The ISS Fluids Integrated Rack (FIR): a Summary of Capabilities

Science.gov (United States)

Gati, F.; Hill, M. E.

2002-01-01

The Fluids Integrated Rack (FIR) is a modular, multi-user scientific research facility that will fly in the U.S. laboratory module, Destiny, of the International Space Station (ISS). The FIR will be one of the two racks that will make up the Fluids and Combustion Facility (FCF) - the other being the Combustion Integrated Rack (CIR). The ISS will provide the FCF with the necessary resources, such as power and cooling. While the ISS crew will be available for experiment operations, their time will be limited. The FCF is, therefore, being designed for autonomous operations and remote control operations. Control of the FCF will be primarily through the Telescience Support Center (TSC) at the Glenn Research Center. The FCF is being designed to accommodate a wide range of combustion and fluids physics experiments within the ISS resources and constraints. The primary mission of the FIR, however, is to accommodate experiments from four major fluids physics disciplines: Complex Fluids; Multiphase Flow and Heat Transfer; Interfacial Phenomena; and Dynamics and Stability. The design of the FIR is flexible enough to accommodate experiments from other science disciplines such as Biotechnology. The FIR flexibility is a result of the large volume dedicated for experimental hardware, easily re-configurable diagnostics that allow for unique experiment configurations, and it's customizable software. The FIR will utilize six major subsystems to accommodate this broad scope of fluids physics experiments. The major subsystems are: structural, environmental, electrical, gaseous, command and data management, and imagers and illumination. Within the rack, the FIR's structural subsystem provides an optics bench type mechanical interface for the precise mounting of experimental hardware; including optical components. The back of the bench is populated with FIR avionics packages and light sources. The interior of the rack is isolated from the cabin through two rack doors that are hinged near

Rollin' in Style!: Students Design Bike Mounted Skateboard Racks

Science.gov (United States)

Massey, Rick

2008-01-01

Recognizing the increasing popularity of skateboarding, the author has found a project that teaches design and manufacturing concepts--and, of equal importance, really gets his students motivated. He challenges them to design and build a skateboard rack that mounts easily on a bicycle. The project benefits students by teaching creativity, the…

Spent fuel storage rack

International Nuclear Information System (INIS)

Morikawa, Matsuo; Uchiyama, Yuichi.

1983-01-01

Purpose: To improve the safety and facilitate the design by limiting the relative displacement in a storage rack. Constitution: The outer wall of a storage rack disposed in water within a fuel pool, the pool wall opposing to the storage rack and the structure between the opposing storages racks are made as a space for confining the pool water or a structure formed with a slight gap, for example, a combination of a recessed structure and a protruded structure. In such a constitution, a space for confirming the pool water is established and the pool water thus confined forms a flow resistance when the storage rack vibrates upon earthquakes, serves as a damper and significantly reduces the responsivity. Furthermore, the relative displacement in the storage rack is limited to inhibit excess earthquake forces to exert on setting bolts and rack clamping bolts of the storage rack. (Sekiya, K.)

Improvement of rotary specimen rack design

International Nuclear Information System (INIS)

Batch, J.M.; Gietzen, A.J.

1978-01-01

A redesign and verification test program has been completed on a new Rotary Specimen Rack ('Lazy Susan') design for the TRIGA Mark III. The purpose of the redesign was to solve a rotation problem which occurred at power levels of about 1 MW and above. The previous redesign effort on the Mark II-type lazy susan was made in 1967 when the bearing was changed to use stellite balls, spring-type separators and stainless-steel bearing races. An extensive test program at that time showed that the design gave excellent service under all anticipated operating conditions. Fifteen of these units have been installed in the past ten years and have been essentially trouble-free. Although the bearing design for the Mark III was very similar, the component layout was such that irradiation-induced heating with associated thermal expansion resulted in decreased bearing clearance and an increase in the required driving torque. The solution involved redesign and re-arrangement of the rack drive mechanism. A series of stringent operational proof tests were made under high temperature and temperature differential conditions which proved successful operation of the new design. The severe conditions under which these tests were performed uncovered further difficulties with the bearing and led to a re-evaluation of the bearing design. A new design was developed in which the spring separators were replaced by similar sized, cylindrical graphite spacers. The entire series of operational and life tests were repeated and the performance was outstanding. Acceptable wear characteristics of the spacers were verified and the bearing was noticeably smoother and quieter than with previous designs. A Mark III lazy susan of this new design was installed in a TRIGA about one year ago and operated at power levels up to 2 MW with excellent performance. The Mark II design has now been changed to incorporate the new drive and bearing design proven for the Mark III. (author)

Combined Cycle Engine Large-Scale Inlet for Mode Transition Experiments: System Identification Rack Hardware Design

Science.gov (United States)

Thomas, Randy; Stueber, Thomas J.

2013-01-01

The System Identification (SysID) Rack is a real-time hardware-in-the-loop data acquisition (DAQ) and control instrument rack that was designed and built to support inlet testing in the NASA Glenn Research Center 10- by 10-Foot Supersonic Wind Tunnel. This instrument rack is used to support experiments on the Combined-Cycle Engine Large-Scale Inlet for Mode Transition Experiment (CCE? LIMX). The CCE?LIMX is a testbed for an integrated dual flow-path inlet configuration with the two flow paths in an over-and-under arrangement such that the high-speed flow path is located below the lowspeed flow path. The CCE?LIMX includes multiple actuators that are designed to redirect airflow from one flow path to the other; this action is referred to as "inlet mode transition." Multiple phases of experiments have been planned to support research that investigates inlet mode transition: inlet characterization (Phase-1) and system identification (Phase-2). The SysID Rack hardware design met the following requirements to support Phase-1 and Phase-2 experiments: safely and effectively move multiple actuators individually or synchronously; sample and save effector control and position sensor feedback signals; automate control of actuator positioning based on a mode transition schedule; sample and save pressure sensor signals; and perform DAQ and control processes operating at 2.5 KHz. This document describes the hardware components used to build the SysID Rack including their function, specifications, and system interface. Furthermore, provided in this document are a SysID Rack effectors signal list (signal flow); system identification experiment setup; illustrations indicating a typical SysID Rack experiment; and a SysID Rack performance overview for Phase-1 and Phase-2 experiments. The SysID Rack described in this document was a useful tool to meet the project objectives.

Reusable Rack Interface Controller Common Software for Various Science Research Racks on the International Space Station

Science.gov (United States)

Lu, George C.

2003-01-01

The purpose of the EXPRESS (Expedite the PRocessing of Experiments to Space Station) rack project is to provide a set of predefined interfaces for scientific payloads which allow rapid integration into a payload rack on International Space Station (ISS). VxWorks' was selected as the operating system for the rack and payload resource controller, primarily based on the proliferation of VME (Versa Module Eurocard) products. These products provide needed flexibility for future hardware upgrades to meet everchanging science research rack configuration requirements. On the International Space Station, there are multiple science research rack configurations, including: 1) Human Research Facility (HRF); 2) EXPRESS ARIS (Active Rack Isolation System); 3) WORF (Window Observational Research Facility); and 4) HHR (Habitat Holding Rack). The RIC (Rack Interface Controller) connects payloads to the ISS bus architecture for data transfer between the payload and ground control. The RIC is a general purpose embedded computer which supports multiple communication protocols, including fiber optic communication buses, Ethernet buses, EIA-422, Mil-Std-1553 buses, SMPTE (Society Motion Picture Television Engineers)-170M video, and audio interfaces to payloads and the ISS. As a cost saving and software reliability strategy, the Boeing Payload Software Organization developed reusable common software where appropriate. These reusable modules included a set of low-level driver software interfaces to 1553B. RS232, RS422, Ethernet buses, HRDL (High Rate Data Link), video switch functionality, telemetry processing, and executive software hosted on the FUC computer. These drivers formed the basis for software development of the HRF, EXPRESS, EXPRESS ARIS, WORF, and HHR RIC executable modules. The reusable RIC common software has provided extensive benefits, including: 1) Significant reduction in development flow time; 2) Minimal rework and maintenance; 3) Improved reliability; and 4) Overall

Development of seismic design method for free standing rack and applicability to Japanese nuclear power plant

International Nuclear Information System (INIS)

Takaki, Yu; Taniguchi, Katsuhiko; Kishimoto, Junichi; Iwasaki, Akihisa; Nekomoto, Yoshitsugu; Kuga, Tohru; Kameyama, Masashi

2017-01-01

Free standing racks which are not anchored to the pool floor nor walls have never been adopted in Japan. Under an earthquake, behaviors of free standing racks are nonlinear and involve a complex combination of motions (sliding, rocking, and twisting) and impacts between a fuel assembly and the fuel cell walls and between a pit floor and rack pedestals. To predict a seismic response of free standing racks, the seismic analysis requires careful considerations of these complex phenomena (sliding, rocking, and twisting), fluid coupling effects and frictional effects. We carried out seismic experiments on the full-scale rack model in both water and dry conditions and obtained the fundamental data about behavior of free standing racks (sliding, and rocking motions). We have developed the nonlinear dynamic analysis method to predict seismic response of free standing racks utilizing the full-scale test result and verified the analysis evaluation method of free standing rack by comparison between analysis results and experimental data. Furthermore, we applied the seismic design method to the free standing rack in the Japanese nuclear plant (Mihama nuclear power station Unit 3), and verified that the free standing rack was applicable to Japanese nuclear plant. (author)

Materials Science Research Rack-1 Fire Suppressant Distribution Test Report

Science.gov (United States)

Wieland, P. O.

2002-01-01

Fire suppressant distribution testing was performed on the Materials Science Research Rack-1 (MSRR-1), a furnace facility payload that will be installed in the U.S. Lab module of the International Space Station. Unlike racks that were tested previously, the MSRR-1 uses the Active Rack Isolation System (ARIS) to reduce vibration on experiments, so the effects of ARIS on fire suppressant distribution were unknown. Two tests were performed to map the distribution of CO2 fire suppressant throughout a mockup of the MSRR-1 designed to have the same component volumes and flowpath restrictions as the flight rack. For the first test, the average maximum CO2 concentration for the rack was 60 percent, achieved within 45 s of discharge initiation, meeting the requirement to reach 50 percent throughout the rack within 1 min. For the second test, one of the experiment mockups was removed to provide a worst-case configuration, and the average maximum CO2 concentration for the rack was 58 percent. Comparing the results of this testing with results from previous testing leads to several general conclusions that can be used to evaluate future racks. The MSRR-1 will meet the requirements for fire suppressant distribution. Primary factors that affect the ability to meet the CO2 distribution requirements are the free air volume in the rack and the total area and distribution of openings in the rack shell. The length of the suppressant flowpath and degree of tortuousness has little correlation with CO2 concentration. The total area of holes in the rack shell could be significantly increased. The free air volume could be significantly increased. To ensure the highest maximum CO2 concentration, the PFE nozzle should be inserted to the stop on the nozzle.

MSRR Rack Materials Science Research Rack

Science.gov (United States)

Reagan, Shawn

2017-01-01

The Materials Science Research Rack (MSRR) is a research facility developed under a cooperative research agreement between NASA and the European Space Agency (ESA) for materials science investigations on the International Space Station (ISS). The MSRR is managed at the Marshall Space Flight Center (MSFC) in Huntsville, AL. The MSRR facility subsystems were manufactured by Teledyne Brown Engineering (TBE) and integrated with the ESA/EADS-Astrium developed Materials Science Laboratory (MSL) at the MSFC Space Station Integration and Test Facility (SSITF) as part of the Systems Development Operations Support (SDOS) contract. MSRR was launched on STS-128 in August 2009, and is currently installed in the U. S. Destiny Laboratory Module on the ISS. Materials science is an integral part of developing new, safer, stronger, more durable materials for use throughout everyday life. The goal of studying materials processing in space is to develop a better understanding of the chemical and physical mechanisms involved, and how they differ in the microgravity environment of space. To that end, the MSRR accommodates advanced investigations in the microgravity environment of the ISS for basic materials science research in areas such as solidification of metals and alloys. MSRR allows for the study of a variety of materials including metals, ceramics, semiconductor crystals, and glasses. Materials science research benefits from the microgravity environment of space, where the researcher can better isolate chemical and thermal properties of materials from the effects of gravity. With this knowledge, reliable predictions can be made about the conditions required on Earth to achieve improved materials. MSRR is a highly automated facility with a modular design capable of supporting multiple types of investigations. Currently the NASA-provided Rack Support Subsystem provides services (power, thermal control, vacuum access, and command and data handling) to the ESA developed Materials

Thesaurus Racks - Categorical racks and applications in the algebraic topology of Lie racks

OpenAIRE

Grøsfjeld, Tobias

2016-01-01

Group objects of categories have been heavily studied in a general setting, but racks are mostly treated explicitly. Since rack structures are more general than groups, this thesis aims to explore the properties of general rack objects and use the tools of category theory to put topological racks in a new light.

40 CFR 63.1105 - Transfer racks.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 10 2010-07-01 2010-07-01 false Transfer racks. 63.1105 Section 63... Technology Standards § 63.1105 Transfer racks. (a) Design requirements. The owner or operator shall equip each transfer rack with one of the control options listed in paragraphs (a)(1) through (4) of this...

Flow in data racks

Directory of Open Access Journals (Sweden)

Manoch Lukáš

2014-03-01

Full Text Available This paper deals with the flow in data racks. The aim of this work is to find a new arrangement of elements regulating the flow in the data rack so that the aerodynamic losses and the recirculation zones were minimized. The main reason for solving this problem is to reduce the costs of data racks cooling. Another problem to be solved is a reverse flow in the servers, thus not cooled, occuring due to the underpressure in the recirculation zones. In order to solve the problem, the experimental and numerical model of 27U data rack fitted with 10 pieces of server models with a total input of 10 kW was created. Different configurations of layout of elements affecting the flow in the inlet area of the data rack were compared. Depending on the results achieved, design solutions for the improvement of existing solutions were adopted and verified by numerical simulations.

Thermal analyses for the rack design with spent fuel pool during the loss of cooling accident

Energy Technology Data Exchange (ETDEWEB)

Yeh, C-L.; Chen, Y-S.; Chen, B-Y., E-mail: clinyeh@iner.gov.tw, E-mail: yschen@iner.gov.tw, E-mail: onepicemine@iner.gov.tw [Inst. of Nuclear Energy Research, Taoyuan County, Taiwan (China); Tseng, Y-S., E-mail: ystseng@mx.nthu.edu.tw [National Tsing Hua Univ., Engineering and System Science, Hsinchu, Taiwan (China); Wei, W-C., E-mail: hn150456@iner.gov.tw [Inst. of Nuclear Energy Research, Taoyuan County, Taiwan (China)

2014-07-01

Alternative fuel arrangements separating the latest fuels discharge from the reactor core are proposed, such as the 1x4 configuration in which the hot assembly is surrounded by 4 assemblies with much lower decay heat. For the rack design in the BWR spent fuel pool design, the lateral flow is eliminated by solid walls. In this study, cooling enhancement of splitting fuel rack is investigated using Computational Fluid Dynamics (CFD). The fuels in the pool are modeled by porous medium. Separating the fuel rack by a distance of 10 cm can lower the peak cladding temperature and the natural convection between the fuels and then earns more response time for the site people to implement necessary mitigation actions. (author)

Compacted spent-fuel storage--designs and problems

International Nuclear Information System (INIS)

Rubinstein, H.J.; Gilcrest, J.D.; Kendall, W.R.

1979-01-01

Typical rack designs, licensing, contracting methods, installation and operational problems are described. Due to the lack of reprocessing and independent fuel storage facilities, new plants built in the United States will continue to install high-density spent-fuel storage racks. As to the rack designs, the most significant feature is the introduction of freestanding rack designs. The trends in spent-fuel storage appear to be toward the use of high-density racks, either with or without absorber, for all plants in the design, construction, or operation phase; the use of freestanding rack designs; and the separation of engineering and fabrication during procurement

Laboratory racks are installed in the MPLM Leonardo

Science.gov (United States)

2000-01-01

In the Space Station Processing Facility, another laboratory rack is placed on the arm of the Rack Insertion Unit to lift it to the workstand height of the Multi-Purpose Logistics Module Leonardo (not seen). The MPLM will transport laboratory racks filled with equipment, experiments and supplies to and from the International Space Station aboard the Space Shuttle. Leonardo will be launched for the first time March 1, 2001, on Shuttle mission STS-102. On that flight, Leonardo will be filled with equipment and supplies to outfit the U.S. laboratory module, being carried to the ISS on the Jan. 19, 2001, launch of STS-98.

Manufacturing and Construction of Spent Fuel Storage Rack for Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Sangjin; Jung, Kwangsub; Oh, Jinho; Lee, Jongmin [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The spent fuel storage rack consists of spent fuel storage racks and support frame. The spent fuel storage racks are installed in the support frame. A spent fuel storage rack consists of frame weldment and storage cell pipe assembly. Storage cell pipe assembly is mounted on the base plate of the frame weldment. The spent fuel storage rack is designed to withstand seismic load and other loads during earthquake. The structural integrity of the spent fuel storage rack is evaluated in accordance with ASME Section III, Subsection NF. Computer Code used for this analysis is ANSYS version 14.0.0. Dead load and seismic load is considered in load condition and hydrodynamic mass is included in the analysis. Design, manufacturing, and construction of the spent fuel storage rack are introduced. The spent fuel storage rack is for storage of spent fuel assemblies. The spent fuel storage rack should be designed, manufactured, and installed with consideration of predicted number of spent fuel assemblies, structural integrity, resistivity to corrosion and radiation, cleaning, and workability.

Head losses in small hydropower plant trash racks (SHP

Directory of Open Access Journals (Sweden)

N. Walczak

2016-12-01

Full Text Available Small hydropower plants (SHP are technical facilities that are part of alternative energy sources [Paish 2002]. They are primarily characterised by low unit power (in Poland below 5 MW and are often constructed on existing barrages. Electrical current produced by these plants is used to meet local demand. Considering the exploitation of SHPs, it is important to ensure a stable flow through turbines. Aggidis et al. [2010] analysed SHP equipment costs depending on the turbine set. The turbines are protected against damage with trash racks applied for capturing water-borne detritus, such as plant debris carried by water. However, trash racks as solid equipment of SHPs cause head losses, and as a consequence reduce the efficiency of the system. These losses result not only from the spacing of bars, their shape and the technical condition of the inlet chamber, but also from plant debris, its nature, and the quantity of accumulated material that effectively limits the flow. The plant debris captured on trash racks is characterised by diversity in terms of species composition related to the vegetation period and the area where hydraulic facilities are located. Therefore, it is important to maintain trash racks clean by regular removal of the accumulated material. In this context, modernised and newly built power plants are fitted with mechanical cleaners. In older facilities, manual intervention for regular cleaning is required. The present study analyses how the bar shape and the orientation angle of trash racks as well as the accumulated plant debris affect head losses. The results were obtained from laboratory tests. The research examined the impact the inclination angle of trash racks (30°, 60° and 80° has on head loss values for three different shapes of bars (cylindrical, angled and flat rectangular and various weight portions of plant debris (0.25, 0.375 and 0.5 kg. The summarised losses were determined by measuring the difference in water

The optimization of spent fuel assembly storage racks in nuclear power plants

International Nuclear Information System (INIS)

Wang Yan

2005-01-01

This paper gives an evaluation of the spent fuel assembly storage racks in the nuclear power plants at home and abroad, focusing on the characteristics of the high density storage racks and the aseismatic design. It mainly discusses structures and characteristics of the spent fuel assembly storage racks in the Qinshan nuclear power phase II project. Concluding the crucial technical difficulties of the high density spent fuel assembly storage racks: the neutron-absorbing materials, the structural aseismatic design technology and the security analysis technology, this paper firstly generalizes several important neutron-absorbing materials, then introduces the evolution of the aseismatic design of the spent fuel assembly storage racks . In the last part, it describes the advanced aseismatic analysis technology in the Qinshan nuclear power phase II project. Through calculation and analysis for such storage racks, the author concludes several main factors that could have an influence on the aseismatic performance and thus gives the key points and methods for designing the optimal racks and provides some references for the design of advanced spent fuel assembly storage racks in the future. (authors)

An upgrade practice of a double-rack source 60Co source irradiator

International Nuclear Information System (INIS)

Dong Hui; Peng Wei; Liu Zhaomin

2009-01-01

An upgrade practice of a double-rack irradiator with the design capacity of 2.96 x10 16 Bq (800 kCi) was reported. The detailed contents and characteristics of this upgrade, a comparison on the facility performance before and after the upgrade, and the cost-benefit analysis were carried out. After upgrade, the facility performance increased over 50%, and brought much directly economical benefit and indirectly economical benefit. The upgrade was successful, and set up a demonstrational sample. (authors)

RackSaver neutron absorbing device development and testing

International Nuclear Information System (INIS)

Lambert, R.; O'Leary, P.; Roberts, P.

1996-01-01

Siemens Power Corporation (SPC), in cooperation with the Electric Power Research Institute (EPRI), has developed the RackSaver neutron absorbing insert. The RackSaver insert can be installed onto spent nuclear fuel assemblies to replace deteriorating Boraflex neutron absorbing material installed in some spent-fuel storage racks. This paper describes results of a development and in-pool demonstration program performed to support potential utilization of the RackSaver neutron absorbing insert by affected utilities. The program objective was to advance the RackSaver concept into a field-demonstrated product. This objective was accomplished through three phases: design, licensing and criticality evaluations, and demonstration testing

Conceptual design of reactor TRIGA PUSPATI (RTP) spent fuel storage rack

International Nuclear Information System (INIS)

Tonny Lanyau; Mohd Fazli Zakaria; Zaredah Hashim; Ahmad Nabil Ab Rahim; Mohammad Suhaimi Kassim

2010-01-01

PUSPATI TRIGA Reactor (RTP) is a pool type research reactor with 1MW thermal power. It has been safely operated since 28 June 1982. During 28 years of safe operation, there are several systems and components of the RTP that have been maintained, repaired, upgraded and replaced in order to maintain its function and safety conditions. RTP has been proposed to be upgraded so that optimum operation of RTP could be achieved as well as fulfill the future needs. Thus, competencies and technical capabilities were needed to design and develop the reactor system. In the meantime, there is system or component need to be maintained such as fuel elements. Since early operation, most of the fuel elements still can be used and none of the fuel elements was replaced or sent for reprocessing and final disposal. Towards the power upgrading, preparation of spent fuel storage is needed for temporary storing of the fuels discharged from the reactor core. The spent fuel storage rack will be located in the spent fuel pool to accommodate the spent fuels before it is send to reprocessing or final disposal. This paper proposes the conceptual design of the spent fuel storage rack. The output of this paper focused on the physical and engineering design of the spent fuel storage. (author)

LIE n-RACKS

OpenAIRE

Biyogmam, Guy Roger

2011-01-01

In this paper, we introduce the category of Lie $n$-racks and generalize several results known on racks. In particular, we show that the tangent space of a Lie $n$-Rack at the neutral element has a Leibniz $n$-algebra structure. We also define a cohomology theory of $n$-racks..

Nuclear criticality safety: general. 6. Application of Fixed Neutron Absorbers in the New Hanford PFP Horizontal Rack Design

International Nuclear Information System (INIS)

Lan, J.S.; Miller, E.M.; Toffer, H.; Mo, B.S.

2001-01-01

The Hanford Plutonium Finishing Plant (PFP) is currently in a waste cleanup and plutonium stabilization mode. Plutonium-bearing materials are processed through thermal treatment, creating forms of oxides suitable for long-term storage. Stabilized materials at PFP are stored in a variety of cans such as the bag-less transfer cans (BTCs), which are ultimately contained in the U.S. Department of Energy (DOE) 3013 can; both cans are larger than previously used plutonium storage containers and hold more plutonium. To compensate for the increased plutonium loadings, added engineered safety features were considered in the storage facilities. The vaults in PFP, subdivided into concrete-walled cubicles, will contain both new and older cans. The DOE 3013 and BTC cans may be loaded with up to 4.4 kg of plutonium as a compound (mostly oxide). New racks that store cans horizontally are being constructed to hold both new and older containers. The loading objective is to accommodate 70 kg of plutonium per cubicle. Two design analysis approaches for the new racks were considered. The first approach incorporated neutron absorption provided by the structural materials of the rack and the cans in determining a safe configuration. A rack loading arrangement was determined as shown in Fig. 1 and specified in Table I. This approach provides compliance with criticality control requirements; however, added administrative controls were needed to accommodate a sufficient number of cans in specific locations to achieve 70 kg of plutonium per cubicle. The 4.4-kg plutonium container can be placed only in predetermined locations. The second approach evaluated the addition of a fixed neutron absorber plate along the back wall of the cubicle (Fig. 1). The location of the special plate facilitates installation of the racks and provides additional criticality safety margin beyond the first approach. Its presence permits loading of racks with up to 4.4-kg plutonium cans in any storage locations

Crossed modules of racks

OpenAIRE

Crans, Alissa S.; Wagemann, Friedrich

2014-01-01

We generalize the notion of a crossed module of groups to that of a crossed module of racks. We investigate the relation to categorified racks, namely strict 2-racks, and trunk-like objects in the category of racks, generalizing the relation between crossed modules of groups and strict 2-groups. Then we explore topological applications. We show that by applying the rack-space functor, a crossed module of racks gives rise to a covering. Our main result shows how the fundamental racks associate...

Seismic behavior of steel storage pallet racking systems

CERN Document Server

Castiglioni, Carlo Andrea

2016-01-01

This book presents the main outcomes of the first European research project on the seismic behavior of adjustable steel storage pallet racking systems. In particular, it describes a comprehensive and unique set of full-scale tests designed to assess such behavior. The tests performed include cyclic tests of full-scale rack components, namely beam-to-upright connections and column base connections; static and dynamic tests to assess the friction factor between pallets and rack beams; full-scale pushover and pseudodynamic tests of storage racks in down-aisle and cross-aisle directions; and full-scale dynamic tests on two-bay, three-level rack models. The implications of the findings of this extensive testing regime on the seismic behavior of racking systems are discussed in detail, highlighting e.g. the confirmation that under severe dynamic conditions “sliding” is the main factor influencing rack response. This work was conceived during the development of the SEISRACKS project. Its outcomes will contribute...

Lessons Learned from the Crew Health Care System (CHeCS) Rack 1 Environmental Control and Life Support (ECLS) Design

Science.gov (United States)

Williams, David E.

2006-01-01

This paper will provide an overview of the International Space Station (ISS) Environmental Control and Life Support (ECLS) design of the Crew Health Care System (CHeCS) Rack 1 and it will document some of the lessons that have been learned to date for the ECLS equipment in this rack.

Fabrication of the Spent Fuel Elements Rack on the ISFSF

International Nuclear Information System (INIS)

Slamet Wiranto; Sigit Purwanto; Safrul, H.

2004-01-01

The Interim Storage For Spent Fuel elements (ISFSF) was designed to be able to store the 33 spent fuel element racks with capacity of 1386 of normal spent fuel elements and 2 racks for 36 of defected ones. Until now, only 9 out of 33 racks of normal spent fuel elements and lout of 2 racks of defected fuel elements are available. Five of them have suffered from corrosion so that they are not fulfilled the requirements of the spent fuel elements storage anymore. Meanwhile, the spent fuel storage racks in the reactor are almost full. It means, the transfer of the spent fuel from reactor spent fuel storage to the ISFSF pool are compulsory needed. Therefore, it is necessary to provide the new ISFSF spent fuel storage rack with better material and fabrication method than the old one. In this design all materials consist of SS 316 L that are welded with the Argon TIG-welding. Right now there has been one new spent fuel storage rack fabricated with capacity of 42 normal spent fuel elements. (author)

High density aseismic spent fuel storage racks

International Nuclear Information System (INIS)

Louvat, J.P.

1985-05-01

After the reasons of the development of high density aseismic spent fuel racks by FRAMATOME and LEMER, a description is presented, as also the codes, standards and regulations used to design this FRAMATOME storage rack. Tests have been carried out concerning criticality, irradiation of Cadminox, corrosion of the cell, and the seismic behaviour

Seismic analysis of spent nuclear fuel storage racks

International Nuclear Information System (INIS)

Shah, S.J.; Biddle, J.R.; Bennett, S.M.; Schechter, C.B.; Harstead, G.A.; Marquet, F.

1996-01-01

In many nuclear power plants, existing storage racks are being replaced with high-density racks to accommodate the increasing inventory of spent fuel. In the hypothetical design considered here, the high-density arrangement of fuel assemblies, or consolidated fuel canisters, is accomplished through the use of borated stainless steel (BSS) plates acting as neutron absorbers. No structural benefit from the BSS is assumed. This paper describes the methods used to perform seismic analysis of high density spent fuel storage racks. The sensitivity of important parameters such as the effect of variation of coefficients of friction between the rack legs and the pool floor and fuel loading conditions (consolidated and unconsolidated) are also discussed in the paper. Results of this study are presented. The high-density fuel racks are simply supported by the pool floor with no structural connections to adjacent racks or to the pool walls or floor. Therefore, the racks are free standing and may slide and tip. Several time history, nonlinear, seismic analyses are required to account for variations in the coefficient of friction, rack loading configuration, and the type of the seismic event. This paper presents several of the mathematical models usually used. Friction cannot be precisely predicted, so a range of friction coefficients is assumed. The range assumed for the analysis is 0.2 to 0.8. A detailed model representing a single rack is used to evaluate the 3-D loading effects. This model is a controlling case for the stress analysis. A 2-D multi-rack model representing a row of racks between the spent fuel pool walls is used to evaluate the change in gaps between racks. The racks are normally analyzed for the fuel loading conditions of consolidated, full, empty, and half-loaded with fuel assemblies

Remote inspection of the IFSF spent fuel storage rack

International Nuclear Information System (INIS)

Uldrich, E.D.

1996-01-01

The Irradiated Fuel Storage Facility (IFSF) is a dry storage facility for spent nuclear fuels located at the Idaho Chemical Processing Plant; it was constructed in the 1970's specifically for the Fort Saint Vrain spent reactor fuels. Currently, it is being used for various spent fuels. It was not known if IFSF would met current DOE seismic criteria, so re-analysis was started, with the rack being analyzed first. The rack was inspected to determine the as-built condition. LazrLyne and VideoRuler were used in lieu of using a tape measure with the camera. It was concluded that when a visual inspection shows widely varying weld sizes, the engineer has to use all resources available to determine the most probable specified weld sizes

Test Rack Development for Extended Operation of Advanced Stirling Convertors at NASA Glenn Research Center

Science.gov (United States)

Dugala, Gina M.

2010-01-01

The U.S. Department of Energy, Lockheed Martin Space Systems Company, Sunpower Inc., and NASA Glenn Research Center (GRC) have been developing an Advanced Stirling Radioisotope Generator (ASRG) for use as a power system on space science missions. This generator will make use of free-piston Stirling convertors to achieve higher conversion efficiency than with currently available alternatives. One part of NASA GRC's support of ASRG development includes extended operation testing of Advanced Stirling Convertors (ASCs) developed by Sunpower Inc. and GRC. The ASC consists of a free-piston Stirling engine integrated with a linear alternator. NASA GRC has been building test facilities to support extended operation of the ASCs for several years. Operation of the convertors in the test facility provides convertor performance data over an extended period of time. One part of the test facility is the test rack, which provides a means for data collection, convertor control, and safe operation. Over the years, the test rack requirements have changed. The initial ASC test rack utilized an alternating-current (AC) bus for convertor control; the ASRG Engineering Unit (EU) test rack can operate with AC bus control or with an ASC Control Unit (ACU). A new test rack is being developed to support extended operation of the ASC-E2s with higher standards of documentation, component selection, and assembly practices. This paper discusses the differences among the ASC, ASRG EU, and ASC-E2 test racks.

Thermal Analysis Evaluation of Spent Fuel Storage Rack for Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Sangjin; Oh, Jinho; Kwak, Jinsung; Lee, Jongmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Spent fuel storage rack is to store spent fuel assemblies. The spent fuel storage rack is submerged in the designated pool for cooling. Due to the condition change of the pool water, the effect of thermal load on spent fuel storage rack must be analyzed and evaluated. In this paper, thermal stress analysis is performed and evaluated on a spent fuel storage rack. For thermal stress evaluation of the spent fuel storage rack, load combinations and allowable criteria in ASME Sec. III NB-3220 are applied. In cases of A-1 and B-1, the same temperature applied on the whole model, thermal stress doesn't occur because there is no constraint about the thermal expansion. The support frame is located on the pool bottom in free standing type and the racks are located in the support frame with enough space. Thermal expansion was considered and reflected in the design of spent fuel storage rack in advance. Thermal stress analysis is performed and evaluated on a spent fuel storage rack with consideration of pool water temperature variation. The thermal analysis including a linear heat transfer and the thermal stress analysis is performed for the racks and support frame and resulted stresses are within allowable criteria.

Effects of poison panel shrinkage and gaps on fuel storage rack reactivity

International Nuclear Information System (INIS)

Boyd, W.A.; Mueller, D.E.

1988-01-01

Fixed poison panels are used in spent fuel rack designs to increase enrichment limits and reduce cell spacing; therefore, assurances that the maximum rack reactivity will meet the design limit (0.95) throughout the lifetime of the racks depend on the continued effectiveness of the poison with time. Industry data have shown that poison panels will shrink under irradiated conditions. From recent data, however, poison panels have been found to have gaps spanning their width after relatively short operating periods. This paper presents results of studies showing the fuel rack reactivity changes associated with poison panel shrinkage and formation of gaps. The discovery of gaps in the fuel rack poison panels at an operating plant raises concerns regarding the effectiveness of the poison over the lifetime of the fuel racks. Studies performed to evaluate the effect of the poison panel shrinkage on reactivity show that reactivity changes from zero to several percent are possible depending on the initial panel size. Results of recent studies show that some gaps can be accommodated in the fuel rack poison panels at the fuel midplane without causing the fuel rack K eff limit to be exceeded. With worst-case assumptions concerning gap size and the number of panels affected, other actions will likely be required to show that the rack K eff design limit will not be exceeded

Storage rack for spent nuclear fuels

International Nuclear Information System (INIS)

Kiyama, Yoichi.

1996-01-01

A storage rack comprises a number of rack cells for containing spent nuclear fuels and two upper and lower rack support plates. Small through holes are formed to lateral walls of the rack cell each at a position slightly above the position of the upper rack support plate. Finger members each having a protrusion which fits the small through hole is secured at the upper surface of the upper rack support plate. The finger member is a metal leaf-spring erected at the periphery of a rack insertion hole of the rack support plate. Gaps for allowing thermal expansion of the rack cell are formed each between the edge of the rack cell insertion hole of the rack support plate and the rack cell, and between the lower edge of the small through hole on a side wall of the rack cell and the lower portion of the protrusion of the finger member. If the rack cell is inserted to a bottom, the protrusion of the finger member fits the small through hole on the side of the rack cell. With such a constitution, the rack cell is prevented from withdrawing in conjunction with removal of fuels. (I.N.)

Innovative Ballasted Flat Roof Solar PV Racking System

Energy Technology Data Exchange (ETDEWEB)

Peek, Richard T. [Cascade Engineering, Grand Rapids, MI (United States)

2014-12-15

The objective of this project was to reduce the cost of racking for PV solar on flat commercial rooftops. Cost reductions would come from both labor savings and material savings related to the installation process. The rack would need to accommodate the majority of modules available on the market. Cascade Engineering has a long history of converting traditional metal type applications over to plastic. Injection molding of plastics have numerous advantages including selection of resin for the application, placing the material exactly where it is needed, designing in features that will speed up the installation process, and weight reduction of the array. A plastic rack would need to meet the requirements of UL2703, Mounting systems, mounting devices, clamping/retention devices, and ground lugs for use with flat-plate photovoltaic modules and panels. Comparing original data to the end of project racking design, racking material costs were reduced 50% and labor costs reduced 64%. The racking product accommodates all 60 and 72 cell panels on the market, meets UL2703 requirements, contributes only 1.3 pounds per square foot of weight to the array, requires little ballast to secure the array, automatically grounds the module when the module is secured, stacks/nests well for shipping/fewer lifts to the roof, provides integrated wire routing, allows water to drain on the roof, and accommodates various seismic roof connections. Project goals were achieved as noted in the original funding application.

Design, Fabrication, and Testing of a Composite Rack Prototype in Support of the Deep Space Habitat Program

Science.gov (United States)

Smith, Russ; Hagen, Richard

2015-01-01

In support of the Deep Space Habitat project a number of composite rack prototypes were developed, designed, fabricated and tested to various extents ( with the International Standard Payload Rack configuration, or crew quarters, as a baseline). This paper focuses specifically on a composite rack prototype with a direct tie in to Space Station hardware. The outlined prototype is an all composite construction, excluding metallic fasteners, washers, and their associated inserts. The rack utilizes braided carbon composite tubing for the frame with the sidewalls, backwall and flooring sections utilizing aircraft grade composite honeycomb sandwich panels. Novel additively manufactured thermoplastic joints and tube inserts were also developed in support of this effort. Joint and tube insert screening tests were conducted at a preliminary level. The screening tests allowed for modification, and enhancement, of the fabrication and design approaches, which will be outlined. The initial joint tests did not include mechanical fasteners. Adhesives were utilized at the joint to composite tube interfaces, along with mechanical fasteners during final fabrication (thus creating a stronger joint than the adhesive only variant). In general the prototype was focused on a potential in-space assembly approach, or kit-of-parts construction concept, which would not necessarily require the inclusion of an adhesive in the joint regions. However, given the tie in to legacy Station hardware (and potential flight loads with imbedded hardware mass loadings), the rack was built as stiff and strong as possible. Preliminary torque down tests were also conducted to determine the feasibility of mounting the composite honeycomb panels to the composite tubing sections via the additively manufactured tube inserts. Additional fastener torque down tests were also conducted with inserts (helicoils) imbedded within the joints. Lessons learned are also included and discussed.

Rotating specimen rack repair

International Nuclear Information System (INIS)

Miller, G.E.; Rogers, P.J.; Nabor, W.G.; Bair, H.

1984-01-01

In 1980, an operator at the UCI TRIGA Reactor noticed difficulties with the rotation of the specimen rack. Investigations showed that the drive bearing in the rack had failed and allowed the bearings to enter the rack. After some time of operation in static mode it was decided that installation of a bearing substitute - a graphite sleeve - would be undertaken. Procedures were written and approved for removal of the rack, fabrication and installation of the sleeve, and re-installation of the rack. This paper describes these procedures in some detail. Detailed drawings of the necessary parts may be obtained from the authors

Criticality safety analysis of the NPP Krsko storage racks

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2002-01-01

NPP Krsko is going to increase the capacity of the spent fuel storage pool by replacement of the existing racks with high-density racks. This will be the second reracking campaign since 1983 when storage was increased from 180 to 828 storage locations. The pool capacity will increase from 828 to 1694 with partial reracking by the spring 2003. The installed capacity will be sufficient for the current design plant lifetime. Complete reracking of the spent fuel pool will additionally increase capacity to 2321 storage locations. The design, rack manufacturing and installation has been awarded to the Framatome ANP GmbH. Burnup credit methodology, which was approved by the Slovenian Nuclear Safety Administration in previous licensing of existing racks, will be again implemented in the licensing process with the recent methodology improvements. Specific steps of the criticality safety analysis and representative results are presented in the paper.(author)

Influence of Rack Design and Disease Prevalence on Detection of Rodent Pathogens in Exhaust Debris Samples from Individually Ventilated Caging Systems.

Science.gov (United States)

Bauer, Beth A; Besch-Williford, Cynthia; Livingston, Robert S; Crim, Marcus J; Riley, Lela K; Myles, Matthew H

2016-11-01

Sampling of bedding debris within the exhaust systems of ventilated racks may be a mechanism for detecting murine pathogens in colony animals. This study examined the effectiveness of detecting pathogens by PCR analysis of exhaust debris samples collected from ventilated racks of 2 different rack designs, one with unfiltered air flow from within the cage to the air-exhaust pathway, and the other had a filter between the cage and the air-exhaust pathway. For 12 wk, racks were populated with either 1 or 5 cages of mice (3 mice per cage) infected with one of the following pathogens: mouse norovirus (MNV), mouse parvovirus (MPV), mouse hepatitis virus (MHV), Helicobacter spp., Pasteurella pneumotropica, pinworms, Entamoeba muris, Tritrichomonas muris, and fur mites. Pathogen shedding by infected mice was monitored throughout the study. In the filter-containing rack, PCR testing of exhaust plenums yielded negative results for all pathogens at all time points of the study. In the rack with open air flow, pathogens detected by PCR analysis of exhaust debris included MHV, Helicobacter spp., P. pneumotropica, pinworms, enteric protozoa, and fur mites; these pathogens were detected in racks housing either 1 or 5 cages of infected mice. Neither MPV nor MNV was detected in exhaust debris, even though prolonged viral shedding was confirmed. These results demonstrate that testing rack exhaust debris from racks with unfiltered air flow detected MHV, enteric bacteria and parasites, and fur mites. However, this method failed to reliably detect MNV or MPV infection of colony animals.

Foundations of topological racks and quandles

OpenAIRE

Mohamed Moutuou, El-Kaioum; Elhamdadi, Mohamed

2016-01-01

We give a foundational account on topological racks and quandles. Specifically, we define the notions of ideals, kernels, units, and inner automorphism group in the context of topological racks. Further, we investigate topological rack modules and principal rack bundles. Central extensions of topological racks are then introduced providing a first step towards a general continuous cohomology theory for topological racks and quandles

Chin Shan analyses show advantages of whole pool multi-rack approach

International Nuclear Information System (INIS)

Singh, K.P.; Soler, A.I.

1991-01-01

Nuclear fuel storage racks are essentially thin-walled, cellular structures of prismatic cross-section. Although the details of design vary from one supplier to another, certain key physical attributes are common to all designs. For example, all racks feature square cells of sufficient opening size and height to enable insertion and withdrawal of the fuel assembly. The array of cells is positioned in a vertical orientation and is supported off the pool slab surface by four or more support legs. The spent fuel pool is filled with the individual fuel racks. The plenum created by the support legs is essential for proper cooling of the fuel assemblies stored in the rack, which relies on natural convective cooling to extract the heat emitted by the spent fuel. However, it has the insalutary effect of making it kinematically less stable. Regulatory authorities require careful and comprehensive analysis of the response of the racks under the seismic motions postulated for the pool slab. Results from whole pool multi-rack (WPMR) analyses at the Chin Shan and Oyster Creek nuclear plants point up the potential inadequacies of single rack 3D analyses, and show just how important it is to carry out WPMR simulations, despite their abstruseness and high cost. (author)

Experimental motion behavior of submerged fuel racks

International Nuclear Information System (INIS)

Ellingson, F.J.; Wachter, W.; Moscardini, R.L.

1989-01-01

The design of submerged nuclear storage racks for light water reactor nuclear fuel has undergone a change from fixed position to a free-standing arrangement. Seismic analysis of the motion of the free-standing racks requires three-dimensional computer modeling that uses past studies of hydrodynamic mass and hydraulic coupling for rigid flat plates. This paper describes the results of experiments that show a reduced value for hydrodynamic mass and coupling forces when flexible elements are involved. To support this work, experiments were run with two full-scale welded box sections submerged in a water tank. The preliminary results indicate reduction in hydrodynamic mass due to box wall flexibility, a lack of impacting of box wall to box wall over the entire frequency range, and large hydrodynamic coupling forces under all test conditions. It is hypothesized that the coupling forces are sufficiently strong to prevent rotational motion of one rack when surrounded by adjacent racks

Refurbishment of the rotating rack of the OSU TRIGA MKII reactor

International Nuclear Information System (INIS)

Higginbotham, J.F.; Dodd, B.; Pratt, D.S.; Anderson, T.V.

1992-01-01

Many TRIGA reactors have experienced operational difficulties with the rotating racks used for sample irradiation. Generally the rack gradually becomes more difficult to rotate until it finally seizes. The recommended action at that point is replacement of the entire facility at a significant cost. The purpose of this paper is to describe the symptoms leading to rack failure and to present the results of a refurbishment procedure that does not involve the use of solvents which create mixed chemical and radioactive hazardous waste. The primary reason for rack failure is the buildup of sludge produced through irradiation of lubrication oil. The refurbishment procedure involves using a commercially available degreasing solution which can be pumped into and out of the rack with the objective of removing this sludge. The solution used is sold under the trade name 'Simple Green'. No radioactive material was detected on smear or air samples taken of the work area during the reifurbishment activities and the rack rotates freely in both direction even after eighteen months of operation. The only disadvantage to performing this procedure has been the need to maintain a very aggressive contamination control program when unloading samples from the rack. A very fine particulate material attaches to the outside of tubes used to encapsulate samples. This material can produce contamination levels of 10,000 dpm/100 cm 2 in the worst cases but will typically produce local hot spots on the order of 1000 dpm. (author)

Nuclear reactor spent fuel storage rack

International Nuclear Information System (INIS)

Machado, O.J.; Flynn, W.M.; Flanders, H.E. Jr.; Booker, L.W.

1989-01-01

A fuel rack is described for use in storing nuclear fuel assemblies in a nuclear fuel storage pool having a floor on which an upwardly projecting stud is mounted; the fuel rack comprising: a base structure at the lower end of the fuel rack including base-plate means having flow openings therein, the base-plate means supporting a first network of interlaced beams which form a multiplicity of polygonal openings; a second network of interlaced beams forming polygonal openings positioned in spaced vertical alignment with corresponding polygonal openings in the first network of beams; a plurality of cells, each cell having sides bounded by inner and outer surfaces and being of a size and configuration designed to hold therein a fuel assembly, each cell positioned in a corresponding pair of the aligned polygonal openings, each cell being open at both ends with a guiding funnel at the upper end, and the cells being positioned over the flow openings in the base-plate to permit flow of coolant through the cells; spaced, outwardly directed, projections on the outer surfaces of the sides of the cells near the tops and bottoms of the sides thereof, each cell being sized to be received within a corresponding of the pair of aligned polygonal openings in which the cells are respectively positioned; and means fixedly securing the projections to the beams in the first and second networks of beams thereby to provide a substantially rigid fuel rack of modular design

Improved method to demonstrate the structural integrity of high density fuel storage racks

International Nuclear Information System (INIS)

Hinderks, M.; Ungoreit, H.; Kremer, G.

2001-01-01

Reracking of existing fuel pools to the maximum extent is desirable from an economical point of view. This goal can be achieved by minimizing the gaps between the spent fuel storage racks. Since the rack design is aimed at enabling consolidated fuel rod storage, additional requirements arise with respect to the design and the structural analysis. The loads resulting from seismic events are decisive for the structural analysis and require a specially detailed and in-depth analysis for high seismic loads. The verification of structural integrity and functionality is performed in two phases. In the first phase the motional behavior of single racks, rows of racks and, where required, of all racks in the pool is simulated by excitation with displacement time histories under consideration of the fluid-structure interaction (FSI). The displacements from these simulations are evaluated, while the loads are utilized as input data for the structural analysis of the racks and the pool floor. The structural analyses for the racks comprise substantially stress analyses for base material and welds as well as stability analyses for the support channels and the rack outside walls. The analyses are performed in accordance with the specified codes and standards

Seismic and structural analysis of high density/consolidated spent fuel storage racks

International Nuclear Information System (INIS)

Shah, S.J.; Biddle, J.R.; Bennett, S.M.; Schechter, C.B.; Harstead, G.A.; Kopecky, B.

1995-01-01

In many nuclear power plants, existing storage racks are being replaced with high-density racks to accommodate the increasing inventory of spent fuel. In the hypothetical design considered here, the high-density arrangement of fuel assemblies, or consolidated fuel canisters, is accomplished through the use of borated stainless steel (BSS) plates acting as neutron absorbers. The high-density fuel racks are simply supported by the pool floor with no structural connections to adjacent racks or to the pool walls or floor. Therefore, the racks are free standing and may slide and tip. Several time history, nonlinear, seismic analyses are required to account for variations in the coefficient of friction, rack loading configuration, ad the type of the seismic event. This paper presents several of the mathematical models usually used. The models include features to allow sliding and tipping of the racks and to represent the hydrodynamic coupling which can occur between fuel assemblies and rack cells, between adjacent racks, and between the racks and the reinforced concrete walls. A detailed model representing a single rack is used to evaluate the 3-D loading effects. This model is a controlling case for the stress analysis. A 2-D multi-rack model representing a row of racks between the spent fuel pool walls is used to evaluate the change in gaps between racks. The racks are analyzed for the fuel loading conditions of consolidated, full, empty, and half-loaded with fuel assemblies

A new electronic circuit for NIM rack power supply

International Nuclear Information System (INIS)

Toledo, Fabio de; Domienikan, Claudio; Zahn, Guilherme S.

2013-01-01

A new and useful electronic circuit designed to substitute the old power supply of IPEN model PM 1212 Nuclear Instrument Modules (NIM) racks is presented. Originally, these NIM racks were projected by IPEN workshop at 1974 to be used in nuclear research laboratories. The PM1212 provided mounting space and power sources for up to 12 standard nuclear electronic modules and power supply regulated DC voltages of ±24V (2A), ±12V (4A) and unregulated AC 117V (0.5A). Currently, several of these NIM racks are not in use because the electronic components of the original design have become obsolete and are no longer manufactured. The new electronic circuit provides the same original voltages adjusted in the single circuit and, additionally, ±6V. The new power supply was designed and constructed at IPEN-CNEN/SP by employing modern national components and expertise. (author)

A new electronic circuit for NIM rack power supply

Energy Technology Data Exchange (ETDEWEB)

Toledo, Fabio de; Domienikan, Claudio; Zahn, Guilherme S., E-mail: fatoledo@ipen.br, E-mail: clanikan@ipen.br, E-mail: gzahn@ipen.br [Intituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), Sao Paulo, SP (Brazil)

2013-07-01

A new and useful electronic circuit designed to substitute the old power supply of IPEN model PM 1212 Nuclear Instrument Modules (NIM) racks is presented. Originally, these NIM racks were projected by IPEN workshop at 1974 to be used in nuclear research laboratories. The PM1212 provided mounting space and power sources for up to 12 standard nuclear electronic modules and power supply regulated DC voltages of ±24V (2A), ±12V (4A) and unregulated AC 117V (0.5A). Currently, several of these NIM racks are not in use because the electronic components of the original design have become obsolete and are no longer manufactured. The new electronic circuit provides the same original voltages adjusted in the single circuit and, additionally, ±6V. The new power supply was designed and constructed at IPEN-CNEN/SP by employing modern national components and expertise. (author)

Development of a cosmic rack for characterization of RPCs

International Nuclear Information System (INIS)

Sehgal, S.T.; Pant, L.M.

2011-01-01

A newly designed cosmic rack has been commissioned this year in the RPC Lab., in NPD-BARC. The rack consists of nine shelves each providing a clear area of 160 cm x 225 cm. Each of the shelf is separated by a distance of 30 cm, providing sufficient distance for fast electronics to respond and also providing an easy access for loading and removing the RPCs. The total height of the cosmic rack is 2.8 metres. A typical fully integrated RPCs covers an approximate area of 2 m 2 and weighs about 60-70 kg. The rack has been basically designed, keeping in mind the varied requirements as regards to the RPCs based current and futuristic programmes which are listed as follows: 1. Testing of large area trapezoidal bakelite gas-gaps and RPCs for the CMS experiment, keeping in mind the production rate of five RPCs per month. 2. The proposed muon tomography programme with 1m x 1m glass RPCs and 3. Characterization of glass RPCs (1m x 2m) for the INO experiment in near future

Laboratory glassware rack for seismic safety

Science.gov (United States)

Cohen, M. M. (Inventor)

1985-01-01

A rack for laboratory bottles and jars for chemicals and medicines has been designed to provide the maximum strength and security to the glassware in the event of a significant earthquake. The rack preferably is rectangular and may be made of a variety of chemically resistant materials including polypropylene, polycarbonate, and stainless steel. It comprises a first plurality of parallel vertical walls, and a second plurality of parallel vertical walls, perpendicular to the first. These intersecting vertical walls comprise a self-supporting structure without a bottom which sits on four legs. The top surface of the rack is formed by the top edges of all the vertical walls, which are not parallel but are skewed in three dimensions. These top edges form a grid matrix having a number of intersections of the vertical walls which define a number of rectangular compartments having varying widths and lengths and varying heights.

Analysis of ICPP fuel storage rack inner tie and corner tie substructures

Energy Technology Data Exchange (ETDEWEB)

Nitzel, M.E.; Rahl, R.G.

1996-01-01

Finite element models were developed and analyses performed for the tie plate, inner tie block assembly, and corner tie block assembly of a 25 port fuel rack assembly designed for installation in Pool 1 of Building 666 at the Idaho Chemical Processing Plant. These models were specifically developed to investigate the adequacy of certain welds joining components of the fuel storage rack assembly. The work scope for the task was limited to an investigation of the stress levels in the subject subassemblies when subjected to seismic loads. Structural acceptance criteria used for the elastic calculations performed were as found in the overall rack design report as issued by the rack`s designer, Holtec International. Structural acceptance criteria used for the plastic calculations performed as part of this effort were as defined in Subsection NF and Appendix F of the ASME Boiler & Pressure Vessel Code. The results of the analyses will also apply to the 30 port fuel storage rack design that is also scheduled for installation in Pool 1 of ICPP 666. The results obtained from the analyses performed for this task indicate that the welds joining the inner tie block and corner tie block to the surrounding rack structure meet the acceptance criteria. Further, the structural members (plates and blocks) were also found to be within the allowable stress limits established by the acceptance criteria. The separate analysis performed on the inner tie plate confirmed the structural adequacy for both the inner tie plate, corner tie plate, and tie block bolts. The analysis results verified that the inner tie and corner tie block should be capable of transferring the expected seismic load without structural failure.

Accident Analysis of High Density Storage Rack for Fresh Fuel Assemblies

International Nuclear Information System (INIS)

Jang, K. J.; Lee, M. J.; Jin, H. U.; Park, J. H.; Shin, S. Y.

2009-01-01

Recently KONES and KNF have developed the so called suspension-type High Density Storage Rack (HDSR) for fresh fuel assemblies. The USNRC OT position paper specifies that the design of the rack must ensure the functional integrity of the fuel racks under all credible fuel assembly drop events. In this context the functional integrity means the criticality safety. That is to say, the drop events must not bring any danger to the criticality safety of HDSR. This paper shows the results of the analysis carried out to demonstrate the regulatory compliance of the proposed racks under postulated accidental drop events

Nonlinear analyses of spent-fuel racks for consolidated fuel loading

International Nuclear Information System (INIS)

Kabir, A.F.; Godha, P.C.; Malik, L.E.; Bolourchi, S.

1987-01-01

Storage racks for spent-fuel assemblies in nuclear power plants are designed to withstand various combinations of loads generated by gravity, seismic, thermal, and accidental fuel drops. Due to the need for storing increased amounts of spent fuel in the existing fuel pools, many nuclear power utilities are evaluating existing fuel racks to safely carry the additional loads. The current study presents the seismic analyses of existing fuel racks of Northeast Utility Company's Millstone Unit Number 1 (BWR Mark I) nuclear plant to accommodate a 2:1 fuel consolidation. This objective requires rigorous nonlinear analyses to establish the full available capacities of the racks and thereby avoid expensive modifications or minimize any needed upgrades

ATLAS DAQ/HLT rack DCS

International Nuclear Information System (INIS)

Ermoline, Yuri; Burckhart, Helfried; Francis, David; Wickens, Frederick J.

2007-01-01

The ATLAS Detector Control System (DCS) group provides a set of standard tools, used by subsystems to implement their local control systems. The ATLAS Data Acquisition and High Level Trigger (DAQ/HLT) rack DCS provides monitoring of the environmental parameters (air temperatures, humidity, etc.). The DAQ/HLT racks are located in the underground counting room (20 racks) and in the surface building (100 racks). The rack DCS is based on standard ATLAS tools and integrated into overall operation of the experiment. The implementation is based on the commercial control package and additional components, developed by CERN Joint Controls Project Framework. The prototype implementation and measurements are presented

Design of a new wet storage rack for spent fuels from IEA-R1 reactor

International Nuclear Information System (INIS)

Rodrigues, Antonio C.I.; Madi Filho, Tufic; Siqueira, Paulo T.D.; Ricci Filho, Walter

2015-01-01

The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks of the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating conditions, the storage will have capacity for about six years. Since the estimated useful life of the IEA-R1 is about another 20 years, it will be necessary to increase the storage capacity of spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. After an extensive literature review of material options given for this type of application we got to Boral® manufactured by 3M due to numerous advantages. This paper presents studies on the analysis of criticality using the computer code MCNP 5, demonstrating the possibility of doubling the storage capacity of current racks to attend the demand of the IEA-R1 reactor while attending the safety requirements the International Atomic Energy Agency. (author)

Design of a new wet storage rack for spent fuels from IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, Antonio C.I.; Madi Filho, Tufic; Siqueira, Paulo T.D.; Ricci Filho, Walter, E-mail: acirodri@ipen.br, E-mail: tmfilho@ipen.br, E-mail: ptsiquei@ipen.br, E-mail: wricci@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks of the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating conditions, the storage will have capacity for about six years. Since the estimated useful life of the IEA-R1 is about another 20 years, it will be necessary to increase the storage capacity of spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. After an extensive literature review of material options given for this type of application we got to Boral® manufactured by 3M due to numerous advantages. This paper presents studies on the analysis of criticality using the computer code MCNP 5, demonstrating the possibility of doubling the storage capacity of current racks to attend the demand of the IEA-R1 reactor while attending the safety requirements the International Atomic Energy Agency. (author)

Insert Concepts for the Material Science Research Rack (MSRR-1) of the Material Science Research Facility (MSRF) on the International Space Station (ISS)

Science.gov (United States)

Crouch, Myscha; Carswell, Bill; Farmer, Jeff; Rose, Fred; Tidwell, Paul

2000-01-01

The Material Science Research Rack I (MSRR-1) of the Material Science Research Facility (MSRF) contains an Experiment Module (EM) being developed collaboratively by NASA and the European Space Agency (ESA). This NASA/ESA EM will accommodate several different removable and replaceable Module Inserts (MIs) which are installed on orbit NASA's planned inserts include the Quench Module Insert (QMI) and the Diffusion Module Insert (DMI). The QMI is a high-gradient Bridgman-type vacuum furnace with quench capabilities used for experiments on directional solidification of metal alloys. The DMI is a vacuum Bridgman-Stockbarger-type furnace for experiments on Fickian and Soret diffusion in liquids. This paper discusses specific design features and performance capabilities of each insert. The paper also presents current prototype QMI hardware analysis and testing activities and selected results.

Link invariants from finite Coxeter racks

OpenAIRE

Nelson, Sam; Wieghard, Ryan

2008-01-01

We study Coxeter racks over $\\mathbb{Z}_n$ and the knot and link invariants they define. We exploit the module structure of these racks to enhance the rack counting invariants and give examples showing that these enhanced invariants are stronger than the unenhanced rack counting invariants.

Fuel assembly storing rack

International Nuclear Information System (INIS)

Kajimura, Haruhiko; Nakamura, Masaaki.

1997-01-01

In a nuclear fuel storage rack comprising a plurality of square-shaped rack cells arranged vertically in a lattice-like configuration, the square rack cell comprises a stainless steel having a boron content of 0.75% or less and a boron equivalent with respect to calculated thermal neutron absorbing performance of 1.0 or more, and a distance between each of the gap of the square rack cells in adjacent with each other satisfies a predetermined condition. One example of the content is that B is from 0.05 to 0.75%, Gd is from 0.05 to 1.50%, C is 0.03% or less, Si is 1.0% or less, Mn is from 0.1 to 2.0%, P is 0.03% or less, S is 0.01% or less, Cr is from 18 to 26%, Ni is from 7 to 22% and Al is 0.1% or less. The distance between the rack cells can be reduced by using a material improved with thermal neutron absorbing performance by determining the boron equivalent to a predetermined value or more and with less B-content and good fabricability. In addition, the size of the rack cell itself can be reduced. This can greatly reduce the nuclear fuel storage area. (I.S.)

21 CFR 886.1750 - Skiascopic rack.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Skiascopic rack. 886.1750 Section 886.1750 Food... DEVICES OPHTHALMIC DEVICES Diagnostic Devices § 886.1750 Skiascopic rack. (a) Identification. A skiascopic rack is a device that is a rack and a set of attached ophthalmic lenses of various dioptric strengths...

Effects of suspension of air-conditioning on airtight-type racks.

Science.gov (United States)

Kanzaki, M; Fujieda, M; Furukawa, T

2001-10-01

Although isolation racks are superior to open-type racks in terms of securing breeding conditions for laboratory animals, the contingency-proofing capability of the former has yet to be determined. Therefore, from the view of risk management, we studied the environmental change in isolation racks by forcibly suspending ventilation and air-conditioning and confirming the maximal time length for complete recovery to the original condition after restarting their operations. The isolation racks were placed in a room that was equipped with an independent air-conditioning system. When the inside condition of the racks reached 22-24 degrees C and 59-64% of relative humidity, the air-conditioning and ventilation were forcibly suspended and the subsequent temperature, relative humidity, ammonium and CO2 concentrations in the racks were measured over time. We found that after suspending the air-conditioning and ventilation, it took 40-60 min for temperature, and about 10 min for relative humidity to exceed the maximum values (temperature and relative humidity) referred to in the Showa 58 Nenban Guideline Jikken Doubutsu Shisetsu no Kenchiku oyobi Setsubi (Guidelines of buildings and facilities for experimental animals in Japan; Year 1983 edition). After 17 hr 25 min of the suspension of air-conditioning and ventilation, two rats were found dead. Then, the air-conditioning and ventilation were restarted. It took about 2 hr for temperature, and 50 min for relative humidity to regain the guideline values. The ammonium concentration stayed within the guideline value with a maximum concentration of 2 ppm in the experimental period, whereas the CO2 concentration was found to exceed 9% at the time of animal death.

First Materials Science Research Rack Capabilities and Design Features

Science.gov (United States)

Schaefer, D.; King, R.; Cobb, S.; Whitaker, Ann F. (Technical Monitor)

2001-01-01

The first Materials Science Research Rack (MSRR-1) will accommodate dual Experiment Modules (EM's) and provide simultaneous on-orbit processing operations capability. The first international Materials Science Experiment Module for the MSRR-1 is an international cooperative research activity between NASA's Marshall Space Flight Center (MSFC) and the European Space Agency's (ESA) European Space Research and Technology Center. (ESTEC). This International Standard Payload Rack (ISPR) will contain the Materials Science Laboratory (MSL) developed by ESA as an Experiment Module. The MSL Experiment Module will accommodate several on-orbit exchangeable experiment-specific Module Inserts. Module Inserts currently planned are a Quench Module Insert, Low Gradient Furnace, Solidification with Quench Furnace, and Diffusion Module Insert. The second Experiment Module for the MSRR-1 configuration is a commercial device supplied by MSFC's Space Products Department (SPD). It includes capabilities for vapor transport processes and liquid metal sintering. This Experiment Module will be replaced on-orbit with other NASA Materials Science EMs.

Arbitrary vehicle steering characteristics with changing ratio rack and pinion transmission

Directory of Open Access Journals (Sweden)

András G Bendefy

2015-12-01

Full Text Available In order to achieve arbitrary steering characteristics at vehicles, a steering mechanism was developed, in which changing ratio rack and pinion connections have been applied. In contrary to a regular steering mechanism where only a single rack is used, two racks were applied in order to make arbitrary characteristics possible. The turning wheel’s required motion functions had to be defined first, thereafter could we determine the changing ratio rack and pinion geometry which produces this motion. First, a simplified two-dimensional mockup was created in order to study the difficulties and possibilities of a real construction. Later, a fully functional assembly was designed and manufactured to make further experiments possible.

Spent fuel storage rack

International Nuclear Information System (INIS)

Kurokawa, Hideaki; Kumagaya, Naomi; Oda, Masashi; Matsuda, Masami; Maruyama, Hiromi; Yamanaka, Tsuneyasu.

1997-01-01

The structure of a spent fuel storage rack is determined by the material, thickness, size of square cylindrical tubes (the gap between spent fuel assemblies and the square cylindrical tubes) and pitch of the arrangement (the gap between each of the square cylindrical tubes). In the present invention, the thickness and the pitch of the arrangement of the square tubes are optimized while evaluating subcriticality. Namely, when the sum of the thickness of the water gap at the outer side (the pitch of arrangement of the cylindrical tubes) and the thickness of the cylindrical tubes is made constant, the storage rack is formed by determining the thickness of the cylindrical tubes which is smaller than the optimum value among the combination of the thickness of the water gap at the outer side and that of the cylindrical tube under the effective multiplication factor to be performed. Then, the weight of the rack can be reduced, and the burden of the load on the bottom of the pool can be reduced. Further, the amount of the constitutional materials of the rack itself can be reduced thereby capable of reducing the cost for the materials of the rack. (T.M.)

Seismic testing of the base-isolated PWR spent-fuel storage rack

International Nuclear Information System (INIS)

Fujita, Katsuhisa; Tanaka, Mamoru; Nakamura, Masaaki; Tsujikura, Yonezo.

1990-01-01

The present paper aims to verify the seismic safety of the base-isolated spent-fuel storage rack. A series of seismic tests has been conducted using a three-dimensional shaking table. A sliding-type base-isolation system was employed for the prototype rack considering environmental conditions in an actual plant. A non linear seismic response analysis was also performed, and it is verified that the prototype of a base-isolated spent-fuel storage rack has a sufficient seismic safety margin for design seismic conditions from the viewpoint of seismic response. (author)

Rack Protection Monitor - A Simple System

International Nuclear Information System (INIS)

Orr, S.

1997-12-01

The Rack Protection Monitor is a simple, fail-safe device to monitor smoke, temperature and ventilation sensors. It accepts inputs from redundant sensors and has a hardwired algorithm to prevent nuisance power trips due to random sensor failures. When a sensor is triggered the Rack Protection Monitor latches and annunicates the alarm. If another sensor is triggered, the Rack Protection Monitor locally shuts down the power to the relay rack and sends alarm to central control

Hydrodynamics induced vibration to trash-racks

International Nuclear Information System (INIS)

Sadrnejad, A.

2002-01-01

In conventional power plants trash-racks are provided at the intakes to protect the turbines. In pumped storage plants, the draft tube or tailrace must also have trash-racks to protect the units while pumping. Because the loads believed to cause many failures of trash-racks are dynamic in nature, it is important to understand the dynamic characteristics of trash-racks structures in general and a single rack in particular. The classical added-mass solution structure-fluid dynamic interaction is known as an approximate solution procedure. An accurate added-mass approach mixed with implementation in finite element framework is proposed. In this proposal, experimental conclusions, supported by theory, led to presentation of more accurate results in vibration of trash-racks. This numerical solution as a powerful method to solve such a complex problem can be employed to carry out dynamic characteristics of these structures while vibrating in water

Seismic response of free standing fuel rack construction to 3-D floor motion

International Nuclear Information System (INIS)

Soler, A.I.; Singh, K.

1983-01-01

Seismic analysis of free standing submerged racks is complicated by the presence of water and structural non-linearities such as fuel assembly cell impact and floor interface friction. A direct time integration technique has been proposed to analyze this class of structures. Application of the time integration technique on a fourteen degree of freedom lumped mass model of the rack reveals some heretofore unpublished quirks in the structure's behavior. The method of analysis is utilized to compare the seismic response of some representative rack designs. Results show wide differences in the structural response, depending on the fabrication details of racks

Storage racks for spent fuels

International Nuclear Information System (INIS)

Inoue, Tatsumi.

1983-01-01

Purpose: To provide a storage rack which is light in weight, excellent in constructing performance, earthquake proof and allowable for thermal displacement. Constitution: The rack frame is constituted by disposing mounting seat plates at the legs of profiled-steel post members on a rack-mounting plate as a mounting seat by way of mounting liner plates and then weld-joining each of upper, medium and lower beam members and truss members of the profiled-steel posts by the use of connecting plates. Guide plates are laid transversely and joined onto each of the thus formed upper, medium and lower stage frames. Since apertures for mounting guide tubes are opened to each of the guide plates at a predetermined pitch, the storage rack unit is constituted by mounting guide tubes to the apertures. Then, the storage rack is mounted by means of slide keys to the mounting plates where slight amount of sliding or thermal displacement can be absorbed. (Horiuchi, T.)

40 CFR 63.422 - Standards: Loading racks.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 9 2010-07-01 2010-07-01 false Standards: Loading racks. 63.422....422 Standards: Loading racks. (a) Each owner or operator of loading racks at a bulk gasoline terminal... facility” used in § 60.502 of this chapter means the loading racks that load gasoline cargo tanks at the...

10 CFR 36.35 - Source rack protection.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Source rack protection. 36.35 Section 36.35 Energy NUCLEAR... Requirements for Irradiators § 36.35 Source rack protection. If the product to be irradiated moves on a product conveyor system, the source rack and the mechanism that moves the rack must be protected by a barrier or...

Seismic analysis of freestanding fuel racks

International Nuclear Information System (INIS)

Gilmore, C.B.

1982-01-01

This paper presents a nonlinear transient dynamic time-history analysis of freestanding spent fuel storage racks subjected to seismic excitation. This type of storage rack is structurally unrestrained and submerged in water in the spent fuel pool of a nuclear power complex, holds (spent) fuel assemblies which have been removed from the reactor core. Nonlinearities in the fuel rack system include impact between the fuel assembly and surrounding cell due to clearances between them, friction due to sliding between the fuel rack support structure and spent fuel pool floor, and the lift-off of the fuel rack support structure from the spent fuel pool floor. The analysis of the fuel rack system includes impacting due to gap closures, energy losses due to impacting bodies, Coulomb damping between sliding surfaces, and hydrodynamic mass effects. Acceleration time history excitation development is discussed. Modeling considerations, such as the initial status of nonlinear elements, number of mode shapes to include in the analysis, modal damping, and integration time-step size are presented. The response of the fuel rack subjected to two-dimensional seismic excitation is analyzed by the modal superposition method, which has resulted in significant computer cost savings when compared to that of direct integration

21 CFR 882.4215 - Clip rack.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Clip rack. 882.4215 Section 882.4215 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL DEVICES NEUROLOGICAL DEVICES Neurological Surgical Devices § 882.4215 Clip rack. (a) Identification. A clip rack is a...

High density fuel storage rack

International Nuclear Information System (INIS)

Zezza, L.J.

1980-01-01

High storage density for spent nuclear fuel assemblies in a pool achieved by positioning fuel storage cells of high thermal neutron absorption materials in an upright configuration in a rack. The rack holds the cells at required pitch. Each cell carries an internal fuel assembly support, and most cells are vertically movable in the rack so that they rest on the pool bottom. Pool water circulation through the cells and around the fuel assemblies is permitted by circulation openings at the top and bottom of the cells above and below the fuel assemblies

Water-Cooled Data Center Packs More Power Per Rack | Poster

Science.gov (United States)

By Frank Blanchard and Ken Michaels, Staff Writers Behind each tall, black computer rack in the data center at the Advanced Technology Research Facility (ATRF) is something both strangely familiar and oddly out of place: It looks like a radiator. The back door of each cabinet is gridded with the coils of the Liebert cooling system, which circulates chilled water to remove heat

Dynamic response of piping system on rack structure with gaps and frictions

International Nuclear Information System (INIS)

Kobayashi, Hiroe; Yoshida, Misutoyo; Ochi, Yoshio

1989-01-01

In the seismic design of a piping system on a rack structure, the interaction between the piping system and the rack structure must be evaluated under the condition that the rack structure is not stiff and heavy enough compared with the piping system. Moreover, there are local nonlinearities due to the gap and friction between the piping system and the rack structure. This paper presents the influence of the interaction and the local nonlinearities upon the seismic response by numerical study and a vibration test using a shaking table. In the numerical study, the piping system and the rack structure were represented by the three degrees of freedom mass-spring model taking a vibration mode of the piping system into account. The nonlinearities due to gap and friction were defined as a function of motion and treated as the pseudo force vector (additional applied force) in an equation of motion. From the results of the numerical study and the vibration test, it was clarified that seismic response of both the rack structure and the piping system is reduced by gap and friction. Moreover, the piping system and rack structure can be represented by the three degrees of freedom mass spring model. And the local nonlinearities can be treated by the pseudo force in an equation of motion. (orig.)

Re-racking the spent fuel pit in nuclear power plant Krsko

International Nuclear Information System (INIS)

Volaric, B.; Krajnc, B.

2003-01-01

Krsko NPP was designed to temporary store a limited number of spent fuel assemblies (SFA). They were planned to be either removed for reprocessing or permanently stored. By the design the plant would run out of capacity for temporary storing of SFAs in 2003. This means that the plant could not operate further without additional changes since valid regulations require the Spent Fuel Pit (SFP) free storage capacity for the whole emergency core unloading (ECU). The purpose of the SFP Reracking Project is to assure a safe storage of all SFAs in the existing SFP during the plant lifetime. Design solutions and related analysis did not only consider the quantity of spent fuel for the plant lifetime, i.e. up to the year 2023, but also a possibility of the SFP extension for eventually extended plant lifetime of 20 years. According to the project, racks were designed to provide up to 1694 cells for storage of FAs in Phase I which is sufficient for normal NPP operation up to its lifetime, i.e. the year 2023. The extension of temporary storage capacity of SFAs in the SFP was made by a combination of existing and new high-density racks. Three modules from the existing 12 were eliminated. Thus leaving 621 cells. There are nine new racks added with up to 1073 supercompacted cells installed in the empty part of the pool. The spacing between new cells is smaller than the one between existing cells because of special plates, made of borated stainless steel. The design of the racks fulfils all the applicable requirements to ensure sub-criticality of all stored SFAs, enriched up to 5 % U 235 with peak pellet burnup above 40 GWD/MTU. Besides static and dynamic seismic loading of both, the racks and the fuel handling building, sufficient cooling of FAs is provided as well as accident conditions precluded. Greater cooling capacity is achieved by installing the third heat exchanger, connected in parallel to existing two exchangers. The design and manufacturing of the new heat exchanger

Design concepts and advanced telerobotics development for facilities in the back end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Feldman, M.J.

1987-01-01

In the Fuel Recycle Division at the Oak Ridge National Laboratory, a comprehensive remote systems development program has existed for the past seven years. The new remote technology under development is expected to significantly improve remote operations by extending the range of tasks accomplished by remote means and increasing the efficiency of remote work undertaken. Five areas of the development effort are primary contributors to the goal of higher operating efficiency for major facilities for the back end of the nuclear fuel cycle. These areas are the single-cell concept, the low-flow ventilation concept, television viewing, equipment-mounting racks, and force-reflecting manipulation. These somewhat innovative directions are products of a design process where the technical scenario to be accomplished, the remote equipment to accomplish the scenario, and the facility design to house the equipment, are considered in an iterative design process to optimize performance, maximize long-term costs effectiveness, and minimize initial capital outlay. 14 refs., 3 figs

Design concepts and advanced telerobotics development for facilities in the back end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Feldman, M.J.

1987-01-01

In the Fuel Recycle Division at the Oak Ridge National Laboratory (ORNL), a comprehensive remote systems development program has existed for the past seven years. The new remote technology under development is expected to significantly improve remote operations by extending the range of tasks accomplished by remote means and increasing the efficiency of remote work undertaken. Five areas of the development effort are primary contributors to the goal of higher operating efficiency for major facilities for the back end of the nuclear fuel cycle. These areas are (1) the single-cell concept, (2) the low-flow ventilation concept, (3) television viewing, (4) equipment-mounting racks, and (5) force-reflecting manipulation. These somewhat innovative directions are products of a design process where the technical scenario to be accomplished, the remote equipment to accomplish the scenario, and the facility design to house the equipment, are considered in an iterative design process to optimize performance, maximize long-term costs effectiveness, and minimize initial capital outlay. (author)

Working safely with electronics racks

CERN Document Server

Simon Baird, HSE Unit Head

2016-01-01

Think of CERN and you’ll probably think of particle accelerators and detectors. These are the tools of the trade in particle physics, but behind them are the racks of electronics that include power supplies, control systems and data acquisition networks.   Inside an electronics rack: danger could be lurking if the rack is not powered off. In routine operation, these are no more harmful than the home entertainment system in your living room. But unscrew the cover and it’s a different matter. Even after following appropriate training, and with formal authorisation from your group leader or equivalent to carry out electrical work or any work in the vicinity of electrical hazards, and even with extensive experience of carrying out such operations, it’s important to incorporate safe working practices into your routine. At CERN, before the racks of electronics reach their operational configurations for the accelerators and detectors, they play a vital role in test set-ups ...

Modular nuclear fuel assembly rack

International Nuclear Information System (INIS)

Davis, C.J.

1982-01-01

A modular nuclear fuel assembly rack constructed of an array of identical cells, each cell constructed of a plurality of identical flanged plates. The unique assembly of the plates into a rigid rack provides a cellular compartment for nuclear fuel assemblies and a cavity between the cells for accepting neutron absorbing materials thus allowing a closely spaced array. The modular rack size can be easily adapted to conform with available storage space. U-shaped flanges at the edges of the plates are nested together at the intersection of four cells in the array. A bar is placed at the intersection to lock the cells together

Fuel consumption impacts of auto roof racks

International Nuclear Information System (INIS)

Chen, Yuche; Meier, Alan

2016-01-01

The after-market roof rack is one of the most common components attached to a vehicle for carrying over-sized items, such as bicycles and skis. It is important to understand these racks’ fuel consumption impacts on both individual vehicles and the national fleet because they are widely used. We estimate the national fuel consumption impacts of roof racks using a bottom-up approach. Our model incorporates real-world data and vehicle stock information to enable assessing fuel consumption impacts for several categories of vehicles, rack configurations, and usage conditions. In addition, the model draws on two new data-gathering techniques, on-line forums and crowd-sourcing. The results show that nationwide, roof racks are responsible for 0.8‰ of light duty vehicle fuel consumption in 2015, corresponding to 100 million gallons of gasoline per year. Sensitivity analyses show that results are most sensitive to the fraction of vehicles with installed roof racks but carrying no equipment. The aerodynamic efficiency of typical roof racks can be greatly improved and reduce individual vehicle fuel consumption; however, government policies to minimize extensive driving with empty racks—if successful—could save more fuel nationally. - Highlights: •First estimate of national energy impacts of auto roof racks—about 1‰. •A bottom-up approach reveals details of the fuel consumption penalty caused by racks. •Two novel data collection techniques, on-line forums and crowd-sourcing, improve estimate. •Technical and behavioral policies could significantly cut fuel penalties from roof racks.

Solution structure of the human signaling protein RACK1

Directory of Open Access Journals (Sweden)

Papa Priscila F

2010-06-01

Full Text Available Abstract Background The adaptor protein RACK1 (receptor of activated kinase 1 was originally identified as an anchoring protein for protein kinase C. RACK1 is a 36 kDa protein, and is composed of seven WD repeats which mediate its protein-protein interactions. RACK1 is ubiquitously expressed and has been implicated in diverse cellular processes involving: protein translation regulation, neuropathological processes, cellular stress, and tissue development. Results In this study we performed a biophysical analysis of human RACK1 with the aim of obtaining low resolution structural information. Small angle X-ray scattering (SAXS experiments demonstrated that human RACK1 is globular and monomeric in solution and its low resolution structure is strikingly similar to that of an homology model previously calculated by us and to the crystallographic structure of RACK1 isoform A from Arabidopsis thaliana. Both sedimentation velocity and sedimentation equilibrium analytical ultracentrifugation techniques showed that RACK1 is predominantly a monomer of around 37 kDa in solution, but also presents small amounts of oligomeric species. Moreover, hydrodynamic data suggested that RACK1 has a slightly asymmetric shape. The interaction of RACK1 and Ki-1/57 was tested by sedimentation equilibrium. The results suggested that the association between RACK1 and Ki-1/57(122-413 follows a stoichiometry of 1:1. The binding constant (KB observed for RACK1-Ki-1/57(122-413 interaction was of around (1.5 ± 0.2 × 106 M-1 and resulted in a dissociation constant (KD of (0.7 ± 0.1 × 10-6 M. Moreover, the fluorescence data also suggests that the interaction may occur in a cooperative fashion. Conclusion Our SAXS and analytical ultracentrifugation experiments indicated that RACK1 is predominantly a monomer in solution. RACK1 and Ki-1/57(122-413 interact strongly under the tested conditions.

Compact fuel storage rack for fuel pools

International Nuclear Information System (INIS)

Parras, F.; Louvat, J.P.

1986-01-01

ETS LEMER and FRAMATOME propose a new compact storage rack. This rack permits a considerable increase of the storage capacity of cooling pools. A short description of the structure and the components is presented, to propose racks that are: . Inalterable, . Compact, . Insensitive to earthquakes. Installation in pools already in operation is simplified by their light structure and the bearing device [fr

From racks to pointed Hopf algebras

OpenAIRE

Andruskiewitsch, Nicolás; Graña, Matı́as

2003-01-01

A fundamental step in the classification of finite-dimensional complex pointed Hopf algebras is the determination of all finite-dimensional Nichols algebras of braided vector spaces arising from groups. The most important class of braided vector spaces arising from groups is the class of braided vector spaces (CX, c^q), where C is the field of complex numbers, X is a rack and q is a 2-cocycle on X with values in C^*. Racks and cohomology of racks appeared also in the work of topologists. This...

Spent fuel storage rack for atomic power plant

International Nuclear Information System (INIS)

Kodama, Tatemitsu.

1981-01-01

Purpose: To flexibly cope with the changes in the size and shape of spent fuel storage containers by placing a number of independently-constructed rack cells in a rack frame in such a manner that the guide support members of the storage rack, mounted on each rack cell may be replaced. Constitution: Independently-constructed rack cells are inserted from above into a rack frame rigidly installed on the bottom of a water pool. Each cell is produced by welding, has a handling head mounted at the top, and guide support members made of three replaceable guide tubes are mounted with bolts. If the size and the shape of the containers are altered, this configuration can easily cope with the new container shape by merely having the guide tubes replaced, without adversely affecting other cells and without necessitating draining of the water in the pool. (Yoshino, Y.)

RACK1, A Multifaceted Scaffolding Protein: Structure and Function

LENUS (Irish Health Repository)

Adams, David R

2011-10-06

Abstract The Receptor for Activated C Kinase 1 (RACK1) is a member of the tryptophan-aspartate repeat (WD-repeat) family of proteins and shares significant homology to the β subunit of G-proteins (Gβ). RACK1 adopts a seven-bladed β-propeller structure which facilitates protein binding. RACK1 has a significant role to play in shuttling proteins around the cell, anchoring proteins at particular locations and in stabilising protein activity. It interacts with the ribosomal machinery, with several cell surface receptors and with proteins in the nucleus. As a result, RACK1 is a key mediator of various pathways and contributes to numerous aspects of cellular function. Here, we discuss RACK1 gene and structure and its role in specific signaling pathways, and address how posttranslational modifications facilitate subcellular location and translocation of RACK1. This review condenses several recent studies suggesting a role for RACK1 in physiological processes such as development, cell migration, central nervous system (CN) function and circadian rhythm as well as reviewing the role of RACK1 in disease.

Server rack for improved data center management

Science.gov (United States)

Bermudez Rodriguez, Sergio A.; Hamann, Hendrik F.; Wehle, Hans-Dieter

2018-01-09

Methods and systems for data center management include collecting sensor data from one or more sensors in a rack; determining a location and identifying information for each asset in the rack using a set of asset tags associated with respective assets; communicating the sensor and asset location to a communication module; receiving an instruction from the communication module; and executing the received instruction to change a property of the rack.

Framatome offers new high density Cadminox racks

International Nuclear Information System (INIS)

Anon.

1985-01-01

Framatome have developed a new material called Cadminox for use in high density spent fuel storage racks. It is claimed that Cadminox will remain stable stable in pond storage when racks submerged in boronated water are irradiated by the spent fuel they contain. A brief description of the storage module is given, including the aseismic bearing device which minimises loads on pond walls, racks and fuel assemblies. (UK)

40 CFR 63.650 - Gasoline loading rack provisions.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 10 2010-07-01 2010-07-01 false Gasoline loading rack provisions. 63... loading rack provisions. (a) Except as provided in paragraphs (b) through (c) of this section, each owner or operator of a Group 1 gasoline loading rack classified under Standard Industrial Classification...

Rack assembly for mounting solar modules

Science.gov (United States)

Plaisted, Joshua Reed; West, Brian

2010-12-28

A rack assembly is provided for mounting solar modules over an underlying body. The rack assembly may include a plurality of rail structures that are arrangeable over the underlying body to form an overall perimeter for the rack assembly. One or more retention structures may be provided with the plurality of rail structures, where each retention structure is configured to support one or more solar modules at a given height above the underlying body. At least some of the plurality of rail structures are adapted to enable individual rail structures o be sealed over the underlying body so as to constrain air flow underneath the solar modules. Additionally, at least one of (i) one or more of the rail structures, or (ii) the one or more retention structures are adjustable so as to adapt the rack assembly to accommodate solar modules of varying forms or dimensions.

SCORHE: a novel and practical approach to video monitoring of laboratory mice housed in vivarium cage racks.

Science.gov (United States)

Salem, Ghadi H; Dennis, John U; Krynitsky, Jonathan; Garmendia-Cedillos, Marcial; Swaroop, Kanchan; Malley, James D; Pajevic, Sinisa; Abuhatzira, Liron; Bustin, Michael; Gillet, Jean-Pierre; Gottesman, Michael M; Mitchell, James B; Pohida, Thomas J

2015-03-01

The System for Continuous Observation of Rodents in Home-cage Environment (SCORHE) was developed to demonstrate the viability of compact and scalable designs for quantifying activity levels and behavior patterns for mice housed within a commercial ventilated cage rack. The SCORHE in-rack design provides day- and night-time monitoring with the consistency and convenience of the home-cage environment. The dual-video camera custom hardware design makes efficient use of space, does not require home-cage modification, and is animal-facility user-friendly. Given the system's low cost and suitability for use in existing vivariums without modification to the animal husbandry procedures or housing setup, SCORHE opens up the potential for the wider use of automated video monitoring in animal facilities. SCORHE's potential uses include day-to-day health monitoring, as well as advanced behavioral screening and ethology experiments, ranging from the assessment of the short- and long-term effects of experimental cancer treatments to the evaluation of mouse models. When used for phenotyping and animal model studies, SCORHE aims to eliminate the concerns often associated with many mouse-monitoring methods, such as circadian rhythm disruption, acclimation periods, lack of night-time measurements, and short monitoring periods. Custom software integrates two video streams to extract several mouse activity and behavior measures. Studies comparing the activity levels of ABCB5 knockout and HMGN1 overexpresser mice with their respective C57BL parental strains demonstrate SCORHE's efficacy in characterizing the activity profiles for singly- and doubly-housed mice. Another study was conducted to demonstrate the ability of SCORHE to detect a change in activity resulting from administering a sedative.

Preparation and planning for the replacement of the Oregon State University TRIGA reactor rotary specimen rack assembly

International Nuclear Information System (INIS)

Anderson, T.V.; Dodd, B.; Johnson, A.G.; Carpenter, W.T.

1984-01-01

Recently there have been a number of indications that the rotating rack may be approaching the end of its useful life. In order to benefit from the experience of other reactors who have removed and replaced their rotating racks, General Atomic (GA) was contacted and previous TRIGA Conference proceedings were scanned. It was determined that a number of facilities, had experienced difficulties with their lazy susans and eventually had to replace them. However, most of the written descriptions of this project were not sufficiently detailed to be of great use. The purpose of this paper is to identify some of the more important questions related to the replacement of our rotating rack assembly and OSU's currently proposed solutions, with a view towards soliciting ideas from other members of the TRIGA reactor community

RACK(1) to the future - a historical perspective

LENUS (Irish Health Repository)

Ron, Dorit

2013-08-01

This perspective summarises the first and long overdue RACK1 meeting held at the University of Limerick, Ireland, May 2013, in which RACK1’s role in the immune system, the heart and the brain were discussed and its contribution to disease states such as cancer, cardiac hypertrophy and addiction were described. RACK1 is a scaffolding protein and a member of the WD repeat family of proteins. These proteins have a unique architectural assembly that facilitates protein anchoring and the stabilisation of protein activity. A large body of evidence is accumulating which is helping to define the versatile role of RACK1 in assembling and dismantling complex signaling pathways from the cell membrane to the nucleus in health and disease. In this commentary, we first provide a historical perspective on RACK1. We also address many of the pertinent and topical questions about this protein such as its role in transcription, epigenetics and translation, its cytoskeletal contribution and the merits of targeting RACK1 in disease.

RACK1-mediated translation control promotes liver fibrogenesis

Energy Technology Data Exchange (ETDEWEB)

Liu, Min; Peng, Peike; Wang, Jiajun [Department of Biochemistry and Molecular Biology, School of Basic Medical Sciences, Fudan University, Shanghai 200032 (China); Wang, Lan; Duan, Fangfang [Institute of Biomedical Science, Fudan University, Shanghai 200032 (China); Jia, Dongwei, E-mail: jiadongwei@fudan.edu.cn [Department of Biochemistry and Molecular Biology, School of Basic Medical Sciences, Fudan University, Shanghai 200032 (China); Ruan, Yuanyuan, E-mail: yuanyuanruan@fudan.edu.cn [Department of Biochemistry and Molecular Biology, School of Basic Medical Sciences, Fudan University, Shanghai 200032 (China); Gu, Jianxin [Department of Biochemistry and Molecular Biology, School of Basic Medical Sciences, Fudan University, Shanghai 200032 (China); Institute of Biomedical Science, Fudan University, Shanghai 200032 (China)

2015-07-31

Activation of quiescent hepatic stellate cells (HSCs) is the central event of liver fibrosis. The translational machinery is an optimized molecular network that affects cellular homoeostasis and diseases, whereas the role of protein translation in HSCs activation and liver fibrosis is little defined. Our previous report suggests that up-regulation of receptor for activated C-kinase 1(RACK1) in HSCs is critical for liver fibrogenesis. In this study, we found that RACK1 promoted macrophage conditioned medium (MCM)-induced assembly of eIF4F and phosphorylation of eIF4E in primary HSCs. RACK1 enhanced the translation and expression of pro-fibrogenic factors collagen 1α1, snail and cyclin E1 induced by MCM. Administration of PP242 or knock-down of eIF4E suppressed RACK1-stimulated collagen 1α1 production, proliferation and migration in primary HSCs. In addition, depletion of eIF4E attenuated thioacetamide (TAA)-induced liver fibrosis in vivo. Our data suggest that RACK1-mediated stimulation of cap-dependent translation plays crucial roles in HSCs activation and liver fibrogenesis, and targeting translation initiation could be a promising strategy for the treatment of liver fibrosis. - Highlights: • RACK1 induces the assembly of eIF4F and phosphorylation of eIF4E in primary HSCs. • RACK1 stimulates the translation of collagen 1α1, snail and cyclin E1 in HSCs. • RACK1 promotes HSCs activation via cap-mediated translation. • Depletion of eIF4E suppresses liver fibrogenesis in vivo.

RACK1-mediated translation control promotes liver fibrogenesis

International Nuclear Information System (INIS)

Liu, Min; Peng, Peike; Wang, Jiajun; Wang, Lan; Duan, Fangfang; Jia, Dongwei; Ruan, Yuanyuan; Gu, Jianxin

2015-01-01

Activation of quiescent hepatic stellate cells (HSCs) is the central event of liver fibrosis. The translational machinery is an optimized molecular network that affects cellular homoeostasis and diseases, whereas the role of protein translation in HSCs activation and liver fibrosis is little defined. Our previous report suggests that up-regulation of receptor for activated C-kinase 1(RACK1) in HSCs is critical for liver fibrogenesis. In this study, we found that RACK1 promoted macrophage conditioned medium (MCM)-induced assembly of eIF4F and phosphorylation of eIF4E in primary HSCs. RACK1 enhanced the translation and expression of pro-fibrogenic factors collagen 1α1, snail and cyclin E1 induced by MCM. Administration of PP242 or knock-down of eIF4E suppressed RACK1-stimulated collagen 1α1 production, proliferation and migration in primary HSCs. In addition, depletion of eIF4E attenuated thioacetamide (TAA)-induced liver fibrosis in vivo. Our data suggest that RACK1-mediated stimulation of cap-dependent translation plays crucial roles in HSCs activation and liver fibrogenesis, and targeting translation initiation could be a promising strategy for the treatment of liver fibrosis. - Highlights: • RACK1 induces the assembly of eIF4F and phosphorylation of eIF4E in primary HSCs. • RACK1 stimulates the translation of collagen 1α1, snail and cyclin E1 in HSCs. • RACK1 promotes HSCs activation via cap-mediated translation. • Depletion of eIF4E suppresses liver fibrogenesis in vivo

IFBA credit in the Shearon Harris fuel racks with Vantage 5 fuel

International Nuclear Information System (INIS)

Boyd, W.A.; Schmidt, R.F.; Erwin, R.D.

1989-01-01

At the Shearon Harris nuclear plant, fuel management strategies are being considered which will result in feed fuel enrichments approaching 5.0 w/o U-235. These types of enrichments require a new criticality analysis to raise the existing fuel rack enrichment limit. It is receiving Westinghouse Vantage 5 fuel with integral fuel burnable absorber (IFBA) rods providing the depletable neutron absorber. An analysis was performed on the fuel racks which demonstrates that fuel enriched up to 5.0 w/o U-235 can be stored by taking credit for the IFBA rods present in the high enriched fuel assemblies. This is done by calculating the maximum Vantage 5 fuel assembly reactivity that can be placed in the fuel racks and meet the criticality K-eff limit. A methodology is also developed which conservatively calculates the minimum number of IFBA rods needed per assembly to meet the fuel rack storage limits. This eliminates the need for core designers to determine assembly K-inf terms for every different enrichment/IFBA combination

Microgravity Disturbance Predictions in the Combustion Integrated Rack

Science.gov (United States)

Just, M.; Grodsinsky, Carlos M.

2002-01-01

This paper will focus on the approach used to characterize microgravity disturbances in the Combustion Integrated Rack (CIR), currently scheduled for launch to the International Space Station (ISS) in 2005. Microgravity experiments contained within the CIR are extremely sensitive to vibratory and transient disturbances originating on-board and off-board the rack. Therefore, several techniques are implemented to isolate the critical science locations from external vibration. A combined testing and analysis approach is utilized to predict the resulting microgravity levels at the critical science location. The major topics to be addressed are: 1) CIR Vibration Isolation Approaches, 2) Disturbance Sources and Characterization, 3) Microgravity Predictive Modeling, 4) Science Microgravity Requirements, 6) Microgravity Control, and 7) On-Orbit Disturbance Measurement. The CIR is using the Passive Rack Isolation System (PaRIS) to isolate the rack from offboard rack disturbances. By utilizing this system, CIR is connected to the U.S. Lab module structure by either 13 or 14 umbilical lines and 8 spring / damper isolators. Some on-board CIR disturbers are locally isolated by grommets or wire ropes. CIR's environmental and science on board support equipment such as air circulation fans, pumps, water flow, air flow, solenoid valves, and computer hard drives cause disturbances within the rack. These disturbers along with the rack structure must be characterized to predict whether the on-orbit vibration levels during experimentation exceed the specified science microgravity vibration level requirements. Both vibratory and transient disturbance conditions are addressed. Disturbance levels/analytical inputs are obtained for each individual disturber in a "free floating" condition in the Glenn Research Center (GRC) Microgravity Emissions Lab (MEL). Flight spare hardware is tested on an Orbital Replacement Unit (ORU) basis. Based on test and analysis, maximum disturbance level

Retort Racks for Polymeric Trays in 1400 Style Spray Retorts

National Research Council Canada - National Science Library

Bruins, Henderikus B

2003-01-01

The objective of this project was to design a retort rack that would maximize the retort capacity of a 1400 style spray retort and to select a material that would withstand the harsh retort spray environment...

Universal Test Facility

Science.gov (United States)

Laughery, Mike

A universal test facility (UTF) for Space Station Freedom is developed. In this context, universal means that the experimental rack design must be: automated, highly marketable, and able to perform diverse microgravity experiments according to NASA space station requirements. In order to fulfill these broad objectives, the facility's customers, and their respective requirements, are first defined. From these definitions, specific design goals and the scope of the first phase of this project are determined. An examination is first made into what types of research are most likely to make the UTF marketable. Based on our findings, the experiments for which the UTF would most likely be used included: protein crystal growth, hydroponics food growth, gas combustion, gallium arsenide crystal growth, microorganism development, and cell encapsulation. Therefore, the UTF is designed to fulfill all of the major requirements for the experiments listed above. The versatility of the design is achieved by taking advantage of the many overlapping requirements presented by these experiments.

Evaluation of food storage racks available on the Polish market in the hygienic context

Science.gov (United States)

Grzesińska, Wiesława; Tomaszewska, Marzena; Bilska, Beata; Trafiałek, Joanna; Dziadek, Michał

Providing safe food products to the consumer depends on the material and technology used and adherence to hygienic practices, throughout the production process. The degree of microbial contamination of a surface is an important indicator of equipment cleanliness and effectiveness of cleaning and disinfection. Used material, construction solutions and quality of the applied devices also have an effect on hygienic status. The objective of the present study was to evaluate the influence of the design and construction material of selected food storage racks, available on the Polish market, on their hygienic status. The study was based on determination of the capability of microbial growth on the surface of the racks and the effectiveness of their cleaning. Microbiological cleanliness on the surface of the racks was monitored by the contact plates which are able to estimate the total number of icroorganisms. Examination of effectiveness of cleaning was conducted by the use of ATP bioluminescence method. This experiment has proven a significant influence of adopted construction solutions on the hygienic status of the examined racks. Presence of antibacterial layer and a choice of the appropriate construction material characterized by a low surface roughness impedes the microbial growth and increases the effectiveness of cleaning. Design solutions have significant impact on the hygienic status of shelves. Selection of a suitable material for the construction of racks can greatly reduce the possibility of the development of microorganism, despite the low efficiency of the cleaning. The application of antimicrobial coatings inhibits microbial growth.

Storage rack for fuel cell receiving shrouds

International Nuclear Information System (INIS)

Mollon, L.

1978-01-01

Disclosed is a rack for receiving a multiplicity of vertical tubular shrouds or tubes for storing spent nuclear fuel cells. The rack comprises a plurality of horizontally reticulated frames interconnected by tension rods and spacing tubes surrounding the rods

O-GlcNAcylation of RACK1 promotes hepatocellular carcinogenesis.

Science.gov (United States)

Duan, Fangfang; Wu, Hao; Jia, Dongwei; Wu, Weicheng; Ren, Shifang; Wang, Lan; Song, Shushu; Guo, Xinying; Liu, Fenglin; Ruan, Yuanyuan; Gu, Jianxin

2018-06-01

Aberrant oncogenic mRNA translation and protein O-linked β-N-acetylglucosaminylation (O-GlcNAcylation) are general features during tumorigenesis. Nevertheless, whether and how these two pathways are interlinked remain unknown. Our previous study indicated that ribosomal receptor for activated C-kinase 1 (RACK1) promoted chemoresistance and growth in hepatocellular carcinoma (HCC). The aim of this study is to examine the role of RACK1 O-GlcNAcylation in oncogene translation and HCC carcinogenesis. The site(s) of RACK1 for O-GlcNAcylation was mapped by mass spectrometry analysis. HCC cell lines were employed to examine the effects of RACK1 O-GlcNAcylation on the translation of oncogenic factors and behaviors of tumor cells in vitro. Transgenic knock-in mice were used to detect the role of RACK1 O-GlcNAcylation in modulating HCC tumorigenesis in vivo. The correlation of RACK1 O-GlcNAcylation with tumor progression and relapse were analyzed in clinical HCC samples. We found that ribosomal RACK1 was highly modified by O-GlcNAc at Ser122. O-GlcNAcylation of RACK1 enhanced its protein stability, ribosome binding and interaction with PKCβII (PRKCB), leading to increased eukaryotic translation initiation factor 4E phosphorylation and translation of potent oncogenes in HCC cells. Genetic ablation of RACK1 O-GlcNAcylation at Ser122 dramatically suppressed tumorigenesis, angiogenesis, and metastasis in vitro and in diethylnitrosamine (DEN)-induced HCC mouse model. Increased RACK1 O-GlcNAcylation was also observed in HCC patient samples and correlated with tumor development and recurrence after chemotherapy. These findings demonstrate that RACK1 acts as key mediator linking O-GlcNAc metabolism to cap-dependent translation during HCC tumorigenesis. Targeting RACK1 O-GlcNAcylation provides promising options for HCC treatment. O-GlcNAcylation of ribosomal receptor for activated C-kinase 1 at the amino acid serine122 promotes its stability, ribosome localization and interaction

30 CFR 57.7050 - Tool and drill steel racks.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Tool and drill steel racks. 57.7050 Section 57... Rotary Jet Piercing Drilling-Surface and Underground § 57.7050 Tool and drill steel racks. Receptacles or racks shall be provided for drill steel and tools stored or carried on drills. ...

Knot invariants derived from quandles and racks

OpenAIRE

Kamada, Seiichi

2002-01-01

The homology and cohomology of quandles and racks are used in knot theory: given a finite quandle and a cocycle, we can construct a knot invariant. This is a quick introductory survey to the invariants of knots derived from quandles and racks.

An embedded acceleration measurement capability for EXPRESS Rack Payloads

International Nuclear Information System (INIS)

Foster, William M. II; Sutliff, Thomas J.

2000-01-01

The International Space Station provides a microgravity environment allowing long duration studies to be made on phenomena masked by the presence of earth's gravitational effects. Studies are also enabled in areas requiring a substantial decrease in steady-state and vibratory acceleration environments. In anticipation microgravity science experiments being targeted for EXPRESS (EXpedite the PRocessing of Experiments to Space Station) Racks, a capability has been provided to simplify and conduct a consistent measurement of the microgravity environment for payloads. The Space Acceleration Measurement System-II (SAMS-II) project has collaborated with the EXPRESS Rack Project to embed an electronics unit within the four EXPRESS Racks equipped with Active Rack Isolation Systems (ARIS). Each SAMS-II unit provides a standardized means for payload acceleration measurements to be acquired. Access to this capability is via front panel connections similar to those of power, data and water cooling provided for EXPRESS payloads. Furthermore, an International Subrack Interface Standard (ISIS) drawer configuration has been developed to provide measurement capability to the non-ARIS equipped EXPRESS Racks, as well as to other ISIS-configured racks, for non-isolated experimental measurement needs. This paper describes the SAMS-II acceleration measurement capabilities provided to ISS users and, in particular, to the EXPRESS Rack community

30 CFR 56.7050 - Tool and drill steel racks.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Tool and drill steel racks. 56.7050 Section 56.7050 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL... Jet Piercing Drilling § 56.7050 Tool and drill steel racks. Receptacles or racks shall be provided for...

AP Alternatives Modular Solar Racking

OpenAIRE

ECT Team, Purdue

2015-01-01

Solar panels have been used to generate and supply electricity in various applications such as residential and commercial buildings. Therefore, a need for a quicker approach to installation as well as the need to reduce workmanship to speed up the process is needed. Solar racks are developed through the use of automated equipment to “preassemble the racking hardware, pre-install the solar modules, and drive helical anchors into the ground rapidly”. So instead of installing one panel at a time...

Decreased Blastocyst Production in Mice Exposed to Increased Rack Noise

Science.gov (United States)

Zamora, Bernadette M; Jiang, Meisheng; Wang, Ying; Chai, Minghua; Lawson, P Timothy; Lawson, Gregory W

2009-01-01

This study was conducted to investigate the possible effect of rack type on the blastocyst yield of mouse embryo donors. The first phase of the study consisted of housing some mice (group A) in a ventilated rack and others (group B) in a static rack in the same room for 3 d, followed by euthanasia for blastocyst collection and corticosterone assay. Parametric tests were used to compare groups. The number of blastocysts per donor was lower in group A (5.0 ± 1.4 blastocysts) than group B (13.1 ± 3.7 blastocysts). Mean noise was higher in the ventilated rack (80.4 dBC) than in the static rack (69.2 dBC). Serum corticosterone concentrations did not differ between groups. For the second phase of the study, a third group of mice (group C) was housed in a static rack without a ventilated rack in the same room. The noise level for group C was even lower (45.18 ± 2.91 dBC), and the blastocyst count per donor (16.4 ± 2.4) was higher than that of group B. The mean noise levels of empty ventilated and static racks differed significantly between groups for 10 different sound frequencies. Plotting mean blastocyst production against mean rack noise revealed a negative linear relationship with good strength of correlation. These results support the earlier observation that decreased blastocyst count occurs following housing of bred C57BL/6 donor mice in ventilated cages. PMID:19807968

Materials Science Research Rack Onboard the International Space Station

Science.gov (United States)

Reagan, Shawn; Frazier, Natalie; Lehman, John

2016-01-01

The Materials Science Research Rack (MSRR) is a research facility developed under a cooperative research agreement between NASA and ESA for materials science investigations on the International Space Station (ISS). MSRR was launched on STS-128 in August 2009 and currently resides in the U.S. Destiny Laboratory Module. Since that time, MSRR has logged more than 1400 hours of operating time. The MSRR accommodates advanced investigations in the microgravity environment on the ISS for basic materials science research in areas such as solidification of metals and alloys. The purpose is to advance the scientific understanding of materials processing as affected by microgravity and to gain insight into the physical behavior of materials processing. MSRR allows for the study of a variety of materials, including metals, ceramics, semiconductor crystals, and glasses. Materials science research benefits from the microgravity environment of space, where the researcher can better isolate chemical and thermal properties of materials from the effects of gravity. With this knowledge, reliable predictions can be made about the conditions required on Earth to achieve improved materials. MSRR is a highly automated facility with a modular design capable of supporting multiple types of investigations. The NASA-provided Rack Support Subsystem provides services (power, thermal control, vacuum access, and command and data handling) to the ESA-developed Materials Science Laboratory (MSL) that accommodates interchangeable Furnace Inserts (FI). Two ESA-developed FIs are presently available on the ISS: the Low Gradient Furnace (LGF) and the Solidification and Quenching Furnace (SQF). Sample Cartridge Assemblies (SCAs), each containing one or more material samples, are installed in the FI by the crew and can be processed at temperatures up to 1400?C. ESA continues to develop samples with 14 planned for launch and processing in the near future. Additionally NASA has begun developing SCAs to

Nonlinear dynamics of a rack-pinion-rack device powered by the Casimir force.

Science.gov (United States)

Miri, MirFaez; Nekouie, Vahid; Golestanian, Ramin

2010-01-01

Using the lateral Casimir force-a manifestation of the quantum fluctuations of the electromagnetic field between objects with corrugated surfaces-as the main force transduction mechanism, a nanomechanical device with rich dynamical behaviors is proposed. The device is made of two parallel racks that are moving in the same direction and a pinion in the middle that couples with both racks via the noncontact lateral Casimir force. The built-in frustration in the device causes it to be very sensitive and react dramatically to minute changes in the geometrical parameters and initial conditions of the system. The noncontact nature of the proposed device could help with the ubiquitous wear problem in nanoscale mechanical systems.

An Evaluation of Criticality Margin by an Application of Parallelogram Lattice Arrangement in the Nuclear Fuel Storage Rack

International Nuclear Information System (INIS)

Kim, Song Hyun; Kim, Hong Chul; Shin, Chang Ho; Kim, Jong Kyung; Kim, Kyo Youn

2010-01-01

The criticality evaluation in the nuclear fuel storage rack is essentially required for the prevention of the criticality accident. The square lattice structure of the storage rack is commonly used because it has a simple structure for the storage of the numerous fuel assemblies as well as the good mechanical strength. For the design of the fuel storage rack, the boron plate is commonly used for the criticality reduction. In this study, an arrangement method with the parallelogram lattice structure is proposed for the reduction of the boron concentration or the rack pitch. The criticality margins by the application of the parallelogram lattice were evaluated with MCNP5 code. From the result, the reduction of the boron concentrated in the borated-Al plate was evaluated

Furniture Rack Corrosion Coupon Surveillance - 2012 Update

International Nuclear Information System (INIS)

Mickalonis, J. I.; Murphy, T. R.; Berry, C. J.

2012-01-01

Under the L Basin corrosion surveillance program furniture rack coupons immersed for 14 years (FY2009 coupons) and 16 years (FY2011 coupons) were analyzed and the results trended with coupons exposed for shorter times. In addition, a section harvested from an actual furniture rack that was immersed for 14 years was analyzed for pitting in the weld and heat-affected-zone (HAZ) regions. The L Basin operations maintained very good water quality over the entire immersion period for these samples. These results for FY2009 and FY2011 coupons showed that the average pit depths for the 6061 and 6063 base metal are 1 and 2 mils, respectively, while those for the weld and HAZ are 3 and 4 mils, respectively. The results for the weld and HAZ regions are similar to coupons removed during the period of FY2003 to FY2007. These similarities indicate that the pit development occurred quickly followed by slow kinetics of increase in pit depth. For the actual furniture rack sample average pits of 5 and 2 mils were measured for the HAZ and weld, respectively. These results demonstrate that pitting corrosion of the aluminum furniture racks used to support the spent fuel occurs in waters of good quality. The corrosion kinetics or pit depth growth rate is much less that 1 mil/year, and would not impact long-term use of this material system for fuel storage racks in L Basin if good water quality is maintained

Design and analysis of free-standing spent fuel racks in nuclear power plants

International Nuclear Information System (INIS)

Ashar, H.; DeGrassi, G.

1989-01-01

With the prohibition on reprocessing of spent fuel in the late 1970's the pools which were supposed to be short term storage became quasi-permanent storage spaces for spent fuel. Recognizing a need to provide permanent storage facilities for such nuclear wastes, the US Congress enacted a law cited as the Nuclear Waste Policy Act of 1982. The Act, in essence, required the Department of Energy to find ways for long term storage of high level waste. However, it also is required the owners of nuclear power plants to provide for interim storage of their spent fuel. The permanent government owned repositories are not scheduled to be operational until the year 2005. In order to accommodate the increasing inventory of spent fuel, the US utilities started looking for various means to store spent fuel at the reactor sites. One of the most economical ways to accommodate more spent fuel is to arrange storage locations as closely as possible at the same time making sure that the fuel remains subcritical and that there are adequate means to cope with the heat load. The free standing high density rack configuration is an outcome of efforts to accommodate to more fuel in the limited space. 3 refs., 3 figs

Benchmarking criticality analysis of TRIGA fuel storage racks.

Science.gov (United States)

Robinson, Matthew Loren; DeBey, Timothy M; Higginbotham, Jack F

2017-01-01

A criticality analysis was benchmarked to sub-criticality measurements of the hexagonal fuel storage racks at the United States Geological Survey TRIGA MARK I reactor in Denver. These racks, which hold up to 19 fuel elements each, are arranged at 0.61m (2 feet) spacings around the outer edge of the reactor. A 3-dimensional model was created of the racks using MCNP5, and the model was verified experimentally by comparison to measured subcritical multiplication data collected in an approach to critical loading of two of the racks. The validated model was then used to show that in the extreme condition where the entire circumference of the pool was lined with racks loaded with used fuel the storage array is subcritical with a k value of about 0.71; well below the regulatory limit of 0.8. A model was also constructed of the rectangular 2×10 fuel storage array used in many other TRIGA reactors to validate the technique against the original TRIGA licensing sub-critical analysis performed in 1966. The fuel used in this study was standard 20% enriched (LEU) aluminum or stainless steel clad TRIGA fuel. Copyright © 2016. Published by Elsevier Ltd.

Rack Distribution Effects on MPLM Center of Mass

Science.gov (United States)

Tester, John T.

2005-01-01

This research was in support of exploring the need for more flexible "center of gravity (CG) specifications than those currently established by NASA for the Multi-Purpose Logistics Module (MPLM). The MPLM is the cargo carrier for International Space Station (ISS) missions. The MPLM provides locations for 16 standard racks, as shown in Figure 1; not all positions need to be filled in any given flight. The MPLM coordinate system (X(sub M), Y(sub M), Z(sub M)) is illustrated as well. For this project, the primary missions of interest were those which supply the ISS and remove excess materials on the return flights. These flights use a predominate number of "Resupply Stowage Racks" (RSR) and "Resupply Stowage Platforms" (RSP). In these two types of racks, various smaller items are stowed. Hence, these racks will exhibit a considerable range of mass values as well as a range as to where their individual CG are located.

Experimental and Numerical Study of Bottom Rack Occlusion by Flow with Gravel-Sized Sediment. Application to Ephemeral Streams in Semi-Arid Regions

Directory of Open Access Journals (Sweden)

Luis G. Castillo

2016-04-01

Full Text Available Rainfall runoff collection in ephemeral streams is an objective in semi-arid zones. Rack intake systems are proposed to collect these flash floods with intensive sediment transport. The design parameters address the problem of clogging the spacing between bars. Experiments for two different void ratio racks are shown. Flows, longitudinal slopes in the rack, and water with three gravel-sized sediments were tested. Results such as effective void ratio due to the gravel deposition over the rack, the evolution of the flow rejected during each test, and the quantification of materials collected and deposited, are presented. The optimal longitudinal rack slope seems to be close to 30%. The effective void ratio is related to several hydraulic parameters calculated at the beginning of the rack. Some adjustments were proposed to predict the effective void ratio.

Experimental study on hydraulic characteristic around trash rack of a pumping station

Science.gov (United States)

Zhou, MinZhe; Li, TongChun; Lin, XiangYang; Liu, XiaoQing; Ding, Yuan; Liu, GuangYuan

2017-11-01

This paper focuses on flow pattern around trash rack of intake of a pumping station project. This pumping station undertake the task of supplying up to 3,500,000 m3 water per day for a megacity. Considering the large flow rate, high lift, multi-pipe supply and long-time operation in this water conveyance pumping station, we built a physical model test to measure the flow velocity and observe the flow pattern to verify the reasonability of preliminary design. In this test, we set 3 layers of current meters around each trash rack of intake in reservoir to collect the flow velocity. Furthermore, we design 2 operating conditions of 9 pumps to observe the change of flow pattern. Finally, we found the velocity data were in a normal range under 2 different operating conditions of the 9 pump units.

Nonlinear dynamic response of whole pool multiple spent fuel racks subject to three-dimensional excitations

International Nuclear Information System (INIS)

Zhao, Y.; Wilson, P.R.; Stevenson, J.D.

1995-01-01

The seismic evaluation of submerged free standing spent fuel storage racks is more complicated than most other nuclear structural systems. When subjected to three dimensional (3-D) floor seismic excitations the dynamic responses of racks in a pool are hydro dynamically coupled with each other, with the fuel assemblies water in gaps. The motion behavior of the racks is significantly different from that observed using a 3D single rack mode. Few seismic analyses using 3-D whole pool multiple rack models are available in the literature. I this paper an analysis was performed for twelve racks using potential theory for the fluid-structure interaction, and using a 3-D whole pool multi-rack finite element model developed herein. The analysis includes the potential nonlinear dynamic behavior of the impact of fuel-rack, rack-rack and rack-pool wall, the tilting or uplift and the frictional sliding of rack supports, and the impact of the rack supports to the pool floor. (author). 12 refs., 7 figs., 1 tab

A water-cooling solution for PC-racks of the LHC experiments

CERN Document Server

Vannerem, P

2004-01-01

With ever increasing power consumption and heat dissipation of todays CPUs, cooling of rack-mounted PCs is an issue for the future online farms of the LHC experiments. In order to investigate the viability of a water-cooling solution, a prototype PC-farm rack has been equipped with a commercially available retrofitted heat exchanger. The project has been carried out as a collaboration of the four LHC experiments and the PH-ESS group . This note reports on the results of a series of cooling and power measurements of the prototype rack with configurations of 30 to 48 PCs. The cooling performance of the rack-cooler is found to be adequate; it extracts the heat dissipated by the CPUs efficiently into the cooling water. Hence, the closed PC rack transfers almost no heat into the room. The measurements and the failure tests show that the rack-cooler concept is a viable solution for the future PC farms of the LHC experiments.

A Study on Rack Thickness Effect for Spent Fuel Pool Storage

International Nuclear Information System (INIS)

Kim, Mi Jin; Lee, Hee-Jae; Sohn, Dong-Seong

2015-01-01

For the effective storage of used fuel, the development of high performance neutron absorbing materials is needed. One of the major concern for the used fuel storage is the assurance to keep subcriticality of the storage rack and the high performance neutron absorbing material is the vital part to assure this requirement. According to NRC guide line, the k-effective of the spent fuel storage racks must not exceed 0.95. To ensure its safety, subcriticality analysis is required. Subcriticality analysis of the used storage in spent fuel pool have been performed by different authors. Criticality calculations for light water reactor spent fuel storage rack were carried out by Jae et al. They used AMPX-KENO IV code and considered the effect of rack pitch and rack thickness for consolidated fuel. The criticality analysis has performed at Gd 0.2 and 1 wt% according to thickness change. As thickness increases, the volume of the spent fuel pool rack increases. Therefore, absorbing material also increases according to thickness

A Study on Rack Thickness Effect for Spent Fuel Pool Storage

Energy Technology Data Exchange (ETDEWEB)

Kim, Mi Jin; Lee, Hee-Jae; Sohn, Dong-Seong [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2015-05-15

For the effective storage of used fuel, the development of high performance neutron absorbing materials is needed. One of the major concern for the used fuel storage is the assurance to keep subcriticality of the storage rack and the high performance neutron absorbing material is the vital part to assure this requirement. According to NRC guide line, the k-effective of the spent fuel storage racks must not exceed 0.95. To ensure its safety, subcriticality analysis is required. Subcriticality analysis of the used storage in spent fuel pool have been performed by different authors. Criticality calculations for light water reactor spent fuel storage rack were carried out by Jae et al. They used AMPX-KENO IV code and considered the effect of rack pitch and rack thickness for consolidated fuel. The criticality analysis has performed at Gd 0.2 and 1 wt% according to thickness change. As thickness increases, the volume of the spent fuel pool rack increases. Therefore, absorbing material also increases according to thickness.

Behavior of high-density spent-fuel storage racks

International Nuclear Information System (INIS)

Bailey, W.J.

1986-08-01

Included in this report is a summary of information on neutron-absorbing materials such as B 4 C in an aluminum matrix or organic binder material, stainless steel-boron and aluminum-boron alloys, and stainless steetl-clad cadmium that are used in high-density spent fuel storage racks. A list of the types of neutron-absorbing materials being used in spent fuel storage racks at domestic commercial plants is provided. Recent cases at several domestic plants where swelling of rack side plates (where the B 4 C in an aluminum matrix and B 4 C in an organic binder material were located) occurred are reviewed

Recalculation with SEACAB of the activation by spent fuel neutrons and residual dose originated in the racks replaced at Cofrentes NPP

Directory of Open Access Journals (Sweden)

Ortego Pedro

2017-01-01

Full Text Available In order to increase the storage capacity of the East Spent Fuel Pool at the Cofrentes NPP, located in Valencia province, Spain, the existing storage stainless steel racks were replaced by a new design of compact borated stainless steel racks allowing a 65% increase in fuel storing capacity. Calculation of the activation of the used racks was successfully performed with the use of MCNP4B code. Additionally the dose rate at contact with a row of racks in standing position and behind a wall of shielding material has been calculated using MCNP4B code as well. These results allowed a preliminary definition of the burnker required for the storage of racks. Recently the activity in the racks has been recalculated with SEACAB system which combines the mesh tally of MCNP codes with the activation code ACAB, applying the rigorous two-step method (R2S developed at home, benchmarked with FNG irradiation experiments and usually applied in fusion calculations for ITER project.

Recalculation with SEACAB of the activation by spent fuel neutrons and residual dose originated in the racks replaced at Cofrentes NPP

Science.gov (United States)

Ortego, Pedro; Rodriguez, Alain; Töre, Candan; Compadre, José Luis de Diego; Quesada, Baltasar Rodriguez; Moreno, Raul Orive

2017-09-01

In order to increase the storage capacity of the East Spent Fuel Pool at the Cofrentes NPP, located in Valencia province, Spain, the existing storage stainless steel racks were replaced by a new design of compact borated stainless steel racks allowing a 65% increase in fuel storing capacity. Calculation of the activation of the used racks was successfully performed with the use of MCNP4B code. Additionally the dose rate at contact with a row of racks in standing position and behind a wall of shielding material has been calculated using MCNP4B code as well. These results allowed a preliminary definition of the burnker required for the storage of racks. Recently the activity in the racks has been recalculated with SEACAB system which combines the mesh tally of MCNP codes with the activation code ACAB, applying the rigorous two-step method (R2S) developed at home, benchmarked with FNG irradiation experiments and usually applied in fusion calculations for ITER project.

Fuel storage rack

International Nuclear Information System (INIS)

Mollon, L.

1977-01-01

Disclosed is a storage rack for spent nuclear fuel elements comprising a multiplicity of elongated hollow containers of uniform cross-section, preferably square,some of said containers having laterally extending continuous flanges extending between adjacent containers and defining continuous elongated chambers therebetween for the reception of neutron absorbing panels. 18 claims, 7 figures

FSI-based Overflow Assessment of the Seismically-Isolated SFP with Fuel Racks

Energy Technology Data Exchange (ETDEWEB)

Chung, Gil Y.; Park, Hyun T.; Chang, Soo-Hyuk [Korea Maintenance Co., Seoul (Korea, Republic of); Lee, Sang-Hoon [KEPCO E-C, Yongin (Korea, Republic of)

2014-10-15

To date, effectiveness of the seismic isolation systems for reducing seismic force effectively has been well demonstrated. In this context, practical application of the technology in nuclear engineering fields has become an important issue more and more. This is because fluid motion can be rather amplified due to the increased relative displacement between the base and superstructures by a long-period shift. Therefore, overflow assessment and prediction of the seismically-isolated SFP have to be conducted in design phase. For performing sloshing-induced overflow of the seismically-isolated SFP, a fluid-structure interaction(FSI) approach making a two-way coupling process between structural and fluid solvers is herein employed. In this study, fuel racks inside the SFP are included in FSI modeling to investigate effect of fuel-cell assemblies on SFP overflow. Accordingly, three different assembly sets of fuel cells are assumed to be inserted in fuel racks. In addition, floor acceleration time-histories produced from three different amplitudes of peak ground acceleration (PGA) are applied to the SFP base to investigate load effect on liquid overflow. An approach for the liquid overflow assessment of the seismically-isolated nuclear SFP with fuel storage racks based on FSI analysis was addressed. From the results of the identified cases, the following conclusions are drawn: (i) FSI technique can be effectively used to assess the seismically-isolated SFP overflow, (ii) In a conservative way, the isolated SFP without fuel racks can be used to assess its sloshing-induced overflow under earthquake since effect of fuel-cell assemblies on the SFP overflow is not significant, (iii) for given same conditions (e.g., constant design free surface, same fuel-cell assembly) except seismic loading, the higher PGA is, the more liquid overflow increases.

Development of remote handling technology for nuclear fuel cycle facilities in Japan

International Nuclear Information System (INIS)

Maekawa, Hiromichi; Sakai, Akira; Miura, Noriaki; Kozaka, Tetsuo; Hamada, Takashi

2015-01-01

Remote handling technology has been systematically developed for nuclear fuel cycle facilities in Japan since 1970s, primarily in parallel with the development of reprocessing and HLLW (High Level Liquid Waste) vitrification process. In case of reprocessing and vitrification process to handle highly radioactive and hazardous materials, the most of components are installed in the radiation shielded hot cells and operators are not allowed to enter the work area in the cells for operation and maintenance. Therefore, a completely remote handling system is adopted for the cells to reduce radiation doses of operators and increase the availability of the facility. The hot cells are generally designed considering the scale of components (laboratory, demonstration, or full-scale), the function of the systems (chemical process, material handling, dismantling, decontamination, or chemical analysis), and the environmental conditions (radiation dose rate, airborne concentration, surface contamination, or fume/mist/dust). Throughout our domestic development work for remote handling technology, the concept of the large scale integrated cell has been adopted rather than a number of small scale separated cells, for the reasons to reduce the total installation space and the number of remote handling equipment required for the each cell as much as possible. In our domestic remote maintenance design, several new concepts have been developed, tested, and demonstrated in the Tokai Virtrification Facility (TVF) and the Rokkasho HLLW Vitrification and Storage Facility (K-facility). Layout in the hot cells, the performance of remote handling equipment, and the structure of the in-cell components are important factors for remote maintenance design. In case of TVF (hot tests started in 1995), piping and vessels are prefabricated in the rack modules and installed in two lines on both sides of the cell. These modules are designed to be remotely replaced in the whole rack. Two overhead cranes

'Swab racks are an old fashioned idea'.

Science.gov (United States)

Mumford, M

1991-12-01

Mary Mumford, theatre sister at the Princes of Wales Hospital, Bridgend, was asked to speak in a short debate at an NATN branch meeting, supporting the motion that 'swab racks are an old fashioned idea'. Although she did not like swab racks she had not attempted thus far to do anything about them. In the event, she actually lost the debate--not in principle but because she could offer no effective alternative method of checking swabs. Having been given the incentive, a trial is now being conducted in her hospital similar to that described by Paul Wicker. This is the case presented by Mary Mumford supporting the following motion ... 'that swab racks are an old fashioned idea, which cause more potential problems due to exposure of blood than is proven to be safe in today's theatre environment'.

To the question about the layout of the racks in the warehouse

Directory of Open Access Journals (Sweden)

Ilesaliev D.I.

2017-03-01

Full Text Available Warehouses, which are located at points of transshipment of cargo from one type of transport on the other, play a sig-nificant role in the transformation of cargo to further the most effective transportation of goods. The location of racks and longitudinal passages are important in the work of transhipment warehouse. Typically, racks and longitudinal pas-sages are perpendicular to each other, the article proposes a radical change with the "euclidean advantage". This is an-other way of designing warehouses for efficiency overload packaged cargo in the supply chain. Purpose is to reduce the mileage for one cycle of the loader from loading and unloading areas to storage areas.

Three-dimensional seismic analysis for spent fuel storage rack

International Nuclear Information System (INIS)

Lee, Gyu Mahn; Kim, Kang Soo; Park, Keun Bae; Park, Jong Kyun

1998-01-01

Time history analysis is usually performed to characterize the nonlinear seismic behavior of a spent fuel storage rack (SFSR). In the past, the seismic analyses of the SFSR were performed with two-dimensional planar models, which could not account for torsional response and simultaneous multi-directional seismic input. In this study, three-dimensional seismic analysis methodology is developed for the single SFSR using the ANSY code. The 3-D model can be used to determine the nonlinear behavior of the rack, i.e., sliding, uplifting, and impact evaluation between the fuel assembly and rack, and rack and the pool wall. This paper also reviews the 3-D modeling of the SFSR and the adequacy of the ANSYS for the seismic analysis. As a result of the adequacy study, the method of ANSYS transient analysis with acceleration time history is suitable for the seismic analysis of highly nonlinear structure such as an SFSR but it isn't appropriate to use displacement time history of seismic input. (author)

Flow field mapping in data rack model

Directory of Open Access Journals (Sweden)

Matěcha J.

2013-04-01

Full Text Available The main objective of this study was to map the flow field inside the data rack model, fitted with three 1U server models. The server model is based on the common four-processor 1U server. The main dimensions of the data rack model geometry are taken fully from the real geometry. Only the model was simplified with respect to the greatest possibility in the experimental measurements. The flow field mapping was carried out both experimentally and numerically. PIV (Particle Image Velocimetry method was used for the experimental flow field mapping, when the flow field has been mapped for defined regions within the 2D/3D data rack model. Ansys CFX and OpenFOAM software were used for the numerical solution. Boundary conditions for numerical model were based on data obtained from experimental measurement of velocity profile at the output of the server mockup. This velocity profile was used as the input boundary condition in the calculation. In order to achieve greater consistency of the numerical model with experimental data, the numerical model was modified with regard to the results of experimental measurements. Results from the experimental and numerical measurements were compared and the areas of disparateness were identified. In further steps the obtained proven numerical model will be utilized for the real geometry of data racks and data.

Casimir rack and pinion as a miniaturized kinetic energy harvester

Science.gov (United States)

Miri, MirFaez; Etesami, Zahra

2016-08-01

We study a nanoscale machine composed of a rack and a pinion with no contact, but intermeshed via the lateral Casimir force. We adopt a simple model for the random velocity of the rack subject to external random forces, namely, a dichotomous noise with zero mean value. We show that the pinion, even when it experiences random thermal torque, can do work against a load. The device thus converts the kinetic energy of the random motions of the rack into useful work.

40 CFR 63.2475 - What requirements must I meet for transfer racks?

Science.gov (United States)

2010-07-01

... transfer racks? 63.2475 Section 63.2475 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... must I meet for transfer racks? (a) You must comply with each emission limit and work practice standard in table 5 to this subpart that applies to your transfer racks, and you must meet each applicable...

Design Study and Optimization of Irradiation Facilities for Detector and Accelerator Equipment Testing in the SPS North Area at CERN

CERN Document Server

AUTHOR|(CDS)2079748; Stekl, Ivan

Due to increasing performance of LHC during the last years, the strong need of new detector and electronic equipment test areas at CERN appeared from user communities. This thesis reports on two test facilities: GIF++ and H4IRRAD. GIF++, an upgrade of GIF facility, is a combined high-intensity gamma and particle beam irradiation facility for testing detectors for LHC. It combines a high-rate 137Cs source, providing photons with energy of 662 keV, together with the high-energy secondary particle beam from SPS. H4IRRAD is a new mixed-field irradiation area, designed for testing LHC electronic equipment for radiation damage effects. In particular, large volume assemblies such as full electronic racks of high current power converters can be tested. The area uses alternatively an attenuated primary 400 GeV/c proton beam from SPS, or a secondary, mainly proton, beam of 280 GeV/c directed towards a copper target. Different shielding layers are used to reproduce a radiation field similar to the LHC “tunnel” and �...

NASA/First Materials Science Research Rack (MSRR-1) Module Inserts Development for the International Space Station

Science.gov (United States)

Crouch, Myscha; Carswell, Bill; Farmer, Jeff; Rose, Fred; Tidwell, Paul

1999-01-01

The Material Science Research Rack 1 (MSRR-1) of the Material Science Research Facility (MSRF) contains an Experiment Module (EM) being developed collaboratively by NASA and the European Space Agency (ESA). This NASA/ESA EM will accommodate several different removable and replaceable Module Inserts (MIs) which are installed on orbit. Two of the NASA MIs being developed for specific material science investigations are described herein.

Shaping of Rack Cutter Original Profile for Fine-module Ratchet Teeth Cutting

Science.gov (United States)

Sharkov, O. V.; Koryagin, S. I.; Velikanov, N. L.

2018-05-01

The design models and the process of shaping the cutting edges of the rack cutter for cutting fine-module ratchet teeth are considered in the article. The use of fine-module ratchet teeth can reduce the noise and impact loads during operation of the freewheel mechanisms. Mathematical dependencies for calculating the coordinates determining the geometric position of the points of the front and back edges of the cutting profile of the rack cutter, the workpiece angle of rotation during cutting the ratchet teeth were obtained. When applying the developed method, the initial data are: the radii of the workpiece circumferences passing through the dedendum of the external and internal cut teeth; gradient angles of the front and back edges of the rail.

Inspection and Analysis of Aluminum Storage Racks in Spent Fuel Storage Basins

International Nuclear Information System (INIS)

Howell, J.P.; Nelson, D.Z.

1998-07-01

Aluminum-clad spent nuclear fuel is stored in water filled basins at the Savannah River Site awaiting processing or other disposition. After more than 35 years of service underwater, the aluminum storage racks that position the fuel bundles in the basin were replaced. During the removal of the racks from the basin, a failure occurred in one of the racks and the Savannah River Technology Center was asked to investigate. This paper presents results of the failure analysis and provides a discussion of the effects of corrosion on the structural integrity of the storage racks

Rack Aware Data Placement for Network Consumption in Erasure-Coded Clustered Storage Systems

Directory of Open Access Journals (Sweden)

Bilin Shao

2018-06-01

Full Text Available The amount of encoded data replication in an erasure-coded clustered storage system has a great impact on the bandwidth consumption and network latency, mostly during data reconstruction. Aimed at the reasons that lead to the excess data transmission between racks, a rack aware data block placement method is proposed. In order to ensure rack-level fault tolerance and reduce the frequency and amount of the cross-rack data transmission during data reconstruction, the method deploys partial data block concentration to store the data blocks of a file in fewer racks. Theoretical analysis and simulation results show that our proposed strategy greatly reduces the frequency and data volume of the cross-rack transmission during data reconstruction. At the same time, it has better performance than the typical random distribution method in terms of network usage and data reconstruction efficiency.

Facility design: introduction

International Nuclear Information System (INIS)

Unger, W.E.

1980-01-01

The design of shielded chemical processing facilities for handling plutonium is discussed. The TRU facility is considered in particular; its features for minimizing the escape of process materials are listed. 20 figures

Analysis of thermal issues associated with the pre-amplifier modules in the National Ignition Facility

International Nuclear Information System (INIS)

Lam, K.L.

1998-01-01

The design of the National Ignition Facility (NIF) calls for a desired temperature field of 20.00 ± 0.28 C throughout the facility. This design requirement is needed to prevent degradation of the operating performance and net yield of the NIF by heat loads generated within the facility. In particular, the potential interference of waste heat from the lighting fixtures and equipment such as the electronics racks, and pre-amplifier modules (PAMs), and its impact on the operational performance of the laser beam transport tubes and optical alignment components must be evaluated. This report describes the thermal analyses associated with the PAMs. Evaluation of thermal issues for the other equipment is discussed elsewhere

Arabidopsis scaffold protein RACK1A modulates rare sugar D-allose regulated gibberellin signaling.

Science.gov (United States)

Fennell, Herman; Olawin, Abdulquadri; Mizanur, Rahman M; Izumori, Ken; Chen, Jin-Gui; Ullah, Hemayet

2012-11-01

As energy sources and structural components, sugars are the central regulators of plant growth and development. In addition to the abundant natural sugars in plants, more than 50 different kinds of rare sugars exist in nature, several of which show distinct roles in plant growth and development. Recently, one of the rare sugars, D-allose, an epimer of D-glucose at C3, is found to suppress plant hormone gibberellin (GA) signaling in rice. Scaffold protein RACK1A in the model plant Arabidopsis is implicated in the GA pathway as rack1a knockout mutants show insensitivity to GA in GA-induced seed germination. Using genetic knockout lines and a reporter gene, the functional role of RACK1A in the D-allose pathway was investigated. It was found that the rack1a knockout seeds showed hypersensitivity to D-allose-induced inhibition of seed germination, implicating a role for RACK1A in the D-allose mediated suppression of seed germination. On the other hand, a functional RACK1A in the background of the double knockout mutations in the other two RACK1 isoforms, rack1b/rack1c, showed significant resistance to the D-allose induced inhibition of seed germination. The collective results implicate the RACK1A in the D-allose mediated seed germination inhibition pathway. Elucidation of the rare sugar signaling mechanism will help to advance understanding of this less studied but important cellular signaling pathway.

Rack for storage of nuclear fuel elements

International Nuclear Information System (INIS)

Bosshart, E.

1987-01-01

The rack contains a cluster of parallel, approximately vertical, neutron absorbing square section tubes which are attached to a bottom plate and mutually supported along their edges using welded joining pieces. These welded pieces touch each other laterally in at least one middle plane where the rack is joined. The pieces are additionally secured laterally by screws. Thereby a safe and simple mutual support of the tubes is achieved. It is possible to dismount the tubes by releasing the screws without the necessity to move the tubes in a horizontal direction. 4 figs

CM-2 Environmental/Modal Testing of SPACEHAB Racks

Science.gov (United States)

McNelis, Mark E.; Goodnight, Thomas W.

2001-01-01

Combined environmental/modal vibration testing has been implemented at the NASA Glenn Research Center's Structural Dynamics Laboratory. The benefits of combined vibration testing are that it facilitates test article modal characterization and vibration qualification testing. The Combustion Module-2 (CM-2) is a space experiment that will launch on shuttle mission STS-107 in the SPACEHAB Research Double Module. The CM-2 flight hardware is integrated into a SPACEHAB single and double rack. CM-2 rack-level combined vibration testing was recently completed on a shaker table to characterize the structure's modal response and verify the random vibration response. Control accelerometers and limit force gauges, located between the fixture and rack interface, were used to verify the input excitation. Results of the testing were used to verify the loads and environments for flight on the shuttles.

Facility engineering for Arctic conditions

Energy Technology Data Exchange (ETDEWEB)

Hunt, D.M.; McClusky, K.R.; Shirley, R.; Spitzenberger, R. [Mustang Engineering Inc., Houston, TX (United States)

2001-07-01

The Northstar Development Project is located on Seal Island in the Beaufort Sea, north of Prudhoe Bay. The design and engineering of the facilities for the Northstar Development Project was fraught with challenges. Mustang Engineering Incorporated was involved in the design and engineering of the pipe rack, pump house, process and compressor modules. All the characteristics of an offshore facility are present, even though the project is land-based on a man-made island. A number of the strategies developed for offshore platforms of the Gulf of Mexico were adapted to the fabrication, logistics and installation of the modules. To reduce yard fabrication time, a modularized design concept was adopted. Cost savings and onsite fabrication efficiencies were realized through open communication with the operator, early discussions with vendors, regulatory agencies, and local fabrication and installation contractors. Some improvisation and deviations were required to meet the stringent requirements for operation under Arctic conditions. The lessons learned on this project will be of use in future Arctic projects. 1 tab., 6 figs.

The gravitational plant physiology facility-Description of equipment developed for biological research in spacelab

Science.gov (United States)

Heathcote, D. G.; Chapman, D. K.; Brown, A. H.; Lewis, R. F.

1994-01-01

In January 1992, the NASA Suttle mission STS 42 carried a facility designed to perform experiments on plant gravi- and photo-tropic responses. This equipment, the Gravitational Plant Physiology Facility (GPPF) was made up of a number of interconnected units mounted within a Spacelab double rack. The details of these units and the plant growth containers designed for use in GPPF are described. The equipment functioned well during the mission and returned a substantial body of time-lapse video data on plant responses to tropistic stimuli under conditions of orbital microgravity. GPPF is maintained by NASA Ames Research Center, and is flight qualifiable for future spacelab missions.

A relay rack for a control and protection system for nuclear reactors

International Nuclear Information System (INIS)

Miyata, Yasuyuki; Oda, Noriaki; Akiyama, Toyoshi

1975-01-01

It is obvious that all the equipment in the various systems that constitute a nuclear power plant must exhibit the highest levels of reliability, but the reactor control and protection system is of vital importance, and thus it requires a particularly thorough approach, incorporating redundancy, independence and separation. The paper describes the functions, construction and specifications of the relay rack - one of the most important items of equipment for reactor control and protection in a generating facility using a pressurized-water reactor - and it gives details of the extent to which these three requirements are satisfied. (author)

Stability Analysis Of 3-d Conventional Pallet Rack Structures With Semi-rigid Connections

Directory of Open Access Journals (Sweden)

Kamal M. Bajoria

2009-12-01

Full Text Available This paper describe the three dimensional finite element modeling and buckling analysis of conventional pallet racking system with semi rigid connection. In this study three dimensional models of conventional pallet racking system were prepared using the finiteelement program ANSYS and finite element analysis carried out on conventional pallet racks with the 18 types of column sections developed along with semi-rigid connections. A parametric study was carried out to compare the effective length approach and the finiteelement method for accuracy and appropriateness for cold-formed steel frame design. Numerous frame elastic buckling analyses were carried out to evaluate the alignment chart and the AISI torsional-flexural buckling provisions. The parameters that influence the valueof Kx for column flexural buckling were examined in this study. The alignment chart and the AISI torsional-flexural buckling provisions, used to obtain the effective lengths and elastic buckling load of members were also evaluated. Results showed that the elastic buckling load obtained from the AISI torsional-flexural buckling provisions is generally conservative compared to the results obtained from performing frame elastic buckling analysis. Results also showed that, the effective length approach is more conservative than the finite element approach.

78 FR 63166 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Countervailing...

Science.gov (United States)

2013-10-23

... Shelving and Racks From the People's Republic of China: Countervailing Duty Administrative Review; 2011... order on certain kitchen appliance shelving and racks (kitchen racks) from the People's Republic of.... Scope of the Order This order covers shelving and racks for refrigerators, freezers, combined...

Influence of Rack Slope and Approaching Conditions in Bottom Intake Systems

Directory of Open Access Journals (Sweden)

Luis G. Castillo

2017-01-01

Full Text Available The study analyzes the flow over bottom racks made of longitudinal T-shaped bars. A clear water flow is considered in a laboratory flume. Free surface profiles, wetted rack lengths, and discharge coefficients are measured, changing parameters such as longitudinal slope, void ratio, and approaching flow. The present work complements existing experimental studies, considering the influence of the approaching flow conditions. The velocity field measured with Particle Image Velocimetry (PIV technique and the pressure field with Pitot tubes are quantified. Numerical simulations (CFD are used to complement laboratory data. The energy head along the rack is calculated and compared with the hypothesis of horizontal energy level with minimum energy at the beginning of the rack. A discharge coefficient adjustment that considers the slope, the void ratio, and the position along the rack is proposed and presented with the results of other works. Theoretical proposals to calculate the pressure field along the flow are compared with measurements in the laboratory. The relation between the static pressure head in the space of bars and the discharge coefficient is used as an alternative method to define the discharge.

The NRC activities concerning Boraflex use in spent-fuel storage racks

International Nuclear Information System (INIS)

Kopp, L.I.

1996-01-01

The U.S. Nuclear Regulatory Commission (NRC) has issued several generic communications to the nuclear industry identifying two issues with respect to using Boraflex in spent-fuel storage racks. The first issue related to gamma-radiation-induced shrinkage of Boraflex and the potential to develop tears or gaps in the material. This phenomenon is typically accounted for in criticality analyses of spent-fuel storage racks. The second issue concerned long-term Boraflex performance throughout the intended service life of the racks as a result of both gamma irradiation and exposure to the wet pool environment

Safety Assessment of Multi Purpose Small Payload Rack(MSPR)

Science.gov (United States)

Mizutani, Yoshinobu; Takada, Satomi; Murata, Kosei; Ozawa, Daisaku; Kobayashi, Ryoji; Nakamura, Yasuhiro

2010-09-01

We are reporting summary of preliminary safety assessment for Multi Purpose Small Payload Rack(MSPR), which is one of the micro gravity experiment facilities that are being developed for the 2nd phase JEM utilization(JEM: Japanese Experiment Module) that will be launched on H-II Transfer Vehicle(HTV) 2nd flight in 2011. MSPR is used for multi-purpose micro-g experiment providing experimental spaces and work stations. MSPR has three experimental spaces; first, there is a space called Work Volume(WV) with capacity volume of approximately 350 litters, in which multiple resources including electricity, communication, and moving image functions can be used. Within this space, installation of devices can be done by simple, prompt attachment by Velcro and pins with high degree of flexibility. Second, there is Small Experiment Area(SEA), with capacity volume of approximately 70 litters, in which electricity, communication, and moving image functions can also be used in the same way as WV. These spaces protect experiment devices and specimens from contingent loads by the crewmembers. Third, there is Work Bench with area of 0.5 square meters, on which can be used for maintenance, inspection and data operations of installed devices, etc. This bench can be stored in the rack during contingency. Chamber for Combustion Experiment(CCE) that is planned to be installed in WV is a pressure-resistant experimental container that can be used to seal hazardous materials from combustion experiments. This CCE has double sealing design in chamber itself, which resist gas leakage under normal the temperature and pressure. Electricity, communication, moving image function can be used in the same way as WV. JAXA Phase 2 Safety Review Panel(SRP) has been held in April, 2010. For safety analysis of MSPR, hazards were identified based on Fault Tree Analysis methodology and then these hazards were classified into either eight ISS standard-type hazards or eight unique-type hazards that requires

Parametric Evaluation of Racking Performance of Platform Timber Framed Walls

OpenAIRE

Dhonju, R..; D’Amico, B..; Kermani, A..; Porteous, J..; Zhang, B..

2017-01-01

This paper provides a quantitative assessment of the racking performance of partially anchored timber framed walls, based on experimental tests. A total of 17 timber framed wall specimens, constructed from a combination of materials under different load configurations, were tested. The experimental study was designed toexamine the influence of a range of geometrical parameters, such as fastener size and spacings, wall length, arrangement of studs and horizontal members, as well as the effect ...

77 FR 61396 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Countervailing...

Science.gov (United States)

2012-10-09

... Shelving and Racks From the People's Republic of China: Countervailing Duty Administrative Review; 2010... order on certain kitchen appliance shelving and racks (``kitchen racks'') from the People's Republic of...-1785, respectively. Scope of the Order The scope of the order consists of shelving and racks for...

76 FR 62364 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Preliminary...

Science.gov (United States)

2011-10-07

... Shelving and Racks From the People's Republic of China: Preliminary Results of the Countervailing Duty... countervailable duty order on certain kitchen appliance shelving and racks (``Kitchen Racks'') from the People's...: Background On July 27, 2009, the Department published a CVD order on Kitchen Racks from the PRC. See Certain...

Replacement of the rotary specimen rack in the U.S. Geological Survey TRIGA Reactor (GSTR)

International Nuclear Information System (INIS)

Rusling, D.H.; Helfer, P.G.; Perryman, R.E.; Smith, W.L.

1986-01-01

A new rotary specimen rack was installed in the GSTR on November 13, 1985. The new rack has been modified to allow the pneumatic unloading of samples. Instructions for the removal and installation of the rotary specimen rack were provided by GA Technologies. The first step was to prepare the core for removal of the control rods, T/C fuel elements, and the central thimble. The rack was weighted prior to removal to ensure that it could not float to the surface. The old rack was stored at the side of the tank. Radiation measurements were made with an underwater ion chamber. (author)

Orientation to pollution prevention for facility design

Energy Technology Data Exchange (ETDEWEB)

Raney, E.A.; Whitehead, J.K.; Encke, D.B. [Westinghouse Hanford Co., Richland, WA (United States); Dorsey, J.A. [Kaiser Engineers Hanford Co., Richland, WA (United States)

1994-01-01

This material was developed to assist engineers in incorporating pollution prevention into the design of new or modified facilities within the U.S. Department of Energy (DOE). The material demonstrates how the design of a facility can affect the generation of waste throughout a facility`s entire life and it offers guidance on how to prevent the generation of waste during design. Contents include: Orientation to pollution prevention for facility design training course booklet; Pollution prevention design guideline; Orientation to pollution prevention for facility design lesson plan; Training participant survey and pretest; and Training facilitator`s guide and schedule.

Combat Ration Network for Technology Implementation. Retort Racks for Polymeric Trays in 1400 Style Spray Retorts

National Research Council Canada - National Science Library

Bruins, Henderikus B; Coburn, John F

2003-01-01

The objective of this project was to design a retort rack that would maximize the retort capacity of a 1400 style spray retort and to select a material that would withstand the harsh retort spray environment...

Mathematical Modelling of Involute Spur Gears Manufactured by Rack Cutter

Directory of Open Access Journals (Sweden)

Tufan Gürkan YILMAZ

2016-05-01

Full Text Available In this study, mathematical modelling of asymmetric involute spur gears was situated in by Litvin approach. In this context, firstly, mathematical expressions of rack cutter which manufacture asymmetric involute spur gear, then mathematical expression of asymmetric involute spur gear were obtained by using differential geometry, coordinate transformation and gear theory. Mathematical expressions were modelled in MATLAB and output files including points of involute spur gear’s teeth were designed automatically thanks to macros.

New irradiation facilities at the Australian national medical cyclotron

International Nuclear Information System (INIS)

Parcell, S.K.; Arnott, D.W.; Conard, E.M.

1999-01-01

Two new irradiation facilities have been developed at the National Medical Cyclotron for radionuclide production. The first relocates PET irradiations from the cyclotron vault to a dedicated PET beam room, to improve accessibility and reduce radiation exposures associated with target maintenance. This new facility consists of a beam line to transport 16-30 MeV proton beams from the cyclotron to 1 of 8 PET targets mounted on a target rack. The target rack has increased the number of targets available for production and experimentation. The second is a completely independent solid target irradiation facility for SPECT. This facility consists of a beam line to transport 26-30 MeV proton beams from the cyclotron to a dedicated beam room containing one solid target station. A new pneumatic target transfer system was also developed to transport the solid target to and from the existing chemistry hot cells. The beam line and target components are operated under the control of a dedicated PLC with a PC based user interface. The development and some technical aspects of these new irradiation facilities are discussed here. (author)

Translating DWPF design criteria into an engineered facility design

International Nuclear Information System (INIS)

Kemp, J.B.

1986-01-01

The Defense Waste Processing Facility (DWPF) takes radioactive defense waste sludge and the radioactive nuclides, cesium and strontium, from the salt solution, and incorporates them in borosilicate glass in stainless steel canisters, for subsequent disposal in a deep geologic repository. The facility was designed by Bechtel National, Inc. under a subcontract from E.I. DuPont de Nemurs and Co., the prime contractor for the Department of Energy, for the design, construction and commissioning of the plant. The design criteria were specified by the DuPont Company, based upon their extensive experience as designer, and operator since the early 1950's, of the existing Savannah River Plant facilities. Some of the design criteria imposed unusual or new requirements on the detailed design of the facilities. This paper describes some of these criteria, encompassing several engineering disciplines, and discusses the solutions and designs which were developed for the DWPF

77 FR 21744 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Final Results...

Science.gov (United States)

2012-04-11

... Shelving and Racks From the People's Republic of China: Final Results of the Countervailing Duty... countervailable duty order on certain kitchen appliance shelving and racks (``Kitchen Racks'') from the People's... Kitchen Appliance Shelving and Racks from the People's Republic of China: Preliminary Results of...

White House Communications Agency (WHCA) Presidential Voice Communications Rack Mount System Mechanical Drawing Package

Science.gov (United States)

2015-12-01

Rack Mount System Mechanical Drawing Package by Steven P Callaway Approved for public release; distribution unlimited...Laboratory White House Communications Agency (WHCA) Presidential Voice Communications Rack Mount System Mechanical Drawing Package by Steven P...Note 3. DATES COVERED (From - To) 04/2013 4. TITLE AND SUBTITLE White House Communications Agency (WHCA) Presidential Voice Communications Rack

Shielding of Medical Facilities. Shielding Design Considerations for PET-CT Facilities

International Nuclear Information System (INIS)

Cruzate, J.A.; Discacciatti, A.P.

2011-01-01

The radiological evaluation of a Positron Emission Tomography (PET) facility consists of the assessment of the annual effective dose both to workers occupationally exposed, and to members of the public. This assessment takes into account the radionuclides involved, the facility features, the working procedures, the expected number of patients per year, and so on. The evaluation embraces the distributions of rooms, the thickness and physical material of walls, floors and ceilings. This work detail the methodology used for making the assessment of a PET facility design taking into account only radioprotection aspects. The assessment results must be compared to the design requirements established by national regulations in order to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. The analysis presented is useful for both, facility designers and regulators. In addition, some guidelines for improving the shielding design and working procedures are presented in order to help facility designer's job. (authors)

Melting of fuel element racks and their recycling as granulate

International Nuclear Information System (INIS)

Quade, U.; Kluth, T.; Kreh, R.

1998-01-01

In order to increase the storage capacity for spent fuel elements in the Spanish NPPs of Almaraz and Asco, the existing racks were replaced by compact one in 1991/1993. The 28 racks from Almaraz NPP were cut on site, packed in 200-I-drums and taken to intermediate storage. For the remaining 28 racks of Asco NPP, ENRESA preferred the melting alternative. To demonstrate the recycling path melting in Germany, a test campaign with six racks was performed in 1997. As a result of this test melt, the limits for Carla melting plant were modified to 200 Bq/g total, α, β, γ 100 Bq/g nuclear fuels, max. 3g/100 kg 2,000 Bq/g total Fe55, H 3 , C-14 and Ni63. After the test melt campaign, the German authorities licensed the import and treatment of the remaining 22 racks on the condition that the waste resulting from the melting process as well as the granules produced were taken back to Spain. The shipment from Asco via France to Germany has been carried out in F 20-ft-IPII containers in accordance with ADR. Size reduction to chargeable dimensions was carried out by a plasma burner and hydraulic shears. For melting, a 3.2 Mg medium frequency induction furnace, operated in a separate housing, was used. For granules production outside this housing, the liquid iron was cast into a 5Mg ladle and then, through a water jet, into the granulating basin. The total mass of 287,659 Kg of 28 fuel elements racks and components of the storage basin yielded 297,914 kg of iron granulate. Secondary waste from melting amounted to 9,920 kg, corresponding to 3.45% of the input mass. The granulating process produced 6,589 kg, corresponding to 2.28% of the total mass to be melted. Radiological analysis of samples taken from the melt and different waste components confirmed the main nuclides Co60, Cs134 and Cs137. Fe55 was highly overestimated by the preliminary analysis. (Author) 2 refs

26 CFR 48.4081-2 - Taxable fuel; tax on removal at a terminal rack.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 16 2010-04-01 2010-04-01 true Taxable fuel; tax on removal at a terminal rack..., Tread Rubber, and Taxable Fuel Taxable Fuel § 48.4081-2 Taxable fuel; tax on removal at a terminal rack... rack are subject to tax and the position holder with respect to the fuel is liable for the tax. (b...

Designing Facilities for Collaborative Operations

Science.gov (United States)

Norris, Jeffrey; Powell, Mark; Backes, Paul; Steinke, Robert; Tso, Kam; Wales, Roxana

2003-01-01

A methodology for designing operational facilities for collaboration by multiple experts has begun to take shape as an outgrowth of a project to design such facilities for scientific operations of the planned 2003 Mars Exploration Rover (MER) mission. The methodology could also be applicable to the design of military "situation rooms" and other facilities for terrestrial missions. It was recognized in this project that modern mission operations depend heavily upon the collaborative use of computers. It was further recognized that tests have shown that layout of a facility exerts a dramatic effect on the efficiency and endurance of the operations staff. The facility designs (for example, see figure) and the methodology developed during the project reflect this recognition. One element of the methodology is a metric, called effective capacity, that was created for use in evaluating proposed MER operational facilities and may also be useful for evaluating other collaboration spaces, including meeting rooms and military situation rooms. The effective capacity of a facility is defined as the number of people in the facility who can be meaningfully engaged in its operations. A person is considered to be meaningfully engaged if the person can (1) see, hear, and communicate with everyone else present; (2) see the material under discussion (typically data on a piece of paper, computer monitor, or projection screen); and (3) provide input to the product under development by the group. The effective capacity of a facility is less than the number of people that can physically fit in the facility. For example, a typical office that contains a desktop computer has an effective capacity of .4, while a small conference room that contains a projection screen has an effective capacity of around 10. Little or no benefit would be derived from allowing the number of persons in an operational facility to exceed its effective capacity: At best, the operations staff would be underutilized

Impact Analysis for Fuel Assemblies in Spent Fuel Storage Rack

International Nuclear Information System (INIS)

Oh, Jinho

2013-01-01

The design and structural integrity evaluation of a spent fuel storage rack (SFSR) utilized for storing and protecting the spent fuel assemblies generated during the operation of a reactor are very important in terms of nuclear safety and waste management. The objective of this study is to show the validity of the SFSR design as well as fuel assembly through a structural integrity evaluation based on a numerical analysis. In particular, a dynamic time history analysis considering the gaps between the fuel assemblies and the walls of the storage cell pipes in the SFSR was performed to check the structural integrity of the fuel assembly and storage cell pipe

Impact Analysis for Fuel Assemblies in Spent Fuel Storage Rack

Energy Technology Data Exchange (ETDEWEB)

Oh, Jinho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-07-01

The design and structural integrity evaluation of a spent fuel storage rack (SFSR) utilized for storing and protecting the spent fuel assemblies generated during the operation of a reactor are very important in terms of nuclear safety and waste management. The objective of this study is to show the validity of the SFSR design as well as fuel assembly through a structural integrity evaluation based on a numerical analysis. In particular, a dynamic time history analysis considering the gaps between the fuel assemblies and the walls of the storage cell pipes in the SFSR was performed to check the structural integrity of the fuel assembly and storage cell pipe.

40 CFR Table 2 to Subpart Bbbbbb... - Applicability Criteria, Emission Limits, and Management Practices for Loading Racks

Science.gov (United States)

2010-07-01

... Limits, and Management Practices for Loading Racks 2 Table 2 to Subpart BBBBBB of Part 63 Protection of... Criteria, Emission Limits, and Management Practices for Loading Racks If you own or operate Then you must 1. A gasoline loading rack(s) at a bulk gasoline terminal with a gasoline throughput of 250,000 gallons...

Surveillance of a Ventilated Rack System for Corynebacterium bovis by Sampling Exhaust-Air Manifolds.

Science.gov (United States)

Manuel, Christopher A; Pugazhenthi, Umarani; Leszczynski, Jori K

2016-01-01

Corynebacterium bovis causes an opportunistic infection of nude (Foxn1, nu/nu) mice, leading to nude mouse hyperkeratotic dermatitis (scaly skin disease). Enzootic in many nude mouse colonies, C. bovis spreads rapidly to naive nude mice, despite modern husbandry practices, and is very difficult to eradicate. To facilitate rapid detection in support of eradication efforts, we investigated a surveillance method based on quantitative real-time PCR (qPCR) evaluation of swabs collected from the horizontal exhaust manifold (HEM) of an IVC rack system. We first evaluated the efficacy of rack sanitation methods for removing C. bovis DNA from the HEM of racks housing endemic colonies of infected nude mice. Pressurized water used to flush the racks' air exhaust system followed by a standard rack-washer cycle was ineffective in eliminating C. bovis DNA. Only after autoclaving did all sanitized racks test negative for C. bovis DNA. We then measured the effects of stage of infection (early or established), cage density, and cage location on the rack on time-to-detection at the HEM. Stage of infection significantly affected time-to-detection, independent of cage location. Early infections required 7.3 ± 1.2 d whereas established infections required 1 ± 0 d for detection of C. bovis at the HEM. Cage density influenced the quantity of C. bovis DNA detected but not time-to-detection. The location of the cage on the rack affected the time-to-detection only during early C. bovis infections. We suggest that qPCR swabs of HEM are useful during the routine surveillance of nude mouse colonies for C. bovis infection.

Depletion of WRN protein causes RACK1 to activate several protein kinase C isoforms

DEFF Research Database (Denmark)

Massip, L; Garand, C; Labbé, A

2010-01-01

show that a knock down of the WRN protein in normal human fibroblasts induces phosphorylation and activation of several protein kinase C (PKC) enzymes. Using a tandem affinity purification strategy, we found that WRN physically and functionally interacts with receptor for activated C-kinase 1 (RACK1......), a highly conserved anchoring protein involved in various biological processes, such as cell growth and proliferation. RACK1 binds strongly to the RQC domain of WRN and weakly to its acidic repeat region. Purified RACK1 has no impact on the helicase activity of WRN, but selectively inhibits WRN exonuclease...... activity in vitro. Interestingly, knocking down RACK1 increased the cellular frequency of DNA breaks. Depletion of the WRN protein in return caused a fraction of nuclear RACK1 to translocate out of the nucleus to bind and activate PKCdelta and PKCbetaII in the membrane fraction of cells. In contrast...

Thermal Evaluation of Storage Rack with an Advanced Neutron Absorber during Normal Operation

Energy Technology Data Exchange (ETDEWEB)

Lee, Hee-Jae; Kim, Mi-Jin; Sohn, Dong-Seong [UNIST, Ulsan (Korea, Republic of)

2016-10-15

The storage capacity of the domestic wet storage site is expected to reach saturation from Hanbit in 2024 to Sin-wolseong in 2038 and accordingly management alternatives are urgently taken. Since installation of the dense rack is considered in the short term, it is necessary to urgently develop an advanced neutron absorber which can be applied to a spent nuclear fuel storage facility. Neutron absorber is the material for controlling the reactivity. A material which has excellent thermal neutron absorption ability, high strength and corrosion resistance must be selected as the neutron absorber. Existing neutron absorbers are made of boron which has a good thermal absorption ability such as BORAL and METAMIC. However, possible problems have been reported in using the boron-based neutron absorber for wet storage facility. Gadolinium is known to have higher neutron absorption cross-section than that of boron. And the strength of duplex stainless steel is about 1.5 times higher than stainless steel 304 which has been frequently used as a structural material. Therefore, duplex stainless steel which contains gadolinium is in consideration as an advanced neutron absorber. Temperature distribution is shown in figure 4. In pool bottom region near the inlet shows a relatively low tendency and heat generated from the fuel assemblies is transmitted to the pool upper region by the vertical flow. Also, temperature gradient appear in rack structures for the axial direction and temperature is uniformly distributed in the pool upper region. Table 1 presents the calculated results. The maximum temperature is 306.63K and does not exceed the 333.15K (60℃). The maximum temperature of the neutron absorber is 306.48K.

Design of the PRIDE Facility

International Nuclear Information System (INIS)

You, Gil Sung; Choung, Won Myung; Lee, Eun Pyo; Cho, Il Je; Kwon, Kie Chan; Hong, Dong Hee; Lee, Won Kyung; Ku, Jeong Hoe

2009-01-01

From 2007, KAERI is developing a PyRoprocess Integrated inactive DEmonstration facility (the PRIDE facility). The maximum annual treatment capacity of this facility will be a 10 ton-HM. The process will use a natural uranium feed material or a natural uranium mixed with some surrogate material for a simulation of a spent fuel. KAERI has also another plan to construct a demonstration facility which can treat a real spent fuel by pyroprocessing. This facility is called by ESPF, Engineering Scale Pyroprocess Facility. The ESPF will have the same treatment capability of spent fuel with the PRIDE facility. The only difference between the PRIDE and the ESPF is a radiation shielding capability. From the PRIDE facility designing works and demonstration with a simulated spent fuel after construction, it will be able to obtain the basic facility requirements, remote operability, interrelation properties between process equipment for designing of the ESPF. The flow sheet of the PRIDE processes is composed of five main processes, such as a decladding and voloxidation, an electro-reduction, an electrorefining, an electro-winning, and a salt waste treatment. The final products from the PRIDE facility are a simulated TRU metal and U metal ingot

ISS Payload Racks Automated Flow Control Calibration Method

Science.gov (United States)

Simmonds, Boris G.

2003-01-01

Payload Racks utilize MTL and/or LTL station water for cooling of payloads and avionics. Flow control range from valves of fully closed, to up to 300 Ibmhr. Instrument accuracies are as high as f 7.5 Ibm/hr for flow sensors and f 3 Ibm/hr for valve controller, for a total system accuracy of f 10.5 Ibm/hr. Improved methodology was developed, tested and proven that reduces accuracy of the commanded flows to less than f 1 Ibmhr. Uethodology could be packed in a "calibration kit" for on- orbit flow sensor checkout and recalibration, extending the rack operations before return to earth. -

78 FR 54450 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Preliminary...

Science.gov (United States)

2013-09-04

... Shelving and Racks From the People's Republic of China: Preliminary Results of Antidumping Duty... the antidumping duty order on certain kitchen appliance shelving and racks from the People's Republic...\\ is certain kitchen appliance shelving and racks. The subject merchandise is currently classifiable...

The fabrication of plastic cages for suspension in mass air flow racks.

Science.gov (United States)

Nielsen, F H; Bailey, B

1979-08-01

A cage for suspension in mass air flow racks was constructed of plastic and used to house rats. Little or no difficulty was encountered with the mass air flow rack-suspended cage system during the 4 years it was used for the study of trace elements.

77 FR 72324 - Certain Kitchen Appliance Shelving and Racks from the People's Republic of China: Countervailing...

Science.gov (United States)

2012-12-05

... Shelving and Racks from the People's Republic of China: Countervailing Duty Administrative Review, 2010... countervailing duty order on certain kitchen appliance shelving and racks from the People's Republic of China. See Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Countervailing...

Kale BoRACK1 is involved in the plant response to salt stress and Peronospora brassicae Gaumann.

Science.gov (United States)

Li, Da-Hong; Shen, Fu-Jia; Li, Hong-Yan; Li, Wei

2017-06-01

The receptor for activated C kinase 1 (RACK1) belongs to a protein subfamily containing a tryptophan-aspartic acid-domain (WD) repeat structure. Compelling evidence indicates that RACK1 can interact with many signal molecules and affect different signal transduction pathways. In this study, a kale (Brassica oleracea var. acephala f.tricolor) RACK1 gene (BoRACK1) was cloned by RT-PCR. The amino acid sequence of BoRACK1 had seven WD repeats in which there were typical GH (glycine-histidine) and WD dipeptides. Comparison with AtRACK1 from Arabidopsis revealed 87.1% identity at the amino acid level. Expression pattern analysis by RT-PCR showed that BoRACK1 was expressed in all analyzed tissues of kale and that its transcription in leaves was down-regulated by salt, abscisic acid, and H 2 O 2 at a high concentration. Overexpression of BoRACK1 in kale led to a reduction in symptoms caused by Peronospora brassicae Gaumann on kale leaves. The expression levels of the pathogenesis-related protein genes, PR-1 and PRB-1, increased 2.5-4-fold in transgenic kale, and reactive oxygen species production was more active than in the wild-type. They also exhibited increased tolerance to salt stress in seed germination. H 2 O 2 may also be involved in the regulation of BoRACK1 during seed germination under salt stress. Quantitative real-time PCR analyses showed that the transcript levels of BoRbohs genes were significantly higher in overexpression of BoRACK1 transgenic lines. Yeast two-hybrid assays showed that BoRACK1 could interact with WNK8, eIF6, RAR1, and SGT1. This study and previous work lead us to believe that BoRACK1 may form a complex with regulators of plant salt and disease resistance to coordinate kale reactions to pathogens. Copyright © 2017 Elsevier GmbH. All rights reserved.

40 CFR 60.32c - Designated facilities.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Designated facilities. 60.32c Section 60.32c Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the...

Random Access Frames (RAF): Alternative to Rack and Standoff for Deep Space Habitat Outfitting

Science.gov (United States)

Howe, A. Scott; Polit-Casillas, Raul

2014-01-01

A modular Random Access Frame (RAF) system is proposed as an alternative to the International Standard Payload Rack (ISPR) for internal module layout and outfitting in a Deep Space Habitat (DSH). The ISPR approach was designed to allow for efficient interchangeability of payload and experiments for the International Space Station (ISS) when frequent resupply missions were available (particularly the now-retired Space Shuttle). Though the standard interface approach to the ISPR system allowed integration of subsystems and hardware from a variety of sources and manufacturers, the heavy rack and standoff approach may not be appropriate when resupply or swap-out capabilities are not available, such as on deep space, long-duration missions. The lightweight RAF concept can allow a more dense packing of stowage and equipment, and may be easily broken down for repurposing or reuse. Several example layouts and workstations are presented.

Materials Science Research Rack Onboard the International Space Station Hardware and Operations

Science.gov (United States)

Lehman, John R.; Frazier, Natalie C.; Johnson, Jimmie

2012-01-01

The Materials Science Research Rack (MSRR) is a research facility developed under a cooperative research agreement between NASA and ESA for materials science investigations on the International Space Station (ISS). MSRR was launched on STS-128 in August 2009, and is currently installed in the U.S. Destiny Laboratory Module. Since that time, MSRR has performed virtually flawlessly, logging more than 620 hours of operating time. The MSRR accommodates advanced investigations in the microgravity environment on the ISS for basic materials science research in areas such as solidification of metals and alloys. The purpose is to advance the scientific understanding of materials processing as affected by microgravity and to gain insight into the physical behavior of materials processing. MSRR allows for the study of a variety of materials including metals, ceramics, semiconductor crystals, and glasses. Materials science research benefits from the microgravity environment of space, where the researcher can better isolate chemical and thermal properties of materials from the effects of gravity. With this knowledge, reliable predictions can be made about the conditions required on Earth to achieve improved materials. MSRR is a highly automated facility with a modular design capable of supporting multiple types of investigations. Currently the NASA-provided Rack Support Subsystem provides services (power, thermal control, vacuum access, and command and data handling) to the ESA developed Materials Science Laboratory (MSL) which accommodates interchangeable Furnace Inserts (FI). Two ESA-developed FIs are presently available on the ISS: the Low Gradient Furnace (LGF) and the Solidification and Quenching Furnace (SQF). Sample-Cartridge Assemblies (SCAs), each containing one or more material samples, are installed in the FI by the crew and can be processed at temperatures up to 1400 C. Once an SCA is installed, the experiment can be run by automatic command or science conducted via

77 FR 61385 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Antidumping...

Science.gov (United States)

2012-10-09

... Shelving and Racks From the People's Republic of China: Antidumping Duty Administrative Review, 2010-2011... administrative review of the antidumping duty order on certain kitchen appliance shelving and racks from the... INFORMATION: Scope of the Order The scope of this order consists of shelving and racks for refrigerators...

77 FR 12811 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Partial...

Science.gov (United States)

2012-03-02

... Shelving and Racks From the People's Republic of China: Partial Rescission of Antidumping Duty... review of the antidumping duty order on certain kitchen appliance shelving and racks from the People's... Appliance Shelving and Racks from the People's Republic of China, dated January 10, 2012; and Letter to the...

76 FR 62765 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Preliminary...

Science.gov (United States)

2011-10-11

... Shelving and Racks From the People's Republic of China: Preliminary Results of the First Administrative... review of the antidumping duty order on certain kitchen appliance shelving and racks from the People's... administrative review of certain kitchen appliance shelving and racks from the PRC for the period March 5, 2009...

40 CFR 60.32b - Designated facilities.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Designated facilities. 60.32b Section... facilities. (a) The designated facility to which these guidelines apply is each municipal waste combustor... subpart are not considered in determining whether the unit is a modified or reconstructed facility under...

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.

Design of spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes the general safety requirements applicable to the design of both wet and dry spent fuel storage facilities; Section 3 deals with the design requirements specific to either wet or dry storage. Recommendations for the auxiliary systems of any storage facility are contained in Section 4; these are necessary to ensure the safety of the system and its safe operation. Section 5 provides recommendations for establishing the quality assurance system for a storage facility. Section 6 discusses the requirements for inspection and maintenance that must be considered during the design. Finally, Section 7 provides guidance on design features to be considered to facilitate eventual decommissioning. 18 refs

Design of the PISCES-Upgrade facility

International Nuclear Information System (INIS)

Waganer, L.M.; Doerner, R.

1994-01-01

The PISCES-Upgrade facility is currently in the design and fabrication phases for the University of California. McDonnell Douglas is under contract to develop this experimental facility in order to enhance the capability for investigation of fusion materials erosion-redeposition and edge plasma behaviors. The advance in facility capability requires innovative design approaches and application of sophisticated analysis techniques

National Ignition Facility system design requirements conventional facilities SDR001

International Nuclear Information System (INIS)

Hands, J.

1996-01-01

This System Design Requirements (SDR) document specifies the functions to be performed and the minimum design requirements for the National Ignition Facility (NIF) site infrastructure and conventional facilities. These consist of the physical site and buildings necessary to house the laser, target chamber, target preparation areas, optics support and ancillary functions

26 CFR 48.4081-3 - Taxable fuel; taxable events other than removal at the terminal rack.

Science.gov (United States)

2010-04-01

... at the terminal rack. 48.4081-3 Section 48.4081-3 Internal Revenue INTERNAL REVENUE SERVICE...; taxable events other than removal at the terminal rack. (a) Overview. Although tax is imposed when taxable fuel is removed from the terminal at the rack, tax also is imposed in certain other situations...

16 CFR Figure 3 to Part 1610 - Specimen Holder Supported in Specimen Rack

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Specimen Holder Supported in Specimen Rack 3 Figure 3 to Part 1610 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FLAMMABLE FABRICS ACT... Holder Supported in Specimen Rack ER25MR08.002 ...

Fixing Trailer Hitch for Roof Rack of Cargos

Directory of Open Access Journals (Sweden)

Darina Matisková

2017-02-01

Full Text Available This article presents a new technical solution of fixing trailer hitch which serves as a connection between single track vehicle and cargo, mainly light trailer. They are manufactured from steel girder and nets which are constructed by point welding. They are designed to indicate the necessary solidity and the required load bearing capacity of the cargo. The application of roof racks is universal and these products are in great demand in the field of game management. There are a lot of trailer hitches which the manufacturers tailor to customers´ demands. The stated technical solution is subject of published industrial utility model at the Industrial property office of the Slovak republic.

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...

Review of the Tritium Extraction Facility design

International Nuclear Information System (INIS)

Barton, R.W.; Bamdad, F.; Blackman, J.

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the US Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Review of the Tritium Extraction Facility Design

International Nuclear Information System (INIS)

Ronald W. Barton; Farid Bamdad; Joel Blackman

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the U.S. Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Facility Safeguardability Analysis In Support of Safeguards-by-Design

Energy Technology Data Exchange (ETDEWEB)

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

2010-07-01

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

Tests and calculations on a scale one spent fuel storage rack

International Nuclear Information System (INIS)

Moudrik, R.; Queval, J.C.; Gantenbein, F.; Trollat, C.

1995-01-01

This paper deals with the behaviour of racks of PWR reactor (pressurized water reactor) set in a pool, in case of an earthquake. Several parameters are taken into account: fluid, loading, gaps,... The paper presents some tests that can be implemented on the racks, in order to valid them before use. Moreover, a program and the results are presented, as well as calculation. (TEC). 2 refs., 9 figs

Criticality and Its Uncertainty Analysis of Spent Fuel Storage Rack for Research Reactor

International Nuclear Information System (INIS)

Han, Tae Young; Park, Chang Je; Lee, Byung Chul

2011-01-01

For evaluating the criticality safety of spent fuel storage rack in an open pool type research reactor, a permissible upper limit of criticality should be determined. It can be estimated from the criticality upper limit presented by the regulatory guide and an uncertainty of criticality calculation. In this paper, criticalities for spent fuel storage rack are carried out at various conditions. The calculation uncertainty of MCNP system is evaluated from the calculation results for the benchmark experiments. Then, the upper limit of criticality is determined from the uncertainties and the calculated criticality of the spent fuel storage rack is evaluated

78 FR 21594 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Final Results...

Science.gov (United States)

2013-04-11

... Shelving and Racks From the People's Republic of China: Final Results of Countervailing Duty Administrative... countervailing duty (``CVD'') order on certain kitchen appliance shelving and racks from the People's Republic of...\\ See Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Countervailing...

78 FR 78815 - Certain Kitchen Appliance Shelving and Racks from the People's Republic of China: Rescission of...

Science.gov (United States)

2013-12-27

... Shelving and Racks from the People's Republic of China: Rescission of Antidumping Duty Administrative... administrative review of the antidumping duty order on certain kitchen appliance shelving and racks from the... on certain kitchen appliance shelving and racks from the PRC.\\1\\ On September 30, 2013, the...

77 FR 21734 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Final Results...

Science.gov (United States)

2012-04-11

... Shelving and Racks From the People's Republic of China: Final Results and Partial Rescission of First... duty order on certain kitchen appliance shelving and racks from the People's Republic of China (``PRC... Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Preliminary Results of...

Dioxin modulates expression of receptor for activated C kinase (RACK-1) in developing neurons

Energy Technology Data Exchange (ETDEWEB)

Yang, J.H.; Kim, S.Y.; Lee, H.G.; Kim, M.Y.; Lee, J.H.; Chae, W.G. [Catholic Univ. of Daegu, Dept. of Pharmacology/Toxicology, Daegu (Korea)

2004-09-15

TCDD is sensitive to the central nerve system of the developing brain. The TCDD-induced neurodevelopmental deficits include the cognitive disability and motor dysfunction. While TCDD may lead to neurodevelopmental and neurobehavioral deficit, it is not known which molecular substances are intracellular targets for TCDD. Since TCDD accumulates in brain and the brain contains the Ah receptor, it is possible that TCDD may act at the target site such as cerebellum, which is responsible for cognitive abilities and motor function. A recent in vitro studies using cerebellar granule cells demonstrated a translocation of PKC-{alpha} and {epsilon} following the TCDD or PCB exposure. One of the most pivotal second messenger molecules involved in neuronal function and development is protein kinase C (PKC). PKC signaling pathways have been implicated as an important factor in learning and memory processes. PKC signaling events are optimized by the adaptor proteins, which organize PKCs near their selective substrates and away from others. RACK-1(receptor for activated C-kinase) is one of adaptor proteins that anchor the activated PKC at the site of translocation 6. RACKs bind PKC only in the presence of PKC activators. RACKs are 30- and 36-kDa proteins located in cytoskeletal compartment and play a key role in PKC activation and in membrane amchoring. Since different PKC isoforms translocate to distinct subcellular sites on activation, it is suggested that isoform-specific RACK may be present. Activation of certain PKC isoforms (PKC-a and {beta}II) is preferentially associated with RACK-1. While TCDD modulates PKC signaling pathway, role of RACK-1 on TCDD-mediated signaling pathway is not known. To identify the intracellular target for TCDD and understand a mechanism of signaling pathway in the developing brain, the present study attempted to analyze effects of RACK-1 in the cerebellar granule cells following TCDD exposure.

77 FR 82 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Extension of...

Science.gov (United States)

2012-01-03

... Shelving and Racks From the People's Republic of China: Extension of Time Limit for the Final Results of... administrative review of the countervailing duty order on certain kitchen appliance shelving and racks from the... Kitchen Appliance Shelving and Racks From the People's Republic of China: Preliminary Results of the...

78 FR 5414 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China; 2010-2011...

Science.gov (United States)

2013-01-25

... Shelving and Racks From the People's Republic of China; 2010-2011; Final Results of Antidumping Duty... of the antidumping duty order on certain kitchen appliance shelving and racks from the People's... September 1, 2010, through August 31, 2011. \\1\\ See Certain Kitchen Appliance Shelving and Racks From the...

77 FR 22559 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Extension of...

Science.gov (United States)

2012-04-16

... Shelving and Racks From the People's Republic of China: Extension of Time Limit for the Preliminary Results... administrative review of the antidumping duty order on certain kitchen appliance shelving and racks from the... Appliance Shelving and Racks from the People's Republic of China: Selection of an Additional Mandatory...

76 FR 20950 - Certain Kitchen Appliance Shelving and Racks From the People's Republic of China: Extension of...

Science.gov (United States)

2011-04-14

... Shelving and Racks From the People's Republic of China: Extension of Time Limits for the Preliminary... appliance shelving and racks from the People's Republic of China (``PRC'') for the period March 5, 2009... Racks from the People's Republic of China,'' dated January 20, 2011. The Department sent its antidumping...

Definition of a RACK1 Interaction Network in Drosophila melanogaster Using SWATH-MS.

Science.gov (United States)

Kuhn, Lauriane; Majzoub, Karim; Einhorn, Evelyne; Chicher, Johana; Pompon, Julien; Imler, Jean-Luc; Hammann, Philippe; Meignin, Carine

2017-07-05

Receptor for Activated protein C kinase 1 (RACK1) is a scaffold protein that has been found in association with several signaling complexes, and with the 40S subunit of the ribosome. Using the model organism Drosophila melanogaster , we recently showed that RACK1 is required at the ribosome for internal ribosome entry site (IRES)-mediated translation of viruses. Here, we report a proteomic characterization of the interactome of RACK1 in Drosophila S2 cells. We carried out Label-Free quantitation using both Data-Dependent and Data-Independent Acquisition (DDA and DIA, respectively) and observed a significant advantage for the Sequential Window Acquisition of all THeoretical fragment-ion spectra (SWATH) method, both in terms of identification of interactants and quantification of low abundance proteins. These data represent the first SWATH spectral library available for Drosophila and will be a useful resource for the community. A total of 52 interacting proteins were identified, including several molecules involved in translation such as structural components of the ribosome, factors regulating translation initiation or elongation, and RNA binding proteins. Among these 52 proteins, 15 were identified as partners by the SWATH strategy only. Interestingly, these 15 proteins are significantly enriched for the functions translation and nucleic acid binding. This enrichment reflects the engagement of RACK1 at the ribosome and highlights the added value of SWATH analysis. A functional screen did not reveal any protein sharing the interesting properties of RACK1, which is required for IRES-dependent translation and not essential for cell viability. Intriguingly however, 10 of the RACK1 partners identified restrict replication of Cricket paralysis virus (CrPV), an IRES-containing virus. Copyright © 2017 Kuhn et al.

40 CFR Table 5 to Subpart Ffff of... - Emission Limits and Work Practice Standards for Transfer Racks

Science.gov (United States)

2010-07-01

... Standards for Transfer Racks 5 Table 5 to Subpart FFFF of Part 63 Protection of Environment ENVIRONMENTAL... Limits and Work Practice Standards for Transfer Racks As required in § 63.2475, you must meet each emission limit and work practice standard in the following table that applies to your transfer racks: For...

Updates on HRF Payloads Operations in Columbus ATCS

Science.gov (United States)

DePalo, Savino; Wright, Bruce D.; La,e Robert E.; Challis, Simon; Davenport, Robert; Pietrafesa, Donata

2011-01-01

The NASA developed Human Research Facility 1 (HRF1) and Human Research Facility (HRF2) experiment racks have been operating in the European Space Agency (ESA) Columbus module of the International Space Station (ISS) since Summer 2008. The two racks are of the same design. Since the start of operations, unexpected pressure spikes were observed in the Columbus module's thermal-hydraulic system during the racks activation sequence. The root cause of these spikes was identified in the activation command sequence in the Rack Interface Controller (RIC), which controls the flow of thermal-hydraulic system fluid through the rack. A new Common RIC Software (CRS) release fixed the bug and was uploaded on both racks in late 2009. This paper gives a short introduction to the topic, describes the Columbus module countermeasures to mitigate the spikes, describes the ground validation test of the new software, and describes the flight checks performed before and after the final upload. Finally, the new on-orbit test designed to further simplify the racks hydraulic management is presented.

Implications of natural occlusion of ventilated racks on ammonia and sanitation practices.

Science.gov (United States)

Creamer, Michelle A; Petty, Joann; Martin, Tara; Bergdall, Valerie; Hickman-Davis, Judy M

2014-03-01

Examination of ventilated rat racks prior to semiannual sanitation revealed silicone nozzles and ventilation ports that were partially or completely occluded with granular debris. We subsequently sought to document performance standards for rack sanitation and investigate the effect of ventilation port occlusion on rack function and animal husbandry practices. We hypothesized that individually ventilated cages with occluded airflow would require more frequent cage changes, comparable to those for static cages (that is, every 3 to 4 d). Sprague-Dawley rats were housed under one of 4 conditions: no airflow occlusion, occluded air-supply inlet, occluded air-exhaust outlet, and occlusion of both inlet and outlet. Cages were changed when daily ammonia concentration exceeded 20 ppm or after 14 d had elapsed. Most cages with unoccluded or partial airflow occlusion remained below the 20 ppm limit until day 12 or 13. Cages with occlusion of both inlet and outlet exceeded 20 ppm ammonia by as early as day 5. Airflow was significantly lower in cages with occlusion of both inlet and outlet airflow. Weekly inspection revealed that occlusion of ventilation ports was detectable by 3 mo after semiannual sanitation. This study demonstrates that silicone nozzles should be removed prior to rack sanitation to improve the effectiveness of cleaning ventilation ports and nozzles. While the rack is in use, silicone nozzles and ventilation ports should be inspected regularly to identify occlusion that is likely to diminish environmental quality in the cage. Intracage ammonia levels are significantly higher when both inlet and outlet airflow are occluded.

Facility design, construction, and operation

International Nuclear Information System (INIS)

1995-04-01

France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l'Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l'Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec's contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides' all of the basic information in these areas and reflects actual experience to date

76 FR 27990 - Certain Kitchen Shelving and Racks From the People's Republic of China: Extension of Time Limit...

Science.gov (United States)

2011-05-13

... Racks From the People's Republic of China: Extension of Time Limit for Preliminary Results of... countervailing duty order on certain kitchen appliance shelving and racks from the People's Republic of China... the Countervailing Duty Administrative Review of Certain Kitchen Appliance Shelving and Racks from the...

Robins Air Force Base Solar Cogeneration Facility design

Energy Technology Data Exchange (ETDEWEB)

Pierce, B.L.; Bodenschatz, C.A.

1982-06-01

A conceptual design and a cost estimate have been developed for a Solar Cogeneration Facility at Robins Air Force Base. This demonstration solar facility was designed to generate and deliver electrical power and process steam to the existing base distribution systems. The facility was to have the potential for construction and operation by 1986 and make use of existing technology. Specific objectives during the DOE funded conceptual design program were to: prepare a Solar Cogeneration Facility (overall System) Specification, select a preferred configuration and develop a conceptual design, establish the performance and economic characteristics of the facility, and prepare a development plan for the demonstration program. The Westinghouse team, comprised of the Westinghouse Advanced Energy Systems Division, Heery and Heery, Inc., and Foster Wheeler Solar Development Corporation, in conjunction with the U.S. Air Force Logistics Command and Georgia Power Company, has selected a conceptual design for the facility that will utilize the latest DOE central receiver technology, effectively utilize the energy collected in the application, operate base-loaded every sunny day of the year, and be applicable to a large number of military and industrial facilities throughout the country. The design of the facility incorporates the use of a Collector System, a Receiver System, an Electrical Power Generating System, a Balance of Facility - Steam and Feedwater System, and a Master Control System.

TCR triggering induces the formation of Lck-RACK1-actinin-1 multiprotein network affecting Lck redistribution

Directory of Open Access Journals (Sweden)

Ondrej Ballek

2016-10-01

Full Text Available The initiation of T-cell signaling is critically dependent on the function of the member of Src family tyrosine kinases (SFKs, Lck. Upon TCR triggering, Lck kinase activity induces the nucleation of signal-transducing hubs that regulate the formation of complex signaling network and cytoskeletal rearrangement. In addition, the delivery of Lck function requires rapid and targeted membrane redistribution, but the mechanism underpinning this process is largely unknown. To gain insight into this process, we considered previously described proteins that could assist in this process via their capacity to interact with kinases and regulate their intracellular translocations. An adaptor protein, Receptor for Activated C Kinase 1 (RACK1, was chosen as a viable option and its capacity to bind Lck and aid the process of activation-induced redistribution of Lck was assessed. Our microscopic observation showed that T-cell activation induces a rapid, concomitant and transient co-redistribution of Lck and RACK1 into the forming immunological synapse. Consistent with this observation, the formation of transient RACK1-Lck complexes were detectable in primary CD4+ T-cells with their maximum levels peaking 10 seconds after TCR-CD4 co-aggregation. Moreover, RACK1 preferentially binds to a pool of kinase active pY394Lck which co-purifies with high molecular weight cellular fractions. The formation of RACK1-Lck complexes depends on functional SH2 and SH3 domains of Lck and includes several other signaling and cytoskeletal elements that transiently bind the complex. Notably, the F-actin-crosslinking protein, α-actinin-1, binds to RACK1 only in the presence of kinase active Lck suggesting that the formation of RACK1-pY394Lck-α-actinin-1 complex serves as a signal module coupling actin cytoskeleton bundling with productive TCR/CD4 triggering. In addition, the treatment of CD4+ T-cells with nocodazole, which disrupts the microtubular network, also blocked the formation

Ventilation design for new plutonium recovery facility

International Nuclear Information System (INIS)

Oliver, A.J.; Amos, C.L.

1975-01-01

In 1972 the Atomic Energy Commission (AEC) issued revised guidelines on ''Minimum Design Criteria for New Plutonium Facilities.'' With these criteria as guidelines, a new Plutonium Recovery Facility is being designed and constructed at the AEC Rocky Flats Plant. The methods by which the confinement of contamination and air treatment are being handled in this facility are described. (U.S.)

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

Designation of facility usage categories for Hanford Site facilities

International Nuclear Information System (INIS)

Wodrich, D.; Ellingson, D.; Scott, M.; Schade, A.

1991-01-01

This report summarizes the Hanford Site methodology used to ensure facility compliance with the natural phenomena design criteria set forth in the US Department of Energy orders and guidance. In particular, the Hanford Site approach to designating a suitable facility open-quotes Usage Category,close quotes is presented. The current Hanford Site methodology for Usage Category designation is based on an engineered feature's safety function and on the feature's assigned Safety Class. At the Hanford Site, Safety Class assignments are deterministic in nature and are based on the consequences of failure, without regard to the likelihood of occurrence. The report also proposes a risk-based approach to Usage Category designation, which is being considered for future application at the Hanford Site. To establish a proper Usage Category designation, the safety analysis and engineering design processes must be coupled. This union produces a common understanding of the safety function(s) to be accomplished by the design feature(s) and a sound basis for the assignment of Usage Categories to the appropriate systems, structures, and components

Conceptual design report, Sodium Storage Facility, Fast Flux Test Facility, Project F-031

International Nuclear Information System (INIS)

Shank, D.R.

1995-01-01

The Sodium Storage Facility Conceptual Design Report provides conceptual design for construction of a new facility for storage of the 260,000 gallons of sodium presently in the FFTF plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium

Seismic evaluation of BWR spent fuel storage racks using actual damping by vibration test in water

International Nuclear Information System (INIS)

Yamasaki, Hiroto; Iwakura, Shigeyoshi; Imaoka, Tetsuo; Okumura, Kazue; Orita, Syuichi; Namita, Yoshio

2010-01-01

Damping value for BWR spent fuel storage racks has been used 1 percent damping, which is applied to welded steel structures in air as defined JEAG4601. However, it is considered that the actual damping is higher than that of the above mentioned, because of its underwater installation. This report shows the actual damping value of the Check Arrayed Rack by vibration test in water and Evaluation by the analysis of rack using actual damping. (author)

40 CFR Table 3 to Subpart Eeee of... - Operating Limits-High Throughput Transfer Racks

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits-High Throughput Transfer Racks 3 Table 3 to Subpart EEEE of Part 63 Protection of Environment ENVIRONMENTAL PROTECTION... Throughput Transfer Racks As stated in § 63.2346(e), you must comply with the operating limits for existing...

The scaffold protein RACK1 is a target of endocrine disrupting chemicals (EDCs) with important implication in immunity

Energy Technology Data Exchange (ETDEWEB)

Buoso, Erica; Galasso, Marilisa; Ronfani, Melania [Dipartimento di Scienze del Farmaco, Università degli Studi di Pavia, Viale Taramelli 12/14, 27100 Pavia (Italy); Papale, Angela; Galbiati, Valentina [Laboratory of Toxicology, Dipartimento di Scienze Farmacologiche e Biomolecolari, Università degli Studi di Milano, Via Balzaretti 9, 20133 Milano (Italy); Eberini, Ivano [Laboratorio di Biochimica e Biofisica Computazionale, Dipartimento di Scienze Farmacologiche e Biomolecolari, Università degli Studi di Milano, Milan (Italy); Marinovich, Marina [Laboratory of Toxicology, Dipartimento di Scienze Farmacologiche e Biomolecolari, Università degli Studi di Milano, Via Balzaretti 9, 20133 Milano (Italy); Racchi, Marco [Dipartimento di Scienze del Farmaco, Università degli Studi di Pavia, Viale Taramelli 12/14, 27100 Pavia (Italy); Corsini, Emanuela, E-mail: emanuela.corsini@unimi.it [Laboratory of Toxicology, Dipartimento di Scienze Farmacologiche e Biomolecolari, Università degli Studi di Milano, Via Balzaretti 9, 20133 Milano (Italy)

2017-06-15

We recently demonstrated the existence of a complex hormonal balance between steroid hormones in the control of RACK1 (Receptor for Activated C Kinase 1) expression and immune activation, suggesting that this scaffold protein may also be targeted by endocrine disrupting chemicals (EDCs). As a proof of concept, we investigated the effect of the doping agent nandrolone, an androgen receptor (AR) agonist, and of p,p′DDT (dichlorodiphenyltrichloroethane) and its main metabolite p,p′DDE (dichlorodiphenyldichloroethylene), a weak and strong AR antagonist, respectively, on RACK1 expression and innate immune response. In analogy to endogenous androgens, nandrolone induced a dose-related increase in RACK1 transcriptional activity and protein expression, resulting in increased LPS-induced IL-8 and TNF-α production and proliferation in THP-1 cells. Conversely, p,p′DDT and p,p′DDE significantly decrease RACK1 expression, LPS-induced cytokine production and CD86 expression; with p,p′DDE exerting a stronger repressor effect than p,p′DDT, consistent with its stronger AR antagonistic effect. These results indicate that RACK1 could be a relevant target of EDCs, responding in opposite ways to agonist or antagonist of AR, representing a bridge between the endocrine system and the innate immune system. - Highlights: • RACK1 expression can be induced by AR agonists with a consequent enhancement of the response to LPS. • RACK1 can be negatively modulated by the AR antagonists DDT and its main metabolite p,p′DDE. • RACK1 can be a relevant target of EDCs, representing a bridge between the endocrine system and the immune system.

Evaluation of AMPX-KENO benchmark calculations for high-density spent fuel storage racks

International Nuclear Information System (INIS)

Turner, S.E.; Gurley, M.K.

1981-01-01

The AMPX-KENO computer code package is commonly used to evaluate criticality in high-density spent fuel storage rack designs. Consequently, it is important to know the reliability that can be placed on such calculations and whether or not the results are conservative. This paper evaluates a series of AMPX-KENO calculations which have been made on selected critical experiments. The results are compared with similar analyses reported in the literature by the Oak Ridge National Laboratory and BandW. 8 refs

Landfill gas management facilities design guidelines

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-03-15

In British Columbia, municipal solid waste landfills generate over 1000 tonnes of methane per year; landfill gas management facilities are required to improve the environmental performance of solid waste landfills. The aim of this document, developed by the British Columbia Ministry of the Environment, is to provide guidance for the design, installation, and operation of landfill gas management facilities to address odor and pollutant emissions issues and also address health and safety issues. A review of technical experience and best practices in landfill gas management facilities was carried out, as was as a review of existing regulations related to landfill gas management all over the world. This paper provides useful information to landfill owners, operators, and other professionals for the design of landfill gas management facilities which meet the requirements of landfill gas management regulations.

Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

International Nuclear Information System (INIS)

1985-09-01

The Basis for Design established the functional requirements and design criteria for an Integral Monitored Retrievable Storage (MRS) facility. The MRS Facility design, described in this report, is based on those requirements and includes all infrastructure, facilities, and equipment required to routinely receive, unload, prepare for storage, and store spent fuel (SF), high-level waste (HLW), and transuranic waste (TRU), and to decontaminate and return shipping casks received by both rail and truck. The facility is complete with all supporting facilities to make the MRS Facility a self-sufficient installation

Carbon Dioxide Dispersion in the Combustion Integrated Rack Simulated Numerically

Science.gov (United States)

Wu, Ming-Shin; Ruff, Gary A.

2004-01-01

When discharged into an International Space Station (ISS) payload rack, a carbon dioxide (CO2) portable fire extinguisher (PFE) must extinguish a fire by decreasing the oxygen in the rack by 50 percent within 60 sec. The length of time needed for this oxygen reduction throughout the rack and the length of time that the CO2 concentration remains high enough to prevent the fire from reigniting is important when determining the effectiveness of the response and postfire procedures. Furthermore, in the absence of gravity, the local flow velocity can make the difference between a fire that spreads rapidly and one that self-extinguishes after ignition. A numerical simulation of the discharge of CO2 from PFE into the Combustion Integrated Rack (CIR) in microgravity was performed to obtain the local velocity and CO2 concentration. The complicated flow field around the PFE nozzle exits was modeled by sources of equivalent mass and momentum flux at a location downstream of the nozzle. The time for the concentration of CO2 to reach a level that would extinguish a fire anywhere in the rack was determined using the Fire Dynamics Simulator (FDS), a computational fluid dynamics code developed by the National Institute of Standards and Technology specifically to evaluate the development of a fire and smoke transport. The simulation shows that CO2, as well as any smoke and combustion gases produced by a fire, would be discharged into the ISS cabin through the resource utility panel at the bottom of the rack. These simulations will be validated by comparing the results with velocity and CO2 concentration measurements obtained during the fire suppression system verification tests conducted on the CIR in March 2003. Once these numerical simulations are validated, portions of the ISS labs and living areas will be modeled to determine the local flow conditions before, during, and after a fire event. These simulations can yield specific information about how long it takes for smoke and

Facility design, installation and operation

International Nuclear Information System (INIS)

Fleischmann, A.W.

1985-01-01

Problems that may arise when considering the design, construction and use of a facility that could contain up to tens of petabecquerel of either cobalt-60 or caesium-137 are examined. The safe operation of an irradiation facility depends on an appreciation of the in built safety systems, adequate training of personnel and the existence of an emergency system

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.

Rack for nuclear fuel elements

International Nuclear Information System (INIS)

Rubinstein, H.J.; Gordon, C.B.; Robison, A.; Clark, P.M.

1977-01-01

Disclosed is a rack for storing spent nuclear fuel elements in which a plurality of aligned rows of upright enclosures of generally square cross-sectional areas contain vertically disposed spent fuel elements. Each fuel element is supported at the lower end thereof by a respective support that rests on the floor of the spent fuel pool for a nuclear power plant. An open rack frame is employed as an upright support for the enclosures containing the spent fuel elements. Legs at the lower corners of the frame rest on the floor of the pool to support the frame. In one exemplary embodiment, the support for the fuel element is in the form of a base on which a fuel element rests and the base is supported by legs. In another exemplary embodiment, each fuel element is supported on the pool floor by a self-adjusting support in the form of a base on which a fuel element rests and the base rests on a ball or swivel joint for self-alignment. The lower four corners of the frame are supported by legs adjustable in height for leveling the frame. Each adjustable frame leg is in the form of a base resting on the pool floor and the base supports a threaded post. The threaded post adjustably engages a threaded column on which rests the lower end of the frame. 16 claims, 14 figures

Design aspects of radiological safety in nuclear facilities

International Nuclear Information System (INIS)

Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

2014-01-01

In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

Three-dimensional microelectromechanical tilting platform operated by gear-driven racks

Science.gov (United States)

Klody, Kelly A.; Habbit, Jr., Robert D.

2005-11-01

A microelectromechanical (MEM) tiltable-platform apparatus is disclosed which utilizes a light-reflective platform (i.e. a micromirror) which is supported above a substrate by flexures which can be bent upwards to tilt the platform in any direction over an angle of generally .+-.10 degrees using a gear-driven rack attached to each flexure. Each rack is driven by a rotary microengine (i.e. a micromotor); and an optional thermal actuator can be used in combination with each microengine for initially an initial uplifting of the platform away from the substrate. The MEM apparatus has applications for optical switching (e.g. between a pair of optical fibers) or for optical beam scanning.

Practical design of gamma irradiation facility

International Nuclear Information System (INIS)

Sugimoto, Sen-ichi

1976-01-01

In this report, it is intended to describe mainly the multi-purpose irradiation facilities which carry out the consigned irradiation for the sterilization of medical apparatuses, which is most of the demand of gamma irradiation in Japan. Gamma irradiation criterion is summed up to that ''Apply the specified dose properly and uniformly to product cases and be economic.'' Though the establishment of the design standard for irradiation facilities is not easy and is not solve simply, the factors to be considered in the design are as follows: (1) mechanism safety, (2) multipurpose irradiation structure, (3) irradiation criteria and practice, (4) efficiency of radiation source utilization and related problems, and (5) economical merit. Irradiation facilities are generally itemized as follows: irradiation equipments, radiation source-storing facility, package carrier, radiation source-driving equipments, facilities for safety and operational management and others. Examples and their characteristics are reported for the facilities of Japan Radio-isotope Irradiation Cooperative Association and Radie Industries Ltd. Expenses for construction, processing and radiation sources are shown on the basis of a few references, and the cost trially calculated under a certain presumptive condition is given. (Wakatsuki, Y.)

Exploratory Shaft Facility design basis study report

International Nuclear Information System (INIS)

Langstaff, A.L.

1987-01-01

The Design Basis Study is a scoping/sizing study that evaluated the items concerning the Exploratory Shaft Facility Design including design basis values for water and methane inflow; flexibility of the design to support potential changes in program direction; cost and schedule impacts that could result if the design were changed to comply with gassy mine regulations; and cost, schedule, advantages and disadvantages of a larger second shaft. Recommendations are proposed concerning water and methane inflow values, facility layout, second shaft size, ventilation, and gassy mine requirements. 75 refs., 3 figs., 7 tabs

ISS Material Science Research Rack HWIL Interface Simulation

Science.gov (United States)

Williams, Philip J.; Ballard, Gary H.; Crumbley, Robert T. (Technical Monitor)

2002-01-01

In this paper, the first Material Science Research Rack (MSRR-1) hardware-in-the-loop (HWIL) interface simulation is described. Dynamic Concepts developed this HWIL simulation system with funding and management provided by the Flight Software group (ED14) of NASA-MSFC's Avionics Department. The HWIL system has been used both as a flight software development environment and as a software qualification tool. To fulfill these roles, the HWIL simulator accurately models the system dynamics of many MSRR-1 subsystems and emulates most of the internal interface signals. The modeled subsystems include the Experiment Modules, the Thermal Environment Control System, the Vacuum Access System, the Solid State Power Controller Module, and the Active Rack Isolation Systems. The emulated signals reside on three separate MIL-STD-1553B digital communication buses, the ISS Medium Rate Data Link, and several analog controller and sensor signals. To enhance the range of testing, it was necessary to simulate several off-nominal conditions that may occur in the interfacing subsystems.

Conceptual design of tritium treatment facility

International Nuclear Information System (INIS)

Tachikawa, Katsuhiro

1982-01-01

In connection with the development of fusion reactors, the development of techniques concerning tritium fuel cycle, such as the refining and circulation of fuel, the recovery of tritium from blanket, waste treatment and safe handling, is necessary. In Japan Atomic Energy Research Institute, the design of the tritium process research laboratory has been performed since fiscal 1977, in which the following research is carried out: 1) development of hydrogen isotope separation techniques by deep cooling distillation method and thermal diffusion method, 2) development of the refining, collection and storage techniques for tritium using metallic getters and palladium-silver alloy films, and 3) development of the safe handling techniques for tritium. The design features of this facility are explained, and the design standard for radiation protection is shown. At present, in the detailed design stage, the containment of tritium and safety analysis are studied. The building is of reinforced concrete, and the size is 48 m x 26 m. Glove boxes and various tritium-removing facilities are installed in two operation rooms. Multiple wall containment system and tritium-removing facilities are explained. (Kako, I.)

Cold vacuum drying facility design requirements

Energy Technology Data Exchange (ETDEWEB)

Irwin, J.J.

1997-09-24

This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility.

Cold vacuum drying facility design requirements

International Nuclear Information System (INIS)

Irwin, J.J.

1997-01-01

This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility

Storage rack for holding spent fuel elements from nuclear power plants

International Nuclear Information System (INIS)

Krieger, F.

1978-01-01

In the fuel rack containing a great number of compartments with square cross-sections, the structural elements required by the system are statically designed in such a way, that optimal utilization of space as well as shielding of the compartments with respect to each other is guaranteed. In order to achieve this the compartments may be formed by profiled sheets having got trapezoidal edges taken off. Two sheets, each running parallel with respect to each other, form a double shell. The compartments are formed by another double shell, also consisting of two sheets and lying mirror-inverted with respect to the first shell touching this one. (DG) [de

Engineering test facility design center

International Nuclear Information System (INIS)

Anon.

1980-01-01

The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This section describes the status of this design

Horizontal above-rack pool storage

International Nuclear Information System (INIS)

Moscardini, R.L.

1993-08-01

This report describes a unique method for storing spent, six year out of core, fuel at a prototypical PWR nuclear power station. The study describes a conceptual design, with favorable structural, thermal and criticality technical evaluations. However, economic considerations and licensing risks are judged to be less favorable. The concept study prescribes a fuel over fuel arrangement in an existing Spent Fuel Pool (SFP) with full maintenance of ALARA principles. This concept study is specific to a prototypical pool design, but may easily be projected to other nuclear facilities with other SFP conditions. For the prototypical PWR, the conceptual fuel bridge design will store over 200 additional fuel assemblies without significant facility modifications and for an indefinite time period

Seismic design considerations for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Soni, R.S.; Kushwaha, H.S.; Venkat Raj, V.

2001-01-01

During the last few decades, there have been considerable advances in the field of a seismic design of nuclear structures and components housed inside a Nuclear power Plant (NPP). The seismic design and qualification of theses systems and components are carried out through the use of well proven and established theoretical as well as experimental means. Many of the related research works pertaining to these methods are available in the published literature, codes, guides etc. Contrary to this, there is very little information available with regards to the seismic design aspects of the nuclear fuel cycle facilities. This is probably on account of the little importance attached to these facilities from the point of view of seismic loading. In reality, some of these facilities handle a large inventory of radioactive materials and, therefore, these facilities must survive during a seismic event without giving rise to any sort of undue radiological risk to the plant personnel and the public at large. Presented herein in this paper are the seismic design considerations which are adopted for the design of nuclear fuel cycle facilities in India. (author)

Preliminary Design of the AEGIS Test Facility

CERN Document Server

Dassa, Luca; Cambiaghi, Danilo

2010-01-01

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

Facility Safeguardability Analysis in Support of Safeguards by Design

International Nuclear Information System (INIS)

Wonder, E.F.

2010-01-01

The idea of 'Safeguards-by-Design' (SBD) means designing and incorporating safeguards features into new civil nuclear facilities at the earliest stages in the design process to ensure that the constructed facility is 'safeguardable,' i.e. will meet national and international nuclear safeguards requirements. Earlier consideration of safeguards features has the potential to reduce the need for costly retrofits of the facility and can result in a more efficient and effective safeguards design. A 'Facility Safeguardability Analysis' (FSA) would be a key step in Safeguards-by-Design that would link the safeguards requirements with the 'best practices', 'lessons learned', and design of the safeguards measures for implementing those requirements. The facility designer's nuclear safeguards experts would work closely with other elements of the project design team in performing FSA. The resultant analysis would support discussions and interactions with the national nuclear regulator (i.e. State System of Accounting for and Control of Nuclear Material - SSAC) and the IAEA for development and approval of the proposed safeguards system. FSA would also support the implementation of international safeguards by the IAEA, by providing them with a means to analyse and evaluate the safeguardability of facilities being designed and constructed - i.e. by independently reviewing and validating the FSA as performed by the design team. Development of an FSA methodology is part of a broader U.S. National Nuclear Security Administration program to develop international safeguards-by-design tools and guidance documents for use by facility designers. The NNSA NGSI -sponsored project team is looking, as one element of its work, at how elements of the methodology developed by the Generation IV International Forum's Working Group on Proliferation Resistance and Physical Protection can be adapted to supporting FSA. (author)

Review of the technical basis and verification of current analysis methods used to predict seismic response of spent fuel storage racks

International Nuclear Information System (INIS)

DeGrassi, G.

1992-10-01

This report presents the results of a literature review on spent fuel rack seismic analysis methods and modeling procedures. The analysis of the current generation of free standing high density spent fuel racks requires careful consideration of complex phenomena such as rigid body sliding and tilting motions; impacts between adjacent racks, between fuel assemblies and racks, and between racks and pool walls and floor; fluid coupling and frictional effects. The complexity of the potential seismic response of these systems raises questions regarding the levels of uncertainty and ranges of validity of the analytical results. BNL has undertaken a program to investigate and assess the strengths and weaknesses of current fuel rack seismic analysis methods. The first phase of this program involved a review of technical literature to identify the extent of experimental and analytical verification of the analysis methods and assumptions. Numerous papers describing analysis methods for free standing fuel racks were reviewed. However, the extent of experimental verification of these methods was found to be limited. Based on the information obtained from the literature review, the report provides an assessment of the significance of the issues of concern and makes recommendations for additional studies

Characterization of receptor of activated C kinase 1 (RACK1) and functional analysis during larval metamorphosis of the oyster Crassostrea angulata.

Science.gov (United States)

Yang, Bingye; Pu, Fei; Qin, Ji; You, Weiwei; Ke, Caihuan

2014-03-10

During a large-scale screen of the larval transcriptome library of the Portuguese oyster, Crassostrea angulata, the oyster gene RACK, which encodes a receptor of activated protein kinase C protein was isolated and characterized. The cDNA is 1,148 bp long and has a predicted open reading frame encoding 317 aa. The predicted protein shows high sequence identity to many RACK proteins of different organisms including molluscs, fish, amphibians and mammals, suggesting that it is conserved during evolution. The structural analysis of the Ca-RACK1 genomic sequence implies that the Ca-RACK1 gene has seven exons and six introns, extending approximately 6.5 kb in length. It is expressed ubiquitously in many oyster tissues as detected by RT-PCR analysis. The Ca-RACK1 mRNA expression pattern was markedly increased at larval metamorphosis; and was further increased along with Ca-RACK1 protein synthesis during epinephrine-induced metamorphosis. These results indicate that the Ca-RACK1 plays an important role in tissue differentiation and/or in cell growth during larval metamorphosis in the oyster, C. angulata. Copyright © 2013 Elsevier B.V. All rights reserved.

Design Standards for School Art Facilities

Science.gov (United States)

National Art Education Association, 2015

2015-01-01

"Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

Retrieval-travel-time model for free-fall-flow-rack automated storage and retrieval system

Science.gov (United States)

Metahri, Dhiyaeddine; Hachemi, Khalid

2018-03-01

Automated storage and retrieval systems (AS/RSs) are material handling systems that are frequently used in manufacturing and distribution centers. The modelling of the retrieval-travel time of an AS/RS (expected product delivery time) is practically important, because it allows us to evaluate and improve the system throughput. The free-fall-flow-rack AS/RS has emerged as a new technology for drug distribution. This system is a new variation of flow-rack AS/RS that uses an operator or a single machine for storage operations, and uses a combination between the free-fall movement and a transport conveyor for retrieval operations. The main contribution of this paper is to develop an analytical model of the expected retrieval-travel time for the free-fall flow-rack under a dedicated storage assignment policy. The proposed model, which is based on a continuous approach, is compared for accuracy, via simulation, with discrete model. The obtained results show that the maximum deviation between the continuous model and the simulation is less than 5%, which shows the accuracy of our model to estimate the retrieval time. The analytical model is useful to optimise the dimensions of the rack, assess the system throughput, and evaluate different storage policies.

Ultraviolet Free Electron Laser Facility preliminary design report

Energy Technology Data Exchange (ETDEWEB)

Ben-Zvi, I. (ed.)

1993-02-01

This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA).

Ultraviolet Free Electron Laser Facility preliminary design report

International Nuclear Information System (INIS)

Ben-Zvi, I.

1993-02-01

This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA)

Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

International Nuclear Information System (INIS)

Palomaeki, J.; Ristimaeki, L.

2013-10-01

The purpose of the facility description is to be a specific summary report of the scope of Posiva's nuclear facilities (encapsulation plant and disposal facility) in Olkiluoto. This facility description is based on the 2012 designs and completing Posiva working reports. The facility description depicts the nuclear facilities and their operation as the disposal of spent nuclear fuel starts in Olkiluoto in about 2020. According to the decisions-in-principle of the government, the spent nuclear fuel from Loviisa and Olkiluoto nuclear power plants in operation and in future cumulative spent nuclear fuel from Loviisa 1 and 2, Olkiluoto 1, 2, 3 and 4 nuclear power plants, is permitted to be disposed of in Olkiluoto bedrock. The design of the disposal facility is based on the KBS-3V concept (vertical disposal). Long-term safety concept is based on the multi-barrier principle i.e. several release barriers, which ensure one another so that insufficiency in the performance of one barrier doesn't jeopardize long-term safety of the disposal. The release barriers are the following: canister, bentonite buffer and deposition tunnel backfill, and the host rock around the repository. The canisters are installed into the deposition holes, which are bored to the floor of the deposition tunnels. The canisters are enveloped with compacted bentonite blocks, which swell after absorbing water. The surrounding bedrock and the central and access tunnel backfill provide additional retardation, retention, and dilution. The nuclear facilities consist of an encapsulation plant and of underground final disposal facility including other aboveground buildings and surface structures serving the facility. The access tunnel and ventilation shafts to the underground disposal facility and some auxiliary rooms are constructed as a part of ONKALO underground rock characterization facility during years 2004-2014. The construction works needed for the repository start after obtaining the construction

RAMI strategies in the IFMIF Test Facilities design

Energy Technology Data Exchange (ETDEWEB)

Abal, Javier, E-mail: javier.abal@upc.edu [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Dies, Javier [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Arroyo, José Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Bargalló, Enric [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Casal, Natalia; García, Ángela [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Martínez, Gonzalo; Tapia, Carlos; De Blas, Alfredo [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Mollá, Joaquín; Ibarra, Ángel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain)

2013-10-15

Highlights: • We have implemented fault tolerant design strategies so that the strong availability requirements are met. • The evolution to the present design of the signal and cooling lines inside the TTC has also been compared. • The RAMI analyses have demonstrated a strong capability in being a complementary tool in the design of IFMIF Test Facilities. -- Abstract: In this paper, a RAMI analysis of the different stages in Test Facilities (TF) design is described. The comparison between the availability results has been a milestone not only to evaluate the major unavailability contributors in the updates but also to implement fault tolerant design strategies when possible. These strategies encompass a wide range of design activities: from the definition of degraded modes of operation in the Test Facilities to specific modifications in the test modules in order to guarantee their fail safe operation.

RAMI strategies in the IFMIF Test Facilities design

International Nuclear Information System (INIS)

Abal, Javier; Dies, Javier; Arroyo, José Manuel; Bargalló, Enric; Casal, Natalia; García, Ángela; Martínez, Gonzalo; Tapia, Carlos; De Blas, Alfredo; Mollá, Joaquín; Ibarra, Ángel

2013-01-01

Highlights: • We have implemented fault tolerant design strategies so that the strong availability requirements are met. • The evolution to the present design of the signal and cooling lines inside the TTC has also been compared. • The RAMI analyses have demonstrated a strong capability in being a complementary tool in the design of IFMIF Test Facilities. -- Abstract: In this paper, a RAMI analysis of the different stages in Test Facilities (TF) design is described. The comparison between the availability results has been a milestone not only to evaluate the major unavailability contributors in the updates but also to implement fault tolerant design strategies when possible. These strategies encompass a wide range of design activities: from the definition of degraded modes of operation in the Test Facilities to specific modifications in the test modules in order to guarantee their fail safe operation

Institutionalizing Safeguards By Design for Nuclear Facilities

International Nuclear Information System (INIS)

Morgan, James B.; Kovacic, Donald N.; Whitaker, J. Michael

2008-01-01

Safeguards for nuclear facilities can be significantly improved by developing and implementing methodologies for integrating proliferation resistance into the design of new facilities. This paper proposes a method to systematically analyze a facility's processes, systems, equipment, structures and management controls to ensure that all relevant proliferation scenarios that could potentially result in unacceptable consequences have been identified, evaluated and mitigated. This approach could be institutionalized into a country's regulatory structure similar to the way facilities are licensed to operate safely and are monitored through inspections and incident reporting to ensure compliance with domestic and international safeguards. Furthermore, taking credit for existing systems and equipment that have been analyzed and approved to assure a facility's reliable and safe operations will reduce the overall cost of implementing intrinsic and extrinsic proliferation-resistant features. The ultimate goal is to integrate safety, reliability, security and safeguards operations into the design of new facilities to effectively and efficiently prevent diversion, theft and misuse of nuclear material and sensitive technologies at both the facility and state level. To facilitate this approach at the facility level, this paper discusses an integrated proliferation resistance analysis (IPRA) process. If effectively implemented, this integrated approach will also facilitate the application of International Atomic Energy Agency (IAEA) safeguards

The Multi-User Droplet Combustion Apparatus: the Development and Integration Concept for Droplet Combustion Payloads in the Fluids and Combustion Facility Combustion Integrated Rack

Science.gov (United States)

Myhre, C. A.

2002-01-01

The Multi-user Droplet Combustion Apparatus (MDCA) is a multi-user facility designed to accommodate four different droplet combustion science experiments. The MDCA will conduct experiments using the Combustion Integrated Rack (CIR) of the NASA Glenn Research Center's Fluids and Combustion Facility (FCF). The payload is planned for the International Space Station. The MDCA, in conjunction with the CIR, will allow for cost effective extended access to the microgravity environment, not possible on previous space flights. It is currently in the Engineering Model build phase with a planned flight launch with CIR in 2004. This paper provides an overview of the capabilities and development status of the MDCA. The MDCA contains the hardware and software required to conduct unique droplet combustion experiments in space. It consists of a Chamber Insert Assembly, an Avionics Package, and a multiple array of diagnostics. Its modular approach permits on-orbit changes for accommodating different fuels, fuel flow rates, soot sampling mechanisms, and varying droplet support and translation mechanisms to accommodate multiple investigations. Unique diagnostic measurement capabilities for each investigation are also provided. Additional hardware provided by the CIR facility includes the structural support, a combustion chamber, utilities for the avionics and diagnostic packages, and the fuel mixing capability for PI specific combustion chamber environments. Common diagnostics provided by the CIR will also be utilized by the MDCA. Single combustible fuel droplets of varying sizes, freely deployed or supported by a tether are planned for study using the MDCA. Such research supports how liquid-fuel-droplets ignite, spread, and extinguish under quiescent microgravity conditions. This understanding will help us develop more efficient energy production and propulsion systems on Earth and in space, deal better with combustion generated pollution, and address fire hazards associated with

The Influence of Building Codes on Recreation Facility Design.

Science.gov (United States)

Morrison, Thomas A.

1989-01-01

Implications of building codes upon design and construction of recreation facilities are investigated (national building codes, recreation facility standards, and misperceptions of design requirements). Recreation professionals can influence architectural designers to correct past deficiencies, but they must understand architectural and…

Nanofabricated racks of aligned and anchored DNA substrates for single-molecule imaging.

Science.gov (United States)

Gorman, Jason; Fazio, Teresa; Wang, Feng; Wind, Shalom; Greene, Eric C

2010-01-19

Single-molecule studies of biological macromolecules can benefit from new experimental platforms that facilitate experimental design and data acquisition. Here we develop new strategies to construct curtains of DNA in which the molecules are aligned with respect to one another and maintained in an extended configuration by anchoring both ends of the DNA to the surface of a microfluidic sample chamber that is otherwise coated with an inert lipid bilayer. This "double-tethered" DNA substrate configuration is established through the use of nanofabricated rack patterns comprised of two distinct functional elements: linear barriers to lipid diffusion that align DNA molecules anchored by one end to the bilayer and antibody-coated pentagons that provide immobile anchor points for the opposite ends of the DNA. These devices enable the alignment and anchoring of thousands of individual DNA molecules, which can then be visualized using total internal reflection fluorescence microscopy under conditions that do not require continuous application of buffer flow to stretch the DNA. This unique strategy offers the potential for studying protein-DNA interactions on large DNA substrates without compromising measurements through application of hydrodynamic force. We provide a proof-of-principle demonstration that double-tethered DNA curtains made with nanofabricated rack patterns can be used in a one-dimensional diffusion assay that monitors the motion of quantum dot-tagged proteins along DNA.

Project W-441 cold vacuum drying facility design requirements document

International Nuclear Information System (INIS)

O'Neill, C.T.

1997-01-01

This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage

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)

Nuclear import of transcription factor BR-C is mediated by its interaction with RACK1.

Science.gov (United States)

Cheng, Daojun; Qian, Wenliang; Wang, Yonghu; Meng, Meng; Wei, Ling; Li, Zhiqing; Kang, Lixia; Peng, Jian; Xia, Qingyou

2014-01-01

The transcription factor Broad Complex (BR-C) is an early ecdysone response gene in insects and contains two types of domains: two zinc finger domains for the activation of gene transcription and a Bric-a-brac/Tramtrack/Broad complex (BTB) domain for protein-protein interaction. Although the mechanism of zinc finger-mediated gene transcription is well studied, the partners interacting with the BTB domain of BR-C has not been elucidated until now. Here, we performed a yeast two-hybrid screen using the BTB domain of silkworm BR-C as bait and identified the receptor for activated C-kinase 1 (RACK1), a scaffolding/anchoring protein, as the novel partner capable of interacting with BR-C. The interaction between BR-C and RACK1 was further confirmed by far-western blotting and pull-down assays. Importantly, the disruption of this interaction, via RNAi against the endogenous RACK1 gene or deletion of the BTB domain, abolished the nuclear import of BR-C in BmN4 cells. In addition, RNAi against the endogenous PKC gene as well as phosphorylation-deficient mutation of the predicted PKC phosphorylation sites at either Ser373 or Thr406 in BR-C phenocopied RACK1 RNAi and altered the nuclear localization of BR-C. However, when BTB domain was deleted, phosphorylation mimics of either Ser373 or Thr406 had no effect on the nuclear import of BR-C. Moreover, mutating the PKC phosphorylation sites at Ser373 and Thr406 or deleting the BTB domain significantly decreased the transcriptional activation of a BR-C target gene. Given that RACK1 is necessary for recruiting PKC to close and phosphorylate target proteins, we suggest that the PKC-mediated phosphorylation and nuclear import of BR-C is determined by its interaction with RACK1. This novel finding will be helpful for further deciphering the mechanism underlying the role of BR-C proteins during insect development.

Nuclear import of transcription factor BR-C is mediated by its interaction with RACK1.

Directory of Open Access Journals (Sweden)

Daojun Cheng

Full Text Available The transcription factor Broad Complex (BR-C is an early ecdysone response gene in insects and contains two types of domains: two zinc finger domains for the activation of gene transcription and a Bric-a-brac/Tramtrack/Broad complex (BTB domain for protein-protein interaction. Although the mechanism of zinc finger-mediated gene transcription is well studied, the partners interacting with the BTB domain of BR-C has not been elucidated until now. Here, we performed a yeast two-hybrid screen using the BTB domain of silkworm BR-C as bait and identified the receptor for activated C-kinase 1 (RACK1, a scaffolding/anchoring protein, as the novel partner capable of interacting with BR-C. The interaction between BR-C and RACK1 was further confirmed by far-western blotting and pull-down assays. Importantly, the disruption of this interaction, via RNAi against the endogenous RACK1 gene or deletion of the BTB domain, abolished the nuclear import of BR-C in BmN4 cells. In addition, RNAi against the endogenous PKC gene as well as phosphorylation-deficient mutation of the predicted PKC phosphorylation sites at either Ser373 or Thr406 in BR-C phenocopied RACK1 RNAi and altered the nuclear localization of BR-C. However, when BTB domain was deleted, phosphorylation mimics of either Ser373 or Thr406 had no effect on the nuclear import of BR-C. Moreover, mutating the PKC phosphorylation sites at Ser373 and Thr406 or deleting the BTB domain significantly decreased the transcriptional activation of a BR-C target gene. Given that RACK1 is necessary for recruiting PKC to close and phosphorylate target proteins, we suggest that the PKC-mediated phosphorylation and nuclear import of BR-C is determined by its interaction with RACK1. This novel finding will be helpful for further deciphering the mechanism underlying the role of BR-C proteins during insect development.

Modern tornado design of nuclear and other potentially hazardous facilities

International Nuclear Information System (INIS)

Stevenson, J.D.; Zhao, Y.

1996-01-01

Tornado wind loads and other tornado phenomena, including tornado missiles and differential pressure effects, have not usually been considered in the design of conventional industrial, commercial, or residential facilities in the United States; however, tornado resistance has often become a design requirement for certain hazardous facilities, such as large nuclear power plants and nuclear materials and waste storage facilities, as well as large liquefied natural gas storage facilities. This article provides a review of current procedures for the design of hazardous industrial facilities to resist tornado effects. 23 refs., 19 figs., 13 tabs

Criticality safety and facility design considerations

International Nuclear Information System (INIS)

Waltz, W.R.

1991-06-01

Operations with fissile material introduce the risk of a criticality accident that may be lethal to nearby personnel. In addition, concerns over criticality safety can result in substantial delays and shutdown of facility operations. For these reasons, it is clear that the prevention of a nuclear criticality accident should play a major role in the design of a nuclear facility. The emphasis of this report will be placed on engineering design considerations in the prevention of criticality. The discussion will not include other important aspects, such as the physics of calculating limits nor criticality alarm systems

Waste Encapsulation and Storage Facility (WESF) Design Reconstitution Plan

International Nuclear Information System (INIS)

HERNANDEZ, R.

1999-01-01

The purpose of Design Reconstitution is to establish a Design Baseline appropriate to the current facility mission. The scope of this plan is to ensure that Systems, Structures and Components (SSC) identified in the WESF Basis for Interim Operation (HNF-SDWM-BIO-002) are adequately described and documented, in order to support facility operations. In addition the plan addresses the adequacy of selected Design Topics which are also crucial for support of the facility Basis for Interim Operation (BIO)

Exploratory shaft facility preliminary designs - Permian Basin

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Permian Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Permian Basin, Texas. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references, 13 tables

Construction of irradiated material examination facility-basic design

International Nuclear Information System (INIS)

Ro, Seung Gy; Kim, Eun Ka; Hong, Gye Won; Herr, Young Hoi; Hong, Kwon Pyo; Lee, Myeong Han; Baik, Sang Youl; Choo, Yong Sun; Baik, Seung Je

1989-02-01

The basic design of the hot cell facility which has the main purpose of doing mechanical and physical property tests of irradiated materials, the examination process, and the annexed facility has been made. Also basic and detall designs for the underground excavation work have been performed. The project management and tasks required for the license application have been carried out in due course. The facility is expected to be completed by the end of 1992, if the budgetary support is sufficient. (Author)

Facilities design for TIBER II

International Nuclear Information System (INIS)

Thomson, S.L.; Blevins, J.D.

1987-01-01

This paper describes the conceptual design of the reactor building and reactor maintenance building for the TIBER II tokamak. These buildings are strongly influenced by the reactor configuration, and their characterization allows a better understanding of the economic and technical implications of the reactor design. Key features of TIBER II that affect the facilities design are the small size and compact arrangement, the use of an external vacuum vessel, and the complete reliance on remote maintenance. The building design incorporates requirements for equipment layout, maintenance operations and equipment, safety, and contamination control. 4 figs

Design of a hydrogen test facility

International Nuclear Information System (INIS)

Morgan, M.J.; Beam, J.E.; Sehmbey, M.S.; Pais, M.R.; Chow, L.C.; Hahn, O.J.

1992-01-01

The Air Force has sponsored a program at the University of Kentucky which will lead to a better understanding of the thermal and fluid instabilities during blowdown of supercritical fluids at cryogenic temperatures. An integral part of that program is the design and construction of that hydrogen test facility. This facility will be capable of providing supercritical hydrogen at 30 bars and 35 K at a maximum flow rate of 0.1 kg/s for 90 seconds. Also presented here is an extension of this facility to accommodate the use of supercritical helium

OsRACK1 Is Involved in Abscisic Acid- and H2O2-Mediated Signaling to Regulate Seed Germination in Rice (Oryza sativa, L.)

Science.gov (United States)

Zhang, Dongping; Chen, Li; Li, Dahong; Lv, Bing; Chen, Yun; Chen, Jingui; XuejiaoYan; Liang, Jiansheng

2014-01-01

The receptor for activated C kinase 1 (RACK1) is one member of the most important WD repeat–containing family of proteins found in all eukaryotes and is involved in multiple signaling pathways. However, compared with the progress in the area of mammalian RACK1, our understanding of the functions and molecular mechanisms of RACK1 in the regulation of plant growth and development is still in its infancy. In the present study, we investigated the roles of rice RACK1A gene (OsRACK1A) in controlling seed germination and its molecular mechanisms by generating a series of transgenic rice lines, of which OsRACK1A was either over-expressed or under-expressed. Our results showed that OsRACK1A positively regulated seed germination and negatively regulated the responses of seed germination to both exogenous ABA and H2O2. Inhibition of ABA biosynthesis had no enhancing effect on germination, whereas inhibition of ABA catabolism significantly suppressed germination. ABA inhibition on seed germination was almost fully recovered by exogenous H2O2 treatment. Quantitative analyses showed that endogenous ABA levels were significantly higher and H2O2 levels significantly lower in OsRACK1A-down regulated transgenic lines as compared with those in wildtype or OsRACK1A-up regulated lines. Quantitative real-time PCR analyses showed that the transcript levels of OsRbohs and amylase genes, RAmy1A and RAmy3D, were significantly lower in OsRACK1A-down regulated transgenic lines. It is concluded that OsRACK1A positively regulates seed germination by controlling endogenous levels of ABA and H2O2 and their interaction. PMID:24865690

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.

Facility design consequences of different employees’ quality perceptions

NARCIS (Netherlands)

Kok, Herman; Mobach, Mark P.; Omta, Onno

2015-01-01

An important challenge for facility management is to integrate the complex and comprehensive construct of different service processes and physical elements of the service facility into a meaningful and functional facility design. The difficulty of this task is clearly indicated by the present study

77 FR 27029 - Certain Kitchen Shelving and Racks From the People's Republic of China: Extension of Time Limit...

Science.gov (United States)

2012-05-08

... DEPARTMENT OF COMMERCE International Trade Administration [C-570-942] Certain Kitchen Shelving and Racks From the People's Republic of China: Extension of Time Limit for Preliminary Results of... certain kitchen appliance shelving and racks from the People's Republic of China, covering the review...

Preliminary design for a maglev development facility

Energy Technology Data Exchange (ETDEWEB)

Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. (Argonne National Lab., IL (United States)); Zhang, Z.Y. (Polytechnic Univ., Brooklyn, NY (United States)); Myers, G.; Cvercko, A. (Sterling Engineering, Westchester, IL (United States)); Williams, J.R. (Alfred Benesch and Co., Chicago, IL (United States))

1992-04-01

A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

Lessons Learned "Establishing an Electrically Safe Work Condition" Specifically related to Racking Electrical Breakers

Energy Technology Data Exchange (ETDEWEB)

Martinez, Tommy Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Romero, Philbert Roland [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Garcia, Samuel Anthony [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-11-09

During low voltage electrical equipment maintenance, a bad breaker was identified. The breaker was racked out from the substation cubicle without following the hazardous energy control process identified in the Integrated Work Document (IWD). The IWD required the substation to be in an electrically safe work condition prior to racking the breaker. Per NFPA 70E requirements, electrical equipment shall be put into an electrically safe work condition before an employee performs work on or interacts with equipment in a manner that increases the likelihood of creating an arc flash. Racking in or out a breaker on an energized bus may increase the likelihood of creating an arc flash dependent on equipment conditions. A thorough risk assessment must be performed prior to performing such a task. The risk assessment determines the risk control measures to be put in place prior to performing the work. Electrical Safety Officers (ESO) can assist in performing risk assessments and incorporating risk control measures.

MEMS/Electronic Device Design and Characterization Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility allows DoD to design and characterize state-of-the-art microelectromechanical systems (MEMS) and electronic devices. Device designers develop their own...

40 CFR Table 9 to Subpart Eeee of... - Continuous Compliance With Operating Limits-High Throughput Transfer Racks

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits-High Throughput Transfer Racks 9 Table 9 to Subpart EEEE of Part 63 Protection of Environment...—Continuous Compliance With Operating Limits—High Throughput Transfer Racks As stated in §§ 63.2378(a) and (b...

Status and Prospect of Safeguards By Design for Pyroprocessing Facility

International Nuclear Information System (INIS)

Kim, Ho-Dong; Shin, H.S.; Ahn, S.K.

2010-01-01

The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and

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

Design requirements for new nuclear reactor facilities in Canada

International Nuclear Information System (INIS)

Shim, S.; Ohn, M.; Harwood, C.

2012-01-01

The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

Design of plutonium processing facilities

International Nuclear Information System (INIS)

Derbyshire, W.; Sills, R.J.

1982-01-01

Five considerations for the design of plutonium processing facilities are identified. These are: Toxicity, Radiation, Criticality, Containment and Remote Operation. They are examined with reference to reprocessing spent nuclear fuel and application is detailed both for liquid and dry processes. (author)

Redesign of the spent fuel storage racks at the Trojan Nuclear Plant

International Nuclear Information System (INIS)

Stump, K.

1987-01-01

The spent fuel pool (SFP) at the Trojan Nuclear Plant located near Prescott, Oregon, was originally designed to hold 1.33 cores worth of spent fuel assemblies. Due to the delay in the site selection and preparation process for the spent fuel repository, the SFP storage capacity was increased in 1978 from 260 assemblies to 651 assemblies and in 1983 was increased again from 651 to 1408 assemblies to allow Trojan to continue operations through the year 2003 with a full core reserve in the SFP. Now it appears unlikely that a high level waste repository will be in operation before 2010. This indicates that a further capacity increase in the SFP is required to allow commercial operation until 2010, at which time the repository should be open to receive spent fuel. To accomplish this, an increase of seven times the original SFP capacity of 260 assemblies is needed. This paper presents a spent fuel assembly rack design that enables the required capacity increase in the SFP to be met. By the use of a boron carbide - silicon polymer inside a titanium/vanadium honeycomb as a neutron absorber between the fuel assemblies and by increasing the metal to water ratio of the spent fuel pool to harden the neutron energy spectrum the capacity of the SFP is increased to 1880 assemblies for an increase of 7.23 times the original spent fuel pool capacity. The multiplication factor for the pool with every fuel assembly slot filled in the new rack system is 0.62; well below the NRC regulatory limit of keff < 0.95. The capacity increase with allow the commercial operation of the Trojan Nuclear Plant through 2010 with a full core reserve in the spent fuel pool

Design Guide for Category I reactors critical facilities

International Nuclear Information System (INIS)

Brynda, W.J.; Powell, R.W.

1978-08-01

The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned critical facilities be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission

Overview of the IFMIF test facility design in IFMIF/EVEDA phase

International Nuclear Information System (INIS)

Tian, Kuo; Abou-Sena, Ali; Arbeiter, Frederik; García, Ángela; Gouat, Philippe; Heidinger, Roland; Heinzel, Volker; Ibarra, Ángel; Leysen, Willem; Mas, Avelino; Mittwollen, Martin; Möslang, Anton; Theile, Jürgen; Yamamoto, Michiyoshi; Yokomine, Takehiko

2015-01-01

Highlights: • This paper summarizes the current design status of IFMIF EVEDA test facility. • The principle functions of the test facility and key components are described. • The brief specifications of the systems and key components are addressed. - Abstract: The test facility (TF) is one of the three major facilities of the International Fusion Material Irradiation Facility (IFMIF). Engineering designs of TF main systems and key components have been initiated and developed in the IFMIF EVEDA (Engineering Validation and Engineering Design Activities) phase since 2007. The related work covers the designs of a test cell which is the meeting point of the TF and accelerator facility and lithium facility, a series of test modules for experiments under different irradiation conditions, an access cell to accommodate remote handling systems, four test module handling cells for test module processing and assembling, and test facility ancillary systems for engineering support on energy, media, and control infrastructure. This paper summarizes the principle functions, brief specifications, and the current design status of the above mentioned IFMIF TF systems and key components.

Design study of underground facility of the Underground Research Laboratory

International Nuclear Information System (INIS)

Hibiya, Keisuke; Akiyoshi, Kenji; Ishizuka, Mineo; Anezaki, Susumu

1998-03-01

Geoscientific research program to study deep geological environment has been performed by Power Reactor and Nuclear Fuel Development Corporation (PNC). This research is supported by 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. An Underground Research Laboratory is planned to be constructed at Shoma-sama Hora in the research area belonging to PNC. A wide range of geoscientific research and development activities which have been previously studied at the Tono Area is planned in the laboratory. The Underground Research Laboratory is consisted of Surface Laboratory and Underground Research Facility located from the surface down to depth between several hundreds and 1,000 meters. Based on the results of design study in last year, the design study performed in this year is to investigate the followings in advance of studies for basic design and practical design: concept, design procedure, design flow and total layout. As a study for the concept of the underground facility, items required for the facility are investigated and factors to design the primary form of the underground facility are extracted. Continuously, design methods for the vault and the underground facility are summarized. Furthermore, design procedures of the extracted factors are summarized and total layout is studied considering the results to be obtained from the laboratory. (author)

Standard specification for boron-Based neutron absorbing material systems for use in nuclear spent fuel storage racks

CERN Document Server

American Society for Testing and Materials. Philadelphia

2011-01-01

1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system. 1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials. 1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used. 1.4 The materials systems described herein shall be functional – that is always be capable to maintain a B10 areal density such that subcriticality Keff <0.95 or Keff <0.98 or Keff < 1.0 depending on the design specification for the service...

Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility

International Nuclear Information System (INIS)

Heatherly, D.W.; Thoms, K.R.; Siman-Tov, I.I.; Hurst, M.T.

1999-01-01

A Heavy-Section Steel Irradiation (HSSI) Program project, funded by the US Nuclear Regulatory Commission, was initiated at Oak Ridge National Laboratory to develop reusable materials irradiation facilities in which metallurgical specimens of reactor pressure vessel steels could be irradiated. As a consequence, two new, identical, reusable materials irradiation facilities have been designed, fabricated, installed, and are now operating at the Ford Nuclear Reactor at the University of Michigan. The facilities are referred to as the HSSI-IAR facilities with the individual facilities being designated as IAR-1 and IAR-2. This new and unique facility design requires no cutting or grinding operations to retrieve irradiated specimens, all capsule hardware is totally reusable, and materials transported from site to site are limited to specimens only. At the time of this letter report, the facilities have operated successfully for approximately 2500 effective full-power hours

Cold vacuum drying facility design requirements

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1999-07-01

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

Cold vacuum drying facility design requirements

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified

Conceptual capital-cost estimate and facility design of the Mirror-Fusion Technology Demonstration Facility

International Nuclear Information System (INIS)

1982-09-01

This report contains contributions by Bechtel Group, Inc. to Lawrence Livermore National Laboratory (LLNL) for the final report on the conceptual design of the Mirror Fusion Technology Demonstration Facility (TDF). Included in this report are the following contributions: (1) conceptual capital cost estimate, (2) structural design, and (3) plot plan and plant arrangement drawings. The conceptual capital cost estimate is prepared in a format suitable for inclusion as a section in the TDF final report. The structural design and drawings are prepared as partial inputs to the TDF final report section on facilities design, which is being prepared by the FEDC

Storage racks for spent nuclear fuels

International Nuclear Information System (INIS)

Matsumoto, Takashi; Ukaji, Hideo; Okino, Yoshiyuki; Ishihara, Jo; Ikuta, Isao.

1983-01-01

Purpose: To facilitate the mounting of neutron absorbers made of amorphous alloys to fuel racks. Constitution: Neutron absorbers are mounted to a cylindrical member of a square cross section for containing to retain spent fuels only on paired opposing sides by means of machine screws or the likes. Then, such cylindrical members are disposed so that their sides attached with the neutron absorbers are not in adjacent with each other. In this way, mounting of the neutron absorbers over the entire surface of the cylindrical members is no more necessary thereby enabling to simplify the mounting work. (Ikeda, J.)

Interior Design Factors in Library Facilities.

Science.gov (United States)

Jackson, Patricia Ann

When planning the interior of a library facility, the planning team of librarian, library consultant, architect, and interior design consultant must focus attention on the basic principles of interior design and the psychological needs of the user. Colors for an interior should be selected with careful regard to space, light, and emotional and…

AERIAL DELIVERY DESIGN AND FABRICATION FACILITY

Data.gov (United States)

Federal Laboratory Consortium — Skilled personnel are equipped to design and develop various prototype airdrop items. This facility has all classes of sewing machines, ranging from lightweight to...

Hanford Site waste tank farm facilities design reconstitution program plan

International Nuclear Information System (INIS)

Vollert, F.R.

1994-01-01

Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

RACK1 forms a complex with FGFR1 and PKM2, and stimulates the growth and migration of squamous lung cancer cells.

Science.gov (United States)

Zhou, Chengzhi; Chen, Tao; Xie, Zhanhong; Qin, Yinyin; Ou, Yangming; Zhang, Jiexia; Li, Shiyue; Chen, Rongchang; Zhong, Nanshan

2017-11-01

Phosphorylation of Pyruvate Kinase M2 (PKM2) on Tyr105 by fibroblast growth factor receptor 1 (FGFR1) has been shown to promote its nuclear localization as well as cell growth in lung cancer. Better understanding the regulation of this process would benefit the clinical treatment for lung cancer. Here, it has been found that the adaptor protein receptor for activated PKC kinase (RACK1) formed a complex with FGFR1 and PKM2, and activated the FGFR1/PKM2 signaling. Knocking down the expression of RACK1 impaired the phosphorylation on Tyr105 of PKM2 and inhibited the growth and migration of lung cancer cells, while over-expression of RACK1 in lung cancer cells led to the resistance to Erdafitinib. Moreover, knocking down the expression of RACK1 impaired the tumorigenesis of lung cancer driven by LKB loss and mutated Ras (KrasG12D). Taken together, our study demonstrated the pivotal roles of RACK1 in FGFR1/PKM2 signaling, suggesting FGFR1/RACK1/PKM2 might be a therapeutic target for lung cancer treatment. © 2017 Wiley Periodicals, Inc.

National Ignition Facility Title II Design Plan

International Nuclear Information System (INIS)

Kumpan, S

1997-01-01

This National Ignition Facility (NIF) Title II Design Plan defines the work to be performed by the NIF Project Team between November 1996, when the U.S. Department of Energy (DOE) reviewed Title I design and authorized the initiation of Title H design and specific long-lead procurements, and September 1998, when Title 11 design will be completed

Habitat use by Red Knots (Calidris canutus rufa): Experiments with oyster racks and reefs on the beach and intertidal of Delaware Bay, New Jersey

Science.gov (United States)

Burger, Joanna; Niles, Lawrence J.

2017-07-01

Sea level rise and increasing human activities have decreased intertidal habitat in many places in the world. The expansion of aquaculture in intertidal areas may impact birds and other organisms using these habitats, leading to questions of sustainability of both aquaculture and functioning estuarine ecosystems. Understanding the effect of oyster culture on shorebird activity, particularly on Red Knots (Calidris canutus rufa), a species on the U.S. Threatened List, is important for adaptive management and the expansion of oyster culture. In May 2013 we experimentally compared Red Knot and shorebird use of a beach section with racks and a control, and in 2016 we compared the use of sections with artificial reefs, oyster racks, and control on Delaware Bay, New Jersey (USA). The data included only times when no workers or other people were present. Censuses, conducted every 30 min throughout the day (279 censuses in 2013, 231 censuses in 2016), included the number of Red Knots and other shorebirds in each treatment section. In 2013, the total number of shorebirds was significantly higher in the rack section than in the control section, except for Red Knots and Ruddy Turnstones (Arenaria interpres) that occurred in higher numbers in the control than in the rack section. In 2016 Red Knot numbers were also significantly lower in the rack section. In 2013, the mean number of Red Knots/census was 13 for racks vs 59 for the control (P racks and over 68 for other treatments (P racks while both foraging and roosting, suggesting that caution should be used before placing oyster racks in areas used for foraging by Red Knots.

Implications of system usability on intermodal facility design.

Science.gov (United States)

2010-08-01

Ensuring good design of intermodal transportation facilities is critical for effective and : satisfactory operation. Passenger use of the facilities is often hindered by inadequate space, a poor : layout, or lack of signage. This project aims to impr...

Staphylococcus xylosus PCR-validated Decontamination of Murine Individually Ventilated Cage Racks and Air Handling Units by Using 'Active-Closed' Exposure to Vaporized Hydrogen Peroxide.

Science.gov (United States)

Ragland, Natalie H; Miedel, Emily L; Gomez, Jose M; Engelman, Robert W

2017-11-01

Vaporized hydrogen peroxide (VHP) is used to decontaminate clinical, biocontainment, and research animal rooms and equipment. To assist with its implementation in a murine facility, we developed a safe and effective method of VHP sterilization of IVC racks and air handling units (AHU). Safety of VHP decontamination was assessed by ensuring VHP levels dissipated to less than 1 ppm in the room prior to personnel reentry and inside the primary enclosure prior to the return of mice; this condition occurred at least 18 h after the VHP cycle. Efficacy of VHP sterilization was assessed by using chemical indicators, biologic indicators, and PCR testing for Staphylococcus xylosus, a commensal organism of murine skin and an opportunistic pathogen, which was present in 160 of 172 (93%) of specimens from occupied IVC racks and the interior surfaces of in-use AHU. Neither mechanized washing nor hand-sanitizing eradicated S. xylosus from equipment airway interiors, with 17% to 24% of specimens remaining PCR-positive for S. xylosus. 'Static-open' VHP exposure of sanitized equipment did not ensure its sterilization. In contrast, 'active-closed' VHP exposure, in which IVC racks were assembled, sealed, and connected to AHU set to the VHP cycle, increased the proportion of chemical indicators that detected sterilizing levels of VHP inside the assembled equipment, and significantly decreased PCR-detectable S. xylosus inside the equipment. Supplementing bulk steam sterilization of the primary enclosure with VHP sterilization of the secondary housing equipment during room change-outs may help to mitigate opportunistic agents that jeopardize studies involving immunodeficient strains.

High-level waste canister storage final design, installation, and testing. Topical report

Energy Technology Data Exchange (ETDEWEB)

Connors, B.J.; Meigs, R.A.; Pezzimenti, D.M.; Vlad, P.M.

1998-04-01

This report is a description of the West Valley Demonstration Project`s radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project`s vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access.

High-level waste canister storage final design, installation, and testing. Topical report

International Nuclear Information System (INIS)

Connors, B.J.; Meigs, R.A.; Pezzimenti, D.M.; Vlad, P.M.

1998-04-01

This report is a description of the West Valley Demonstration Project's radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project's vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access

RACK1 downregulates levels of the pro-apoptotic protein Fem1b in apoptosis-resistant colon cancer cells.

Science.gov (United States)

Subauste, M Cecilia; Ventura-Holman, Tereza; Du, Liqin; Subauste, Jose S; Chan, Shing-Leng; Yu, Victor C; Maher, Joseph F

2009-12-01

Evasion of apoptosis plays an important role in colon cancer progression. Following loss of the Apc tumor suppressor gene in mice, the gene encoding Fem1b is upregulated early in neoplastic intestinal epithelium. Fem1b is a pro-apoptotic protein that interacts with Fas, TNFR1 and Apaf-1, and increased expression of Fem1b induces apoptosis of cancer cells. Fem1b is a homolog of FEM-1, a protein in Caenorhabditis elegans that is negatively regulated by ubiquitination and proteasomal degradation. To study Fem1b regulation in colon cancer progression, we used apoptotis-sensitive SW480 cells, derived from a primary colon cancer, and their isogenic, apoptosis-resistant counterparts SW620 cells, derived from a subsequent metastatic lesion in the same patient. Treatment with proteasome inhibitor increased Fem1b protein levels in SW620 cells, but not in SW480 cells. In SW620 cells we found that endogenous Fem1b co-immunoprecipitates in complexes with RACK1, a protein known to mediate ubiquitination and proteasomal degradation of other pro-apoptotic proteins and to be upregulated in colon cancer. Full-length Fem1b, or the N-terminal region of Fem1b, associated with RACK1 when co-expressed in HEK293T cells, and RACK1 stimulated ubiquitination of Fem1b. RACK1 overexpression in SW620 cells led to downregulation of Fem1b protein levels. Conversely, downregulation of RACK1 led to upregulation of Fem1b protein levels, associated with induction of apoptosis, and this apoptosis was inhibited by blocking Fem1b protein upregulation. In conclusion, RACK1 downregulates levels of the pro-apoptotic protein Fem1b in metastatic, apoptosis-resistant colon cancer cells, which may promote apoptosis-resistance during progression of colon cancer.

Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

International Nuclear Information System (INIS)

Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

2010-01-01

Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

Human factors design guidelines for maintainability of Department of Energy nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

1985-06-18

Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed.

Human factors design guidelines for maintainability of Department of Energy nuclear facilities

International Nuclear Information System (INIS)

Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

1985-01-01

Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed

Development of cloud-operating platform for detention facility design

Science.gov (United States)

Tun Lee, Kwan; Hung, Meng-Chiu; Tseng, Wei-Fan; Chan, Yi-Ping

2017-04-01

In the past 20 years, the population of Taiwan has accumulated in urban areas. The land development has changed the hydrological environment and resulted in the increase of surface runoff and shortened the time to peak discharge. The change of runoff characteristics increases the flood risk and reduces resilient ability of the city during flood. Considering that engineering measures may not be easy to implement in populated cities, detention facilities set on building basements have been proposed to compromise the increase of surface runoff resulting from development activities. In this study, a web-based operational platform has been developed to integrate the GIS technologies, hydrological analyses, as well as relevant regulations for the design of detention facilities. The design procedure embedded in the system includes a prior selection of type and size of the detention facility, integrated hydrological analysis for the developing site, and inspection of relevant regulations. After login the platform, designers can access the system database to retrieve road maps, land use coverages, and storm sewer information. Once the type, size, inlet, and outlet of the detention facility are assigned, the system can acquire the rainfall intensity-duration-frequency information from adjacent rain gauges to perform hydrological analyses for the developing site. The increase of the runoff volume due to the development and the reduction of the outflow peak through the construction of the detention facility can be estimated. The outflow peak at the target site is then checked with relevant regulations to confirm the suitability of the detention facility design. The proposed web-based platform can provide a concise layout of the detention facility and the drainageway of the developing site on a graphical interface. The design information can also be delivered directly through a web link to authorities for inspecting to simplify the complex administrative procedures.

Design considerations for the Yucca Mountain project exploratory shaft facility

International Nuclear Information System (INIS)

Bullock, R.L. Sr.

1990-01-01

This paper reports on the regulatory/requirements challenges of this project which exist because this is the first facility of its kind to ever be planned, characterized, designed, and built under the purview of a U.S. Nuclear Regulatory Agency. The regulations and requirements that flow down to the Architect/Engineer (A/E) for development of the Exploratory Shaft Facility (ESF) design are voluminous and unique to this project. The subsurface design and construction of the ESF underground facility may eventually become a part of the future repository facility and, if so, will require licensing by the Nuclear Regulatory Commission (NRC). The Fenix and Scisson of Nevada-Yucca Mountain Project (FSN-YMP) group believes that all of the UMP design and construction related activities, with good design/construct control, can be performed to meet all engineering requirements, while following a strict quality assurance program that will also meet regulatory requirements

Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2010-10-01

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Conceptual layout design of CFETR Hot Cell Facility

Energy Technology Data Exchange (ETDEWEB)

Gong, Zheng, E-mail: gongz@mail.ustc.edu.cn [University of Science and Technology of China, Hefei 230026 (China); Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Qi, Minzhong, E-mail: qiminzhong@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Cheng, Yong, E-mail: chengyong@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Song, Yuntao, E-mail: songyt@ipp.ac.cn [University of Science and Technology of China, Hefei 230026 (China); Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China)

2015-11-15

Highlights: • This article proposed a conceptual layout design for CFETR. • The design principles are to support efficient maintenance to ensure the realization of high duty time. • The preliminary maintenance process and logistics are described in detail. • Life cycle management, maneuverability, risk and safety are in the consideration of design. - Abstract: CFETR (China Fusion Engineering Test Reactor) is new generation of Tokomak device beyond EAST in China. An overview of hot cell layout design for CFETR has been proposed by ASIPP&USTC. Hot Cell, as major auxiliary facility, not only plays a pivotal role in supporting maintenance to meet the requirements of high duty time 0.3–0.5 but also supports installation and decommissioning. Almost all of the Tokomak devices are lateral handling internal components like ITER and JET, but CFETR maintain the blanket module from 4 vertical ports, which is quite a big challenge for the hot cell layout design. The activated in-vessel components and several diagnosis instruments will be repaired and refurbished in the Hot Cell Facility, so the appropriate layout is very important to the Hot Cell Facility to ensure the high duty time, it is divided into different parts equipped with a variety of RH equipment and diagnosis devices based on the functional requirements. The layout of the Hot Cell Facility should make maintenance process more efficient and reliable, and easy to service and rescue when a sudden events taking place, that is the capital importance issue considered in design.

Can an off-the-rack orthotic stiletto alter pressure and comfort scores in the forefoot, arch and heel?

DEFF Research Database (Denmark)

Penny, Jeannette Østergaard; Speedtsberg, Merete Brink; Kallemose, Thomas

2018-01-01

MTH2+3 pressure (p rack orthotic stilettos can notably reduce...... plantar pressures and improve forefoot and heel comfort during everyday use. Practitioner Summary: Off-the-rack orthotic stilettos with built-in metatarsal pad, arch support and heel caps can lower the pressure under the heel and forefoot in comparison with a standard stiletto and can improve comfort...

Design of the disposal facility 2012

International Nuclear Information System (INIS)

Saanio, T.; Ikonen, A.; Keto, P.; Kirkkomaeki, T.; Kukkola, T.; Nieminen, J.; Raiko, H.

2013-11-01

The spent nuclear fuel accumulated from the nuclear power plants in Olkiluoto in Eurajoki and in Haestholmen in Loviisa will be disposed of in Olkiluoto. A facility complex will be constructed at Olkiluoto, and it will include two nuclear waste facilities according to Government Degree 736/2008. The nuclear waste facilities are an encapsulation plant, constructed to encapsulate spent nuclear fuel and a disposal facility consisting of an underground repository and other underground rooms and above ground service spaces. The repository is planned to be excavated to a depth of 400 - 450 meters. Access routes to the disposal facility are an inclined access tunnel and vertical shafts. The encapsulated fuel is transferred to the disposal facility in the canister lift. The canisters are transferred from the technical rooms to the disposal area via central tunnel and deposited in the deposition holes which are bored in the floors of the deposition tunnels and are lined beforehand with compacted bentonite blocks. Two parallel central tunnels connect all the deposition tunnels and these central tunnels are inter-connected at regular intervals. The solution improves the fire safety of the underground rooms and allows flexible backfilling and closing of the deposition tunnels in stages during the operational phase of the repository. An underground rock characterization facility, ONKALO, is excavated at the disposal level. ONKALO is designed and constructed so that it can later serve as part of the repository. The goal is that the first part of the disposal facility will be constructed under the building permit phase in the 2010's and operations will start in the 2020's. The fuel from 4 operating reactors as well the fuel from the fifth nuclear power plant under construction, has been taken into account in designing the disposal facility. According to the information from TVO and Fortum, the amount of the spent nuclear fuel is 5,440 tU. The disposal facility is being excavated

Status and Prospect of Safeguards By Design for the Pyroprocessing Facility

International Nuclear Information System (INIS)

Kim, Hodong; Shin, H.S.; Ahn, S.K.

2010-01-01

The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and

High level radioactive waste management facility design criteria

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1993-01-01

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding

CIF---Design basis for an integrated incineration facility

International Nuclear Information System (INIS)

Bennett, G.F.

1991-01-01

This paper discusses the evolution of chosen technologies that occurred during the design process of the US Department of Energy (DOE) incineration system designated the Consolidated Incineration Facility (CIF) as the Savannah River Plant, Aiken, South Carolina. The Plant is operated for DOE by the Westinghouse Savannah River Company. The purpose of the incineration system is to treat low level radioactive and/or hazardous liquid and solid wastes by combustion. The objective for the facility is to thermally destroy toxic constituents and volume reduce waste material. Design criteria requires operation be controlled within the limits of RCRA's permit envelope

Proposed BISOL Facility - a Conceptual Design

Science.gov (United States)

Ye, Yanlin

2018-05-01

In China, a new large-scale nuclear-science research facility, namely the "Beijing Isotope-Separation-On-Line neutron-rich beam facility (BISOL)", has been proposed and reviewed by the governmental committees. This facility aims at both basic science and application goals, and is based on a double-driver concept. On the basic science side, the radioactive ion beams produced from the ISOL device, driven by a research reactor or by an intense deuteron-beam ac- celerator, will be used to study the new physics and technologies at the limit of the nuclear stability in the medium mass region. On the other side regarding to the applications, the facility will be devoted to the material research asso- ciated with the nuclear energy system, by using typically the intense neutron beams produced from the deuteron-accelerator driver. The initial design will be outlined in this report.

Conceptual design of an in-space cryogenic fluid management facility, executive summary

Science.gov (United States)

Willen, G. S.; Riemer, D. H.; Hustvedt, D. C.

1981-01-01

The conceptual design of a Spacelab experiment to develop the technology associated with low gravity propellant management is summarized. The preliminary facility definition, conceptual design and design analysis, and facility development plan, including schedule and cost estimates for the facility, are presented.

Design of special facility for liquor irradiation

International Nuclear Information System (INIS)

Yao Shibin; Chen Zigen

1989-01-01

The design principle, physical scheme, technological process, construction and safety features of a special facility used for irradiating liquors is briefly described. 0.925 x 10 15 Bq cobalt source is used and the irradiation capacity for liquors approaches 10 t per day. The facility bears advantages of simple in construction, easy to operate, safe, reliable and efficient in source utilization

Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

Fattor, Steven [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2014-06-01

The manual contains general requirements that apply to nonnuclear and nonexplosive facilities. For design and construction requirements for modifications to nuclear or explosive facilities, see the project-specific design requirements noted in the Design Criteria.

Staphylococcus xylosus PCR-validated Decontamination of Murine Individually Ventilated Cage Racks and Air Handling Units by Using ‘Active–Closed’ Exposure to Vaporized Hydrogen Peroxide

Science.gov (United States)

Ragland, Natalie H; Miedel, Emily L; Gomez, Jose M; Engelman, Robert W

2017-01-01

Vaporized hydrogen peroxide (VHP) is used to decontaminate clinical, biocontainment, and research animal rooms and equipment. To assist with its implementation in a murine facility, we developed a safe and effective method of VHP sterilization of IVC racks and air handling units (AHU). Safety of VHP decontamination was assessed by ensuring VHP levels dissipated to less than 1 ppm in the room prior to personnel reentry and inside the primary enclosure prior to the return of mice; this condition occurred at least 18 h after the VHP cycle. Efficacy of VHP sterilization was assessed by using chemical indicators, biologic indicators, and PCR testing for Staphylococcus xylosus, a commensal organism of murine skin and an opportunistic pathogen, which was present in 160 of 172 (93%) of specimens from occupied IVC racks and the interior surfaces of in-use AHU. Neither mechanized washing nor hand-sanitizing eradicated S. xylosus from equipment airway interiors, with 17% to 24% of specimens remaining PCR-positive for S. xylosus. ‘Static–open’ VHP exposure of sanitized equipment did not ensure its sterilization. In contrast, ‘active–closed’ VHP exposure, in which IVC racks were assembled, sealed, and connected to AHU set to the VHP cycle, increased the proportion of chemical indicators that detected sterilizing levels of VHP inside the assembled equipment, and significantly decreased PCR-detectable S. xylosus inside the equipment. Supplementing bulk steam sterilization of the primary enclosure with VHP sterilization of the secondary housing equipment during room change-outs may help to mitigate opportunistic agents that jeopardize studies involving immunodeficient strains. PMID:29256369

Performance evaluation of METAMIC neutron absorber in spent fuel storage rack

Directory of Open Access Journals (Sweden)

Kiyoung Kim

2018-06-01

Full Text Available High-density spent fuel (SF storage racks have been installed to increase SF pool capacity. In these SF racks, neutron absorber materials were placed between fuel assemblies allowing the storage of fuel assemblies in close proximity to one another. The purpose of the neutron absorber materials is to preclude neutronic coupling between adjacent fuel assemblies and to maintain the fuel in a subcritical storage condition. METAMIC neutron absorber has been used in high-density storage racks. But, neutron absorber materials can be subject to severe conditions including long-term exposure to gamma radiation and neutron radiation. Recently, some of them have experienced degradation, such as white spots on the surface. Under these conditions, the material must continue to serve its intended function of absorbing neutrons. For the first time in Korea, this article uses a neutron attenuation test to examine the performance of METAMIC surveillance coupons. Also, scanning electron microscope analysis was carried out to verify the white spots that were detected on the surface of METAMIC. In the neutron attenuation test, there was no significant sign of boron loss in most of the METAMIC coupons, but the coupon with white spots had relatively less B-10 content than the others. In the scanning electron microscope analysis, corrosion material was detected in all METAMIC coupons. Especially, it was confirmed that the coupon with white spots contains much more corrosion material than the others. Keywords: Blister, Criticality, METAMIC, Neutron Absorber, Neutron Attenuation Test, Scanning Electron Microscope

Designation of facility usage categories for Hanford Site facilities

International Nuclear Information System (INIS)

Woodrich, D.D.; Ellingson, D.R.; Scott, M.A.; Schade, A.R.

1991-10-01

This report summarizes the Hanford Site methodology used to ensure facility compliance with the natural phenomena design criteria set forth in the US Department of Energy Orders and guidance. The current Hanford Site methodology for Usage Category designation is based on an engineered feature's safety function and on the feature's assigned Safety Class. At the Hanford Site, Safety Class assignments are deterministic in nature and are based on teh consequences of failure, without regard to the likelihood of occurrence. The report also proposes a risk-based approach to Usage Category designation, which is being considered for future application at the Hanford Site. To establish a proper Usage Category designation, the safety analysis and engineering design processes must be coupled. This union produces a common understanding of the safety function(s) to be accomplished by the design feature(s) and a sound basis for the assignment of Usage Categories to the appropriate systems, structures, and components. 4 refs., 9 figs., 1 tab

Design and construction of a fast critical facility

International Nuclear Information System (INIS)

Kato, W.Y.; Dates, L.R.

1962-01-01

Design and construction of a fast critical facility. In a fast-power-reactor development programme, a critical facility is found to be a highly useful tool to ascertain calculational techniques, to verify neutron cross-section sets, and to obtain integral reactor-physics parameters necessary for the nuclear design of a power system. Since it is primarily a physics instrument, the design of a fast critical facility itself poses a number of different problems not found in the design of a power reactor. In addition to usual questions of site, containment, core design and instrumentation , there arise such problems as: how to obtain a large degree of flexibility consistent with safety, the determination of the size and type of facility to meet the experimental physics requirements, the determination of the number and location of control and safety rods minimizing perturbation effects and the specification of the reproducibility of control rods and other movable components to obtain the accuracy required in reactivity measurements. These are some of the problems which are discussed in this paper based on recent experience at the Argonne National Laboratory which has under construction a fast critical facility, ZPR-VI at its Lemont, Illinois site for fast-reactor-physics studies. The ZPR-VI is a movable half- or split-table-type machine similar to ZPR-III. It has a matrix about two and a half times the volume of the earlier machine and will be used to investigate the physics of large, highly dilute, metal and cermet, unmoderated and partially moderated systems having core volumes up to about 1500 l. A detailed description of the ZPR-VI with a discussion on the criteria used in the design of its various components from the point of view of reactor physics is presented. In addition, such topics as management and operating procedures, potential hazards during operation, experimental techniques to be used and construction costs are also included. (author) [fr

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

International Nuclear Information System (INIS)

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

2015-01-01

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

A Facilities Manager's Guide to Green Building Design.

Science.gov (United States)

Simpson, Walter

2001-01-01

Explains how the "green building" approach to educational facilities design creates healthy, naturally lit, attractive buildings with lower operating and life cycle costs. Tips on getting started on a green design and overcoming the barriers to the green design concept are discussed. (GR)

HOTLink rack monitor

International Nuclear Information System (INIS)

Al R Franck et al.

2001-01-01

A remote data acquisition chassis, called a HOTLink Rack Monitor, HRM, has been developed for use in the Fermilab control system. This chassis provides for 64 analog input channels, 8 analog output channels, and 8 bytes of digital I/O. The interface to the host VMEbus crate is by way of a 320 MHz HOTLink serial connection to a PMC mezzanine module. With no processor intervention, all data sources in the remote chassis are read at 100 sec intervals, time stamped, and stored in a 2 MB circular buffer on the PMC module. In operation, the memory always contains the most recent 16 k samples of 10 kHz data from all 64 analog input channels. An expansion module that resides in the HRM chassis records snapshot data for 8 analog channels, each channel consisting of up to 16 k readings, digitized at rates up to 10 MHz. Snapshot data is also returned and stored in buffers on the PMC module. Because the HRM presents a memory-mapped interface to the host, it is independent of the operating system and may be used in any system that supports PMC mezzanine modules

Preliminary design for hot dirty-gas control-valve test facility. Final report

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

Design and operation of radiation facilities

International Nuclear Information System (INIS)

Gay, H.G.

1983-01-01

The design, manufacture, and operation of Cobalt-60 Radiation Processing Facilities is a well established technology. However, the products requiring radiation processing are constantly increasing. Product and dose variations create different requirements in the irradiator design. Several basic design concepts which have been developed and installed by Atomic Energy of Canada Limited are discussed. Irradiators are most efficient when designed to handle a limited product density range at an established dose. Requirements for irradiators to process a multitude of different products at different doses leads to a reduction of irradiator efficiency with resultant increase in processing costs

Steel Rack Connections: Identification of Most Influential Factors and a Comparison of Stiffness Design Methods

Science.gov (United States)

Shah, S. N. R.; Sulong, N. H. Ramli; Shariati, Mahdi; Jumaat, M. Z.

2015-01-01

Steel pallet rack (SPR) beam-to-column connections (BCCs) are largely responsible to avoid the sway failure of frames in the down-aisle direction. The overall geometry of beam end connectors commercially used in SPR BCCs is different and does not allow a generalized analytic approach for all types of beam end connectors; however, identifying the effects of the configuration, profile and sizes of the connection components could be the suitable approach for the practical design engineers in order to predict the generalized behavior of any SPR BCC. This paper describes the experimental behavior of SPR BCCs tested using a double cantilever test set-up. Eight sets of specimens were identified based on the variation in column thickness, beam depth and number of tabs in the beam end connector in order to investigate the most influential factors affecting the connection performance. Four tests were repeatedly performed for each set to bring uniformity to the results taking the total number of tests to thirty-two. The moment-rotation (M-θ) behavior, load-strain relationship, major failure modes and the influence of selected parameters on connection performance were investigated. A comparative study to calculate the connection stiffness was carried out using the initial stiffness method, the slope to half-ultimate moment method and the equal area method. In order to find out the more appropriate method, the mean stiffness of all the tested connections and the variance in values of mean stiffness according to all three methods were calculated. The calculation of connection stiffness by means of the initial stiffness method is considered to overestimate the values when compared to the other two methods. The equal area method provided more consistent values of stiffness and lowest variance in the data set as compared to the other two methods. PMID:26452047

Steel Rack Connections: Identification of Most Influential Factors and a Comparison of Stiffness Design Methods.

Directory of Open Access Journals (Sweden)

S N R Shah

Full Text Available Steel pallet rack (SPR beam-to-column connections (BCCs are largely responsible to avoid the sway failure of frames in the down-aisle direction. The overall geometry of beam end connectors commercially used in SPR BCCs is different and does not allow a generalized analytic approach for all types of beam end connectors; however, identifying the effects of the configuration, profile and sizes of the connection components could be the suitable approach for the practical design engineers in order to predict the generalized behavior of any SPR BCC. This paper describes the experimental behavior of SPR BCCs tested using a double cantilever test set-up. Eight sets of specimens were identified based on the variation in column thickness, beam depth and number of tabs in the beam end connector in order to investigate the most influential factors affecting the connection performance. Four tests were repeatedly performed for each set to bring uniformity to the results taking the total number of tests to thirty-two. The moment-rotation (M-θ behavior, load-strain relationship, major failure modes and the influence of selected parameters on connection performance were investigated. A comparative study to calculate the connection stiffness was carried out using the initial stiffness method, the slope to half-ultimate moment method and the equal area method. In order to find out the more appropriate method, the mean stiffness of all the tested connections and the variance in values of mean stiffness according to all three methods were calculated. The calculation of connection stiffness by means of the initial stiffness method is considered to overestimate the values when compared to the other two methods. The equal area method provided more consistent values of stiffness and lowest variance in the data set as compared to the other two methods.

Design of good manufacturing facility for sterile radioactive pharmaceuticals

International Nuclear Information System (INIS)

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

2002-01-01

Based on the GMP codes for radiopharmaceuticals in U.K. and some advanced countries, suitable guidelines for the production facility have been established and followed them up. The facility designs were fairly modified to maintain cleanliness criteria for installation in the existing radioisotope production facilities which are installed only in radiation safety points of view. Detailed design brief was drawn up by the Hyundai Engineering staffs, on the basis of initial planning and conceptual design was carried out by authors. Hot cells were installed in preparation room for radioactive handling. As hot cells under negative air pressure are not properly airtight, the surrounding environment was designed to keep less than class 10,000. Hot cells were designed to maintain less than class 1 0,000 and partially less than class 1 00 for production of sterile products. Final products will be autoclaved for sterilization after filling. To avoid contamination by microorganisms and particles of surrounding area, air curtain with vertical laminar flow will be installed between anteroom and corridor. In a pharmaceutical environment, the main consideration is the protection of the product. Thus, work station is held above ambient pressure. However, when handling radioactive materials, air pressure for work station should be lower than in surrounding areas to protect the operators and the remainder of the facility from airborne radioactive contamination. As Radiopharmaceuticals are radioactive materials for medical use, changing room could be held higher pressure than any other zones. It is expected that the facility will be effectively used for both routine preparation and research for sterile radiopharmaceuticals. (Author)

An automatic device for sample insertion and extraction to/from reactor irradiation facilities

International Nuclear Information System (INIS)

Alloni, L.; Venturelli, A.; Meloni, S.

1990-01-01

At the previous European Triga Users Conference in Vienna,a paper was given describing a new handling tool for irradiated samples at the L.E.N.A plant. This tool was the first part of an automatic device for the management of samples to be irradiated in the TRIGA MARK ii reactor and successively extracted and stored. So far sample insertion and extraction to/from irradiation facilities available on reactor top (central thimble,rotatory specimen rack and channel f),has been carried out manually by reactor and health-physics operators using the ''traditional'' fishing pole provided by General Atomic, thus exposing reactor personnel to ''unjustified'' radiation doses. The present paper describes the design and the operation of a new device, a ''robot''type machine,which, remotely operated, takes care of sample insertion into the different irradiation facilities,sample extraction after irradiation and connection to the storage pits already described. The extraction of irradiated sample does not require the presence of reactor personnel on the reactor top and,therefore,radiation doses are strongly reduced. All work from design to construction has been carried out by the personnel of the electronic group of the L.E.N.A plant. (orig.)

UTN's gamma irradiation facility: design and concept

International Nuclear Information System (INIS)

Mohamad Noor Mohamad Yunus

1986-01-01

UTN is building a multipurpose gamma irradiation facility which compromises of research and pilot scale irradiation cells in The Fifth Malaysia Plan. The paper high-lights the basic futures of the facility in terms of its design and selection including layout sketches. Plant performances and limitations are discussed. Plants safety is briefly highlighted in block diagrams. Lastly, a typical specification brief is tabled in appendix for reference purposes. (author)

Conceptual Design of an In-Space Cryogenic Fluid Management Facility

Science.gov (United States)

Willen, G. S.; Riemer, D. H.; Hustvedt, D. C.

1981-01-01

The conceptual design of a Spacelab experiment to develop the technology associated with low gravity propellant management is presented. The proposed facility consisting of a supply tank, receiver tank, pressurization system, instrumentation, and supporting hardware, is described. The experimental objectives, the receiver tank to be modeled, and constraints imposed on the design by the space shuttle, Spacelab, and scaling requirements, are described. The conceptual design, including the general configurations, flow schematics, insulation systems, instrumentation requirements, and internal tank configurations for the supply tank and the receiver tank, is described. Thermal, structural, fluid, and safety and reliability aspects of the facility are analyzed. The facility development plan, including schedule and cost estimates for the facility, is presented. A program work breakdown structure and master program schedule for a seven year program are included.

Material handling for the Los Alamos National Laboratory Nuclear Storage Facility

International Nuclear Information System (INIS)

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-01-01

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels

Method and apparatus for storing nuclear fuel assemblies in maximum density racks

International Nuclear Information System (INIS)

Wachter, W.J.; Robbins, T.R.

1979-01-01

A maximum density storage rack is provided for long term or semipermanent storage of spent nuclear fuel assemblies. The rack consists of storage cells arranged in a regular array, such as a checkerboard, and intended to be immersed in water. Initially, cap members are placed on alternate cells in such a manner that at least 50% of the cells are left open, some of the caps being removable. Spent fuel assemblies are then placed in the open cells until all of them are filled. The level of reactivity of each of the stored fuel assemblies is then determined by accurate calculation or by measurement, and the removable caps are removed and rearranged so that other cells are opened, permitting the storage of additional fuel assemblies in a pattern based on the actual reactivity such that criticality is prevented

Storage rack for nuclear fuel assemblies

International Nuclear Information System (INIS)

Wachter, W.J.

1988-01-01

A storage rack for nuclear fuel assemblies is described comprising storage tubes, each having a polygon cross-section. The tubes being nested with cell walls of one tube aligned with and confronting cell walls of other tubes. Each cell wall having an array of embossed buttons so arranged that buttons of one cell wall engage buttons of a confronting cell wall, and the engage buttons are welded together to secure the tubes. At least one layer of neutron-poison material comprises a flexible, resilient pad interprosed between the aligned cell walls; whereby a major portion of the total outer surface area of each confronting cell wall is engaged with the layer of neutron-poison material

Evaluation of seismic criteria used in design of INEL facilities

International Nuclear Information System (INIS)

Young, G.A.

1977-01-01

This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities

Technical considerations in the design of near surface disposal facilities for radioactive waste

International Nuclear Information System (INIS)

2001-11-01

Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

Cold Vacuum Drying facility civil - structural system design description (SYS 06)

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying (CVD) Facility civil - structural system. This system consists of the facility structure, including the administrative and process areas. The system's primary purpose is to provide for a facility to house the CVD process and personnel and to provide a tertiary level of containment. The document provides a description of the facility and demonstrates how the design meets the various requirements imposed by the safety analysis report and the design requirements document

The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

Energy Technology Data Exchange (ETDEWEB)

Nitti, F.S., E-mail: francesco.nitti@enea.it [IFMIF/EVEDA Project Team, Rokkasho Japan (Japan); Ibarra, A. [CIEMAT, Madrid (Spain); Ida, M. [IHI Corporation, Tokyo (Japan); Favuzza, P. [ENEA Research Center Firenze (Italy); Furukawa, T. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Groeschel, F. [KIT Research Center, Karlsruhe (Germany); Heidinger, R. [F4E Research Center, Garching (Germany); Kanemura, T. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Knaster, J. [IFMIF/EVEDA Project Team, Rokkasho Japan (Japan); Kondo, H. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Micchiche, G. [ENEA Research Center, Brasimone (Italy); Sugimoto, M. [JAEA Research Center, Rokkasho Japan (Japan); Wakai, E. [JAEA Research Center, Tokai-mura, Ibaraki (Japan)

2015-11-15

Highlights: • Results of validation and design activity for the Li loop facility of IFMIF. • Demonstration of Li target stability, with surface disturbance <1 mm. • Demonstration of start-up and shut down procedures of Li loop. • Complete design of the heat removal system and C and O purification system. • Conceptual design of N and H isotopes purification systems. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

International Nuclear Information System (INIS)

Nitti, F.S.; Ibarra, A.; Ida, M.; Favuzza, P.; Furukawa, T.; Groeschel, F.; Heidinger, R.; Kanemura, T.; Knaster, J.; Kondo, H.; Micchiche, G.; Sugimoto, M.; Wakai, E.

2015-01-01

Highlights: • Results of validation and design activity for the Li loop facility of IFMIF. • Demonstration of Li target stability, with surface disturbance <1 mm. • Demonstration of start-up and shut down procedures of Li loop. • Complete design of the heat removal system and C and O purification system. • Conceptual design of N and H isotopes purification systems. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

International Nuclear Information System (INIS)

1985-09-01

This document, Volume 5 Book 1, contains cost estimate summaries for a monitored retrievable storage (MRS) facility. The cost estimate is based on the engineering performed during the conceptual design phase of the MRS Facility project

Design of the target area for the National Ignition Facility

International Nuclear Information System (INIS)

Foley, R.J.; Karpenko, V.P.; Adams, C.H.

1997-01-01

The preliminary design of the target area for the National Ignition Facility has been completed. The target area is required to meet a challenging set of engineering system design requirements and user needs. The target area must provide the appropriate conditions before, during, and after each shot. The repeated introduction of large amounts of laser energy into the chamber and subsequent target emissions represent new design challenges for ICF facility design. Prior to each shot, the target area must provide the required target illumination, target chamber vacuum, diagnostics, and optically stable structures. During the shot, the impact of the target emissions on the target chamber, diagnostics, and optical elements is minimized and the workers and public are protected from excessive prompt radiation doses. After the shot, residual radioactivation is managed to allow the required accessibility. Diagnostic data is retrieved, operations and maintenance activities are conducted, and the facility is ready for the next shot. The target area subsystems include the target chamber, target positioner, structural systems, target diagnostics, environmental systems, and the final optics assembly. The engineering design of the major elements of the target area requires a unique combination of precision engineering, structural analysis, opto-mechanical design, random vibration suppression, thermal stability, materials engineering, robotics, and optical cleanliness. The facility has been designed to conduct both x- ray driven targets and to be converted at a later date for direct drive experiments. The NIF has been configured to provide a wide range of experimental environments for the anticipated user groups of the facility. The design status of the major elements of the target area is described

Spatial Rack Drives Pitch Configurations: Essence and Content

Science.gov (United States)

Abadjieva, Emilia; Abadjiev, Valentin; Naganawa, Akihiro

2018-03-01

The practical realization of all types of mechanical motions converters is preceded by solving the task of their kinematic synthesis. In this way, the determination of the optimal values of the constant geometrical parameters of the chosen structure of the created mechanical system is achieved. The searched result is a guarantee of the preliminary defined kinematic characteristics of the synthesized transmission and in the first place, to guarantee the law of motions transformation. The kinematic synthesis of mechanical transmissions is based on adequate mathematical modelling of the process of motions transformation and on the object, realizing this transformation. Basic primitives of the mathematical models for synthesis upon a pitch contact point are geometric and kinematic pitch configurations. Their dimensions and mutual position in space are the input parameters for the processes of design and elaboration of the synthesized mechanical device. The study presented here is a brief review of the theory of pitch configurations. It is an independent scientific branch of the spatial gearing theory (theory of hyperboloid gears). On this basis, the essence and content of the corresponding primitives, applicable to the synthesis of spatial rack drives, are defined.

Conceptual design and neutronics analyses of a fusion reactor blanket simulation facility

International Nuclear Information System (INIS)

Beller, D.E.; Ott, K.O.; Terry, W.K.

1987-01-01

A new conceptual design of a fusion reactor blanket simulation facility has been developed. This design follows the principles that have been successfully employed in the Purdue Fast Breeder Blanket Facility (FBBF), where experiments have resulted in the discovery of substantial deficiencies in neutronics predictions. With this design, discrepancies between calculation and experimental data can be nearly fully attributed to calculation methods because design deficiencies that could affect results are insignificant. The conceptual design of this FBBF analog, the Fusion Reactor Blanket Facility, is presented

Conceptual design of the National Ignition Facility

International Nuclear Information System (INIS)

Paisner, J.A.; Kumpan, S.A.; Lowdermilk, W.H.; Boyes, J.D.; Sorem, M.

1995-01-01

DOE commissioned a Conceptual Design Report (CDR) for the National Ignition Facility (NIF) in January 1993 as part of a Key Decision Zero (KDO), justification of Mission Need. Motivated by the progress to date by the Inertial Confinement Fusion (ICF) program in meeting the Nova Technical Contract goals established by the National Academy of Sciences in 1989, the Secretary requested a design using a solid-state laser driver operating at the third harmonic (0.35 μm) of neodymium (Nd) glass. The participating ICF laboratories signed a Memorandum of Agreement in August 1993, and established a Project organization, including a technical team from the Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the Laboratory for Laser Energetics at the University of Rochester. Since then, we completed the NIF conceptual design, based on standard construction at a generic DOE Defense Program's site, and issued a 7,000-page, 27-volume CDR in May 1994.2 Over the course of the conceptual design study, several other key documents were generated, including a Facilities Requirements Document, a Conceptual Design Scope and Plan, a Target Physics Design Document, a Laser Design Cost Basis Document, a Functional Requirements Document, an Experimental Plan for Indirect Drive Ignition, and a Preliminary Hazards Analysis (PHA) Document. DOE used the PHA to categorize the NIF as a low-hazard, non-nuclear facility. On October 21, 1994 the Secretary of Energy issued a Key Decision One (KD1) for the NIF, which approved the Project and authorized DOE to request Office of Management and Budget-approval for congressional line-item FY 1996 NIF funding for preliminary engineering design and for National Environmental Policy Act activities. In addition, the Secretary declared Livermore as the preferred site for constructing the NIF. The Project will cost approximately $1.1 billion and will be completed at the end of FY 2002

Exploratory shaft facility preliminary designs - Paradox Basin. Technical report

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Paradox Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Paradox Basin, Utah. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling Method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers is included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references

Seismic design standardization of nuclear facilities

International Nuclear Information System (INIS)

Reddy, G.R.; Vaze, K.K.

2011-01-01

Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

Design and construction of the Fuels and Materials Examination Facility

International Nuclear Information System (INIS)

Burgess, C.A.

1979-01-01

Final design is more than 85 percent complete on the Fuels and Materials Examination Facility, the facility for post-irradiation examination of the fuels and materials tests irradiated in the FFTF and for fuel process development, experimental test pin fabrication and supporting storage, assay, and analytical chemistry functions. The overall facility is generally described with specific information given on some of the design features. Construction has been initiated and more than 10% of the construction contracts have been awarded on a fixed price basis

Implementation of decommissioning criteria in the conceptual design of the MRS facility

International Nuclear Information System (INIS)

Gross, D.L.; Wilcox, A.D.; Huang, S.

1986-01-01

The US Department of Energy (DOE) selected the Ralph M. Parsons Company (RMP) to prepare the conceptual design of the Monitored Retrievable Storage (MRS) Facility. The purpose of this facility is to consolidate and temporarily store spent fuel from civilian nuclear power plants. In addition, it will overpack, handle, and store high-level radioactive waste from non-defense related sources. The Functional Design Criteria (FDC) prepared by Pacific Northwest Laboratories, as well as 10 CFR 72, requires the facility to be designed for decommissioning, with provisions to facilitate decontamination of structures and equipment to minimize the volume of radioactive wastes and contaminated equipment at the time of decommissioning. Many problems associated with decommissioning a nuclear facility have been identified in recent years and the design for the MRS Facility presents a unique opportunity for RMP to implement decommissioning criteria into the conceptual design of a major nuclear facility. The provisions made in the design to facilitate decommissioning include good housekeeping during operations, controlled personnel access, access for equipment removal, equipment design, installed radiation monitors, adequate work space, installed decontamination systems and areas, control of all effluents, and operational documentation. These topics will be the major points of discussion for this paper

Final design of ITER port plug test facility

Energy Technology Data Exchange (ETDEWEB)

Cerisier, Thierry, E-mail: thierry.cerisier@yahoo.fr [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Levesy, Bruno [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Romannikov, Alexander [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation); Rumyantsev, Yuri [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Cordier, Jean-Jacques; Dammann, Alexis [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Minakov, Victor; Rosales, Natalya; Mitrofanova, Elena [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Portone, Sergey; Mironova, Ekaterina [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation)

2016-11-01

Highlights: • We introduce the port plug test facility (purpose and status of the design). • We present the PPTF sub-systems. • We present the environmental and functional tests. • We present the occupational and nuclear safety functions. • We conclude on the achievements and next steps. - Abstract: To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installation on the machine and after refurbishment. The ITER port plug test facility (PPTF) is composed of several test stands that can be used to test the port plugs whereas at the end of manufacturing (in a non-nuclear environment), or after refurbishment in the ITER hot cell facility. The PPTF provides the possibility to perform environmental (leak tightness, vacuum and thermo-hydraulic performances) and functional tests (radio frequency acceptance tests, behavior of the plugs’ steering mechanism and calibration of diagnostics) on upper and equatorial port plugs. The final design of the port plug test facility is described. The configuration of the standalone test stands and the integration in the hot cell facility are presented.

Designing Animation Facilities for gCSP

NARCIS (Netherlands)

van der Steen, T.T.J.; Groothuis, M.A.; Broenink, Johannes F.

To improve feedback on how concurrent CSP-based programs run, the graphical CSP design tool has been extended with animation facilities. The state of processes, constructs, and channel ends are indicated with colours both in the gCSP diagrams and in the composition tree (hierarchical tree showing

Final Design Report for the RH LLW Disposal Facility (RDF) Project, Revision 3

International Nuclear Information System (INIS)

Austad, Stephanie Lee

2015-01-01

The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

Development of demonstration facility design technology for advanced nuclear fuel cycle process

International Nuclear Information System (INIS)

Cho, Il Je; You, G. S.; Choung, W. M.; Lee, E. P.; Hong, D. H.; Lee, W. K.; Ku, J. H.; Moon, S. I.; Kwon, K. C.; Lee, K. I. and other

2012-04-01

PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. It is essential to develop design technologies for the advanced nuclear fuel cycle demonstration facilities and complete the detailed design of PRIDE facility with capabilities of the stringent inert atmosphere control, fully remote operation which are necessary to develop the high-temperature molten salts technology. For these, it is necessary to design the essential equipment of large scale inert cell structure and the control system to maintain the inert atmosphere, and evaluate the safety. To construct the hot cell system which is appropriate for pyroprocess, some design technologies should be developed, which include safety evaluation for effective operation and maintenance, radiation safety analysis for hot cell, structural analysis, environmental evaluation, HVAC systems and electric equipment

Shielding design for positron emission tomography facility

International Nuclear Information System (INIS)

Abdallah, I.I.

2007-01-01

With the recent advent of readily available tracer isotopes, there has been marked increase in the number of hospital-based and free-standing positron emission tomography (PET) clinics. PET facilities employ relatively large activities of high-energy photon emitting isotopes, which can be dangerous to the health of humans and animals. This coupled with the current dose limits for radiation worker and members of the public can result in shielding requirements. This research contributes to the calculation of the appropriate shielding to keep the level of radiation within an acceptable recommended limit. Two different methods were used including measurements made at selected points of an operating PET facility and computer simulations by using Monte Carlo Transport Code. The measurements mainly concerned the radiation exposure at different points around facility using the survey meter detectors and Thermoluminescent Dosimeters (TLD). Then the set of manual calculation procedures were used to estimate the shielding requirements for a newly built PEF facility. The results from the measurement and the computer simulation were compared to the results obtained from the set manual calculation procedure. In general, the estimated weekly dose at the points of interest is lower than the regulatory limits for the little company of Mary Hospital. Furthermore, the density and the HVL for normal strength concrete and clay bricks are almost similar. In conclusion, PET facilities present somewhat different design requirements and are more likely to require additional radiation shielding. Therefore, existing shields at the little Company of Mary Hospital are in general found to be adequate and satisfactory and additional shielding was found necessary at the new PET facility in the department of Nuclear Medicine of the Dr. George Mukhari Hospital. By use of appropriate design, by implying specific shielding requirements and by maintaining good operating practices, radiation doses to

Functional design criteria for an exploratory shaft facility in salt: Technical report

International Nuclear Information System (INIS)

1986-11-01

The purpose of the Functional Criteria for Design is to provide technical direction for the development of detailed design criteria for the exploratory shaft facility. This will assure that the exploratory shaft facility will be designed in accordance with the current Mission Plan as well as the Nuclear Waste Policy Act and 10 CFR Part 60, which will facilitate the licensing process. The functional criteria for design are not intended to limit or constrain the designer's flexibility. The following philosophies will be incorporated in the designs: (1) The exploratory shaft will be designed to fulfill its intended purpose which is to characterize the salt site by subsurface testing; (2) the design will minimize any adverse impact which the facility may cause to the environment and any damage to the site if it should be found suitable for a repository; (3) the health and safety of the public and of the workers will be an essential factor in the design; (4) sound engineering principles and practices will be consistently employed in the design process; (5) the exploratory shaft and related surface and subsurface facilities will be designed to be economical and reliable in construction, operation, and maintenance; and (6) the exploratory shaft facility will be designed in accordance with applicable federal, state, and local regulations, as well as all applicable national consensus codes and standards

Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

International Nuclear Information System (INIS)

1985-09-01

This report presents a summary design description of the Conceptual Design for an Integral Monitored Retrievable Storage (MRS) Facility, as prepared by The Ralph M. Parsons Company under an A-E services contract with the Richland Operations Office of the Department of Energy. More detailed design requirements and design data are set forth in the Basis for Design and Design Report, bound under separate cover and available for reference by those desiring such information. The design data provided in this Design Report Executive Summary, the Basis for Design, and the Design Report include contributions by the Waste Technology Services Division of Westinghouse Electric Corporation (WEC), which was responsible for the development of the waste receiving, packaging, and storage systems, and Golder Associates Incorporated (GAI), which supported the design development with program studies. The MRS Facility design requirements, which formed the basis for the design effort, were prepared by Pacific Northwest Laboratory for the US Department of Energy, Richland Operations Office, in the form of a Functional Design Criteria (FDC) document, Rev. 4, August 1985. 9 figs., 6 tabs

Controlling allergens in animal rooms by using curtains

DEFF Research Database (Denmark)

Krohn, Thomas Cæcius; Itter, Gabi; Fosse, Richard

2006-01-01

The reduction and control of allergens in the animal facility is important for staff working with laboratory animals. This study was designed to evaluate the efficiency of perforated Makrolon curtains in front of racks as a method to reduce the amount of allergen in the animal room. The experimen......The reduction and control of allergens in the animal facility is important for staff working with laboratory animals. This study was designed to evaluate the efficiency of perforated Makrolon curtains in front of racks as a method to reduce the amount of allergen in the animal room....... The experimental situation we studied provides some information regarding allergen disposition in animal rooms but is clearly artificial and does not reflect a typical, ‘real-world’ environment in terms of preventing exposure of workers to allergens. Plastic curtains with holes were placed in front of racks......, and a corridor between the racks and a curtain was present. The room was ventilated with air, which was blown into the room through the middle of the corridor, flowing downstream and passing through the holes in the curtain. This set-up resulted in air flow from the corridor through the curtain. Air samples were...

Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

International Nuclear Information System (INIS)

1985-09-01

This document, Volume 6 Book 1, contains information on design studies of a Monitored Retrievable Storage (MRS) facility. Topics include materials handling; processing; support systems; support utilities; spent fuel; high-level waste and alpha-bearing waste storage facilities; and field drywell storage

Integral Monitored Retrievable Storage (MRS) Facility conceptual basis for design

International Nuclear Information System (INIS)

1985-10-01

The purpose of the Conceptual Basis for Design is to provide a control document that establishes the basis for executing the conceptual design of the Integral Monitored Retrievable Storage (MRS) Facility. This conceptual design shall provide the basis for preparation of a proposal to Congress by the Department of Energy (DOE) for construction of one or more MRS Facilities for storage of spent nuclear fuel, high-level radioactive waste, and transuranic (TRU) waste. 4 figs., 25 tabs

A strategic approach to the conceptual design of complex radwaste facilities

International Nuclear Information System (INIS)

Mackay, Stewart; Scott Dam, A.; Holmes, Robert G.G.

1992-01-01

The design of radwaste treatment facilities is often complicated by the variety of waste types being treated. Further uncertainties over their composition and final waste form specifications can make the normal conceptual design phase difficult and unreliable. This paper describes the strategic planning necessary to define the facility functions and the process to prepare a Functional Design Criteria. The paper shows clearly, that for complex waste management problems, it is vital to consider and resolve uncertainties by means of a strategic plan before embarking on conceptual design. The paper shows an approach to preparation of design criteria using functional analysis. The paper provides examples where these methods were and are being used, both in the U.K. and the U.S. Strategic plans and functional criteria can be used as a basis for conceptual design which then provides a more meaningful basis for detailed technology selection during the detailed design process. The paper discusses experiences and lessons learned in the planning process. This process is widely applicable to a number of complex waste treatment facilities being planned and developed to process wastes generated at government facilities. (author)

E-4 Test Facility Design Status

Science.gov (United States)

Ryan, Harry; Canady, Randy; Sewell, Dale; Rahman, Shamim; Gilbrech, Rick

2001-01-01

Combined-cycle propulsion technology is a strong candidate for meeting NASA space transportation goals. Extensive ground testing of integrated air-breathing/rocket system (e.g., components, subsystems and engine systems) across all propulsion operational modes (e.g., ramjet, scramjet) will be needed to demonstrate this propulsion technology. Ground testing will occur at various test centers based on each center's expertise. Testing at the NASA John C. Stennis Space Center will be primarily concentrated on combined-cycle power pack and engine systems at sea level conditions at a dedicated test facility, E-4. This paper highlights the status of the SSC E-4 test Facility design.

Nuclear fuel rack lateral support and preload device

International Nuclear Information System (INIS)

Knight, C.B.

1979-01-01

A lateral support device for a nuclear fuel rack is described. It is vertically positioned within a walled enclosure which provides a preload to maintain effective support. The device includes a scissors-jack which is mounted so that the drive screw is vertical. Upon rotation of the drive screw the jack expands horizontally, seating a load pad against a vertical wall. The load pad is affixed to the jack by an arm having a stack of spring washers which compress between the pad and the jack, thereby applying a selected preload

LASL experimental engineered waste burial facility: design considerations and preliminary plan

International Nuclear Information System (INIS)

DePoorter, G.L.

1980-01-01

The LASL Experimental Engineered Waste Burial Facility is a part of the National Low-Level Waste Management Program on Shallow-Land Burial Technology. It is a test facility where basic information can be obtained on the processes that occur in shallow-land burial operations and where new concepts for shallow-land burial can be tested on an accelerated basis on an appropriate scale. The purpose of this paper is to present some of the factors considered in the design of the facility and to present a preliminary description of the experiments that are initially planned. This will be done by discussing waste management philosophies, the purposes of the facility in the context of the waste management philosophy for the facility, and the design considerations, and by describing the experiments initially planned for inclusion in the facility, and the facility site

Conceptual design and cost estimation of dry cask storage facility for spent fuel

International Nuclear Information System (INIS)

Maki, Yasuro; Hironaga, Michihiko; Kitano, Koichi; Shidahara, Isao; Shiomi, Satoshi; Ohnuma, Hiroshi; Saegusa, Toshiari

1985-01-01

In order to propose an optimum storage method of spent fuel, studies on the technical and economical evaluation of various storage methods have been carried out. This report is one of the results of the study and deals with storage facility of dry cask storage. The basic condition of this work conforms to ''Basic Condition for Spent Fuel Storage'' prepared by Project Group of Spent Fuel Dry Storage at July 1984. Concerning the structural system of cask storage facilities, trench structure system and concrete silo system are selected for storage at reactor (AR), and a reinforced concrete structure of simple design and a structure with membrance roof are selected for away from reactor (AFR) storage. The basic thinking of this selection are (1) cask is put charge of safety against to radioactivity and (2) storage facility is simplified. Conceptual designs are made for the selected storage facilities according to the basic condition. Attached facilities of storage yard structure (these are cask handling facility, cask supervising facility, cask maintenance facility, radioactivity control facility, damaged fuel inspection and repack facility, waste management facility) are also designed. Cost estimation of cask storage facility are made on the basis of the conceptual design. (author)

Engineering design of the Nova Laser Facility for inertial-confinement fusion

International Nuclear Information System (INIS)

Simmons, W.W.; Godwin, R.O.; Hurley, C.A.

1982-01-01

The design of the Nova Laser Facility for inertial confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to-performance requirements as they impact the various subsystems that comprise this complex experimental facility

Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

International Nuclear Information System (INIS)

1975-12-01

The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

AN INTERNET RACK MONITOR-CONTROLLER FOR APS LINAC RF ELECTRONICS UPGRADE

Energy Technology Data Exchange (ETDEWEB)

Ma, Hengjie; Smith, Terry; Nassiri, Alireza; Sun, Yine; Doolittle, Lawrence; Ratti, Alex

2016-06-01

To support the research and development in APS LINAC area, the existing LINAC rf control performance needs to be much improved, and thus an upgrade of the legacy LINAC rf electronics becomes necessary. The proposed upgrade plan centers on the concept of using a modern, network-attached, rackmount digital electronics platform –Internet Rack Monitor-Controller (or IRMC) to achieve the goal of modernizing the rf electronics at a lower cost. The system model of the envisioned IRMC is basically a 3-tier stack with a high-performance DSP in the mid-layer to perform the core tasks of real-time rf data processing and controls. The Digital Front-End (DFE) attachment layer at bottom bridges the applicationspecific rf front-ends to the DSP. A network communication gateway, together with an embedded event receiver (EVR) in the top layer merges the Internet Rack MonitorController node into the networks of the accelerator controls infrastructure. Although the concept is very much in trend with today’s Internet-of-Things (IoT), this implementation has actually been used in the accelerators for over two decades.

Earthquake resistant design of nuclear facilities with limited radioactive inventory

International Nuclear Information System (INIS)

1985-10-01

This document comprises the essential elements of an earthquake resistant design code for nuclear facilities with limited radioactive inventory. The purpose of the document is the enhancement of seismic safety for such facilities without the necessity to resort to complicated and sophisticated methodologies which are often associated with and borrowed from nuclear power plant analysis and design. The first two sections are concerned with the type of facility for which the document is applicable and the radiological consideration for accident conditions. The principles of facility classification and item categorization as a function of the potential radiological consequences of failure are given in section 3. The design basis ground motion is evaluated in sections 4-6 using a simplified but conservative approach which also includes considerations for the underlying soil characteristics. Sections 7 and 8 specify the principles of seismic design of building structures and equipment using two methods, called the equivalent static and simplified dynamic approach. Considerations for the detailing of equipment and piping and those other than for lateral load calculations, such as sloshing effects, are given in the subsequent sections. Several appendices are given for illustration of the principles presented in the text. Finally, a design tree diagram is included to facilitate the user's task of making the appropriate selections. (author)

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.

Design of an integrated non-destructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.

1984-01-01

The Department of Energy requires improved technology for nuclear materials accounting as an essential part of new plutonium processing facilities. New facilities are being constructed at the Savannah River Plant by the Du Pont Company, Operating Contractor, to recover plutonium from scrap and waste material generated at SRP and other DOE contract processing facilities. This paper covers design concepts and planning required to incorporate state-of-the-art plutonium assay instruments developed at several national laboratories into an integrated, at-line nuclear material accounting facility operating in the production area. 3 figures

Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

2009-09-01

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOE’s Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

Graphical explanation in an expert system for Space Station Freedom rack integration

Science.gov (United States)

Craig, F. G.; Cutts, D. E.; Fennel, T. R.; Purves, B.

1990-01-01

The rationale and methodology used to incorporate graphics into explanations provided by an expert system for Space Station Freedom rack integration is examined. The rack integration task is typical of a class of constraint satisfaction problems for large programs where expertise from several areas is required. Graphically oriented approaches are used to explain the conclusions made by the system, the knowledge base content, and even at more abstract levels the control strategies employed by the system. The implemented architecture combines hypermedia and inference engine capabilities. The advantages of this architecture include: closer integration of user interface, explanation system, and knowledge base; the ability to embed links to deeper knowledge underlying the compiled knowledge used in the knowledge base; and allowing for more direct control of explanation depth and duration by the user. The graphical techniques employed range from simple statis presentation of schematics to dynamic creation of a series of pictures presented motion picture style. User models control the type, amount, and order of information presented.

Study and project of the new rack with boron for storage of fuel elements burned in the IEA-R1 research reactor

International Nuclear Information System (INIS)

Rodrigues, Antonio Carlos Iglesias; Madi Filho, Tufic; Silva, Davilson Gomes da

2017-01-01

The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor's pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3TMhis) was chosen due to its properties. This work presents studies: (a) for the construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Library were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission - CNEN and the International Atomic Energy Agency (IAEA). To calculate the k eff were considered new fuel elements (maximum possible reactivity) used in full charge of the storage rack. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff < 0.95). (author)

Study and project of the new rack with boron for storage of fuel elements burned in the IEA-R1 research reactor

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, Antonio Carlos Iglesias; Madi Filho, Tufic; Silva, Davilson Gomes da, E-mail: acirodri@ipen.br, E-mail: tmfilho@usp.br, E-mail: dgsilva@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The IEA-R1 research reactor works 40h weekly with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions (current conditions of reactor operation 32h weekly will have 3 spend fuel by year, then, approximately 3 utilization rate Positions/year). Thus, we will have only about six years of capacity for storage. Whereas the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel. Hence, it is necessary to double the wet storage capacity (storage in the IEA-R1 reactor's pool). After reviewing the literature about materials available for use in the construction of the new storage rack with absorber of neutrons, the BoralcanTM (manufactured by 3TMhis) was chosen due to its properties. This work presents studies: (a) for the construction of new storages racks with double of the current capacity using the same place of current storages racks and (b) criticality analysis using the MCNP-5 code. Two American Nuclear Data Library were used: ENDF / B-VI and ENDF / B-VII, and the results obtained for each data bases were compared. These analyzes confirm the possibility of doubling the storage capacity of fuel elements burned in the same place occupied by the current storage rack attending to the IEA-R1 reactor needs and attending the safety requirements according to the National Nuclear Energy Commission - CNEN and the International Atomic Energy Agency (IAEA). To calculate the k{sub eff} were considered new fuel elements (maximum possible reactivity) used in full charge of the storage rack. With the results obtained in the simulation we can conclude that doubling the amount of racks for spent fuel elements are complied with safety limits established in the IAEA standards and CNEN of criticality (keff < 0.95). (author)

Design strategies for the International Space University's variable gravity research facility

Science.gov (United States)

Bailey, Sheila G.; Chiaramonte, Francis P.; Davidian, Kenneth J.

1990-01-01

A variable gravity research facility named 'Newton' was designed by 58 students from 13 countries at the International Space University's 1989 summer session at the Universite Louis Pasteur, Strasbourge, France. The project was comprehensive in scope, including a political and legal foundation for international cooperation, development and financing; technical, science and engineering issues; architectural design; plausible schedules; and operations, crew issues and maintenance. Since log-term exposure to zero gravity is known to be harmful to the human body, the main goal was to design a unique variable gravity research facility which would find a practical solution to this problem, permitting a manned mission to Mars. The facility would not duplicate other space-based facilities and would provide the flexibility for examining a number of gravity levels, including lunar and Martian gravities. Major design alternatives included a truss versus a tether based system which also involved the question of docking while spinning or despinning to dock. These design issues are described. The relative advantages or disadvantages are discussed, including comments on the necessary research and technology development required for each.

Sound & Vibration 20 Design Guidelines for Health Care Facilities

CERN Document Server

Tocci, Gregory; Cavanaugh, William

2013-01-01

Sound, vibration, noise and privacy have significant impacts on health and performance. As a result, they are recognized as essential components of effective health care environments. However, acoustics has only recently become a prominent consideration in the design, construction, and operation of healthcare facilities owing to the absence, prior to 2010, of clear and objective guidance based on research and best practices. Sound & Vibration 2.0 is the first publication to comprehensively address this need. Sound & Vibration 2.0 is the sole reference standard for acoustics in health care facilities and is recognized by: the 2010 FGI Guidelines for the Design and Construction of Health Care Facilities (used in 60 countries); the US Green Building Council’s LEED for Health Care (used in 87 countries); The Green Guide for Health Care V2.2; and the International Code Council (2011). Sound & Vibration 2.0 was commissioned by the Facility Guidelines Institute in 2005, written by the Health Care Acous...

Lactobacillus casei triggers a TLR mediated RACK-1 dependent p38 MAPK pathway in Caenorhabditis elegans to resist Klebsiella pneumoniae infection.

Science.gov (United States)

Kamaladevi, Arumugam; Balamurugan, Krishnaswamy

2016-07-13

In the present study, the effect of Lactic Acid Bacteria (LAB) was investigated at the molecular level using the model organism Caenorhabditis elegans against Klebsiella pneumoniae. Out of the 13 LAB screened, Lactobacillus casei displayed excellent protective efficacy by prolonging the survival of K. pneumoniae-infected nematodes. Pretreatment with L. casei significantly decreased bacterial colonization and rescued K. pneumoniae-infected C. elegans from various physiological impairments. The concomitant upregulation of key immune genes that regulate the TLR, RACK-1 as well as the p38 MAPK pathway rather than the IIS and ERK pathway suggested that the plausible immunomodulatory mechanism of L. casei could be by triggering the TLR, RACK-1 and p38 MAPK pathway. Furthermore, the hyper-susceptibility of L. casei treated loss-of-function mutants of the tol-1, RACK-1 and p38 MAPK pathway (sek-1 and pmk-1) to K. pneumoniae infection and gene expression analysis suggested that L. casei triggered a TLR mediated RACK-1 dependent p38 MAPK pathway to increase host resistance and protect nematodes against K. pneumoniae infection.

ECONOMIC EVALUATION OF MAINTAINING THE CAPACITY OF TRASH RACKS IN HYDRAULIC ENGINEERING STRUCTURES

Directory of Open Access Journals (Sweden)

Natalia Walczak

2017-05-01

Full Text Available Considering the limited capabilities of obtaining energy in a traditional way from coal combustion and the requirements of the European Union, other alternative energy sources should be sought. They have been being increasingly used by business entities and individual investors and are designed to provide financial profits, which will be ensured only with correct operation of the energy system. One of examples of alternative energy sources application is the construction of small hydropower plants, where the efficiency of all elements included is of great importance. The article analyses financial losses incurred by owners of power plants when the energy system lacks 100% capacity of the inlet channel. Material that accumulates on SHP trash racks might be analysed in two ways: biologically (these are screenings – as in wastewater treatment plants and hydraulically.

Design and Construction of a Hydroturbine Test Facility

Science.gov (United States)

Ayli, Ece; Kavurmaci, Berat; Cetinturk, Huseyin; Kaplan, Alper; Celebioglu, Kutay; Aradag, Selin; Tascioglu, Yigit; ETU Hydro Research Center Team

2014-11-01

Hydropower is one of the clean, renewable, flexible and efficient energy resources. Most of the developing countries invest on this cost-effective energy source. Hydroturbines for hydroelectric power plants are tailor-made. Each turbine is designed and constructed according to the properties, namely the head and flow rate values of the specific water source. Therefore, a center (ETU Hydro-Center for Hydro Energy Research) for the design, manufacturing and performance tests of hydraulic turbines is established at TOBB University of Economics and Technology to promote research in this area. CFD aided hydraulic and structural design, geometry optimization, manufacturing and performance tests of hydraulic turbines are the areas of expertise of this center. In this paper, technical details of the design and construction of this one of a kind test facility in Turkey, is explained. All the necessary standards of IEC (International Electrotechnical Commission) are met since the test facility will act as a certificated test center for hydraulic turbines.

Design Integration of Facilities Management

DEFF Research Database (Denmark)

Jensen, Per Anker

2009-01-01

One of the problems in the building industry is a limited degree of learning from experiences of use and operation of existing buildings. Development of professional facilities management (FM) can be seen as the missing link to bridge the gap between building operation and building design....... Strategies, methods and barriers for the transfer and integration of operational knowledge into the design process are discussed. Multiple strategies are needed to improve the integration of FM in design. Building clients must take on a leading role in defining and setting up requirements and procedures...... on literature studies and case studies from the Nordic countries in Europe, including research reflections on experiences from a main case study, where the author, before becoming a university researcher, was engaged in the client organization as deputy project director with responsibility for the integration...

The Life Cycle Application of Intelligent Software Modeling for the First Materials Science Research Rack

Science.gov (United States)

Rice, Amanda; Parris, Frank; Nerren, Philip

2000-01-01

Marshall Space Flight Center (MSFC) has been funding development of intelligent software models to benefit payload ground operations for nearly a decade. Experience gained from simulator development and real-time monitoring and control is being applied to engineering design, testing, and operation of the First Material Science Research Rack (MSRR-1). MSRR-1 is the first rack in a suite of three racks comprising the Materials Science Research Facility (MSRF) which will operate on the International Space Station (ISS). The MSRF will accommodate advanced microgravity investigations in areas such as the fields of solidification of metals and alloys, thermo-physical properties of polymers, crystal growth studies of semiconductor materials, and research in ceramics and glasses. The MSRR-1 is a joint venture between NASA and the European Space Agency (ESA) to study the behavior of different materials during high temperature processing in a low gravity environment. The planned MSRR-1 mission duration is five (5) years on-orbit and the total design life is ten (IO) years. The MSRR-1 launch is scheduled on the third Utilization Flight (UF-3) to ISS, currently in February of 2003). The objective of MSRR-1 is to provide an early capability on the ISS to conduct material science, materials technology, and space product research investigations in microgravity. It will provide a modular, multi-user facility for microgravity research in materials crystal growth and solidification. An intelligent software model of MSRR-1 is under development and will serve multiple purposes to support the engineering analysis, testing, training, and operational phases of the MSRR-1 life cycle development. The G2 real-time expert system software environment developed by Gensym Corporation was selected as the intelligent system shell for this development work based on past experience gained and the effectiveness of the programming environment. Our approach of multi- uses of the simulation model and

Design and integration of lower ports for ITER diagnostic systems

Energy Technology Data Exchange (ETDEWEB)

Casal, Natalia, E-mail: Natalia.casal@iter.org [ITER Organization, Route de Vinon-sur-Verdon – CS 90 046 – 13067 St Paul Lez Durance Cedex (France); Bertalot, Luciano; Cheng, Hao; Drevon, Jean Marc; Duckworth, Philip; Giacomin, Thibaud; Guirao, Julio; Iglesias, Silvia [ITER Organization, Route de Vinon-sur-Verdon – CS 90 046 – 13067 St Paul Lez Durance Cedex (France); Kochergin, Mikhail [IOFFE Institute, Saint Petersburg (Russian Federation); Martin, Alex [ITER Organization, Route de Vinon-sur-Verdon – CS 90 046 – 13067 St Paul Lez Durance Cedex (France); McCarron, Eddie [Oxford Technologies Ltd., Abingdon (United Kingdom); Mokeev, Alexander [Russian Federation Domestic Agency, Moscow (Russian Federation); Mota, Fernando [CIEMAT, Madrid (Spain); Penot, Christophe; Portales, Mickael [ITER Organization, Route de Vinon-sur-Verdon – CS 90 046 – 13067 St Paul Lez Durance Cedex (France); Kitazawa, Sin-iti [Japanese Domestic Agency, Naka (Japan); Sky, Jack [Oxford Technologies Ltd., Abingdon (United Kingdom); Suarez, Alejandro; Udintsev, Victor; Utin, Yuri [ITER Organization, Route de Vinon-sur-Verdon – CS 90 046 – 13067 St Paul Lez Durance Cedex (France); and others

2015-10-15

Highlights: • Lower port structures are in its conceptual design phase. • Electromagnetic and seismic loads, will dominate all other mechanical loads. • Design allows diagnostics support, neutron shielding while and signals transmission. • Installation and maintenance operations are fully remote handling compatible. - Abstract: All around the ITER vacuum vessel, forty-four ports will provide access to the vacuum vessel for remote handling operations, diagnostic systems, heating, and vacuum systems: 18 upper ports, 17 equatorial ports, and 9 lower ports. Among the lower ports, three of them will be used for the remote handling installation of the ITER divertor. Once the divertor is in place, these ports will host various diagnostic systems mounted in the so-called diagnostic racks. The diagnostic racks must allow the support and cooling of the diagnostics, extraction of the required diagnostic signals, and providing access and maintainability while minimizing the leakage of radiation toward the back of the port where the humans are allowed to enter. A fully integrated inner rack, carrying the near plasma diagnostic components, will be an stainless steel structure, 4.2 m long, with a maximum weight of 10 t. This structure brings water for cooling and baking at maximum temperature of 240 °C and provides connection with gas, vacuum and electric services. Additional racks (placed away from plasma and not requiring cooling) may be required for the support of some particular diagnostic components. The diagnostics racks and its associated ex vessel structures, which are in its conceptual design phase, are being designed to survive the lifetime of ITER of 20 years. This paper presents the current state of development including interfaces, diagnostic integration, operation and maintenance, shielding requirements, remote handling, loads cases and discussion of the main challenges coming from the severe environment and engineering requirements.

Metal-driven and covalent synthesis of supramolecular grids from racks: a convergent approach to heterometallic and heteroleptic nanostructures.

Science.gov (United States)

Schmittel, Michael; Kalsani, Venkateshwarlu; Bats, Jan W

2005-06-13

Supramolecular nanogrids were prepared from dynamic supramolecular racks through the coupling of terminal alkynes using either a covalent (with CuCl/O(2)) or a coordinative (with [trans-(PEt(3))(2)PtCl(2)]) approach. Because of the rapid equilibration of the racks (as tested by exchange reactions), oligomeric adducts potentially formed in the coupling process will selectively furnish the nanogrids through an entropically driven self-repair mechanism. To ascertain the structural assignment, the nanogrids were also synthesized by an independent strategy.

Design and operations at the National Tritium Labelling Facility

International Nuclear Information System (INIS)

Morimoto, H.; Williams, P.G.

1991-09-01

The National Tritium Labelling Facility (NTLF) is a multipurpose facility engaged in tritium labeling research. It offers to the biomedical research community a fully equipped laboratory for the synthesis and analysis of tritium labeled compounds. The design of the tritiation system, its operations and some labeling techniques are presented

Engineering test facility design definition

Science.gov (United States)

Bercaw, R. W.; Seikel, G. R.

1980-01-01

The Engineering Test Facility (ETF) is the major focus of the Department of Energy (DOE) Magnetohydrodynamics (MHD) Program to facilitate commercialization and to demonstrate the commercial operability of MHD/steam electric power. The ETF will be a fully integrated commercial prototype MHD power plant with a nominal output of 200 MW sub e. Performance of this plant is expected to meet or surpass existing utility standards for fuel, maintenance, and operating costs; plant availability; load following; safety; and durability. It is expected to meet all applicable environmental regulations. The current design concept conforming to the general definition, the basis for its selection, and the process which will be followed in further defining and updating the conceptual design.

Advanced conceptual design report solid waste retrieval facility, phase I, project W-113

International Nuclear Information System (INIS)

Smith, K.E.

1994-01-01

Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design

An ARM Mobile Facility Designed for Marine Deployments

Science.gov (United States)

Wiscombe, W. J.

2007-05-01

The U.S. Dept. of Energy's ARM (Atmospheric Radiation Measurements) Program is designing a Mobile Facility exclusively for marine deployments. This marine facility is patterned after ARM's land Mobile Facility, which had its inaugural deployment at Point Reyes, California, in 2005, followed by deployments to Niger in 2006 and Germany in 2007 (ongoing), and a planned deployment to China in 2008. These facilities are primarily intended for the study of clouds, radiation, aerosols, and surface processes with a goal to include these processes accurately in climate models. They are preferably embedded within larger field campaigns which provide context. They carry extensive instrumentation (in several large containers) including: cloud radar, lidar, microwave radiometers, infrared spectrometers, broadband and narrowband radiometers, sonde-launching facilities, extensive surface aerosol measurements, sky imagers, and surface latent and sensible heat flux devices. ARM's Mobile Facilities are designed for 6-10 month deployments in order to capture climatically-relevant datasets. They are available to any scientist, U.S. or international, who wishes to submit a proposal during the annual Spring call. The marine facility will be adapted to, and ruggedized for, the harsh marine environment and will add a scanning two-frequency radar, a boundary-layer wind profiler, a shortwave spectrometer, and aerosol instrumentation adapted to typical marine aerosols like sea salt. Plans also include the use of roving small UAVs, automated small boats, and undersea autonomous vehicles in order to address the point-to-area-average problem which is so crucial for informing climate models. Initial deployments are planned for small islands in climatically- interesting cloud regimes, followed by deployments on oceanic platforms (like decommissioned oil rigs and the quasi-permanent platform of this session's title) and eventually on large ships like car carriers plying routine routes.

Conceptual design report for the spent fuel management technology research and test (SMATER) facility

Energy Technology Data Exchange (ETDEWEB)

Park, S W; Ro, S G; Lee, J S; Min, D K; Shin, Y J [Korea Atomic Energy Research Institute, Taejon (Korea)

1998-10-01

This study was intended to develop concept for a pilot-scale remote operation facility for longer term management of spent fuel and therefrom to provide technical requirement for later basic design of the facility. Main scope of work for the study was to revise the past (1990) conceptual design in functions, scale, hot cell layout etc. based on user requirements. Technical reference was made to the PKA facility in Germany, through collaboration with appropriate partner, to elaborate the design and requirements. The study was focused on establishing design criteria and conceptual design of the SMATER facility. The results of this study should be an essential and useful basis upon optimization for further work to basic design of the facility. (author). 17 figs., 12 tabs.

Structural design considerations for a radwaste processing facility

International Nuclear Information System (INIS)

Foelber, S.C.; Sabbe, M.A.

1985-01-01

The structural engineer needs to consider several criteria when designing a radioactive-waste processing facility in order to properly balance the requirements of safety and economy. This paper addresses the design criteria and structural design of a vitrification building and the special equipment and supports associated with remote process operations. In addition, approaches to construction, and the role of scale models to aid in engineering design and construction are discussed. 5 figures

Incorporating design for decommissioning into the layout of nuclear facilities

International Nuclear Information System (INIS)

Collum, B.; Druart, A.

2008-01-01

Design for Decommissioning (DfD) is the design of nuclear facilities in a manner that facilitates ultimate decommissioning in as safe, technically efficient and cost effective way as possible. Strictly speaking, (DfD) should need minimal introduction and this paper should ideally be aimed at discussing the finer points of some improvement to a practice that is already widely embedded throughout the nuclear industry. The reality though is quite different. As an industry, we all know what DfD is and indeed we do incorporate it into our designs. However, application is at best patchy and there is little evidence of applying it to the level that will be advocated here. When applied at its highest level, DfD is all about truly designing nuclear facilities with their whole life cycle in mind, such that the decommissioning phase is an integral part of the design of a facility from the very first day. In this way, when a facility comes to the end of its operational life, it can move smoothly to Post Operational Clean Out (POCO) and then through the various phases of decommissioning. Demonstrating from the start that the nuclear industry addresses the challenges posed by decommissioning will help it to gain support from the regulators and the general public for proposals to build new nuclear generating capacity. (author)

Basic design study on plutonium electro-refining facility of oxide fuel pyroelectrochemical reprocessing

International Nuclear Information System (INIS)

Ogura, Kenji; Kondo, Naruhito; Kamoshida, Hiroshi; Omori, Takashi

2001-02-01

The test facility basic design, utility necessity and estimation cost of the Oxide Fuel Pyro-process for the use of Chemical Processing Facility (CPF) of JNC have been studied with the information of the previous year concept study and the additional conditions. Drastic down sizing design change or the building reconstruction is necessary to place the Oxide Fuel Pyro-process Facility in the laboratory ''C'', because it is not possible to reserve enough maintenance space and the weight of the facility is over the acceptable limit of the building. A further study such as facility down sizing, apparatus detail design and experiment detail process treatment has to be planned. (author)

Plasmonic rack-and-pinion gear with chiral metasurface

Science.gov (United States)

Gorodetski, Yuri; Karabchevsky, Alina

2016-04-01

The effect of circularly polarized beaming excited by traveling surface plasmons, via chiral metasurface is experimentally studied. Here we show that the propagation direction of the plasmonic wave, evanescently excited on the thin gold film affects the handedness of the scattered beam polarization. Nanostructured metasurface leads to excitation of localized plasmonic modes whose relative spatial orientation induces overall spin-orbit interaction. This effect is analogical to the rack-and-pinion gear: the rotational motion into the linear motion converter. From the practical point of view, the observed effect can be utilized in integrated optical circuits for communication systems, cyber security and sensing.

Key points for the design of Mox facilities

International Nuclear Information System (INIS)

Ducroux, R.; Gaiffe, L.; Dumond, S.; Cret, L.

1998-01-01

The design of a MOX fuel fabrication facility involves specific technical difficulties: - Process aspects: for example, its is necessary to meet the stringent requirements on the end products, while handling large quantities of powders and pellets; - Safety aspects: for example, containment of radioactive materials requires to use gloveboxes, to design process equipment so as to limit dispersion to the gloveboxes and to use systems for dust collection. - Technological aspects: for example, it is necessary to take into account maintenance early in the design, in order to lower the operation costs and lower the dose to the personnel. - Quality control and information systems: for example, it is necessary to be able to trace all the different products (powder lots, pellets, rods, assemblies). The design methods and organization set-up by COGEMA enables to master these technical difficulties during the different design steps and to obtain a MOX fabrication facility at the best performance versus cost compromise. These design methods rely mainly on: - taking into account all the different above mentioned constraints from the very beginning of the design process (by using the know-how resulting from experience feed-back, and also specific design tools developed by COGEMA and SGN); - launching a technical development and testing program at the beginning of the project and incorporating its results in the course of the design. (author)

Engineered surface barriers for waste disposal sites: lysimeter facility design and construction

International Nuclear Information System (INIS)

Phillips, S.J.; Ruben, M.S.; Kirkham, R.R.

1988-01-01

A facility to evaluate performance of engineered surface carriers for confinement of buried wastes has been designed, constructed, and operations initiated. The Field Lysimeter Test Facility is located at the US Department of Energy's Hanford Site in Richland, Washington. The facility consists of 18 one-dimensional drainage and weighing lysimeters used to evaluate 7 replicated barrier treatments. Distinct layers of natural earth materials were used to construct layered soil and rock barriers in each lysimeter. These barrier designs are capable in principal of significantly reducing or precluding infiltration of meteoric water through barriers into underlying contaminated zones. This paper summarizes salient facility design and construction features used in testing of the Hanford Site's engineered surface barriers

Design issues for a laboratory high gain fusion facility

International Nuclear Information System (INIS)

Hogan, W.J.

1987-01-01

In an inertial fusion laboratory high gain facility, experiments will be carried out with up to 1000 MJ of thermonuclear yield. The experiment area of such a facility will include many systems and structures that will have to operate successfully in the difficult environment created by the sudden large energy release. This paper estimates many of the nuclear effects that will occur, discusses the implied design issues and suggests possible solutions so that a useful experimental facility can be built. 4 figs

Exploratory shaft facility preliminary designs - Gulf Interior Region salt domes

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Gulf Interior Region, is to provide a description of the preliminary design for an Exploratory Shaft Facility on the Richton Dome, Mississippi. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description and Construction Cost Estimate

Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

Peterson, Timothy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-09-01

At Sandia National Laboratories in New Mexico (SNL/NM), 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/NM 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. These design standards generally apply to all disciplines on all SNL/NM projects. Architectural and engineering design must be both functional and cost-effective. Facility design must be tailored to fit its intended function, while emphasizing low-maintenance, energy-efficient, and energy-conscious design. Design facilities that can be maintained easily, with readily accessible equipment areas, low maintenance, and quality systems. To promote an orderly and efficient appearance, architectural features of new facilities must complement and enhance the existing architecture at the site. As an Architectural and Engineering (A/E) professional, you must advise the Project Manager when this approach is prohibitively expensive. You are encouraged to use professional judgment and ingenuity to produce a coordinated interdisciplinary design that is cost-effective, easily contractible or buildable, high-performing, aesthetically pleasing, and compliant with applicable building codes. Close coordination and development of civil, landscape, structural, architectural, fire

Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

International Nuclear Information System (INIS)

Dippre, M. A.

2003-01-01

A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational

Integrated safeguards and facility design and operations

International Nuclear Information System (INIS)

Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

1987-01-01

The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

AFR spent fuel storage program. Technical progress report, January 1981-March 1981

International Nuclear Information System (INIS)

1981-01-01

Work on this project is focused on developing design and licensing information for the model facility. Deliverables were submitted to DOE for facility modification, security design, and licensing documentation. Work is essentially complete on the high-density rack design with deliverable planned for April 30, 1981. A continuing program for completion of design and licensing information development was initiated by AGNS in February 1981. Progress to date is satisfactory

Requirements and design concept for a facility mapping system

International Nuclear Information System (INIS)

Barry, R.E.; Burks, B.L.; Little, C.Q.

1995-01-01

The Department of Energy (DOE) has for some time been considering the Decontamination and Dismantlement (D ampersand D) of facilities which are no longer in use, but which are highly contaminated with radioactive wastes. One of the holdups in performing the D ampersand D task is the accumulation of accurate facility characterizations that can enable a safe and orderly cleanup process. According to the Technical Strategic Plan for the Decontamination and Decommissioning Integrated Demonstration, open-quotes the cost of characterization using current baseline technologies for approximately 100 acres of gaseous diffusion plant at Oak Ridge alone is, for the most part incalculableclose quotes. Automated, robotic techniques will be necessary for initial characterization and continued surveillance of these types of sites. Robotic systems are being designed and constructed to accomplish these tasks. This paper describes requirements and design concepts for a system to accurately map a facility contaminated with hazardous wastes. Some of the technologies involved in the Facility Mapping System are: remote characterization with teleoperated, sensor-based systems, fusion of data sets from multiple characterization systems, and object recognition from 3D data models. This Facility Mapping System is being assembled by Oak Ridge National Laboratory for the DOE Office of Technology Development Robotics Technology Development Program

GreenChill Store Certification Protocol for Sub-Cooling Contained on Racks Separate from Refrigeration Equipment

Science.gov (United States)

Document describes the protocol used to determine the total load and refrigerant charge of stores that have placed all sub-cooling on a rack separate from all other commercial refrigeration equipment.

Design Of Dry Cask Storage For Serpong Multipurpose Reactor Spent Nuclear Fuel

Directory of Open Access Journals (Sweden)

Dyah Sulistyani Rahayu

2018-03-01

Full Text Available DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear fuel (SNF from Serpong Multipurpose Reactor, after 100 days storing in the reactor pond, is transferred to water pool interim storage for spent fuel (ISFSF. At present there are a remaining of 245 elements of SNF on the ISSF,198 element of which have been re-exported to the USA. The dry-cask storage allows the SNF, which has already been cooled in the ISSF, to lower its radiation exposure and heat decayat a very low level. Design of the dry cask storage for SNF has been done. Dual purpose of unventilated vertical dry cask was selected among other choices of metal cask, horizontal concrete modules, and modular vaults by taking into account of technical and economical advantages. The designed structure of cask consists of SNF rack canister, inner steel liner, concrete shielding of cask, and outer steel liner. To avoid bimetallic corrosion, the construction material for canister and inner steel liner follows the same material construction of fuel cladding, i.e. the alloy of AlMg2. The construction material of outer steel liner is copper to facilitate the heat transfer from the cask to the atmosphere. The total decay heat is transferred from SNF elements bundle to the atmosphere by a serial of heat transfer resistance for canister wall, inner steel liner, concrete shielding, and outer steel liner respectedly. The rack canister optimum capacity of 34 fuel elements was designed by geometric similarity method basedon SNF position arrangement of 7 x 6 triangular pitch array of fuel elements for prohibiting criticality by spontaneous neutron. The SNF elements are stored vertically on the rack canister.  The thickness of concrete wall shielding was calculated by trial and error to give air temperature of 30 oC and radiation dose on the wall surface of outer liner of 200 mrem/h. The SNF elements bundles originate from the existing racks of wet storage, i

Conceptual design study advanced concepts test (ACT) facility

Energy Technology Data Exchange (ETDEWEB)

Zaloudek, F.R.

1978-09-01

The Advanced Concepts Test (ACT) Project is part of program for developing improved power plant dry cooling systems in which ammonia is used as a heat transfer fluid between the power plant and the heat rejection tower. The test facility will be designed to condense 60,000 lb/hr of exhaust steam from the No. 1 turbine in the Kern Power Plant at Bakersfield, CA, transport the heat of condensation from the condenser to the cooling tower by an ammonia phase-change heat transport system, and dissipate this heat to the environs by a dry/wet deluge tower. The design and construction of the test facility will be the responsibility of the Electric Power Research Institute. The DOE, UCC/Linde, and the Pacific Northwest Laboratories will be involved in other phases of the project. The planned test facilities, its structures, mechanical and electrical equipment, control systems, codes and standards, decommissioning requirements, safety and environmental aspects, and energy impact are described. Six appendices of related information are included. (LCL)

Gas cooled fast breeder reactor design for a circulator test facility (modified HTGR circulator test facility)

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

A GCFR helium circulator test facility sized for full design conditions is proposed for meeting the above requirements. The circulator will be mounted in a large vessel containing high pressure helium which will permit testing at the same power, speed, pressure, temperature and flow conditions intended in the demonstration plant. The electric drive motor for the circulator will obtain its power from an electric supply and distribution system in which electric power will be taken from a local utility. The conceptual design decribed in this report is the result of close interaction between the General Atomic Company (GA), designer of the GCFR, and The Ralph M. Parson Company, architect/engineer for the test facility. A realistic estimate of total project cost is presented, together with a schedule for design, procurement, construction, and inspection.

Building Design Guidelines for Interior Architecture Concerned with Animal Researches Facilities