concentrated in three northeastern South Dakota counties: Brown, Marshall and Day. Most of the acreage was planted in Brohm Grass and Western Switchgrass. Technology under development at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL), and at other institutions, is directed towards the economical production of fuel-grade ethanol from these grasses. The objective of this study is to identify and evaluate a site in northeastern South Dakota which would have the greatest potential for long-term operation of a financially attractive biomass-to-ethanol production facility. The effort shall focus on ethanol marketing issues which would provide for long-term viability of the facility, feedstock production and delivery systems (and possible alternatives), and preliminary engineering considerations for the facility, as well as developing financial pro-formas for a proposed biomass-to-ethanol production facility in northeastern South Dakota. This Final Report summarizes what was learned in the tasks of this project, pulling out the most important aspects of each of the tasks done as part of this study. For greater detail on each area it is advised that the reader refer to the entire reports which are included as appendixes.

Dependence of the source performance on plasma parameters at the BATMAN test facility

Science.gov (United States)

Wimmer, C.; Fantz, U.

2015-04-01

The investigation of the dependence of the source performance (high jH-, low je) for optimum Cs conditions on the plasma parameters at the BATMAN (Bavarian Test MAchine for Negative hydrogen ions) test facility is desirable in order to find key parameters for the operation of the source as well as to deepen the physical understanding. The most relevant source physics takes place in the extended boundary layer, which is the plasma layer with a thickness of several cm in front of the plasma grid: the production of H-, its transport through the plasma and its extraction, inevitably accompanied by the co-extraction of electrons. Hence, a link of the source performance with the plasma parameters in the extended boundary layer is expected. In order to characterize electron and negative hydrogen ion fluxes in the extended boundary layer, Cavity Ring-Down Spectroscopy and Langmuir probes have been applied for the measurement of the H- density and the determination of the plasma density, the plasma potential and the electron temperature, respectively. The plasma potential is of particular importance as it determines the sheath potential profile at the plasma grid: depending on the plasma grid bias relative to the plasma potential, a transition in the plasma sheath from an electron repelling to an electron attracting sheath takes place, influencing strongly the electron fraction of the bias current and thus the amount of co-extracted electrons. Dependencies of the source performance on the determined plasma parameters are presented for the comparison of two source pressures (0.6 Pa, 0.45 Pa) in hydrogen operation. The higher source pressure of 0.6 Pa is a standard point of operation at BATMAN with external magnets, whereas the lower pressure of 0.45 Pa is closer to the ITER requirements (p ≤ 0.3 Pa).

Dependence of the source performance on plasma parameters at the BATMAN test facility

International Nuclear Information System (INIS)

Wimmer, C.; Fantz, U.

2015-01-01

The investigation of the dependence of the source performance (high j H − , low j e ) for optimum Cs conditions on the plasma parameters at the BATMAN (Bavarian Test MAchine for Negative hydrogen ions) test facility is desirable in order to find key parameters for the operation of the source as well as to deepen the physical understanding. The most relevant source physics takes place in the extended boundary layer, which is the plasma layer with a thickness of several cm in front of the plasma grid: the production of H − , its transport through the plasma and its extraction, inevitably accompanied by the co-extraction of electrons. Hence, a link of the source performance with the plasma parameters in the extended boundary layer is expected. In order to characterize electron and negative hydrogen ion fluxes in the extended boundary layer, Cavity Ring-Down Spectroscopy and Langmuir probes have been applied for the measurement of the H − density and the determination of the plasma density, the plasma potential and the electron temperature, respectively. The plasma potential is of particular importance as it determines the sheath potential profile at the plasma grid: depending on the plasma grid bias relative to the plasma potential, a transition in the plasma sheath from an electron repelling to an electron attracting sheath takes place, influencing strongly the electron fraction of the bias current and thus the amount of co-extracted electrons. Dependencies of the source performance on the determined plasma parameters are presented for the comparison of two source pressures (0.6 Pa, 0.45 Pa) in hydrogen operation. The higher source pressure of 0.6 Pa is a standard point of operation at BATMAN with external magnets, whereas the lower pressure of 0.45 Pa is closer to the ITER requirements (p ≤ 0.3 Pa)

Dosimetry. Standard practice for dosimetry in gamma irradiation facilities for food and non-food processing

International Nuclear Information System (INIS)

2008-01-01

This Ghana Standard outlines the installation qualification program for an irradiator and the dosimetry procedures to be followed during operational qualification, performance qualification and routine processing in facilities that process food and non-food with gamma rays. This is to ensure that the product has been treated with predetermined range of absorbed dose. It is not intended for use in X-ray and electron beam facilities and therefore dosimetry systems in such facilities are not covered

Sustainability Performance of an Italian Textile Product

Directory of Open Access Journals (Sweden)

Paola Lenzo

2018-03-01

Full Text Available Companies are more and more interested in the improvement of sustainability performance of products, services and processes. For this reason, appropriate and suitable assessment tools supporting the transition to a green economy are highly necessary. Currently, there are a number of methods and approaches for assessing products’ environmental impact and improving their performances; among these, the Life Cycle Thinking (LCT approach has emerged as the most comprehensive and effective to achieve sustainability goals. Indeed, the LCT approach aims to reduce the use of resources and emissions to the environment associated with a product’s life cycle. It can be used as well to improve socio-economic performance through the entire life cycle of a product. Life Cycle Assessment (LCA, Life Cycle Costing (LCC and Social Life Cycle Assessment (S-LCA are undoubtedly the most relevant methodologies to support product-related decision-making activities for the extraction and processing of raw materials, manufacturing, distribution, use, reuse, maintenance, recycling and final disposal. While LCA is an internationally standardized tool (ISO 14040 2006, LCC (except for the ISO related to the building sector and S-LCA have yet to attain international standardization (even if guidelines and general frameworks are available. The S-LCA is still in its experimental phase for many aspects of the methodological structure and practical implementation. This study presents the application of LCA and S-LCA to a textile product. The LCA and S-LCA are implemented following the ISO 14040-44:2006 and the guidelines from UNEP/SETAC (2009, respectively. The functional unit of the study is a cape knitted in a soft blend of wool and cashmere produced by a textile company located in Sicily (Italy. The system boundary of the study includes all phases from cradle-to-gate, from raw material production through fabric/accessory production to the manufacturing process of the

Improvement in performance and operational experience of 14 UD Pelletron accelerator facility, BARC-TIFR

International Nuclear Information System (INIS)

Bhagwat, P.V.

2002-01-01

14 UD Pelletron accelerator facility at Mumbai has been operational since 1989. The project MEHIA (Medium Energy Heavy Ion Accelerator) started in 1982 and was formally inaugurated on 30th December 1988. Since then the accelerator has been working round the clock. Improvement in accelerator performance and operational experience are described. (author)

9 CFR 590.540 - Spray process drying facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Spray process drying facilities. 590.540 Section 590.540 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF..., Processing, and Facility Requirements § 590.540 Spray process drying facilities. (a) Driers shall be of a...

Explosive Components Facility

Data.gov (United States)

Federal Laboratory Consortium — The 98,000 square foot Explosive Components Facility (ECF) is a state-of-the-art facility that provides a full-range of chemical, material, and performance analysis...

Powder metallurgy inspired low-temperature fabrication of high-performance stereocomplexed polylactide products with good optical transparency

Science.gov (United States)

Bai, Dongyu; Liu, Huili; Bai, Hongwei; Zhang, Qin; Fu, Qiang

2016-02-01

Stereocomplexation between enantiomeric poly(L-lactide) (PLLA) and poly(D-lactide) (PDLA) provides an avenue to greatly enhance performance of eco-friendly polylactide (PLA). Unfortunately, although the manufacturing of semicrystalline polymers generally involves melt processing, it is still hugely challenging to create high-performance stereocomplexed polylactide (sc-PLA) products from melt-processed high-molecular-weight PLLA/PDLA blends due to the weak crystallization memory effect of stereocomplex (sc) crystallites after complete melting as well as the substantial degradation of PLA chains at elevated melt-processing temperatures of ca. 240-260 °C. Inspired by the concept of powder metallurgy, here we report a new facile route to address these obstacles by sintering of sc-PLA powder at temperatures as low as 180-210 °C, which is distinctly different from traditional sintering of polymer powders performed at temperatures far exceeding their melting temperatures. The enantiomeric PLA chain segments from adjacent powder particles can interdiffuse across particle interfaces and co-crystallize into new sc crystallites capable of tightly welding the interfaces during the low-temperature sintering process, and thus highly transparent sc-PLA products with outstanding heat resistance, mechanical strength, and hydrolytic stability have been successfully fabricated for the first time.

Powder metallurgy inspired low-temperature fabrication of high-performance stereocomplexed polylactide products with good optical transparency

Science.gov (United States)

Bai, Dongyu; Liu, Huili; Bai, Hongwei; Zhang, Qin; Fu, Qiang

2016-01-01

Stereocomplexation between enantiomeric poly(l-lactide) (PLLA) and poly(d-lactide) (PDLA) provides an avenue to greatly enhance performance of eco-friendly polylactide (PLA). Unfortunately, although the manufacturing of semicrystalline polymers generally involves melt processing, it is still hugely challenging to create high-performance stereocomplexed polylactide (sc-PLA) products from melt-processed high-molecular-weight PLLA/PDLA blends due to the weak crystallization memory effect of stereocomplex (sc) crystallites after complete melting as well as the substantial degradation of PLA chains at elevated melt-processing temperatures of ca. 240–260 °C. Inspired by the concept of powder metallurgy, here we report a new facile route to address these obstacles by sintering of sc-PLA powder at temperatures as low as 180–210 °C, which is distinctly different from traditional sintering of polymer powders performed at temperatures far exceeding their melting temperatures. The enantiomeric PLA chain segments from adjacent powder particles can interdiffuse across particle interfaces and co-crystallize into new sc crystallites capable of tightly welding the interfaces during the low-temperature sintering process, and thus highly transparent sc-PLA products with outstanding heat resistance, mechanical strength, and hydrolytic stability have been successfully fabricated for the first time. PMID:26837848

Powder metallurgy inspired low-temperature fabrication of high-performance stereocomplexed polylactide products with good optical transparency.

Science.gov (United States)

Bai, Dongyu; Liu, Huili; Bai, Hongwei; Zhang, Qin; Fu, Qiang

2016-02-03

Stereocomplexation between enantiomeric poly(l-lactide) (PLLA) and poly(d-lactide) (PDLA) provides an avenue to greatly enhance performance of eco-friendly polylactide (PLA). Unfortunately, although the manufacturing of semicrystalline polymers generally involves melt processing, it is still hugely challenging to create high-performance stereocomplexed polylactide (sc-PLA) products from melt-processed high-molecular-weight PLLA/PDLA blends due to the weak crystallization memory effect of stereocomplex (sc) crystallites after complete melting as well as the substantial degradation of PLA chains at elevated melt-processing temperatures of ca. 240-260 °C. Inspired by the concept of powder metallurgy, here we report a new facile route to address these obstacles by sintering of sc-PLA powder at temperatures as low as 180-210 °C, which is distinctly different from traditional sintering of polymer powders performed at temperatures far exceeding their melting temperatures. The enantiomeric PLA chain segments from adjacent powder particles can interdiffuse across particle interfaces and co-crystallize into new sc crystallites capable of tightly welding the interfaces during the low-temperature sintering process, and thus highly transparent sc-PLA products with outstanding heat resistance, mechanical strength, and hydrolytic stability have been successfully fabricated for the first time.

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

Harris, W.J.; Wagner, E.P.

1979-01-01

The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained