The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

International Nuclear Information System (INIS)

Wenzel, D.R.

1994-02-01

The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Norm Stanley

2011-02-01

This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

International Nuclear Information System (INIS)

2011-01-01

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Computer Security at Nuclear Facilities. Reference Manual (Arabic Edition)

International Nuclear Information System (INIS)

2011-01-01

category of the IAEA Nuclear Security Series, and deals with computer security at nuclear facilities. It is based on national experience and practices as well as publications in the fields of computer security and nuclear security. The guidance is provided for consideration by States, competent authorities and operators. The preparation of this publication in the IAEA Nuclear Security Series has been made possible by the contributions of a large number of experts from Member States. An extensive consultation process with all Member States included consultants meetings and open-ended technical meetings. The draft was then circulated to all Member States for 120 days to solicit further comments and suggestions. The comments received from Member States were reviewed and considered in the final version of the publication.

Computer Security at Nuclear Facilities. Reference Manual (Russian Edition)

International Nuclear Information System (INIS)

2012-01-01

category of the IAEA Nuclear Security Series, and deals with computer security at nuclear facilities. It is based on national experience and practices as well as publications in the fields of computer security and nuclear security. The guidance is provided for consideration by States, competent authorities and operators. The preparation of this publication in the IAEA Nuclear Security Series has been made possible by the contributions of a large number of experts from Member States. An extensive consultation process with all Member States included consultants meetings and open-ended technical meetings. The draft was then circulated to all Member States for 120 days to solicit further comments and suggestions. The comments received from Member States were reviewed and considered in the final version of the publication.

Computer Security at Nuclear Facilities. Reference Manual (Chinese Edition)

International Nuclear Information System (INIS)

2012-01-01

category of the IAEA Nuclear Security Series, and deals with computer security at nuclear facilities. It is based on national experience and practices as well as publications in the fields of computer security and nuclear security. The guidance is provided for consideration by States, competent authorities and operators. The preparation of this publication in the IAEA Nuclear Security Series has been made possible by the contributions of a large number of experts from Member States. An extensive consultation process with all Member States included consultants meetings and open-ended technical meetings. The draft was then circulated to all Member States for 120 days to solicit further comments and suggestions. The comments received from Member States were reviewed and considered in the final version of the publication.

Health physics manual of good practices for plutonium facilities. [Contains glossary

Energy Technology Data Exchange (ETDEWEB)

Brackenbush, L.W.; Heid, K.R.; Herrington, W.N.; Kenoyer, J.L.; Munson, L.F.; Munson, L.H.; Selby, J.M.; Soldat, K.L.; Stoetzel, G.A.; Traub, R.J.

1988-05-01

This manual consists of six sections: Properties of Plutonium, Siting of Plutonium Facilities, Facility Design, Radiation Protection, Emergency Preparedness, and Decontamination and Decommissioning. While not the final authority, the manual is an assemblage of information, rules of thumb, regulations, and good practices to assist those who are intimately involved in plutonium operations. An in-depth understanding of the nuclear, physical, chemical, and biological properties of plutonium is important in establishing a viable radiation protection and control program at a plutonium facility. These properties of plutonium provide the basis and perspective necessary for appreciating the quality of control needed in handling and processing the material. Guidance in selecting the location of a new plutonium facility may not be directly useful to most readers. However, it provides a perspective for the development and implementation of the environmental surveillance program and the in-plant controls required to ensure that the facility is and remains a good neighbor. The criteria, guidance, and good practices for the design of a plutonium facility are also applicable to the operation and modification of existing facilities. The design activity provides many opportunities for implementation of features to promote more effective protection and control. The application of ''as low as reasonably achievable'' (ALARA) principles and optimization analyses are generally most cost-effective during the design phase. 335 refs., 8 figs., 20 tabs.

Manual of a suite of computer codes, EXPRESS (EXact PREparedness Supporting System)

International Nuclear Information System (INIS)

Chino, Masamichi

1992-06-01

The emergency response supporting system EXPRESS (EXact PREparedness Supporting System) is constructed in JAERI for low cost engineering work stations under the UNIX operation. The purpose of this system is real-time predictions of affected areas due to radioactivities discharged into atmosphere from nuclear facilities. The computational models in EXPRESS are the mass-consistent wind field model EXPRESS-I and the particle dispersion model EXPRESS-II for atmospheric dispersions. In order to attain the quick response even when the codes are used in a small-scale computer, a high-speed iteration method MILUCR (Modified Incomplete Linear Unitary Conjugate Residual) is applied to EXPRESS-I and kernel density method is to EXPRESS-II. This manual describes the model configurations, code structures, related files, namelists and sample outputs of EXPRESS-I and -II. (author)

MELCOR computer code manuals

Energy Technology Data Exchange (ETDEWEB)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A.; Hyman, C.R.; Sanders, R.L. [Oak Ridge National Lab., TN (United States)

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.

MELCOR computer code manuals

International Nuclear Information System (INIS)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

Joint Computing Facility

Data.gov (United States)

Federal Laboratory Consortium — Raised Floor Computer Space for High Performance ComputingThe ERDC Information Technology Laboratory (ITL) provides a robust system of IT facilities to develop and...

Computer-Aided Facilities Management Systems (CAFM).

Science.gov (United States)

Cyros, Kreon L.

Computer-aided facilities management (CAFM) refers to a collection of software used with increasing frequency by facilities managers. The six major CAFM components are discussed with respect to their usefulness and popularity in facilities management applications: (1) computer-aided design; (2) computer-aided engineering; (3) decision support…

National Ignition Facility TestController for automated and manual testing

Energy Technology Data Exchange (ETDEWEB)

Zielinski, Jason, E-mail: fishler2@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)

2012-12-15

The Controls and Information Systems (CIS) organization for the National Ignition Facility (NIF) has developed controls, configuration and analysis software applications that combine for several million lines of code. The team delivers updates throughout the year, from major releases containing hundreds of changes to patch releases containing a small number of focused updates. To ensure the quality of each delivery, manual and automated tests are performed using the NIF TestController test infrastructure. The TestController system provides test inventory management, test planning, automated and manual test execution, release testing summaries and results search, all through a web browser interface. As part of the three-stage software testing strategy, the NIF TestController system helps plan, evaluate and track the readiness of each release to the NIF production environment. After several years of use in testing NIF software applications, the TestController's manual testing features have been leveraged for verifying the installation and operation of NIF Target Diagnostic hardware. The TestController recorded its first test results in 2004. Today, the system has recorded the execution of more than 160,000 tests and continues to play a central role in ensuring that NIF hardware and software meet the requirements of a high reliability facility. This paper describes the TestController system and discusses its use in assuring the quality of software delivered to the NIF.

National Ignition Facility TestController for automated and manual testing

International Nuclear Information System (INIS)

Zielinski, Jason

2012-01-01

The Controls and Information Systems (CIS) organization for the National Ignition Facility (NIF) has developed controls, configuration and analysis software applications that combine for several million lines of code. The team delivers updates throughout the year, from major releases containing hundreds of changes to patch releases containing a small number of focused updates. To ensure the quality of each delivery, manual and automated tests are performed using the NIF TestController test infrastructure. The TestController system provides test inventory management, test planning, automated and manual test execution, release testing summaries and results search, all through a web browser interface. As part of the three-stage software testing strategy, the NIF TestController system helps plan, evaluate and track the readiness of each release to the NIF production environment. After several years of use in testing NIF software applications, the TestController's manual testing features have been leveraged for verifying the installation and operation of NIF Target Diagnostic hardware. The TestController recorded its first test results in 2004. Today, the system has recorded the execution of more than 160,000 tests and continues to play a central role in ensuring that NIF hardware and software meet the requirements of a high reliability facility. This paper describes the TestController system and discusses its use in assuring the quality of software delivered to the NIF.

Clean Lead Facility Inventory System user's manual

International Nuclear Information System (INIS)

Garcia, J.F.

1994-12-01

The purpose of this user's manual is to provide instruction and guidance needed to enter and maintain inventory information for the Clean Lead Facility (CLF), PER-612. Individuals responsible for maintaining and using the system should study and understand the information provided. The user's manual describes how to properly use and maintain the CLF Inventory System. Annual, quarterly, monthly, and current inventory reports may be printed from the Inventory System for reporting purposes. Profile reports of each shipment of lead may also be printed for verification and documentation of lead transactions. The CLF Inventory System was designed on Microsoft Access version 2.0. Similar inventory systems are in use at the Idaho National Engineering Laboratory (INEL) to facilitate site-wide compilations of mixed waste data. The CLF Inventory System was designed for inventorying the clean or non-radioactive contaminated lead stored at the CLF. This data, along with the mixed waste data, will be compiled into the Idaho Mixed Waste Information (IMWI) system for reporting to the Department of Energy Idaho Office, Department of Energy Headquarters, and/or the State of Idaho

Computer mapping and visualization of facilities for planning of D and D operations

International Nuclear Information System (INIS)

Wuller, C.E.; Gelb, G.H.; Cramond, R.; Cracraft, J.S.

1995-01-01

The lack of as-built drawings for many old nuclear facilities impedes planning for decontamination and decommissioning. Traditional manual walkdowns subject workers to lengthy exposure to radiological and other hazards. The authors have applied close-range photogrammetry, 3D solid modeling, computer graphics, database management, and virtual reality technologies to create geometrically accurate 3D computer models of the interiors of facilities. The required input to the process is a set of photographs that can be acquired in a brief time. They fit 3D primitive shapes to objects of interest in the photos and, at the same time, record attributes such as material type and link patches of texture from the source photos to facets of modeled objects. When they render the model as either static images or at video rates for a walk-through simulation, the phototextures are warped onto the objects, giving a photo-realistic impression. The authors have exported the data to commercial CAD, cost estimating, robotic simulation, and plant design applications. Results from several projects at old nuclear facilities are discussed

Computer program user's manual for FIREFINDER digital topographic data verification library dubbing system

Science.gov (United States)

Ceres, M.; Heselton, L. R., III

1981-11-01

This manual describes the computer programs for the FIREFINDER Digital Topographic Data Verification-Library-Dubbing System (FFDTDVLDS), and will assist in the maintenance of these programs. The manual contains detailed flow diagrams and associated descriptions for each computer program routine and subroutine. Complete computer program listings are also included. This information should be used when changes are made in the computer programs. The operating system has been designed to minimize operator intervention.

User's manual for BINIAC: A computer code to translate APET bins

International Nuclear Information System (INIS)

Gough, S.T.

1994-03-01

This report serves as the user's manual for the FORTRAN code BINIAC. BINIAC is a utility code designed to format the output from the Defense Waste Processing Facility (DWPF) Accident Progression Event Tree (APET) methodology. BINIAC inputs the accident progression bins from the APET methodology, converts the frequency from occurrences per hour to occurrences per year, sorts the progression bins, and converts the individual dimension character codes into facility attributes. Without the use of BINIAC, this process would be done manually at great time expense. BINIAC was written under the quality assurance control of IQ34 QAP IV-1, revision 0, section 4.1.4. Configuration control is established through the use of a proprietor and a cognizant users list

User manual of FRAPCON-I computer code

International Nuclear Information System (INIS)

Chia, C.T.

1985-11-01

The manual for using the FRAPCON-I code implanted by Reactor Department of Brazilian-CNEN to convert IBM FORTRAN in FORTRAN 77 of Honeywell Bull computer is presented. The FRAPCON-I code describes the behaviour of fuel rods of PWR type reactors at stationary state during long periods of burnup. (M.C.K.)

Computer Processing 10-20-30. Teacher's Manual. Senior High School Teacher Resource Manual.

Science.gov (United States)

Fisher, Mel; Lautt, Ray

Designed to help teachers meet the program objectives for the computer processing curriculum for senior high schools in the province of Alberta, Canada, this resource manual includes the following sections: (1) program objectives; (2) a flowchart of curriculum modules; (3) suggestions for short- and long-range planning; (4) sample lesson plans;…

Training manual for process operation and management of radioactive waste treatment facility

Energy Technology Data Exchange (ETDEWEB)

Shon, J. S.; Kim, K. J.; Ahn, S. J. [and others

2004-12-01

Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure.

Training manual for process operation and management of radioactive waste treatment facility

International Nuclear Information System (INIS)

Shon, J. S.; Kim, K. J.; Ahn, S. J.

2004-12-01

Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure

Fire Protection Program Manual

Energy Technology Data Exchange (ETDEWEB)

Sharry, J A

2012-05-18

This manual documents the Lawrence Livermore National Laboratory (LLNL) Fire Protection Program. Department of Energy (DOE) Orders 420.1B, Facility Safety, requires LLNL to have a comprehensive and effective fire protection program that protects LLNL personnel and property, the public and the environment. The manual provides LLNL and its facilities with general information and guidance for meeting DOE 420.1B requirements. The recommended readers for this manual are: fire protection officers, fire protection engineers, fire fighters, facility managers, directorage assurance managers, facility coordinators, and ES and H team members.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

Operating manual for the critical experiments facility

International Nuclear Information System (INIS)

1986-01-01

The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written

Operating manual for the critical experiments facility

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written.

NIF ICCS Test Controller for Automated and Manual Testing

International Nuclear Information System (INIS)

Zielinski, J S

2007-01-01

The National Ignition Facility (NIF) Integrated Computer Control System (ICCS) is a large (1.5 MSLOC), hierarchical, distributed system that controls all aspects of the NIF laser [1]. The ICCS team delivers software updates to the NIF facility throughout the year to support shot operations and commissioning activities. In 2006, there were 48 releases of ICCS: 29 full releases, 19 patches. To ensure the quality of each delivery, thousands of manual and automated tests are performed using the ICCS Test Controller test infrastructure. The TestController system provides test inventory management, test planning, automated test execution and manual test logging, release testing summaries and test results search, all through a web browser interface. Automated tests include command line based frameworks server tests and Graphical User Interface (GUI) based Java tests. Manual tests are presented as a checklist-style web form to be completed by the tester. The results of all tests, automated and manual, are kept in a common repository that provides data to dynamic status reports. As part of the 3-stage ICCS release testing strategy, the TestController system helps plan, evaluate and track the readiness of each release to the NIF facility

Computational Science at the Argonne Leadership Computing Facility

Science.gov (United States)

Romero, Nichols

2014-03-01

The goal of the Argonne Leadership Computing Facility (ALCF) is to extend the frontiers of science by solving problems that require innovative approaches and the largest-scale computing systems. ALCF's most powerful computer - Mira, an IBM Blue Gene/Q system - has nearly one million cores. How does one program such systems? What software tools are available? Which scientific and engineering applications are able to utilize such levels of parallelism? This talk will address these questions and describe a sampling of projects that are using ALCF systems in their research, including ones in nanoscience, materials science, and chemistry. Finally, the ways to gain access to ALCF resources will be presented. This research used resources of the Argonne Leadership Computing Facility at Argonne National Laboratory, which is supported by the Office of Science of the U.S. Department of Energy under contract DE-AC02-06CH11357.

Introduction to Computing: Lab Manual. Faculty Guide [and] Student Guide.

Science.gov (United States)

Frasca, Joseph W.

This lab manual is designed to accompany a college course introducing students to computing. The exercises are designed to be completed by the average student in a supervised 2-hour block of time at a computer lab over 15 weeks. The intent of each lab session is to introduce a topic and have the student feel comfortable with the use of the machine…

Conducting Computer Security Assessments at Nuclear Facilities

International Nuclear Information System (INIS)

2016-06-01

Computer security is increasingly recognized as a key component in nuclear security. As technology advances, it is anticipated that computer and computing systems will be used to an even greater degree in all aspects of plant operations including safety and security systems. A rigorous and comprehensive assessment process can assist in strengthening the effectiveness of the computer security programme. This publication outlines a methodology for conducting computer security assessments at nuclear facilities. The methodology can likewise be easily adapted to provide assessments at facilities with other radioactive materials

Computer technology: its potential for industrial energy conservation. A technology applications manual

Energy Technology Data Exchange (ETDEWEB)

None

1979-01-01

Today, computer technology is within the reach of practically any industrial corporation regardless of product size. This manual highlights a few of the many applications of computers in the process industry and provides the technical reader with a basic understanding of computer technology, terminology, and the interactions among the various elements of a process computer system. The manual has been organized to separate process applications and economics from computer technology. Chapter 1 introduces the present status of process computer technology and describes the four major applications - monitoring, analysis, control, and optimization. The basic components of a process computer system also are defined. Energy-saving applications in the four major categories defined in Chapter 1 are discussed in Chapter 2. The economics of process computer systems is the topic of Chapter 3, where the historical trend of process computer system costs is presented. Evaluating a process for the possible implementation of a computer system requires a basic understanding of computer technology as well as familiarity with the potential applications; Chapter 4 provides enough technical information for an evaluation. Computer and associated peripheral costs and the logical sequence of steps in the development of a microprocessor-based process control system are covered in Chapter 5.

TUNL computer facilities

International Nuclear Information System (INIS)

Boyd, M.; Edwards, S.E.; Gould, C.R.; Roberson, N.R.; Westerfeldt, C.R.

1985-01-01

The XSYS system has been relatively stable during the last year, and most of our efforts have involved routine software maintenance and enhancement of existing XSYS capabilities. Modifications were made in the MBD program GDAP to increase the execution speed in key GDAP routines. A package of routines has been developed to allow communication between the XSYS and the new Wien filter microprocessor. Recently the authors have upgraded their operating system from VSM V3.7 to V4.1. This required numerous modifications to XSYS, mostly in the command procedures. A new reorganized edition of the XSYS manual will be issued shortly. The TUNL High Resolution Laboratory's VAX 11/750 computer has been in operation for its first full year as a replacement for the PRIME 300 computer which was purchased in 1974 and retired nine months ago. The data acquisition system on the VAX has been in use for the past twelve months performing a number of experiments

SAFE users manual. Volume 4. Computer programs

International Nuclear Information System (INIS)

Grady, L.M.

1983-06-01

Documentation for the Safeguards Automated Facility Evaluation (SAFE) computer programs is presented. The documentation is in the form of subprogram trees, program abstracts, flowcharts, and listings. Listings are provided on microfiche

Automated computation of femoral angles in dogs from three-dimensional computed tomography reconstructions: Comparison with manual techniques.

Science.gov (United States)

Longo, F; Nicetto, T; Banzato, T; Savio, G; Drigo, M; Meneghello, R; Concheri, G; Isola, M

2018-02-01

The aim of this ex vivo study was to test a novel three-dimensional (3D) automated computer-aided design (CAD) method (aCAD) for the computation of femoral angles in dogs from 3D reconstructions of computed tomography (CT) images. The repeatability and reproducibility of three manual radiography, manual CT reconstructions and the aCAD method for the measurement of three femoral angles were evaluated: (1) anatomical lateral distal femoral angle (aLDFA); (2) femoral neck angle (FNA); and (3) femoral torsion angle (FTA). Femoral angles of 22 femurs obtained from 16 cadavers were measured by three blinded observers. Measurements were repeated three times by each observer for each diagnostic technique. Femoral angle measurements were analysed using a mixed effects linear model for repeated measures to determine the levels of intra-observer agreement (repeatability) and inter-observer agreement (reproducibility). Repeatability and reproducibility of measurements using the aCAD method were excellent (intra-class coefficients, ICCs≥0.98) for all three angles assessed. Manual radiography and CT exhibited excellent agreement for the aLDFA measurement (ICCs≥0.90). However, FNA repeatability and reproducibility were poor (ICCscomputation of the 3D aCAD method provided the highest repeatability and reproducibility among the tested methodologies. Copyright © 2017 Elsevier Ltd. All rights reserved.

Operating manual for the Tower Shielding Facility

International Nuclear Information System (INIS)

1985-12-01

This manual provides information necessary to operate and perform maintenance on the reactor systems and all equipment or systems which can affect their operation or the safety of personnel at the Tower Shielding Facility. The first four chapters consist of introductory and descriptive material of benefit to personnel in training, the qualifications required for training, the responsibilities of the personnel in the organization, and the procedures for reviewing proposed experiments. Chapter 8, Emergency Procedures, is also a necessary part of the indoctrination of personnel. The procedures for operation of the Tower Shielding Reactor (TSR-II), its water cooling system, and the main tower hoists are outlined in Chapters 5, 6, and 7. The Technical Specification surveillance requirements for the TSR-II are summarized in Chapter 9. The maintenance and calibration schedule is spelled out in Chapter 10. The procedures for assembly and disassembly of the TSR-II are outlined in Chapter 11

Integration of a browser based operator manual in the system environment of a process computer system

International Nuclear Information System (INIS)

Weber, Andreas; Erfle, Robert; Feinkohl, Dirk

2012-01-01

The integration of a browser based operator manual in the system environment of a process computer system is an optimization of the operating procedure in the control room and a safety enhancement due to faster and error-free access to the manual contents. Several requirements by the authorities have to be fulfilled: the operating manual has to be available as hard copy, the format has to be true to original, protection against manipulation has to be provided, the manual content of the browser-based version and the hard copy have to identical, and the display presentation has to be consistent with ergonomic principals. The integration of the on-line manual in the surveillance process computer system provides the operator with the relevant comments to the surveillance signal. The described integration of the on-line manual is an optimization of the operator's everyday job with respect to ergonomics and safety (human performance).

Viscous wing theory development. Volume 2: GRUMWING computer program user's manual

Science.gov (United States)

Chow, R. R.; Ogilvie, P. L.

1986-01-01

This report is a user's manual which describes the operation of the computer program, GRUMWING. The program computes the viscous transonic flow over three-dimensional wings using a boundary layer type viscid-inviscid interaction approach. The inviscid solution is obtained by an approximate factorization (AFZ)method for the full potential equation. The boundary layer solution is based on integral entrainment methods.

Health physics manual of good practices for accelerator facilities

International Nuclear Information System (INIS)

Casey, W.R.; Miller, A.J.; McCaslin, J.B.; Coulson, L.V.

1988-04-01

It is hoped that this manual will serve both as a teaching aid as well as a useful adjunct for program development. In the context of application, this manual addresses good practices that should be observed by management, staff, and designers since the achievement of a good radiation program indeed involves a combined effort. Ultimately, radiation safety and good work practices become the personal responsibility of the individual. The practices presented in this manual are not to be construed as mandatory rather they are to be used as appropriate for the specific case in the interest of radiation safety. As experience is accrued and new data obtained in the application of this document, ONS will update the guidance to assure that at any given time the guidance reflects optimum performance consistent with current technology and practice.The intent of this guide therefore is to: define common health physics problems at accelerators; recommend suitable methods of identifying, evaluating, and managing accelerator health physics problems; set out the established safety practices at DOE accelerators that have been arrived at by consensus and, where consensus has not yet been reached, give examples of safe practices; introduce the technical literature in the accelerator health physics field; and supplement the regulatory documents listed in Appendix D. Many accelerator health physics problems are no different than those at other kinds of facilities, e.g., ALARA philosophy, instrument calibration, etc. These problems are touched on very lightly or not at all. Similarly, this document does not cover other hazards such as electrical shock, toxic materials, etc. This does not in any way imply that these problems are not serious. 160 refs

Portable Digital Radiography and Computed Tomography Manual

Energy Technology Data Exchange (ETDEWEB)

2007-11-01

This user manual describes the function and use of the portable digital radiography and computed tomography (DRCT) scanner. The manual gives a general overview of x-ray imaging systems along with a description of the DRCT system. An inventory of the all the system components, organized by shipping container, is also included. In addition, detailed, step-by-step procedures are provided for all of the exercises necessary for a novice user to successfully collect digital radiographs and tomographic images of an object, including instructions on system assembly and detector calibration and system alignment. There is also a short section covering the limited system care and maintenance needs. Descriptions of the included software packages, the DRCT Digital Imager used for system operation, and the DRCT Image Processing Interface used for image viewing and tomographic data reconstruction are given in the appendixes. The appendixes also include a cheat sheet for more experienced users, a listing of known system problems and how to mitigate them, and an inventory check-off sheet suitable for copying and including with the machine for shipment purposes.

Measurement of mesothelioma on thoracic CT scans: A comparison of manual and computer-assisted techniques

International Nuclear Information System (INIS)

Armato, Samuel G. III; Oxnard, Geoffrey R.; MacMahon, Heber; Vogelzang, Nicholas J.; Kindler, Hedy L.; Kocherginsky, Masha; Starkey, Adam

2004-01-01

Our purpose in this study was to evaluate the variability of manual mesothelioma tumor thickness measurements in computed tomography (CT) scans and to assess the relative performance of six computerized measurement algorithms. The CT scans of 22 patients with malignant pleural mesothelioma were collected. In each scan, an initial observer identified up to three sites in each of three CT sections at which tumor thickness measurements were to be made. At each site, five observers manually measured tumor thickness through a computer interface. Three observers repeated these measurements during three separate sessions. Inter- and intra-observer variability in the manual measurement of tumor thickness was assessed. Six automated measurement algorithms were developed based on the geometric relationship between a specified measurement site and the automatically extracted lung regions. Computer-generated measurements were compared with manual measurements. The tumor thickness measurements of different observers were highly correlated (r≥0.99); however, the 95% limits of agreement for relative inter-observer difference spanned a range of 30%. Tumor thickness measurements generated by the computer algorithms also correlated highly with the average of observer measurements (r≥0.93). We have developed computerized techniques for the measurement of mesothelioma tumor thickness in CT scans. These techniques achieved varying levels of agreement with measurements made by human observers

Facility Interface Capability Assessment (FICA) user manual

International Nuclear Information System (INIS)

Pope, R.B.; MacDonald, R.R.; Massaglia, J.L.; Williamson, D.A.; Viebrock, J.M.; Mote, N.

1995-09-01

The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is describe the FICA computer software and to provide the FICA user with a guide on how to use the FICA system. The FICA computer software consists of two executable programs: the FICA Reactor Report program and the FICA Summary Report program (written in the Ca-Clipper version 5.2 development system). The complete FICA software system is contained on either a 3.5 in. (double density) or a 5.25 in. (high density) diskette and consists of the two FICA programs and all the database files (generated using dBASE III). The FICA programs are provided as ''stand alone'' systems and neither the Ca-Clipper compiler nor dBASE III is required to run the FICA programs. The steps for installing the FICA software system and executing the FICA programs are described in this report. Instructions are given on how to install the FICA software system onto the hard drive of the PC and how to execute the FICA programs from the FICA subdirectory on the hard drive. Both FICA programs are menu driven with the up-arrow and down-arrow keys used to move the cursor to the desired selection

Computing facility at SSC for detectors

International Nuclear Information System (INIS)

Leibold, P.; Scipiono, B.

1990-01-01

A description of the RISC-based distributed computing facility for detector simulaiton being developed at the SSC Laboratory is discussed. The first phase of this facility is scheduled for completion in early 1991. Included is the status of the project, overview of the concepts used to model and define system architecture, networking capabilities for user access, plans for support of physics codes and related topics concerning the implementation of this facility

Theoretical background and user's manual for the computer code on groundwater flow and radionuclide transport calculation in porous rock

International Nuclear Information System (INIS)

Shirakawa, Toshihiko; Hatanaka, Koichiro

2001-11-01

In order to document a basic manual about input data, output data, execution of computer code on groundwater flow and radionuclide transport calculation in heterogeneous porous rock, we investigated the theoretical background about geostatistical computer codes and the user's manual for the computer code on groundwater flow and radionuclide transport which calculates water flow in three dimension, the path of moving radionuclide, and one dimensional radionuclide migration. In this report, based on above investigation we describe the geostatistical background about simulating heterogeneous permeability field. And we describe construction of files, input and output data, a example of calculating of the programs which simulates heterogeneous permeability field, and calculates groundwater flow and radionuclide transport. Therefore, we can document a manual by investigating the theoretical background about geostatistical computer codes and the user's manual for the computer code on groundwater flow and radionuclide transport calculation. And we can model heterogeneous porous rock and analyze groundwater flow and radionuclide transport by utilizing the information from this report. (author)

A large-scale computer facility for computational aerodynamics

International Nuclear Information System (INIS)

Bailey, F.R.; Balhaus, W.F.

1985-01-01

The combination of computer system technology and numerical modeling have advanced to the point that computational aerodynamics has emerged as an essential element in aerospace vehicle design methodology. To provide for further advances in modeling of aerodynamic flow fields, NASA has initiated at the Ames Research Center the Numerical Aerodynamic Simulation (NAS) Program. The objective of the Program is to develop a leading-edge, large-scale computer facility, and make it available to NASA, DoD, other Government agencies, industry and universities as a necessary element in ensuring continuing leadership in computational aerodynamics and related disciplines. The Program will establish an initial operational capability in 1986 and systematically enhance that capability by incorporating evolving improvements in state-of-the-art computer system technologies as required to maintain a leadership role. This paper briefly reviews the present and future requirements for computational aerodynamics and discusses the Numerical Aerodynamic Simulation Program objectives, computational goals, and implementation plans

DOE explosives safety manual. Revision 7

Energy Technology Data Exchange (ETDEWEB)

1994-08-01

This manual prescribes the Department of Energy (DOE) safety rules used to implement the DOE safety policy for operations involving explosives. This manual is applicable to all DOE facilities engaged in operations of development, manufacturing, handling, storage, transportation, processing, or testing of explosives, pyrotechnics and propellants, or assemblies containing these materials. The standards of this manual deal with the operations involving explosives, pyrotechnics and propellants, and the safe management of such operations. The design of all new explosives facilities shall conform to the requirements established in this manual and implemented in DOE 6430.1A, ``General Design Criteria Manual.`` It is not intended that existing physical facilities be changed arbitrarily to comply with these provisions, except as required by law. Existing facilities that do not comply with these standards may continue to be used for the balance of their functional life, as long as the current operation presents no significantly greater risk than that assumed when the facility was originally designed and it can be demonstrated clearly that a modification to bring the facility into compliance is not feasible. However, in the case of a major renovation, the facility must be brought into compliance with current standards. The standards are presented as either mandatory or advisory. Mandatory standards, denoted by the words ``shall,`` ``must,`` or ``will,`` are requirements that must be followed unless written authority for deviation is granted as an exemption by the DOE. Advisory standards denoted by ``should`` or ``may`` are standards that may be deviated from with a waiver granted by facility management.

FORIG: a computer code for calculating radionuclide generation and depletion in fusion and fission reactors. User's manual

International Nuclear Information System (INIS)

Blink, J.A.

1985-03-01

In this manual we describe the use of the FORIG computer code to solve isotope-generation and depletion problems in fusion and fission reactors. FORIG runs on a Cray-1 computer and accepts more extensive activation cross sections than ORIGEN2 from which it was adapted. This report is an updated and a combined version of the previous ORIGEN2 and FORIG manuals. 7 refs., 15 figs., 13 tabs

Oak Ridge Leadership Computing Facility (OLCF)

Data.gov (United States)

Federal Laboratory Consortium — The Oak Ridge Leadership Computing Facility (OLCF) was established at Oak Ridge National Laboratory in 2004 with the mission of standing up a supercomputer 100 times...

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

protection, mechanical, electrical, telecommunications, and security features is expected to ensure compatibility with planned functional equipment and to facilitate constructability. If portions of the design are subcontracted to specialists, delivery of the finished design documents must not be considered complete until the subcontracted portions are also submitted for review. You must, along with support consultants, perform functional analyses and programming in developing design solutions. These solutions must reflect coordination of the competing functional, budgetary, and physical requirements for the project. During design phases, meetings between you and the SNL/NM Project Team to discuss and resolve design issues are required. These meetings are a normal part of the design process. For specific design-review requirements, see the project-specific Design Criteria. In addition to the design requirements described in this manual, instructive information is provided to explain the sustainable building practice goals for design, construction, operation, and maintenance of SNL/NM facilities. Please notify SNL/NM personnel of design best practices not included in this manual, so they can be incorporated in future updates. You must convey all documents describing work to the SNL/NM Project Manager in both hard copy and in an electronic format compatible with the SNL/NM-prescribed CADD and other software packages, and in accordance with a SNL/NM approved standard format. Print all hard copy versions of submitted documents (excluding drawings and renderings) double-sided when practical.

Environmental Compliance and Pollution Prevention Training Manual for Campus-Based Organizations--Operational and Facility Maintenance Personnel.

Science.gov (United States)

New York State Dept. of Environmental Conservation, Albany.

This manual was designed to be used as part of the Workshop on Environmental Compliance and Pollution Prevention for campus-based facilities. It contains basic information on New York state and federal laws, rules, and regulations for protecting the environment. The information presented is a summary with emphasis on those items believed to be…

SNAP operating system reference manual

International Nuclear Information System (INIS)

Sabuda, J.D.; Polito, J.; Walker, J.L.; Grant, F.H. III.

1982-03-01

The SNAP Operating System (SOS) is a FORTRAN 77 program which provides assistance to the safeguards analyst who uses the Safeguards Automated Facility Evaluation (SAFE) and the Safeguards Network Analysis Procedure (SNAP) techniques. Features offered by SOS are a data base system for storing a library of SNAP applications, computer graphics representation of SNAP models, a computer graphics editor to develop and modify SNAP models, a SAFE-to-SNAP interface, automatic generation of SNAP input data, and a computer graphic post-processor for SNAP. The SOS Reference Manual provides detailed application information concerning SOS as well as a detailed discussion of all SOS components and their associated command input formats. SOS was developed for the US Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the US Naval Surface Weapons Center by Pritsker and Associates, Inc., under contract to Sandia National Laboratories

A data acquisition computer for high energy physics applications DAFNE:- hardware manual

International Nuclear Information System (INIS)

Barlow, J.; Seller, P.; De-An, W.

1983-07-01

A high performance stand alone computer system based on the Motorola 68000 micro processor has been built at the Rutherford Appleton Laboratory. Although the design was strongly influenced by the requirement to provide a compact data acquisition computer for the high energy physics environment, the system is sufficiently general to find applications in a wider area. It provides colour graphics and tape and disc storage together with access to CAMAC systems. This report is the hardware manual of the data acquisition computer, DAFNE (Data Acquisition For Nuclear Experiments), and as such contains a full description of the hardware structure of the computer system. (author)

Hydrogen Mixing Studies (HMS), user's manual

International Nuclear Information System (INIS)

Lam, K.L.; Wilson, T.L.; Travis, J.R.

1994-12-01

Hydrogen Mixing Studies (HMS) is a best-estimate analysis tool for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facilities. It can model geometrically complex facilities having multiple compartments and internal structures. The code can simulate the effects of steam condensation, heat transfer to walls and internal structures, chemical kinetics, and fluid turbulence. The gas mixture may consist of components included in a built-in library of 20 species. HMS is a finite-volume computer code that solves the time-dependent, three-dimensional (3D) compressible Navier Stokes equations. Both Cartesian and cylindrical coordinate systems are available. Transport equations for the fluid internal energy and for gas species densities are also solved. HMS was originally developed to run on Cray-type supercomputers with vector-processing units that greatly improve the computational speed, especially for large, complex problems. Recently the code has been converted to run on Sun workstations. Both the Cray and Sun versions have the same built-in graphics capabilities that allow 1D, 2D, 3D, and time-history plots of all solution variables. Other code features include a restart capability and flexible definitions of initial and time-dependent boundary conditions. This manual describes how to use the code. It explains how to set up the model geometry, define walls and obstacles, and specify gas species and material properties. Definitions of initial and boundary conditions are also described. The manual also describes various physical model and numerical procedure options, as well as how to turn them on. The reader also learns how to specify different outputs, especially graphical display of solution variables. Finally sample problems are included to illustrate some applications of the code. An input deck that illustrates the minimum required data to run HMS is given at the end of this manual

Assessing the effects of manual dexterity and playing computer games on catheter-wire manipulation for inexperienced operators.

Science.gov (United States)

Alsafi, Z; Hameed, Y; Amin, P; Shamsad, S; Raja, U; Alsafi, A; Hamady, M S

2017-09-01

To investigate the effect of playing computer games and manual dexterity on catheter-wire manipulation in a mechanical aortic model. Medical student volunteers filled in a preprocedure questionnaire assessing their exposure to computer games. Their manual dexterity was measured using a smartphone game. They were then shown a video clip demonstrating renal artery cannulation and were asked to reproduce this. All attempts were timed. Two-tailed Student's t-test was used to compare continuous data, while Fisher's exact test was used for categorical data. Fifty students aged 18-22 years took part in the study. Forty-six completed the task at an average of 168 seconds (range 103-301 seconds). There was no significant difference in the dexterity score or time to cannulate the renal artery between male and female students. Students who played computer games for >10 hours per week had better dexterity scores than those who did not play computer games: 9.1 versus 10.2 seconds (p=0.0237). Four of 19 students who did not play computer games failed to complete the task, while all of those who played computer games regularly completed the task (p=0.0168). Playing computer games is associated with better manual dexterity and ability to complete a basic interventional radiology task for novices. Copyright © 2017 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

TA-55 change control manual

International Nuclear Information System (INIS)

Blum, T.W.; Selvage, R.D.; Courtney, K.H.

1997-11-01

This manual is the guide for initiating change at the Plutonium Facility, which handles the processing of plutonium as well as research on plutonium metallurgy. It describes the change and work control processes employed at TA-55 to ensure that all proposed changes are properly identified, reviewed, approved, implemented, tested, and documented so that operations are maintained within the approved safety envelope. All Laboratory groups, their contractors, and subcontractors doing work at TA-55 follow requirements set forth herein. This manual applies to all new and modified processes and experiments inside the TA-55 Plutonium Facility; general plant project (GPP) and line item funded construction projects at TA-55; temporary and permanent changes that directly or indirectly affect structures, systems, or components (SSCs) as described in the safety analysis, including Facility Control System (FCS) software; and major modifications to procedures. This manual does not apply to maintenance performed on process equipment or facility SSCs or the replacement of SSCs or equipment with documented approved equivalents

2016 Annual Report - Argonne Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Collins, Jim [Argonne National Lab. (ANL), Argonne, IL (United States); Papka, Michael E. [Argonne National Lab. (ANL), Argonne, IL (United States); Cerny, Beth A. [Argonne National Lab. (ANL), Argonne, IL (United States); Coffey, Richard M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-01-01

The Argonne Leadership Computing Facility (ALCF) helps researchers solve some of the world’s largest and most complex problems, while also advancing the nation’s efforts to develop future exascale computing systems. This report presents some of the ALCF’s notable achievements in key strategic areas over the past year.

NNS computing facility manual P-17 Neutron and Nuclear Science

International Nuclear Information System (INIS)

Hoeberling, M.; Nelson, R.O.

1993-11-01

This document describes basic policies and provides information and examples on using the computing resources provided by P-17, the Neutron and Nuclear Science (NNS) group. Information on user accounts, getting help, network access, electronic mail, disk drives, tape drives, printers, batch processing software, XSYS hints, PC networking hints, and Mac networking hints is given

Nuclear fuel cycle facility accident analysis handbook

International Nuclear Information System (INIS)

Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

1988-05-01

The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

Computer Security at Nuclear Facilities

International Nuclear Information System (INIS)

Cavina, A.

2013-01-01

This series of slides presents the IAEA policy concerning the development of recommendations and guidelines for computer security at nuclear facilities. A document of the Nuclear Security Series dedicated to this issue is on the final stage prior to publication. This document is the the first existing IAEA document specifically addressing computer security. This document was necessary for 3 mains reasons: first not all national infrastructures have recognized and standardized computer security, secondly existing international guidance is not industry specific and fails to capture some of the key issues, and thirdly the presence of more or less connected digital systems is increasing in the design of nuclear power plants. The security of computer system must be based on a graded approach: the assignment of computer system to different levels and zones should be based on their relevance to safety and security and the risk assessment process should be allowed to feed back into and influence the graded approach

Academic Computing Facilities and Services in Higher Education--A Survey.

Science.gov (United States)

Warlick, Charles H.

1986-01-01

Presents statistics about academic computing facilities based on data collected over the past six years from 1,753 institutions in the United States, Canada, Mexico, and Puerto Rico for the "Directory of Computing Facilities in Higher Education." Organizational, functional, and financial characteristics are examined as well as types of…

WYLBUR reference manual. [For interactive text editing

Energy Technology Data Exchange (ETDEWEB)

Krupp, R.F.; Messina, P.C.; Peavler, J.M.; Schustack, S.; Starai, T.

1977-04-01

WYLBUR is a system for manipulating various kinds of text, such as computer programs, manuscripts, letters, forms, articles, or reports. Its on-line interactive text-editing capabilities allow the user to create, change, and correct text, and to search and display it. WYLBUR also has facilities for job submission and retrieval from remote terminals that make it possible for a user to inquire about the status of any job in the system, cancel jobs that are executing or awaiting execution, reroute output, raise job priority, or get information on the backlog of batch jobs. WYLBUR also has excellent recovery capabilities and a fast response time. This manual describes the WYLBUR version currently used at ANL. It is intended primarily as a reference manual; thus, examples of WYLBUR commands are kept to a minimum. (RWR)

Study of developing nuclear fabrication facility's integrated emergency response manual

International Nuclear Information System (INIS)

Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang; Min, Guem Young; Han, Ji Ah

2016-01-01

Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type

2015 Annual Report - Argonne Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Collins, James R. [Argonne National Lab. (ANL), Argonne, IL (United States); Papka, Michael E. [Argonne National Lab. (ANL), Argonne, IL (United States); Cerny, Beth A. [Argonne National Lab. (ANL), Argonne, IL (United States); Coffey, Richard M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-01-01

The Argonne Leadership Computing Facility provides supercomputing capabilities to the scientific and engineering community to advance fundamental discovery and understanding in a broad range of disciplines.

2014 Annual Report - Argonne Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Collins, James R. [Argonne National Lab. (ANL), Argonne, IL (United States); Papka, Michael E. [Argonne National Lab. (ANL), Argonne, IL (United States); Cerny, Beth A. [Argonne National Lab. (ANL), Argonne, IL (United States); Coffey, Richard M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2014-01-01

The Argonne Leadership Computing Facility provides supercomputing capabilities to the scientific and engineering community to advance fundamental discovery and understanding in a broad range of disciplines.

HVAC system operation manual of IMEF

International Nuclear Information System (INIS)

Baek, Sang Yeol; Park, Dae Kyu; Ahn, Sang Bok; Ju, Yong Sun.

1997-06-01

This manual is operation procedures of the IMEF(Irradiated Material Examination Facility) HVAC(Heating, Ventilation and Air Conditioning) System. General operation procedures and test method of the IMEF HVAC system are described. The manual is as follows; 1. HVAC system operation manual 2. HVAC system management guide 3. HVAC system maintenance manual 4. HVAC system air velocity and flowrate measurement manual 5. HVAC system HEPA filter leak test manual 6. HVAC system charcoal filter leak test manual 7. HVAC system HEPA and charcoal filter exchange manual. (author). 8 tabs

High Performance Computing Facility Operational Assessment 2015: Oak Ridge Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Barker, Ashley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bernholdt, David E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bland, Arthur S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Gary, Jeff D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Hack, James J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; McNally, Stephen T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Rogers, James H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Smith, Brian E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Straatsma, T. P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Sukumar, Sreenivas Rangan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Thach, Kevin G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Tichenor, Suzy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Vazhkudai, Sudharshan S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Wells, Jack C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility

2016-03-01

Oak Ridge National Laboratory’s (ORNL’s) Leadership Computing Facility (OLCF) continues to surpass its operational target goals: supporting users; delivering fast, reliable systems; creating innovative solutions for high-performance computing (HPC) needs; and managing risks, safety, and security aspects associated with operating one of the most powerful computers in the world. The results can be seen in the cutting-edge science delivered by users and the praise from the research community. Calendar year (CY) 2015 was filled with outstanding operational results and accomplishments: a very high rating from users on overall satisfaction that ties the highest-ever mark set in CY 2014; the greatest number of core-hours delivered to research projects; the largest percentage of capability usage since the OLCF began tracking the metric in 2009; and success in delivering on the allocation of 60, 30, and 10% of core hours offered for the INCITE (Innovative and Novel Computational Impact on Theory and Experiment), ALCC (Advanced Scientific Computing Research Leadership Computing Challenge), and Director’s Discretionary programs, respectively. These accomplishments, coupled with the extremely high utilization rate, represent the fulfillment of the promise of Titan: maximum use by maximum-size simulations. The impact of all of these successes and more is reflected in the accomplishments of OLCF users, with publications this year in notable journals Nature, Nature Materials, Nature Chemistry, Nature Physics, Nature Climate Change, ACS Nano, Journal of the American Chemical Society, and Physical Review Letters, as well as many others. The achievements included in the 2015 OLCF Operational Assessment Report reflect first-ever or largest simulations in their communities; for example Titan enabled engineers in Los Angeles and the surrounding region to design and begin building improved critical infrastructure by enabling the highest-resolution Cybershake map for Southern

The computer code Eurdyn - 1 M. (Release 1) Part 2: User's Manual

International Nuclear Information System (INIS)

Donea, J.; Giuliani, S.

1979-01-01

This report is the user's manual for the computer code Eurdyn-1 M developed at the J.R.C. Ispra for use in containment and fuel subassembly analyses for fast reactor safety studies. The input data are defined and a test problem is presented to illustrate both the input and the output of results

GASFLOW: A Computational Fluid Dynamics Code for Gases, Aerosols, and Combustion, Volume 2: User's Manual

Energy Technology Data Exchange (ETDEWEB)

Nichols, B. D.; Mueller, C.; Necker, G. A.; Travis, J. R.; Spore, J. W.; Lam, K. L.; Royl, P.; Wilson, T. L.

1998-10-01

Los Alamos National Laboratory (LANL) and Forschungszentrum Karlsruhe (FzK) are developing GASFLOW, a three-dimensional (3D) fluid dynamics field code as a best-estimate tool to characterize local phenomena within a flow field. Examples of 3D phenomena include circulation patterns; flow stratification; hydrogen distribution mixing and stratification; combustion and flame propagation; effects of noncondensable gas distribution on local condensation and evaporation; and aerosol entrainment, transport, and deposition. An analysis with GASFLOW will result in a prediction of the gas composition and discrete particle distribution in space and time throughout the facility and the resulting pressure and temperature loadings on the walls and internal structures with or without combustion. A major application of GASFLOW is for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containment and other facilities. It has been applied to situations involving transporting and distributing combustible gas mixtures. It has been used to study gas dynamic behavior in low-speed, buoyancy-driven flows, as well as sonic flows or diffusion dominated flows; and during chemically reacting flows, including deflagrations. The effects of controlling such mixtures by safety systems can be analyzed. The code version described in this manual is designated GASFLOW 2.1, which combines previous versions of the United States Nuclear Regulatory Commission code HMS (for Hydrogen Mixing Studies) and the Department of Energy and FzK versions of GASFLOW. The code was written in standard Fortran 90. This manual comprises three volumes. Volume I describes the governing physical equations and computational model. Volume II describes how to use the code to set up a model geometry, specify gas species and material properties, define initial and boundary conditions, and specify different outputs, especially graphical displays. Sample problems are included. Volume III

Missouri Highway Safety Manual Recalibration

Science.gov (United States)

2018-05-01

The Highway Safety Manual (HSM) is a national manual for analyzing the highway safety of various facilities, including rural roads, urban arterials, freeways, and intersections. The HSM was first published in 2010, and a 2014 supplement addressed fre...

Operational Circular nr 5 - October 2000 USE OF CERN COMPUTING FACILITIES

CERN Multimedia

Division HR

2000-01-01

New rules covering the use of CERN Computing facilities have been drawn up. All users of CERN’s computing facilites are subject to these rules, as well as to the subsidiary rules of use. The Computing Rules explicitly address your responsibility for taking reasonable precautions to protect computing equipment and accounts. In particular, passwords must not be easily guessed or obtained by others. Given the difficulty to completely separate work and personal use of computing facilities, the rules define under which conditions limited personal use is tolerated. For example, limited personal use of e-mail, news groups or web browsing is tolerated in your private time, provided CERN resources and your official duties are not adversely affected. The full conditions governing use of CERN’s computing facilities are contained in Operational Circular N° 5, which you are requested to read. Full details are available at : http://www.cern.ch/ComputingRules Copies of the circular are also available in the Divis...

Computer applications for the Fast Flux Test Facility

International Nuclear Information System (INIS)

Worth, G.A.; Patterson, J.R.

1976-01-01

Computer applications for the FFTF reactor include plant surveillance functions and fuel handling and examination control functions. Plant surveillance systems provide the reactor operator with a selection of over forty continuously updated, formatted displays of correlated data. All data are checked for limits and validity and the operator is advised of any anomaly. Data are also recorded on magnetic tape for historical purposes. The system also provides calculated variables, such as reactor thermal power and anomalous reactivity. Supplementing the basic plant surveillance computer system is a minicomputer system that monitors the reactor cover gas to detect and characterize absorber or fuel pin failures. In addition to plant surveillance functions, computers are used in the FFTF for controlling selected refueling equipment and for post-irradiation fuel pin examination. Four fuel handling or examination systems operate under computer control with manual monitoring and over-ride capability

COMPUTER ORIENTED FACILITIES OF TEACHING AND INFORMATIVE COMPETENCE

Directory of Open Access Journals (Sweden)

Olga M. Naumenko

2010-09-01

Full Text Available In the article it is considered the history of views to the tasks of education, estimations of its effectiveness from the point of view of forming of basic vitally important competences. Opinions to the problem in different countries, international organizations, corresponding experience of the Ukrainian system of education are described. The necessity of forming of informative competence of future teacher is reasonable in the conditions of application of the computer oriented facilities of teaching at the study of naturally scientific cycle subjects in pedagogical colleges. Prognosis estimations concerning the development of methods of application of computer oriented facilities of teaching are presented.

A guide for the selection of computer assisted mapping (CAM) and facilities informations systems

Energy Technology Data Exchange (ETDEWEB)

Haslin, S.; Baxter, P.; Jarvis, L.

1980-12-01

Many distribution engineers are now aware that computer assisted mapping (CAM) and facilities informations systems are probably the most significant breakthrough to date in computer applications for distribution engineering. The Canadian Electrical Asociation (CEA) recognized this and requested engineers of B.C. Hydro make a study of the state of the art in Canadian utilities and the progress of CAM systems on an international basis. The purpose was to provide a guide to assist Canadian utility distribution engineers faced with the problem of studying the application of CAM systems as an alternative to present methods, consideration being given to the long-term and other benefits that were perhaps not apparent for those approaching this field for the first time. It soon became apparent that technology was developing at a high rate and competition in the market was very strong. Also a number of publications were produced by other sources which adequately covered the scope of this study. This report is thus a collection of references to reports, manuals, and other documents with a few considerations provided for those companies interested in exploring further the use of interactive graphics. 24 refs.

User's guide for the small-angle neutron scattering facility

International Nuclear Information System (INIS)

Vlak, W.A.H.M.; Werkhoven, E.J.

1989-04-01

This report serves as a manual for the users of the small-angle neutron scattering instrument located at beamport HB3 of the High Flux Reactor in Petten. The main part of the text is devoted to the control of the facility and the data handling by means of a μVAX computer. Also, the various possibilities to access the facility across computer networks are discussed. A collection of menu-driven and command-driven programs, which utilize the flexibility of the VMS operating system without requiring detailed knowledge of the user about the computer environment, enables to control the instrument. For the convenience of the experienced user, who might wish to update or extend the software, a technical supplement is included. 15 figs.; 8 refs

National Uranium Resource Evaluation Program. Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Reports Computer Program Requests Manual

International Nuclear Information System (INIS)

1980-01-01

This manual is intended to aid those who are unfamiliar with ordering computer output for verification and preparation of Uranium Resource Evaluation (URE) Project reconnaissance basic data reports. The manual is also intended to help standardize the procedures for preparing the reports. Each section describes a program or group of related programs. The sections are divided into three parts: Purpose, Request Forms, and Requested Information

Modern computer hardware and the role of central computing facilities in particle physics

International Nuclear Information System (INIS)

Zacharov, V.

1981-01-01

Important recent changes in the hardware technology of computer system components are reviewed, and the impact of these changes assessed on the present and future pattern of computing in particle physics. The place of central computing facilities is particularly examined, to answer the important question as to what, if anything, should be their future role. Parallelism in computing system components is considered to be an important property that can be exploited with advantage. The paper includes a short discussion of the position of communications and network technology in modern computer systems. (orig.)

REBA experimenters' manual

International Nuclear Information System (INIS)

Schuch, R.L.

1977-04-01

The REBA is a high-energy, pulsed electron beam or bremsstrahlung x-ray generator whose operational purpose is to provide an energy source of short duration for conducting experiments, primarily to determine material responses to rapid surface and in-depth deposition of energy. The purpose of this manual is to serve as a basic source of information for prospective users of REBA. Included is a brief discussion of the design and operation of the facility as well as a summary of output characteristics for electron beam modes and environmental data for x-ray operation. The manual also contains a description of the REBA experimental facilities, including geometry of the test cell, instrumentation and data collection capabilities, and services and support available to experimenters

SHEAT for PC. A computer code for probabilistic seismic hazard analysis for personal computer, user's manual

International Nuclear Information System (INIS)

Yamada, Hiroyuki; Tsutsumi, Hideaki; Ebisawa, Katsumi; Suzuki, Masahide

2002-03-01

The SHEAT code developed at Japan Atomic Energy Research Institute is for probabilistic seismic hazard analysis which is one of the tasks needed for seismic Probabilistic Safety Assessment (PSA) of a nuclear power plant. At first, SHEAT was developed as the large sized computer version. In addition, a personal computer version was provided to improve operation efficiency and generality of this code in 2001. It is possible to perform the earthquake hazard analysis, display and the print functions with the Graphical User Interface. With the SHEAT for PC code, seismic hazard which is defined as an annual exceedance frequency of occurrence of earthquake ground motions at various levels of intensity at a given site is calculated by the following two steps as is done with the large sized computer. One is the modeling of earthquake generation around a site. Future earthquake generation (locations, magnitudes and frequencies of postulated earthquake) is modeled based on the historical earthquake records, active fault data and expert judgment. Another is the calculation of probabilistic seismic hazard at the site. An earthquake ground motion is calculated for each postulated earthquake using an attenuation model taking into account its standard deviation. Then the seismic hazard at the site is calculated by summing the frequencies of ground motions by all the earthquakes. This document is the user's manual of the SHEAT for PC code. It includes: (1) Outline of the code, which include overall concept, logical process, code structure, data file used and special characteristics of code, (2) Functions of subprogram and analytical models in them, (3) Guidance of input and output data, (4) Sample run result, and (5) Operational manual. (author)

The highway capacity manual a conceptual and research history

CERN Document Server

Roess, Roger P

2014-01-01

Since 1950, the Highway Capacity Manual has been a standard used in the planning, design, analysis, and operation of virtually any highway traffic facility in the United States. It has also been widely used abroad, and has spurred the development of similar manuals in other countries. The twin concepts of capacity and level of service have been developed in the manual, and methodologies have been presented that allow highway traffic facilities to be designed on a common basis, and allow for the analysis of operational quality under various traffic demand scenarios. The manual also addresses related pedestrian, bicycle, and transit issues.   This book details the fundamental development of the concepts of capacity and level of service, and of the specific methodologies developed to describe them over a wide range of facility types. The book is comprised of two volumes. Volume 1 (this book) focuses on the development of basic principles, and their application to uninterrupted flow facilities: freeways, multila...

Manual on quality assurance for computer software related to the safety of nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

The objective of the Manual is to provide guidance in the assurance of quality of specification, design, maintenance and use of computer software related to items and activities important to safety (hereinafter referred to as safety related) in nuclear power plants. This guidance is consistent with, and supplements, the requirements and recommendations of Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, 50-C-QA, and related Safety Guides on quality assurance for nuclear power plants. Annex A identifies the IAEA documents referenced in the Manual. The Manual is intended to be of use to all those who, in any way, are involved with software for safety related applications for nuclear power plants, including auditors who may be called upon to audit management systems and product software. Figs

The Fermilab central computing facility architectural model

International Nuclear Information System (INIS)

Nicholls, J.

1989-01-01

The goal of the current Central Computing Upgrade at Fermilab is to create a computing environment that maximizes total productivity, particularly for high energy physics analysis. The Computing Department and the Next Computer Acquisition Committee decided upon a model which includes five components: an interactive front-end, a Large-Scale Scientific Computer (LSSC, a mainframe computing engine), a microprocessor farm system, a file server, and workstations. With the exception of the file server, all segments of this model are currently in production: a VAX/VMS cluster interactive front-end, an Amdahl VM Computing engine, ACP farms, and (primarily) VMS workstations. This paper will discuss the implementation of the Fermilab Central Computing Facility Architectural Model. Implications for Code Management in such a heterogeneous environment, including issues such as modularity and centrality, will be considered. Special emphasis will be placed on connectivity and communications between the front-end, LSSC, and workstations, as practiced at Fermilab. (orig.)

The Fermilab Central Computing Facility architectural model

International Nuclear Information System (INIS)

Nicholls, J.

1989-05-01

The goal of the current Central Computing Upgrade at Fermilab is to create a computing environment that maximizes total productivity, particularly for high energy physics analysis. The Computing Department and the Next Computer Acquisition Committee decided upon a model which includes five components: an interactive front end, a Large-Scale Scientific Computer (LSSC, a mainframe computing engine), a microprocessor farm system, a file server, and workstations. With the exception of the file server, all segments of this model are currently in production: a VAX/VMS Cluster interactive front end, an Amdahl VM computing engine, ACP farms, and (primarily) VMS workstations. This presentation will discuss the implementation of the Fermilab Central Computing Facility Architectural Model. Implications for Code Management in such a heterogeneous environment, including issues such as modularity and centrality, will be considered. Special emphasis will be placed on connectivity and communications between the front-end, LSSC, and workstations, as practiced at Fermilab. 2 figs

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-02-01

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

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

Users manual for CAFE-3D : a computational fluid dynamics fire code

International Nuclear Information System (INIS)

Khalil, Imane; Lopez, Carlos; Suo-Anttila, Ahti Jorma

2005-01-01

The Container Analysis Fire Environment (CAFE) computer code has been developed to model all relevant fire physics for predicting the thermal response of massive objects engulfed in large fires. It provides realistic fire thermal boundary conditions for use in design of radioactive material packages and in risk-based transportation studies. The CAFE code can be coupled to commercial finite-element codes such as MSC PATRAN/THERMAL and ANSYS. This coupled system of codes can be used to determine the internal thermal response of finite element models of packages to a range of fire environments. This document is a user manual describing how to use the three-dimensional version of CAFE, as well as a description of CAFE input and output parameters. Since this is a user manual, only a brief theoretical description of the equations and physical models is included

Computer security at ukrainian nuclear facilities: interface between nuclear safety and security

International Nuclear Information System (INIS)

Chumak, D.; Klevtsov, O.

2015-01-01

Active introduction of information technology, computer instrumentation and control systems (I and C systems) in the nuclear field leads to a greater efficiency and management of technological processes at nuclear facilities. However, this trend brings a number of challenges related to cyber-attacks on the above elements, which violates computer security as well as nuclear safety and security of a nuclear facility. This paper considers regulatory support to computer security at the nuclear facilities in Ukraine. The issue of computer and information security considered in the context of physical protection, because it is an integral component. The paper focuses on the computer security of I and C systems important to nuclear safety. These systems are potentially vulnerable to cyber threats and, in case of cyber-attacks, the potential negative impact on the normal operational processes can lead to a breach of the nuclear facility security. While ensuring nuclear security of I and C systems, it interacts with nuclear safety, therefore, the paper considers an example of an integrated approach to the requirements of nuclear safety and security

Survey of computer codes applicable to waste facility performance evaluations

International Nuclear Information System (INIS)

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

1988-01-01

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

National facility for advanced computational science: A sustainable path to scientific discovery

Energy Technology Data Exchange (ETDEWEB)

Simon, Horst; Kramer, William; Saphir, William; Shalf, John; Bailey, David; Oliker, Leonid; Banda, Michael; McCurdy, C. William; Hules, John; Canning, Andrew; Day, Marc; Colella, Philip; Serafini, David; Wehner, Michael; Nugent, Peter

2004-04-02

Lawrence Berkeley National Laboratory (Berkeley Lab) proposes to create a National Facility for Advanced Computational Science (NFACS) and to establish a new partnership between the American computer industry and a national consortium of laboratories, universities, and computing facilities. NFACS will provide leadership-class scientific computing capability to scientists and engineers nationwide, independent of their institutional affiliation or source of funding. This partnership will bring into existence a new class of computational capability in the United States that is optimal for science and will create a sustainable path towards petaflops performance.

Molecular Science Computing Facility Scientific Challenges: Linking Across Scales

Energy Technology Data Exchange (ETDEWEB)

De Jong, Wibe A.; Windus, Theresa L.

2005-07-01

The purpose of this document is to define the evolving science drivers for performing environmental molecular research at the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) and to provide guidance associated with the next-generation high-performance computing center that must be developed at EMSL's Molecular Science Computing Facility (MSCF) in order to address this critical research. The MSCF is the pre-eminent computing facility?supported by the U.S. Department of Energy's (DOE's) Office of Biological and Environmental Research (BER)?tailored to provide the fastest time-to-solution for current computational challenges in chemistry and biology, as well as providing the means for broad research in the molecular and environmental sciences. The MSCF provides integral resources and expertise to emerging EMSL Scientific Grand Challenges and Collaborative Access Teams that are designed to leverage the multiple integrated research capabilities of EMSL, thereby creating a synergy between computation and experiment to address environmental molecular science challenges critical to DOE and the nation.

Integration of small computers in the low budget facility

International Nuclear Information System (INIS)

Miller, G.E.; Crofoot, T.A.

1988-01-01

Inexpensive computers (PC's) are well within the reach of low budget reactor facilities. It is possible to envisage many uses that will both improve capabilities of existing instrumentation and also assist operators and staff with certain routine tasks. Both of these opportunities are important for survival at facilities with severe budget and staffing limitations. (author)

FTMP (Fault Tolerant Multiprocessor) programmer's manual

Science.gov (United States)

Feather, F. E.; Liceaga, C. A.; Padilla, P. A.

1986-01-01

The Fault Tolerant Multiprocessor (FTMP) computer system was constructed using the Rockwell/Collins CAPS-6 processor. It is installed in the Avionics Integration Research Laboratory (AIRLAB) of NASA Langley Research Center. It is hosted by AIRLAB's System 10, a VAX 11/750, for the loading of programs and experimentation. The FTMP support software includes a cross compiler for a high level language called Automated Engineering Design (AED) System, an assembler for the CAPS-6 processor assembly language, and a linker. Access to this support software is through an automated remote access facility on the VAX which relieves the user of the burden of learning how to use the IBM 4381. This manual is a compilation of information about the FTMP support environment. It explains the FTMP software and support environment along many of the finer points of running programs on FTMP. This will be helpful to the researcher trying to run an experiment on FTMP and even to the person probing FTMP with fault injections. Much of the information in this manual can be found in other sources; we are only attempting to bring together the basic points in a single source. If the reader should need points clarified, there is a list of support documentation in the back of this manual.

Automation of electromagnetic compatability (EMC) test facilities

Science.gov (United States)

Harrison, C. A.

1986-01-01

Efforts to automate electromagnetic compatibility (EMC) test facilities at Marshall Space Flight Center are discussed. The present facility is used to accomplish a battery of nine standard tests (with limited variations) deigned to certify EMC of Shuttle payload equipment. Prior to this project, some EMC tests were partially automated, but others were performed manually. Software was developed to integrate all testing by means of a desk-top computer-controller. Near real-time data reduction and onboard graphics capabilities permit immediate assessment of test results. Provisions for disk storage of test data permit computer production of the test engineer's certification report. Software flexibility permits variation in the tests procedure, the ability to examine more closely those frequency bands which indicate compatibility problems, and the capability to incorporate additional test procedures.

VARIABILITY OF MANUAL AND COMPUTERIZED METHODS FOR MEASURING CORONAL VERTEBRAL INCLINATION IN COMPUTED TOMOGRAPHY IMAGES

Directory of Open Access Journals (Sweden)

Tomaž Vrtovec

2015-06-01

Full Text Available Objective measurement of coronal vertebral inclination (CVI is of significant importance for evaluating spinal deformities in the coronal plane. The purpose of this study is to systematically analyze and compare manual and computerized measurements of CVI in cross-sectional and volumetric computed tomography (CT images. Three observers independently measured CVI in 14 CT images of normal and 14 CT images of scoliotic vertebrae by using six manual and two computerized measurements. Manual measurements were obtained in coronal cross-sections by manually identifying the vertebral body corners, which served to measure CVI according to the superior and inferior tangents, left and right tangents, and mid-endplate and mid-wall lines. Computerized measurements were obtained in two dimensions (2D and in three dimensions (3D by manually initializing an automated method in vertebral centroids and then searching for the planes of maximal symmetry of vertebral anatomical structures. The mid-endplate lines were the most reproducible and reliable manual measurements (intra- and inter-observer variability of 0.7° and 1.2° standard deviation, SD, respectively. The computerized measurements in 3D were more reproducible and reliable (intra- and inter-observer variability of 0.5° and 0.7° SD, respectively, but were most consistent with the mid-wall lines (2.0° SD and 1.4° mean absolute difference. The manual CVI measurements based on mid-endplate lines and the computerized CVI measurements in 3D resulted in the lowest intra-observer and inter-observer variability, however, computerized CVI measurements reduce observer interaction.

Operation and maintenance manual for the temporary septic holding tank at the 100-D remedial action support facility. Revision 1

International Nuclear Information System (INIS)

Kelty, G.G.

1996-09-01

This manual provides detailed information for the operation and maintenance of the sanitary wastewater holding system at the 100-D Remedial Action Support Facility located in the 100-DR-1 Operable Unit of the Hanford Site. This document describes operations, including the type and frequency of required maintenance, and system failure response procedures

Methane measurements manual; Handbok metanmaetningar

Energy Technology Data Exchange (ETDEWEB)

Holmgren, Magnus Andreas (SP Technical research institute of Sweden, Boraas (Sweden))

2011-02-15

Emissions to air in different parts of the system may arise in biogas plants, where there is biological treatment of organic matter by anaerobic degradation, and during upgrading of biogas to vehicle fuel. There are mainly four reasons why these emissions must be minimized. These are safety, greenhouse gas emissions, economy and smell. This manual gathers experience of several years of work with measurement of methane emissions from biogas and upgrading facilities. This work has been done mainly in the context of Swedish Waste Management's system of voluntary commitment. The purpose of this manual is to standardize methods and procedures when methane measurements are carried out so that the results are comparable between different providers. The main target group of the manual is measurement consultants performing such measurements. Calculation template in Excel is part of the manual, which further contributes to the measurements evaluated in a standardized way. The manual contains several examples which have been calculated in the accompanying Excel template. The handbook also contains a chapter mainly intended for facility staff, in which implementation of accurate leak detection is described, and where there are hints of a system of so-called intermediate inspections to detect leaks in time

The manual of a computer software 'FBR Plant Planning Design Prototype System'

International Nuclear Information System (INIS)

2003-10-01

This is a manual of a computer software 'FBR Plant Planning Design Prototype System', which enables users to conduct case studies of deviated FBR design concepts based on 'MONJU'. The calculations simply proceed as the user clicks displayed buttons, therefore step-by-step explanation is supposed not be necessary. The following pages introduce only particular features of this software, i.e, each interactive screens, functions of buttons and consequences after clicks, and the quitting procedure. (author)

Accuracy of computer-calculated and manual QRS duration assessments: Clinical implications to select candidates for cardiac resynchronization therapy.

Science.gov (United States)

De Pooter, Jan; El Haddad, Milad; Stroobandt, Roland; De Buyzere, Marc; Timmermans, Frank

2017-06-01

QRS duration (QRSD) plays a key role in the field of cardiac resynchronization therapy (CRT). Computer-calculated QRSD assessments are widely used, however inter-manufacturer differences have not been investigated in CRT candidates. QRSD was assessed in 377 digitally stored ECGs: 139 narrow QRS, 140 LBBB and 98 ventricular paced ECGs. Manual QRSD was measured as global QRSD, using digital calipers, by two independent observers. Computer-calculated QRSD was assessed by Marquette 12SL (GE Healthcare, Waukesha, WI, USA) and SEMA3 (Schiller, Baar, Switzerland). Inter-manufacturer differences of computer-calculated QRSD assessments vary among different QRS morphologies: narrow QRSD: 4 [2-9] ms (median [IQR]), p=0.010; LBBB QRSD: 7 [2-10] ms, p=0.003 and paced QRSD: 13 [6-18] ms, p=0.007. Interobserver differences of manual QRSD assessments measured: narrow QRSD: 4 [2-6] ms, p=non-significant; LBBB QRSD: 6 [3-12] ms, p=0.006; paced QRSD: 8 [4-18] ms, p=0.001. In LBBB ECGs, intraclass correlation coefficients (ICCs) were comparable for inter-manufacturer and interobserver agreement (ICC 0.830 versus 0.837). When assessing paced QRSD, manual measurements showed higher ICC compared to inter-manufacturer agreement (ICC 0.902 versus 0.776). Using guideline cutoffs of 130ms, up to 15% of the LBBB ECGs would be misclassified as <130ms or ≥130ms by at least one method. Using a cutoff of 150ms, this number increases to 33% of ECGs being misclassified. However, by combining LBBB-morphology and QRSD, the number of misclassified ECGs can be decreased by half. Inter-manufacturer differences in computer-calculated QRSD assessments are significant and may compromise adequate selection of individual CRT candidates when using QRSD as sole parameter. Paced QRSD should preferentially be assessed by manual QRSD measurements. Copyright © 2017 Elsevier B.V. All rights reserved.

Manual on decontamination of surfaces

International Nuclear Information System (INIS)

1979-01-01

The manual is intended for those who are responsible for the organization and implementation of decontamination programmes for facilities where radioactive materials are handled mainly on a laboratory scale. It contains information and guidelines on practical methods for decontaminating working spaces, equipment, laboratory benches and protective clothing. Useful information is also provided on the removal of loose skin contamination from personnel by mild, non-medical processes. Methods of removing skin contamination needing medical supervision, or of internal decontamination, which is entirely a medical process, are not covered in this manual. Large-scale decontamination of big nuclear facilities is also considered as outside its scope

A manual for implementing residual radioactive material guidelines

International Nuclear Information System (INIS)

Gilbert, T.L.; Yu, C.; Yuan, Y.C.; Zielen, A.J.; Jusko, M.J.; Wallo, A. III; Argonne National Lab., IL; Dames and Moore, West Valley, NY; Argonne National Lab., IL; USDOE Assistant Secretary for Nuclear Energy, Washington, DC

1989-06-01

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) and the Surplus Facilities Management Program (SFMP). It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. 36 refs., 16 figs, 22 tabs

Site security personnel training manual

International Nuclear Information System (INIS)

1978-10-01

As required by 10 CFR Part 73, this training manual provides guidance to assist licensees in the development of security personnel training and qualifications programs. The information contained in the manual typifies the level and scope of training for personnel assigned to perform security related tasks and job duties associated with the protection of nuclear fuel cycle facilities and nuclear power reactors

TJ-II Library Manual (Version 2)

International Nuclear Information System (INIS)

Tribaldos, V.; Milligen, B. Ph. van; Lopez-Fraguas, A.

2001-01-01

This is a manual of use of the TJ2 Numerical Library that has been developed for making numerical computations of different TJ-II configurations. This manual is a new version of the earlier manual CIEMAT report 806. (Author)

Operation and maintenance manual for the temporary septic holding tank at the 100-D remedial action support facility. Revision 2

International Nuclear Information System (INIS)

Kelty, G.G.

1996-10-01

This manual was prepared to provide detailed information for the operation and maintenance of the sanitary wastewater holding system at the 100-D Remedial Action Support Facility located in the 100-DR-1 Operable Unit at the Hanford Site. This document describes operations, including the type and frequency of required maintenance, and system failure response procedures

Study of developing nuclear fabrication facility's integrated emergency response manual

Energy Technology Data Exchange (ETDEWEB)

Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang [KEPCO, Daejeon (Korea, Republic of); Min, Guem Young; Han, Ji Ah [Dongguk Univ., Daejeon (Korea, Republic of)

2016-05-15

Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type.

High Performance Computing Facility Operational Assessment, FY 2010 Oak Ridge Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

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

2010-08-01

Oak Ridge National Laboratory's (ORNL's) Cray XT5 supercomputer, Jaguar, kicked off the era of petascale scientific computing in 2008 with applications that sustained more than a thousand trillion floating point calculations per second - or 1 petaflop. Jaguar continues to grow even more powerful as it helps researchers broaden the boundaries of knowledge in virtually every domain of computational science, including weather and climate, nuclear energy, geosciences, combustion, bioenergy, fusion, and materials science. Their insights promise to broaden our knowledge in areas that are vitally important to the Department of Energy (DOE) and the nation as a whole, particularly energy assurance and climate change. The science of the 21st century, however, will demand further revolutions in computing, supercomputers capable of a million trillion calculations a second - 1 exaflop - and beyond. These systems will allow investigators to continue attacking global challenges through modeling and simulation and to unravel longstanding scientific questions. Creating such systems will also require new approaches to daunting challenges. High-performance systems of the future will need to be codesigned for scientific and engineering applications with best-in-class communications networks and data-management infrastructures and teams of skilled researchers able to take full advantage of these new resources. The Oak Ridge Leadership Computing Facility (OLCF) provides the nation's most powerful open resource for capability computing, with a sustainable path that will maintain and extend national leadership for DOE's Office of Science (SC). The OLCF has engaged a world-class team to support petascale science and to take a dramatic step forward, fielding new capabilities for high-end science. This report highlights the successful delivery and operation of a petascale system and shows how the OLCF fosters application development teams, developing cutting-edge tools

The OSG Open Facility: an on-ramp for opportunistic scientific computing

Science.gov (United States)

Jayatilaka, B.; Levshina, T.; Sehgal, C.; Gardner, R.; Rynge, M.; Würthwein, F.

2017-10-01

The Open Science Grid (OSG) is a large, robust computing grid that started primarily as a collection of sites associated with large HEP experiments such as ATLAS, CDF, CMS, and DZero, but has evolved in recent years to a much larger user and resource platform. In addition to meeting the US LHC community’s computational needs, the OSG continues to be one of the largest providers of distributed high-throughput computing (DHTC) to researchers from a wide variety of disciplines via the OSG Open Facility. The Open Facility consists of OSG resources that are available opportunistically to users other than resource owners and their collaborators. In the past two years, the Open Facility has doubled its annual throughput to over 200 million wall hours. More than half of these resources are used by over 100 individual researchers from over 60 institutions in fields such as biology, medicine, math, economics, and many others. Over 10% of these individual users utilized in excess of 1 million computational hours each in the past year. The largest source of these cycles is temporary unused capacity at institutions affiliated with US LHC computational sites. An increasing fraction, however, comes from university HPC clusters and large national infrastructure supercomputers offering unused capacity. Such expansions have allowed the OSG to provide ample computational resources to both individual researchers and small groups as well as sizable international science collaborations such as LIGO, AMS, IceCube, and sPHENIX. Opening up access to the Fermilab FabrIc for Frontier Experiments (FIFE) project has also allowed experiments such as mu2e and NOvA to make substantial use of Open Facility resources, the former with over 40 million wall hours in a year. We present how this expansion was accomplished as well as future plans for keeping the OSG Open Facility at the forefront of enabling scientific research by way of DHTC.

The OSG Open Facility: An On-Ramp for Opportunistic Scientific Computing

Energy Technology Data Exchange (ETDEWEB)

Jayatilaka, B. [Fermilab; Levshina, T. [Fermilab; Sehgal, C. [Fermilab; Gardner, R. [Chicago U.; Rynge, M. [USC - ISI, Marina del Rey; Würthwein, F. [UC, San Diego

2017-11-22

The Open Science Grid (OSG) is a large, robust computing grid that started primarily as a collection of sites associated with large HEP experiments such as ATLAS, CDF, CMS, and DZero, but has evolved in recent years to a much larger user and resource platform. In addition to meeting the US LHC community’s computational needs, the OSG continues to be one of the largest providers of distributed high-throughput computing (DHTC) to researchers from a wide variety of disciplines via the OSG Open Facility. The Open Facility consists of OSG resources that are available opportunistically to users other than resource owners and their collaborators. In the past two years, the Open Facility has doubled its annual throughput to over 200 million wall hours. More than half of these resources are used by over 100 individual researchers from over 60 institutions in fields such as biology, medicine, math, economics, and many others. Over 10% of these individual users utilized in excess of 1 million computational hours each in the past year. The largest source of these cycles is temporary unused capacity at institutions affiliated with US LHC computational sites. An increasing fraction, however, comes from university HPC clusters and large national infrastructure supercomputers offering unused capacity. Such expansions have allowed the OSG to provide ample computational resources to both individual researchers and small groups as well as sizable international science collaborations such as LIGO, AMS, IceCube, and sPHENIX. Opening up access to the Fermilab FabrIc for Frontier Experiments (FIFE) project has also allowed experiments such as mu2e and NOvA to make substantial use of Open Facility resources, the former with over 40 million wall hours in a year. We present how this expansion was accomplished as well as future plans for keeping the OSG Open Facility at the forefront of enabling scientific research by way of DHTC.

Computer-Assisted School Facility Planning with ONPASS.

Science.gov (United States)

Urban Decision Systems, Inc., Los Angeles, CA.

The analytical capabilities of ONPASS, an on-line computer-aided school facility planning system, are described by its developers. This report describes how, using the Canoga Park-Winnetka-Woodland Hills Planning Area as a test case, the Department of City Planning of the city of Los Angeles employed ONPASS to demonstrate how an on-line system can…

Hanford whole body counting manual

International Nuclear Information System (INIS)

Palmer, H.E.; Brim, C.P.; Rieksts, G.A.; Rhoads, M.C.

1987-05-01

This document, a reprint of the Whole Body Counting Manual, was compiled to train personnel, document operation procedures, and outline quality assurance procedures. The current manual contains information on: the location, availability, and scope of services of Hanford's whole body counting facilities; the administrative aspect of the whole body counting operation; Hanford's whole body counting facilities; the step-by-step procedure involved in the different types of in vivo measurements; the detectors, preamplifiers and amplifiers, and spectroscopy equipment; the quality assurance aspect of equipment calibration and recordkeeping; data processing, record storage, results verification, report preparation, count summaries, and unit cost accounting; and the topics of minimum detectable amount and measurement accuracy and precision. 12 refs., 13 tabs

Development of an environmental safety case guidance manual

International Nuclear Information System (INIS)

Wellstead, Matthew John

2014-01-01

NDA RWMD is currently considering the scope, purpose and structure of a safety case manual that covers the development of nuclear operational, transport and environmental safety cases for a geological disposal facility in the United Kingdom. This paper considers the Environmental Safety Case (ESC) input into such a manual (herein referred to as the 'ESC Manual'), looking at the drivers and benefits that a guidance manual in this area may provide. (authors)

TrueAllele casework on Virginia DNA mixture evidence: computer and manual interpretation in 72 reported criminal cases.

Directory of Open Access Journals (Sweden)

Mark W Perlin

Full Text Available Mixtures are a commonly encountered form of biological evidence that contain DNA from two or more contributors. Laboratory analysis of mixtures produces data signals that usually cannot be separated into distinct contributor genotypes. Computer modeling can resolve the genotypes up to probability, reflecting the uncertainty inherent in the data. Human analysts address the problem by simplifying the quantitative data in a threshold process that discards considerable identification information. Elevated stochastic threshold levels potentially discard more information. This study examines three different mixture interpretation methods. In 72 criminal cases, 111 genotype comparisons were made between 92 mixture items and relevant reference samples. TrueAllele computer modeling was done on all the evidence samples, and documented in DNA match reports that were provided as evidence for each case. Threshold-based Combined Probability of Inclusion (CPI and stochastically modified CPI (mCPI analyses were performed as well. TrueAllele's identification information in 101 positive matches was used to assess the reliability of its modeling approach. Comparison was made with 81 CPI and 53 mCPI DNA match statistics that were manually derived from the same data. There were statistically significant differences between the DNA interpretation methods. TrueAllele gave an average match statistic of 113 billion, CPI averaged 6.68 million, and mCPI averaged 140. The computer was highly specific, with a false positive rate under 0.005%. The modeling approach was precise, having a factor of two within-group standard deviation. TrueAllele accuracy was indicated by having uniformly distributed match statistics over the data set. The computer could make genotype comparisons that were impossible or impractical using manual methods. TrueAllele computer interpretation of DNA mixture evidence is sensitive, specific, precise, accurate and more informative than manual

Neutronic computational modeling of the ASTRA critical facility using MCNPX

International Nuclear Information System (INIS)

Rodriguez, L. P.; Garcia, C. R.; Milian, D.; Milian, E. E.; Brayner, C.

2015-01-01

The Pebble Bed Very High Temperature Reactor is considered as a prominent candidate among Generation IV nuclear energy systems. Nevertheless the Pebble Bed Very High Temperature Reactor faces an important challenge due to the insufficient validation of computer codes currently available for use in its design and safety analysis. In this paper a detailed IAEA computational benchmark announced by IAEA-TECDOC-1694 in the framework of the Coordinated Research Project 'Evaluation of High Temperature Gas Cooled Reactor (HTGR) Performance' was solved in support of the Generation IV computer codes validation effort using MCNPX ver. 2.6e computational code. In the IAEA-TECDOC-1694 were summarized a set of four calculational benchmark problems performed at the ASTRA critical facility. Benchmark problems include criticality experiments, control rod worth measurements and reactivity measurements. The ASTRA Critical Facility at the Kurchatov Institute in Moscow was used to simulate the neutronic behavior of nuclear pebble bed reactors. (Author)

Use of toxicity assessment to develop site specific remediation criteria for oil and gas facilities : guidance manual

International Nuclear Information System (INIS)

1996-01-01

The results of a two year study into the evaluation of toxicity-based methods to develop site-specific, risk-based cleanup objectives for the decommissioning of oil and gas facilities were compiled into a manual of guidance. The two basic approaches used in determining remediation criteria for contaminated sites are: (1) comparison of the concentrations of chemicals found on-site with broad regional or national soil and water quality objectives developed for the chemicals involved, and (2) site-specific risk assessment. Toxicity tests are used to test organisms such as earthworms, lettuce seeds, or larval fish directly in the soil, water or sediment suspected of being contaminated. The effects of any contamination on the survival, growth, reproduction, and behaviour of the test organisms are then evaluated. The manual provides guidance in: (1) using toxicity assessments within the regulatory framework of site decommissioning, (2) performing a toxicity assessment, and (3) developing site-specific criteria for a risk assessment. 18 refs., 3 tabs., 5 figs

Integration of a browser based operator manual in the system environment of a process computer system; Integration eines browserbasierten Betriebshandbuchs in die Systemumgebung einer Prozessrechneranlage

Energy Technology Data Exchange (ETDEWEB)

Weber, Andreas [Westinghouse Electric Germany GmbH (Germany); Erfle, Robert [DOSCO GmbH, Heidelberg (Germany); Feinkohl, Dirk [E.ON Kernkraft GmbH (Germany). Kernkraftwerk Unterweser

2012-11-01

The integration of a browser based operator manual in the system environment of a process computer system is an optimization of the operating procedure in the control room and a safety enhancement due to faster and error-free access to the manual contents. Several requirements by the authorities have to be fulfilled: the operating manual has to be available as hard copy, the format has to be true to original, protection against manipulation has to be provided, the manual content of the browser-based version and the hard copy have to identical, and the display presentation has to be consistent with ergonomic principals. The integration of the on-line manual in the surveillance process computer system provides the operator with the relevant comments to the surveillance signal. The described integration of the on-line manual is an optimization of the operator's everyday job with respect to ergonomics and safety (human performance).

Development of computer model for radionuclide released from shallow-land disposal facility

International Nuclear Information System (INIS)

Suganda, D.; Sucipta; Sastrowardoyo, P.B.; Eriendi

1998-01-01

Development of 1-dimensional computer model for radionuclide release from shallow land disposal facility (SLDF) has been done. This computer model is used for the SLDF facility at PPTA Serpong. The SLDF facility is above 1.8 metres from groundwater and 150 metres from Cisalak river. Numerical method by implicit method of finite difference solution is chosen to predict the migration of radionuclide with any concentration.The migration starts vertically from the bottom of SLDF until the groundwater layer, then horizontally in the groundwater until the critical population group. Radionuclide Cs-137 is chosen as a sample to know its migration. The result of the assessment shows that the SLDF facility at PPTA Serpong has the high safety criteria. (author)

CSTEM User Manual

Science.gov (United States)

Hartle, M.; McKnight, R. L.

2000-01-01

This manual is a combination of a user manual, theory manual, and programmer manual. The reader is assumed to have some previous exposure to the finite element method. This manual is written with the idea that the CSTEM (Coupled Structural Thermal Electromagnetic-Computer Code) user needs to have a basic understanding of what the code is actually doing in order to properly use the code. For that reason, the underlying theory and methods used in the code are described to a basic level of detail. The manual gives an overview of the CSTEM code: how the code came into existence, a basic description of what the code does, and the order in which it happens (a flowchart). Appendices provide a listing and very brief description of every file used by the CSTEM code, including the type of file it is, what routine regularly accesses the file, and what routine opens the file, as well as special features included in CSTEM.

Biosafety Manual

Energy Technology Data Exchange (ETDEWEB)

King, Bruce W.

2010-05-18

Work with or potential exposure to biological materials in the course of performing research or other work activities at Lawrence Berkeley National Laboratory (LBNL) must be conducted in a safe, ethical, environmentally sound, and compliant manner. Work must be conducted in accordance with established biosafety standards, the principles and functions of Integrated Safety Management (ISM), this Biosafety Manual, Chapter 26 (Biosafety) of the Health and Safety Manual (PUB-3000), and applicable standards and LBNL policies. The purpose of the Biosafety Program is to protect workers, the public, agriculture, and the environment from exposure to biological agents or materials that may cause disease or other detrimental effects in humans, animals, or plants. This manual provides workers; line management; Environment, Health, and Safety (EH&S) Division staff; Institutional Biosafety Committee (IBC) members; and others with a comprehensive overview of biosafety principles, requirements from biosafety standards, and measures needed to control biological risks in work activities and facilities at LBNL.

Building Condition and Suitability Evaluation Manual.

Science.gov (United States)

MGT of America, Inc., Tallahassee, FL.

This educational facility evaluation manual contains the overall building condition rating form and the supporting check sheets which have been field tested in several states and, where appropriate, modified for use in the Idaho School Facilities Needs Assessment. The exterior building condition form examines the foundation, structure, walls,…

A test matrix sequencer for research test facility automation

Science.gov (United States)

Mccartney, Timothy P.; Emery, Edward F.

1990-01-01

The hardware and software configuration of a Test Matrix Sequencer, a general purpose test matrix profiler that was developed for research test facility automation at the NASA Lewis Research Center, is described. The system provides set points to controllers and contact closures to data systems during the course of a test. The Test Matrix Sequencer consists of a microprocessor controlled system which is operated from a personal computer. The software program, which is the main element of the overall system is interactive and menu driven with pop-up windows and help screens. Analog and digital input/output channels can be controlled from a personal computer using the software program. The Test Matrix Sequencer provides more efficient use of aeronautics test facilities by automating repetitive tasks that were once done manually.

PROCESS DESIGN MANUAL FOR SLUDGE TREATMENT AND DISPOSAL

Science.gov (United States)

The purpose of this manual is to provide the engineering community and related industry with a new source of information to be used in the planning, design, and operation of present and future wastewater pollution control facilities. This manual supplements this existing knowledg...

Simple heuristics: A bridge between manual core design and automated optimization methods

International Nuclear Information System (INIS)

White, J.R.; Delmolino, P.M.

1993-01-01

The primary function of RESCUE is to serve as an aid in the analysis and identification of feasible loading patterns for LWR reload cores. The unique feature of RESCUE is that its physics model is based on some recent advances in generalized perturbation theory (GPT) methods. The high order GPT techniques offer the accuracy, computational efficiency, and flexibility needed for the implementation of a full range of capabilities within a set of compatible interactive (manual and semi-automated) and automated design tools. The basic design philosophy and current features within RESCUE are reviewed, and the new semi-automated capability is highlighted. The online advisor facility appears quite promising and it provides a natural bridge between the traditional trial-and-error manual process and the recent progress towards fully automated optimization sequences. (orig.)

CAISSE (Computer Aided Information System on Solar Energy) technical manual

Energy Technology Data Exchange (ETDEWEB)

Cantelon, P E; Beinhauer, F W

1979-01-01

The Computer Aided Information System on Solar Energy (CAISSE) was developed to provide the general public with information on solar energy and its potential uses and costs for domestic consumption. CAISSE is an interactive computing system which illustrates solar heating concepts through the use of 35 mm slides, text displays on a screen and a printed report. The user communicates with the computer by responding to questions about his home and heating requirements through a touch sensitive screen. The CAISSE system contains a solar heating simulation model which calculates the heating load capable of being supplied by a solar heating system and uses this information to illustrate installation costs, fuel savings and a 20 year life-cycle analysis of cost and benefits. The system contains several sets of radiation and weather data for Canada and USA. The selection of one of four collector models is based upon the requirements input during the computer session. Optimistic and pessimistic fuel cost forecasts are made for oil, natural gas, electricity, or propane; and the forecasted fuel cost is made the basis of the life cycle cost evaluation for the solar heating application chosen. This manual is organized so that each section describes one major aspect of the use of solar energy systems to provide energy for domestic consumption. The sources of data and technical information and the method of incorporating them into the CAISSE display system are described in the same order as the computer processing. Each section concludes with a list of future developments that could be included to make CAISSE outputs more regionally specific and more useful to designers. 19 refs., 1 tab.

WISDAAM software programmer's manual

International Nuclear Information System (INIS)

Ball, J.R.

1992-10-01

The WISDAAM system was developed to provide quality control over test data associated with in situ testing at the Waste Isolation Pilot Plant (WIPP). Assurance of data quality is of critical importance as these tests supply the information which will be used for development and verification of the technology required for repository implementation. The amount of data collected from the tests, which are some of the largest ever fielded in an underground facility, prompted the undertaking of a major project task to address data processing. The goal was to create a conceptual umbrella under which all of the activities associated with processing WIPP data (i.e., data reduction, archiving, retrieval, etc.) could be grouped. The WISDAAM system was the product of this task. The overall system covers electronic as well as manual data processing; however, this document deals primarily with those operations implemented by software running on a VAX computer

User's manual for the NEFTRAN II computer code

International Nuclear Information System (INIS)

Olague, N.E.; Campbell, J.E.; Leigh, C.D.; Longsine, D.E.

1991-02-01

This document describes the NEFTRAN II (NEtwork Flow and TRANsport in Time-Dependent Velocity Fields) computer code and is intended to provide the reader with sufficient information to use the code. NEFTRAN II was developed as part of a performance assessment methodology for storage of high-level nuclear waste in unsaturated, welded tuff. NEFTRAN II is a successor to the NEFTRAN and NWFT/DVM computer codes and contains several new capabilities. These capabilities include: (1) the ability to input pore velocities directly to the transport model and bypass the network fluid flow model, (2) the ability to transport radionuclides in time-dependent velocity fields, (3) the ability to account for the effect of time-dependent saturation changes on the retardation factor, and (4) the ability to account for time-dependent flow rates through the source regime. In addition to these changes, the input to NEFTRAN II has been modified to be more convenient for the user. This document is divided into four main sections consisting of (1) a description of all the models contained in the code, (2) a description of the program and subprograms in the code, (3) a data input guide and (4) verification and sample problems. Although NEFTRAN II is the fourth generation code, this document is a complete description of the code and reference to past user's manuals should not be necessary. 19 refs., 33 figs., 25 tabs

The minimal manual: is less really more?

NARCIS (Netherlands)

Lazonder, Adrianus W.; van der Meij, Hans

1993-01-01

Carroll, Smith-Kerker, Ford and Mazur-Rimetz (The minimal manual, Human-Computer Interaction , 3, 123-153, 1987) have introduced the minimal manual as an alternative to standard self-instruction manuals. While their research indicates strong gains, only a few attempts have been made to validate

A user's manual of Tools for Error Estimation of Complex Number Matrix Computation (Ver.1.0)

International Nuclear Information System (INIS)

Ichihara, Kiyoshi.

1997-03-01

'Tools for Error Estimation of Complex Number Matrix Computation' is a subroutine library which aids the users in obtaining the error ranges of the complex number linear system's solutions or the Hermitian matrices' eigen values. This library contains routines for both sequential computers and parallel computers. The subroutines for linear system error estimation calulate norms of residual vectors, matrices's condition numbers, error bounds of solutions and so on. The error estimation subroutines for Hermitian matrix eigen values' derive the error ranges of the eigen values according to the Korn-Kato's formula. This user's manual contains a brief mathematical background of error analysis on linear algebra and usage of the subroutines. (author)

Guide to good practices at plutonium facilities

International Nuclear Information System (INIS)

Faust, L.G.; Brackenbush, L.W.; Carter, L.A.; Endres, G.W.R.; Glenn, R.D.; Jech, J.J.; Selby, J.M.; Smith, R.C.; Waite, D.A.; Walsh, W.P.

1977-09-01

This manual establishes guidelines and principles for use in setting up a sound radiation protection program for work with plutonium. The guidance presented is based on the experiences of Energy Research and Development Administration (ERDA) contractors and those portions of private industry concerned with the operation of plutonium facilities, specifically with the fabrication of mixed oxide reactor fuel. The manual is directed primarily to those facilities which have as their sole purpose the handling of large quantities of plutonium for military or industrial uses. It is not intended for use by facilities engaged in reactor or chemical separation operations nor for partial or occasional use by analytical laboratories; while these facilities would find the manual beneficial, it would be incomplete for their needs. The manual addresses good practices that should be observed by management, staff and designers, since the benefits of a good radiation protection program are the result of their joint efforts. Methods for the diagnostic evaluation of internally deposited Pu are included

Computer codes for ventilation in nuclear facilities

International Nuclear Information System (INIS)

Mulcey, P.

1987-01-01

In this paper the authors present some computer codes, developed in the last years, for ventilation and radioprotection. These codes are used for safety analysis in the conception, exploitation and dismantlement of nuclear facilities. The authors present particularly: DACC1 code used for aerosol deposit in sampling circuit of radiation monitors; PIAF code used for modelization of complex ventilation system; CLIMAT 6 code used for optimization of air conditioning system [fr

Health and Safety Research Division manual for the x-ray facility in Building 2008

International Nuclear Information System (INIS)

Stansbury, P.S.

1977-11-01

The facility in the east end of Building 2008, ORNL, consists of an x-ray machine and a shielded enclosure. The x-ray machine is of the constant potential type and can be operated continuously at generating potentials up to 125 kVcp with tube currents ranging from 0.1 μA to 10 mA. Both the generating potential and the tube current are highly regulated and stabilized. The machine is installed and operated within a large shielded enclosure. In addition to the x-ray machine and its ancillary equipment, the shielded enclosure contains many of the features of a general chemistry and physics laboratory including work benches, sinks, storage space, and electrical and gas service. This manual contains instructions for the safe operation of the x-ray machine

The environmental survey manual

International Nuclear Information System (INIS)

1987-08-01

The purpose of this manual is to provide guidance to the Survey and Sampling and Analysis teams that conduct the one-time Environmental Survey of the major US Department of Energy (DOE) operating facilities. This manual includes a discussion of DOE's policy on environmental issues, a review of statutory guidance as it applies to the Survey, the procedures and protocols to be used by the Survey teams, criteria for the use of the Survey teams in evaluating existing environmental data for the Survey effort, generic technical checklists used in every Survey, health and safety guidelines for the personnel conducting the Survey, including the identification of potential hazards, prescribed protective equipment, and emergency procedures, the required formats for the Survey reports, guidance on identifying environmental problems that need immediate attention by the Operations Office responsible for the particular facility, and procedures and protocols for the conduct of sampling and analysis

Transportation security personnel training manual

International Nuclear Information System (INIS)

1978-11-01

Objective of this manual is to train security personnel to protect special nuclear materials and nuclear facilities against theft and sabotage as required by 10 CFR Part 73. This volume contains the introduction and rationale

Computer control and data acquisition system for the R.F. Test Facility

International Nuclear Information System (INIS)

Stewart, K.A.; Burris, R.D.; Mankin, J.B.; Thompson, D.H.

1986-01-01

The Radio Frequency Test Facility (RFTF) at Oak Ridge National Laboratory, used to test and evaluate high-power ion cyclotron resonance heating (ICRH) systems and components, is monitored and controlled by a multicomponent computer system. This data acquisition and control system consists of three major hardware elements: (1) an Allen-Bradley PLC-3 programmable controller; (2) a VAX 11/780 computer; and (3) a CAMAC serial highway interface. Operating in LOCAL as well as REMOTE mode, the programmable logic controller (PLC) performs all the control functions of the test facility. The VAX computer acts as the operator's interface to the test facility by providing color mimic panel displays and allowing input via a trackball device. The VAX also provides archiving of trend data acquired by the PLC. Communications between the PLC and the VAX are via the CAMAC serial highway. Details of the hardware, software, and the operation of the system are presented in this paper

MINTEQ user's manual

International Nuclear Information System (INIS)

Peterson, S.R.; Hostetler, C.J.; Deutsch, W.J.; Cowan, C.E.

1987-02-01

This manual will aid the user in applying the MINTEQ geochemical computer code to model aqueous solutions and the interactions of aqueous solutions with hypothesized assemblages of solid phases. The manual will provide a basic understanding of how the MINTEQ computer code operates and the important principles that are incorporated into the code and instruct a user of the MINTEQ code on how to create input files to simulate a variety of geochemical problems. Chapters 2 through 8 are for the user who has some experience with or wishes to review the principles important to geochemical computer codes. These chapters include information on the methodology MINTEQ uses to incorporate these principles into the code. Chapters 9 through 11 are for the user who wants to know how to create input data files to model various types of problems. 35 refs., 2 figs., 5 tabs

The CAIN computer code for the generation of MABEL input data sets: a user's manual

International Nuclear Information System (INIS)

Tilley, D.R.

1983-03-01

CAIN is an interactive FORTRAN computer code designed to overcome the substantial effort involved in manually creating the thermal-hydraulics input data required by MABEL-2. CAIN achieves this by processing output from either of the whole-core codes, RELAP or TRAC, interpolating where necessary, and by scanning RELAP/TRAC output in order to generate additional information. This user's manual describes the actions required in order to create RELAP/TRAC data sets from magnetic tape, to create the other input data sets required by CAIN, and to operate the interactive command procedure for the execution of CAIN. In addition, the CAIN code is described in detail. This programme of work is part of the Nuclear Installations Inspectorate (NII)'s contribution to the United Kingdom Atomic Energy Authority's independent safety assessment of pressurized water reactors. (author)

Centralized computer-based controls of the Nova Laser Facility

International Nuclear Information System (INIS)

Krammen, J.

1985-01-01

This article introduces the overall architecture of the computer-based Nova Laser Control System and describes its basic components. Use of standard hardware and software components ensures that the system, while specialized and distributed throughout the facility, is adaptable. 9 references, 6 figures

Procedures for economic distribution of radionuclides in research facilities

International Nuclear Information System (INIS)

Perry, N.A.

1979-01-01

A radionuclide accountability system for use in a research facility is described. It can be operated manually or adapted for computer use. All radionuclides are ordered, received, distributed and paid for by the Radiological Control Office who keep complete records of date of order, receipt, calibration use, transfer and/or disposal. Wipe leak tests, specific activity and lot number are also recorded. The procedure provides centralized total accountability records, including financial records, of all radionuclide orders, and the economic advantages of combined purchasing. The use of this system in two medical facilities has resulted in considerable financial savings in the first year of operation. (author)

A users manual for a computer program which calculates time optical geocentric transfers using solar or nuclear electric and high thrust propulsion

Science.gov (United States)

Sackett, L. L.; Edelbaum, T. N.; Malchow, H. L.

1974-01-01

This manual is a guide for using a computer program which calculates time optimal trajectories for high-and low-thrust geocentric transfers. Either SEP or NEP may be assumed and a one or two impulse, fixed total delta V, initial high thrust phase may be included. Also a single impulse of specified delta V may be included after the low thrust state. The low thrust phase utilizes equinoctial orbital elements to avoid the classical singularities and Kryloff-Boguliuboff averaging to help insure more rapid computation time. The program is written in FORTRAN 4 in double precision for use on an IBM 360 computer. The manual includes a description of the problem treated, input/output information, examples of runs, and source code listings.

Comparison of 3D computer-aided with manual cerebral aneurysm measurements in different imaging modalities

International Nuclear Information System (INIS)

Groth, M.; Buhk, J.H.; Schoenfeld, M.; Goebell, E.; Fiehler, J.; Forkert, N.D.

2013-01-01

To compare intra- and inter-observer reliability of aneurysm measurements obtained by a 3D computer-aided technique with standard manual aneurysm measurements in different imaging modalities. A total of 21 patients with 29 cerebral aneurysms were studied. All patients underwent digital subtraction angiography (DSA), contrast-enhanced (CE-MRA) and time-of-flight magnetic resonance angiography (TOF-MRA). Aneurysm neck and depth diameters were manually measured by two observers in each modality. Additionally, semi-automatic computer-aided diameter measurements were performed using 3D vessel surface models derived from CE- (CE-com) and TOF-MRA (TOF-com) datasets. Bland-Altman analysis (BA) and intra-class correlation coefficient (ICC) were used to evaluate intra- and inter-observer agreement. BA revealed the narrowest relative limits of intra- and inter-observer agreement for aneurysm neck and depth diameters obtained by TOF-com (ranging between ±5.3 % and ±28.3 %) and CE-com (ranging between ±23.3 % and ±38.1 %). Direct measurements in DSA, TOF-MRA and CE-MRA showed considerably wider limits of agreement. The highest ICCs were observed for TOF-com and CE-com (ICC values, 0.92 or higher for intra- as well as inter-observer reliability). Computer-aided aneurysm measurement in 3D offers improved intra- and inter-observer reliability and a reproducible parameter extraction, which may be used in clinical routine and as objective surrogate end-points in clinical trials. (orig.)

Davis PV plant operation and maintenance manual

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

This operation and maintenance manual contains the information necessary to run the Photovoltaics for Utility Scale Applications (PVUSA) test facility in Davis, California. References to more specific information available in drawings, data sheets, files, or vendor manuals are included. The PVUSA is a national cooperative research and demonstration program formed in 1987 to assess the potential of utility scale photovoltaic systems.

33 CFR 154.310 - Operations manual: Contents.

Science.gov (United States)

2010-07-01

..., maps, drawings, aerial photographs or diagrams, showing the boundaries of the facility subject to Coast... products and the location in the Operations Manual where a chart or list of symbols utilized is located and... vapor collection system at the facility which includes: (1) A line diagram or simplified piping and...

Evaluation of the discrete vortex wake cross flow model using vector computers. Part 2: User's manual for DIVORCE

Science.gov (United States)

Deffenbaugh, F. D.; Vitz, J. F.

1979-01-01

The users manual for the Discrete Vortex Cross flow Evaluator (DIVORCE) computer program is presented. DIVORCE was developed in FORTRAN 4 for the DCD 6600 and CDC 7600 machines. Optimal calls to a NASA vector subroutine package are provided for use with the CDC 7600.

Emergency facility control device for nuclear reactor

International Nuclear Information System (INIS)

Ikehara, Morihiko.

1981-01-01

Purpose: To increase the reliability of a nuclear reactor by allowing an emergency facility to be manually started and stopped to make its operation more convenient and eliminate the possibility of erroneous operation in an emergency. Constitution: There are provided a first water level detector for detecting a level lower than the first low water level in a reactor container and a second water level detector for detecting a level lower than the second low water level lower than the first low water level, and an emergency facility can be started and stopped manually only when the level is higher than the second low water level, but the facility will be started regardless of the state of the manual operation when the level is lower than the second low water level. Thus, the emergency facility can be started by manual operation, but will be automatically started so as to secure the necessary minimum operation if the level becomes lower than the second low water level and the stopping operation thereafter is forgotten. (Kamimura, M.)

TAP 1, Training Program Manual

International Nuclear Information System (INIS)

1991-01-01

Training programs at DOE nuclear facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

Brookhaven Reactor Experiment Control Facility, a distributed function computer network

International Nuclear Information System (INIS)

Dimmler, D.G.; Greenlaw, N.; Kelley, M.A.; Potter, D.W.; Rankowitz, S.; Stubblefield, F.W.

1975-11-01

A computer network for real-time data acquisition, monitoring and control of a series of experiments at the Brookhaven High Flux Beam Reactor has been developed and has been set into routine operation. This reactor experiment control facility presently services nine neutron spectrometers and one x-ray diffractometer. Several additional experiment connections are in progress. The architecture of the facility is based on a distributed function network concept. A statement of implementation and results is presented

Public Computer Assisted Learning Facilities for Children with Visual Impairment: Universal Design for Inclusive Learning

Science.gov (United States)

Siu, Kin Wai Michael; Lam, Mei Seung

2012-01-01

Although computer assisted learning (CAL) is becoming increasingly popular, people with visual impairment face greater difficulty in accessing computer-assisted learning facilities. This is primarily because most of the current CAL facilities are not visually impaired friendly. People with visual impairment also do not normally have access to…

FINAS. Example manual. 2

International Nuclear Information System (INIS)

Iwata, Koji; Tsukimori, Kazuyuki; Ueno, Mutsuo

2003-12-01

FINAS is a general purpose structural analysis computer program which was developed by Japan Nuclear Cycle Development Institute for the analysis of static, dynamic and thermal responses of elastic and inelastic structures by the finite element method. This manual contains typical analysis examples that illustrate applications of FINAS to a variety of structural engineering problems. The first part of this manual presents fundamental examples in which numerical solutions by FINAS are compared with some analytical reference solutions, and the second part of this manual presents more complex examples intended for practical application. All the input data images and principal results for each problem are included in this manual for beginners' convenience. All the analyses are performed by using the FINAS Version 13.0. (author)

PLEXFIN a computer model for the economic assessment of nuclear power plant life extension. User's manual

International Nuclear Information System (INIS)

2007-01-01

The IAEA developed PLEXFIN, a computer model analysis tool aimed to assist decision makers in the assessment of the economic viability of a nuclear power plant life/licence extension. This user's manual was produced to facilitate the application of the PLEXFIN computer model. It is widely accepted in the industry that the operational life of a nuclear power plant is not limited to a pre-determined number of years, sometimes established on non-technical grounds, but by the capability of the plant to comply with the nuclear safety and technical requirements in a cost effective manner. The decision to extend the license/life of a nuclear power plant involves a number of political, technical and economic issues. The economic viability is a cornerstone of the decision-making process. In a liberalized electricity market, the economics to justify a nuclear power plant life/license extension decision requires a more complex evaluation. This user's manual was elaborated in the framework of the IAEA's programmes on Continuous process improvement of NPP operating performance, and on Models for analysis and capacity building for sustainable energy development, with the support of four consultants meetings

BPACK -- A computer model package for boiler reburning/co-firing performance evaluations. User`s manual, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Wu, K.T.; Li, B.; Payne, R.

1992-06-01

This manual presents and describes a package of computer models uniquely developed for boiler thermal performance and emissions evaluations by the Energy and Environmental Research Corporation. The model package permits boiler heat transfer, fuels combustion, and pollutant emissions predictions related to a number of practical boiler operations such as fuel-switching, fuels co-firing, and reburning NO{sub x} reductions. The models are adaptable to most boiler/combustor designs and can handle burner fuels in solid, liquid, gaseous, and slurried forms. The models are also capable of performing predictions for combustion applications involving gaseous-fuel reburning, and co-firing of solid/gas, liquid/gas, gas/gas, slurry/gas fuels. The model package is conveniently named as BPACK (Boiler Package) and consists of six computer codes, of which three of them are main computational codes and the other three are input codes. The three main codes are: (a) a two-dimensional furnace heat-transfer and combustion code: (b) a detailed chemical-kinetics code; and (c) a boiler convective passage code. This user`s manual presents the computer model package in two volumes. Volume 1 describes in detail a number of topics which are of general users` interest, including the physical and chemical basis of the models, a complete description of the model applicability, options, input/output, and the default inputs. Volume 2 contains a detailed record of the worked examples to assist users in applying the models, and to illustrate the versatility of the codes.

On-line satellite/central computer facility of the Multiparticle Argo Spectrometer System

International Nuclear Information System (INIS)

Anderson, E.W.; Fisher, G.P.; Hien, N.C.; Larson, G.P.; Thorndike, A.M.; Turkot, F.; von Lindern, L.; Clifford, T.S.; Ficenec, J.R.; Trower, W.P.

1974-09-01

An on-line satellite/central computer facility has been developed at Brookhaven National Laboratory as part of the Multiparticle Argo Spectrometer System (MASS). This facility consisting of a PDP-9 and a CDC-6600, has been successfully used in study of proton-proton interactions at 28.5 GeV/c. (U.S.)

TRUBA User Manual

International Nuclear Information System (INIS)

Tereshchenko, M. A.; Castejon, F.; Cappa, A.

2008-01-01

The TRUBA (pipeline in Russian) code is a computational tool for studying the propagation of Gaussian-shaped microwave beams in a prescribed equilibrium plasma. This manual covers the basic material handed to use the implementation of TRUBA (version 3,4) interfaced with the numerical library of the TJ-II stellarator. The manual provides a concise theoretical background of the problem, specifications for setting up the input files and interpreting the output of the code, and some information useful in modifying TRUBA. (Author) 13 refs

TRUBA User Manual

Energy Technology Data Exchange (ETDEWEB)

Tereshchenko, M. A.; Castejon, F.; Cappa, A.

2008-04-25

The TRUBA (pipeline in Russian) code is a computational tool for studying the propagation of Gaussian-shaped microwave beams in a prescribed equilibrium plasma. This manual covers the basic material handed to use the implementation of TRUBA (version 3,4) interfaced with the numerical library of the TJ-II stellarator. The manual provides a concise theoretical background of the problem, specifications for setting up the input files and interpreting the output of the code, and some information useful in modifying TRUBA. (Author) 13 refs.

A Course on Operational Considerations in Wastewater Treatment Plant Design. Instructor's Manual.

Science.gov (United States)

Cooper, John W.; And Others

This manual contains 17 instructional units (sequenced to correspond to parallel chapters in a student's manual) focusing on upgrading the design of wastewater plant facilities and serving as a reference source for establishing criteria for upgrading wastewater treatment plants. The manual also furnishes information for modifying plant design to…

Program user's manual: cryogen system for the analysis for the Mirror Fusion Test Facility

International Nuclear Information System (INIS)

1979-04-01

The Mirror Fusion Test Facility being designed and constructed at the Lawrence Livermore Laboratory requires a liquid helium liquefaction, storage, distribution, and recovery system and a liquid nitrogen storage and distribution system. To provide a powerful analytical tool to aid in the design evolution of this system through hardware, a thermodynamic fluid flow model was developed. This model allows the Lawrence Livermore Laboratory to verify that the design meets desired goals and to play what if games during the design evolution. For example, what if the helium flow rate is changed in the magnet liquid helium flow loop; how does this affect the temperature, fluid quality, and pressure. This manual provides all the information required to run all or portions of this program as desired. In addition, the program is constructed in a modular fashion so changes or modifications can be made easily to keep up with the evolving design

Planning Tools For Estimating Radiation Exposure At The National Ignition Facility

International Nuclear Information System (INIS)

Verbeke, J.; Young, M.; Brereton, S.; Dauffy, L.; Hall, J.; Hansen, L.; Khater, H.; Kim, S.; Pohl, B.; Sitaraman, S.

2010-01-01

A set of computational tools was developed to help estimate and minimize potential radiation exposure to workers from material activation in the National Ignition Facility (NIF). AAMI (Automated ALARA-MCNP Interface) provides an efficient, automated mechanism to perform the series of calculations required to create dose rate maps for the entire facility with minimal manual user input. NEET (NIF Exposure Estimation Tool) is a web application that combines the information computed by AAMI with a given shot schedule to compute and display the dose rate maps as a function of time. AAMI and NEET are currently used as work planning tools to determine stay-out times for workers following a given shot or set of shots, and to help in estimating integrated doses associated with performing various maintenance activities inside the target bay. Dose rate maps of the target bay were generated following a low-yield 10 16 D-T shot and will be presented in this paper.

TAP 2: Performance-Based Training Manual

International Nuclear Information System (INIS)

1993-08-01

Cornerstone of safe operation of DOE nuclear facilities is personnel performing day-to-day functions which accomplish the facility mission. Performance-based training is fundamental to the safe operation. This manual has been developed to support the Training Accreditation Program (TAP) and assist contractors in efforts to develop performance-based training programs. It provides contractors with narrative procedures on performance-based training that can be modified and incorporated for facility-specific application. It is divided into sections dealing with analysis, design, development, implementation, and evaluation

Operating manual for the Bulk Shielding Reactor

International Nuclear Information System (INIS)

1983-04-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxillary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supercedes all previous operating manuals for the BSR

Operating manual for the Bulk Shielding Reactor

International Nuclear Information System (INIS)

1987-03-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxiliary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supersedes all previous operating manuals for the BSR

Operating manual for the Bulk Shielding Reactor

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxiliary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supersedes all previous operating manuals for the BSR.

Operating manual for the Bulk Shielding Reactor

Energy Technology Data Exchange (ETDEWEB)

1983-04-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxillary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supercedes all previous operating manuals for the BSR.

Oak Ridge Leadership Computing Facility Position Paper

Energy Technology Data Exchange (ETDEWEB)

Oral, H Sarp [ORNL; Hill, Jason J [ORNL; Thach, Kevin G [ORNL; Podhorszki, Norbert [ORNL; Klasky, Scott A [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL

2011-01-01

This paper discusses the business, administration, reliability, and usability aspects of storage systems at the Oak Ridge Leadership Computing Facility (OLCF). The OLCF has developed key competencies in architecting and administration of large-scale Lustre deployments as well as HPSS archival systems. Additionally as these systems are architected, deployed, and expanded over time reliability and availability factors are a primary driver. This paper focuses on the implementation of the Spider parallel Lustre file system as well as the implementation of the HPSS archive at the OLCF.

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.

Hanford Waste Vitrification Plant technical manual

Energy Technology Data Exchange (ETDEWEB)

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Hanford Waste Vitrification Plant technical manual

International Nuclear Information System (INIS)

Larson, D.E.; Watrous, R.A.; Kruger, O.L.

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

Hanford Environmental Information System (HEIS) Operator`s Manual. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Schreck, R.I.

1991-10-01

The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. This manual describes the facilities available to the operational user who is responsible for data entry, processing, scheduling, reporting, and quality assurance. A companion manual, the HEIS User`s Manual, describes the facilities available-to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines.

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-08-01

Oak Ridge National Laboratory's Leadership Computing Facility (OLCF) continues to deliver the most powerful resources in the U.S. for open science. At 2.33 petaflops peak performance, the Cray XT Jaguar delivered more than 1.5 billion core hours in calendar year (CY) 2010 to researchers around the world for computational simulations relevant to national and energy security; advancing the frontiers of knowledge in physical sciences and areas of biological, medical, environmental, and computer sciences; and providing world-class research facilities for the nation's science enterprise. Scientific achievements by OLCF users range from collaboration with university experimentalists to produce a working supercapacitor that uses atom-thick sheets of carbon materials to finely determining the resolution requirements for simulations of coal gasifiers and their components, thus laying the foundation for development of commercial-scale gasifiers. OLCF users are pushing the boundaries with software applications sustaining more than one petaflop of performance in the quest to illuminate the fundamental nature of electronic devices. Other teams of researchers are working to resolve predictive capabilities of climate models, to refine and validate genome sequencing, and to explore the most fundamental materials in nature - quarks and gluons - and their unique properties. Details of these scientific endeavors - not possible without access to leadership-class computing resources - are detailed in Section 4 of this report and in the INCITE in Review. Effective operations of the OLCF play a key role in the scientific missions and accomplishments of its users. This Operational Assessment Report (OAR) will delineate the policies, procedures, and innovations implemented by the OLCF to continue delivering a petaflop-scale resource for cutting-edge research. The 2010 operational assessment of the OLCF yielded recommendations that have been addressed (Reference Section 1) and

Computer modeling of commercial refrigerated warehouse facilities

International Nuclear Information System (INIS)

Nicoulin, C.V.; Jacobs, P.C.; Tory, S.

1997-01-01

The use of computer models to simulate the energy performance of large commercial refrigeration systems typically found in food processing facilities is an area of engineering practice that has seen little development to date. Current techniques employed in predicting energy consumption by such systems have focused on temperature bin methods of analysis. Existing simulation tools such as DOE2 are designed to model commercial buildings and grocery store refrigeration systems. The HVAC and Refrigeration system performance models in these simulations tools model equipment common to commercial buildings and groceries, and respond to energy-efficiency measures likely to be applied to these building types. The applicability of traditional building energy simulation tools to model refrigerated warehouse performance and analyze energy-saving options is limited. The paper will present the results of modeling work undertaken to evaluate energy savings resulting from incentives offered by a California utility to its Refrigerated Warehouse Program participants. The TRNSYS general-purpose transient simulation model was used to predict facility performance and estimate program savings. Custom TRNSYS components were developed to address modeling issues specific to refrigerated warehouse systems, including warehouse loading door infiltration calculations, an evaporator model, single-state and multi-stage compressor models, evaporative condenser models, and defrost energy requirements. The main focus of the paper will be on the modeling approach. The results from the computer simulations, along with overall program impact evaluation results, will also be presented

ATLAS experience with HEP software at the Argonne leadership computing facility

International Nuclear Information System (INIS)

Uram, Thomas D; LeCompte, Thomas J; Benjamin, D

2014-01-01

A number of HEP software packages used by the ATLAS experiment, including GEANT4, ROOT and ALPGEN, have been adapted to run on the IBM Blue Gene supercomputers at the Argonne Leadership Computing Facility. These computers use a non-x86 architecture and have a considerably less rich operating environment than in common use in HEP, but also represent a computing capacity an order of magnitude beyond what ATLAS is presently using via the LCG. The status and potential for making use of leadership-class computing, including the status of integration with the ATLAS production system, is discussed.

ATLAS Experience with HEP Software at the Argonne Leadership Computing Facility

CERN Document Server

LeCompte, T; The ATLAS collaboration; Benjamin, D

2014-01-01

A number of HEP software packages used by the ATLAS experiment, including GEANT4, ROOT and ALPGEN, have been adapted to run on the IBM Blue Gene supercomputers at the Argonne Leadership Computing Facility. These computers use a non-x86 architecture and have a considerably less rich operating environment than in common use in HEP, but also represent a computing capacity an order of magnitude beyond what ATLAS is presently using via the LCG. The status and potential for making use of leadership-class computing, including the status of integration with the ATLAS production system, is discussed.

Sandia SWiFT Wind Turbine Manual.

Energy Technology Data Exchange (ETDEWEB)

White, Jonathan; LeBlanc, Bruce Philip; Berg, Jonathan Charles; Bryant, Joshua; Johnson, Wesley D.; Paquette, Joshua

2016-01-01

The Scaled Wind Farm Technology (SWiFT) facility, operated by Sandia National Laboratories for the U.S. Department of Energy's Wind and Water Power Program, is a wind energy research site with multiple wind turbines scaled for the experimental study of wake dynamics, advanced rotor development, turbine control, and advanced sensing for production-scale wind farms. The SWiFT site currently includes three variable-speed, pitch-regulated, three-bladed wind turbines. The six volumes of this manual provide a detailed description of the SWiFT wind turbines, including their operation and user interfaces, electrical and mechanical systems, assembly and commissioning procedures, and safety systems. Further dissemination only as authorized to U.S. Government agencies and their contractors; other requests shall be approved by the originating facility or higher DOE programmatic authority. 111 UNCLASSIFIED UNLIMITED RELEASE Sandia SWiFT Wind Turbine Manual (SAND2016-0746 ) approved by: Department Manager SWiFT Site Lead Dave Minster (6121) Date Jonathan White (6121) Date SWiFT Site Supervisor Dave Mitchell (6121) Date Note: Document revision logs are found after the title page of each volume of this manual. iv

An analytical model for computation of reliability of waste management facilities with intermediate storages

International Nuclear Information System (INIS)

Kallweit, A.; Schumacher, F.

1977-01-01

A high reliability is called for waste management facilities within the fuel cycle of nuclear power stations which can be fulfilled by providing intermediate storage facilities and reserve capacities. In this report a model based on the theory of Markov processes is described which allows computation of reliability characteristics of waste management facilities containing intermediate storage facilities. The application of the model is demonstrated by an example. (orig.) [de

Operating manual for the Health Physics Research Reactor

International Nuclear Information System (INIS)

1985-11-01

This manual is intended to serve as a guide in the operation and maintenance of the Health Physics Researh Reactor (HPRR) of the Health Physics Dosimetry Applications Research (DOSAR) Facility. It includes descriptions of the HPRR and of associated equipment such as the reactor positioning devises and the derrick. Procedures for routine operation of the HPRR are given in detail, and checklists for the various steps are provided where applicable. Emergency procedures are similarly covered, and maintenance schedules are outlined. Also, a bibliography of references giving more detailed information on the DOSAR Facility is included. Changes to this manual will be approved by at least two of the following senior staff members: (1) the Operations Division Director, (2) the Reactor Operations Department Head, (3) the Supervisor of Reactor Operations TSF-HPRR Areas. The master copy and the copy of the manual issued to the HPRR Operations Supervisor will always reflect the latest revision. 22 figs

ARIES NDA Robot operators' manual

International Nuclear Information System (INIS)

Scheer, N.L.; Nelson, D.C.

1998-05-01

The ARIES NDA Robot is an automation device for servicing the material movements for a suite of Non-destructive assay (NDA) instruments. This suite of instruments includes a calorimeter, a gamma isotopic system, a segmented gamma scanner (SGS), and a neutron coincidence counter (NCC). Objects moved by the robot include sample cans, standard cans, and instrument plugs. The robot computer has an RS-232 connection with the NDA Host computer, which coordinates robot movements and instrument measurements. The instruments are expected to perform measurements under the direction of the Host without operator intervention. This user's manual describes system startup, using the main menu, manual operation, and error recovery

COMPUTER ORIENTED FACILITIES OF TEACHING AND INFORMATIVE COMPETENCE

OpenAIRE

Olga M. Naumenko

2010-01-01

In the article it is considered the history of views to the tasks of education, estimations of its effectiveness from the point of view of forming of basic vitally important competences. Opinions to the problem in different countries, international organizations, corresponding experience of the Ukrainian system of education are described. The necessity of forming of informative competence of future teacher is reasonable in the conditions of application of the computer oriented facilities of t...

TAP 2, Performance-Based Training Manual

Energy Technology Data Exchange (ETDEWEB)

1991-07-01

Training programs at DOE nuclear facilities should provide well- trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two comparison manuals provide additional information to assist contractors in their efforts to accredit training programs.

TAP 3, Training Program Support Manual

International Nuclear Information System (INIS)

1991-07-01

Training programs at DOE facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

TAP 2, Performance-Based Training Manual

International Nuclear Information System (INIS)

1991-07-01

Training programs at DOE nuclear facilities should provide well- trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two comparison manuals provide additional information to assist contractors in their efforts to accredit training programs

Performance assessment handbook for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

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

1992-02-01

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

Maintenance of reactor safety and control computers at a large government facility

International Nuclear Information System (INIS)

Brady, H.G.

1985-01-01

In 1950 the US Government contracted the Du Pont Company to design, build, and operate the Savannah River Plant (SRP). At the time, it was the largest construction project ever undertaken by man. It is still the largest of the Department of Energy facilities. In the nearly 35 years that have elapsed, Du Pont has met its commitments to the US Government and set world safety records in the construction and operation of nuclear facilities. Contributing factors in achieving production goals and setting the safety records are a staff of highly qualified personnel, a well maintained plant, and sound maintenance programs. There have been many ''first ever'' achievements at SRP. These ''firsts'' include: (1) computer control of a nuclear rector, and (2) use of computer systems as safety circuits. This presentation discusses the maintenance program provided for these computer systems and all digital systems at SRP. An in-house computer maintenance program that was started in 1966 with five persons has grown to a staff of 40 with investments in computer hardware increasing from $4 million in 1970 to more than $60 million in this decade. 4 figs

A Manual of Simplified Laboratory Methods for Operators of Wastewater Treatment Facilities.

Science.gov (United States)

Westerhold, Arnold F., Ed.; Bennett, Ernest C., Ed.

This manual is designed to provide the small wastewater treatment plant operator, as well as the new or inexperienced operator, with simplified methods for laboratory analysis of water and wastewater. It is emphasized that this manual is not a replacement for standard methods but a guide for plants with insufficient equipment to perform analyses…

Web-Based Requesting and Scheduling Use of Facilities

Science.gov (United States)

Yeager, Carolyn M.

2010-01-01

Automated User's Training Operations Facility Utilization Request (AutoFUR) is prototype software that administers a Web-based system for requesting and allocating facilities and equipment for astronaut-training classes in conjunction with scheduling the classes. AutoFUR also has potential for similar use in such applications as scheduling flight-simulation equipment and instructors in commercial airplane-pilot training, managing preventive- maintenance facilities, and scheduling operating rooms, doctors, nurses, and medical equipment for surgery. Whereas requesting and allocation of facilities was previously a manual process that entailed examination of documents (including paper drawings) from different sources, AutoFUR partly automates the process and makes all of the relevant information available via the requester s computer. By use of AutoFUR, an instructor can fill out a facility-utilization request (FUR) form on line, consult the applicable flight manifest(s) to determine what equipment is needed and where it should be placed in the training facility, reserve the corresponding hardware listed in a training-hardware inventory database, search for alternative hardware if necessary, submit the FUR for processing, and cause paper forms to be printed. Auto-FUR also maintains a searchable archive of prior FURs.

The Argonne Leadership Computing Facility 2010 annual report.

Energy Technology Data Exchange (ETDEWEB)

Drugan, C. (LCF)

2011-05-09

Researchers found more ways than ever to conduct transformative science at the Argonne Leadership Computing Facility (ALCF) in 2010. Both familiar initiatives and innovative new programs at the ALCF are now serving a growing, global user community with a wide range of computing needs. The Department of Energy's (DOE) INCITE Program remained vital in providing scientists with major allocations of leadership-class computing resources at the ALCF. For calendar year 2011, 35 projects were awarded 732 million supercomputer processor-hours for computationally intensive, large-scale research projects with the potential to significantly advance key areas in science and engineering. Argonne also continued to provide Director's Discretionary allocations - 'start up' awards - for potential future INCITE projects. And DOE's new ASCR Leadership Computing (ALCC) Program allocated resources to 10 ALCF projects, with an emphasis on high-risk, high-payoff simulations directly related to the Department's energy mission, national emergencies, or for broadening the research community capable of using leadership computing resources. While delivering more science today, we've also been laying a solid foundation for high performance computing in the future. After a successful DOE Lehman review, a contract was signed to deliver Mira, the next-generation Blue Gene/Q system, to the ALCF in 2012. The ALCF is working with the 16 projects that were selected for the Early Science Program (ESP) to enable them to be productive as soon as Mira is operational. Preproduction access to Mira will enable ESP projects to adapt their codes to its architecture and collaborate with ALCF staff in shaking down the new system. We expect the 10-petaflops system to stoke economic growth and improve U.S. competitiveness in key areas such as advancing clean energy and addressing global climate change. Ultimately, we envision Mira as a stepping-stone to exascale-class computers

The DREO Elint Browser Utility (DEBU) reference manual

Science.gov (United States)

Ford, Barbara; Jones, David

1992-04-01

An electronic intelligent database browsing tool called DEBU has been developed that allows databases such as ELP, Kilting, EWIR, and AFEWC to be reviewed and analyzed from a user-friendly environment on a personal computer. DEBU's basic function is to allow users to examine the contents of user-selected subfiles of user-selected emitters of user-selected databases. DEBU augments this functionality with support for selecting (filtering) and combining subsets of emitters by user-selected attributes such as name, parameter type, or parameter value. DEBU provides facilities for examining histograms and x-y plots of selected parameters, for doing ambiguity analysis and mode level analysis, and for generating and printing a variety of reports. A manual is provided for users of DEBU, including descriptions and illustrations of menus and windows.

Vehicle access and search training manual. Report for Oct 77-sep 79

International Nuclear Information System (INIS)

Obermiller, J.E.; Wait, H.J.

1979-11-01

This Vehicle Access and Search Training Manual is intended to assist NRC-licensed organizations and their security personnel in developing vehicle access, control and search operations necessary at nuclear fuel cycle facilities and at reactor facilities. The manual is based on security requirements prescribed by The Nuclear Regulatory Commission as contained in Title 10 of the Code of Federal Regulations, Part 73, 'Physical Protection of Plants and Materials.' As a condition of the licensing agreement, the licensee is required to maintain a physical protection system which includes a training program for security personnel. The manual includes lesson plans in (1) controlling vehicle entry and exit, (2) searching for contraband, and (3) protecting the facility from sabotage and/or theft of special nuclear materials. These training guidelines provide information and instruction for self-study, discussion and hands-on training. A job knowledge test reviews the entire training program

Operating instructions for LBL radon measurement facilities

International Nuclear Information System (INIS)

Ingersoll, J.G.

1980-06-01

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

Experience with the EPA manual for waste minimization opportunity assessments

International Nuclear Information System (INIS)

Bridges, J.S.

1990-01-01

The EPA Waste Minimization Opportunity Assessment Manual (EPA/625/788/003) was published to assist those responsible for managing waste minimization activities at the waste generating facility and at corporate levels. The Manual sets forth a procedure that incorporates technical and managerial principles and motivates people to develop and implement pollution prevention concepts and ideas. Environmental management has increasingly become one of cooperative endeavor whereby whether in government, industry, or other forms of enterprise, the effectiveness with whirl, people work together toward the attainment of a clean environment is largely determined by the ability of those who hold managerial position. This paper offers a description of the EPA Waste Minimization Opportunity Assessment Manual procedure which supports the waste minimization assessment as a systematic planned procedure with the objective of identifying ways to reduce or eliminate waste generation. The Manual is a management tool that blends science and management principles. The practice of managing waste minimization/pollution prevention makes use of the underlying organized science and engineering knowledge and applies it in the light of realities to gain a desired, practical result. The early stages of EPA's Pollution Prevention Research Program centered on the development of the Manual and its use at a number of facilities within the private and public sectors. This paper identifies a number of case studies and waste minimization opportunity assessment reports that demonstrate the value of using the Manual's approach. Several industry-specific waste minimization assessment manuals have resulted from the Manual's generic approach to waste minimization. There were some modifications to the Manual's generic approach when the waste stream has been other than industrial hazardous waste

CANAL user's manual

International Nuclear Information System (INIS)

Faya, A.; Wolf, L.; Todreas, N.

1979-11-01

CANAL is a subchannel computer program for the steady-state and transient thermal hydraulic analysis of BWR fuel rod bundles. The purpose of this manual is to introduce the user into the mechanism of running the code by providing information about the input data and options

The environmental survey manual: Appendix D

International Nuclear Information System (INIS)

1987-08-01

The purpose of this manual is to provide guidance to the Survey and Sampling and Analysis teams that conduct the one-time Environmental Survey of the major US Department of Energy operating facilities. This appendix contains procedures for chemical analysis of organics, inorganics, and radioisotopes

Nuclear electronics laboratory manual

International Nuclear Information System (INIS)

1984-05-01

The Nuclear Electronics Laboratory Manual is a joint product of several electronics experts who have been associated with IAEA activity in this field for many years. The manual does not include experiments of a basic nature, such as characteristics of different active electronics components. It starts by introducing small electronics blocks, employing one or more active components. The most demanding exercises instruct a student in the design and construction of complete circuits, as used in commercial nuclear instruments. It is expected that a student who completes all the experiments in the manual should be in a position to design nuclear electronics units and also to understand the functions of advanced commercial instruments which need to be repaired or maintained. The future tasks of nuclear electronics engineers will be increasingly oriented towards designing and building the interfaces between a nuclear experiment and a computer. The manual pays tribute to this development by introducing a number of experiments which illustrate the principles and the technology of interfacing

SEVERO code - user's manual

International Nuclear Information System (INIS)

Sacramento, A.M. do.

1989-01-01

This user's manual contains all the necessary information concerning the use of SEVERO code. This computer code is related to the statistics of extremes = extreme winds, extreme precipitation and flooding hazard risk analysis. (A.C.A.S.)

MELCOR computer code manuals: Primer and user's guides, Version 1.8.3 September 1994. Volume 1

International Nuclear Information System (INIS)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the US Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users' Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

Quality assurance manual: Volume 1

International Nuclear Information System (INIS)

Oijala, J.E.

1988-06-01

Stanford Linear Accelerator Center (SLAC) is a DOE-supported research facility that carries out experimental and theoretical research in high energy physics and developmental work in new techniques for particle acceleration and experimental instrumentation. The purpose of this manual is to describe SLAC quality assurance policies and practices in various parts of the Laboratory

Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

Energy Technology Data Exchange (ETDEWEB)

Graf, F.A. Jr.

1995-02-27

This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System`s pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System.

Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

International Nuclear Information System (INIS)

Graf, F.A. Jr.

1995-01-01

This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System's pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System

Manual control models of industrial management

Science.gov (United States)

Crossman, E. R. F. W.

1972-01-01

The industrial engineer is often required to design and implement control systems and organization for manufacturing and service facilities, to optimize quality, delivery, and yield, and minimize cost. Despite progress in computer science most such systems still employ human operators and managers as real-time control elements. Manual control theory should therefore be applicable to at least some aspects of industrial system design and operations. Formulation of adequate model structures is an essential prerequisite to progress in this area; since real-world production systems invariably include multilevel and multiloop control, and are implemented by timeshared human effort. A modular structure incorporating certain new types of functional element, has been developed. This forms the basis for analysis of an industrial process operation. In this case it appears that managerial controllers operate in a discrete predictive mode based on fast time modelling, with sampling interval related to plant dynamics. Successive aggregation causes reduced response bandwidth and hence increased sampling interval as a function of level.

MANUAL LOGIC CONTROLLER (MLC)

OpenAIRE

Claude Ziad Bayeh

2015-01-01

The “Manual Logic Controller” also called MLC, is an electronic circuit invented and designed by the author in 2008, in order to replace the well known PLC (Programmable Logic Controller) in many applications for its advantages and its low cost of fabrication. The function of the MLC is somewhat similar to the well known PLC, but instead of doing it by inserting a written program into the PLC using a computer or specific software inside the PLC, it will be manually programmed in a manner to h...

RSAC 6.2 with WinRP 2.0 User Manual

Energy Technology Data Exchange (ETDEWEB)

Bradley Schrader

2005-09-01

The Radiological Safety Analysis Computer Program (RSAC-6.2) calculates the consequences of a release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or a nuclear criticality accident. RSAC-6.2 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for resuspension, inhalation, immersion, ground surface, and ingestion pathways. WinRP 2.0, a windows based overlay to RSAC-6.2, assists users in creating and running RSAC-6.2 input files. This users manual contains the mathematical models and operating instructions for RSAC-6.2 and WinRP 2.0. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-6.2 and WinRP 2.0. These programs are designed for users who are familiar with radiological dose assessment methods.

Data collection system. Volume 1, Overview and operators manual; Volume 2, Maintenance manual; Appendices

Energy Technology Data Exchange (ETDEWEB)

Caudell, R.B.; Bauder, M.E.; Boyer, W.B.; French, R.E.; Isidoro, R.J.; Kaestner, P.C.; Perkins, W.G.

1993-09-01

Sandia National Laboratories (SNL) Instrumentation Development Department was tasked by the Defense Nuclear Agency (DNA) to record data on Tektronix RTD720 Digitizers on the HUNTERS TROPHY field test conducted at the Nevada Test Site (NTS) on September 18, 1992. This report contains a overview and description of the computer hardware and software that was used to acquire, reduce, and display the data. The document is divided into two volumes: an overview and operators manual (Volume 1) and a maintenance manual (Volume 2).

Exercise manual for the Augmented Computer Exercise for Inspection Training (ACE-IT) software

Energy Technology Data Exchange (ETDEWEB)

Dobranich, P.R.; Widney, T.W.; Goolsby, P.T. [Sandia National Labs., Albuquerque, NM (United States). Cooperative Monitoring Center and Regional Security; Nelson, J.D.; Evanko, D.A. [Ogden Environmental and Energy Services, Inc., Albuquerque, NM (United States)

1997-09-01

The on-site inspection provisions in many current and proposed arms control agreements require extensive preparation and training on the part of both the Inspected Party and the Inspection Team. Current training techniques include table-top inspections and practice inspections. The Augmented Computer Exercise for Inspection Training (ACE-IT), an interactive computer training tool, increases the utility of table-top inspections. ACE-IT has been designed to provide training for a hypothetical challenge inspection under the Chemical Weapons Convention (CWC); however, this training tool can be modified for other inspection regimes. Although ACE-IT provides training from notification of an inspection through post-inspection activities, the primary emphasis of ACE-IT is in the inspection itself--particularly with the concept of managed access. ACE-IT also demonstrates how inspection provisions impact compliance determination and the protection of sensitive information. The Exercise Manual supplements the ACE-IT software by providing general information on on-site inspections and detailed information for the CWC challenge inspection exercise. The detailed information includes the pre-inspection briefing, maps, list of sensitive items, medical records, and shipping records.

User's Manual for FOMOCO Utilities-Force and Moment Computation Tools for Overset Grids

Science.gov (United States)

Chan, William M.; Buning, Pieter G.

1996-01-01

In the numerical computations of flows around complex configurations, accurate calculations of force and moment coefficients for aerodynamic surfaces are required. When overset grid methods are used, the surfaces on which force and moment coefficients are sought typically consist of a collection of overlapping surface grids. Direct integration of flow quantities on the overlapping grids would result in the overlapped regions being counted more than once. The FOMOCO Utilities is a software package for computing flow coefficients (force, moment, and mass flow rate) on a collection of overset surfaces with accurate accounting of the overlapped zones. FOMOCO Utilities can be used in stand-alone mode or in conjunction with the Chimera overset grid compressible Navier-Stokes flow solver OVERFLOW. The software package consists of two modules corresponding to a two-step procedure: (1) hybrid surface grid generation (MIXSUR module), and (2) flow quantities integration (OVERINT module). Instructions on how to use this software package are described in this user's manual. Equations used in the flow coefficients calculation are given in Appendix A.

Computer based training simulator for Hunterston Nuclear Power Station

International Nuclear Information System (INIS)

Bowden, R.S.M.; Hacking, D.

1978-01-01

For reasons which are stated, the Hunterston-B nuclear power station automatic control system includes a manual over-ride facility. It is therefore essential for the station engineers to be trained to recognise and control all feasible modes of plant and logic malfunction. A training simulator has been built which consists of a replica of the shutdown monitoring panel in the Central Control Room and is controlled by a mini-computer. This paper highlights the computer aspects of the simulator and relevant derived experience, under the following headings: engineering background; shutdown sequence equipment; simulator equipment; features; software; testing; maintenance. (U.K.)

33 CFR 385.28 - Operating Manuals.

Science.gov (United States)

2010-07-01

... Processes § 385.28 Operating Manuals. (a) General provisions. (1) The Corps of Engineers and the non-Federal... emergencies that can be expected to occur at a project are: drowning and other accidents, failure of the operation facilities, chemical spills, treatment plant failures and other temporary pollution problems...

Comparison of automated and manual shielding block fabrication

International Nuclear Information System (INIS)

Weeks, K.J.; Fraass, B.A.; McShan, D.L.; Hardybala, S.S.; Hargreaves, E.A.; Lichter, A.S.

1989-01-01

This work reports the results of a study comparing computer controlled and manual shielding block cutting. The general problems inherent in automated block cutting have been identified and minimized. A system whose accuracy is sufficient for clinical applications has been developed. The relative accuracy of our automated system versus experienced technician controlled cutting was investigated. In general, it is found that automated cutting is somewhat faster and more accurate than manual cutting for very large fields, but that the reverse is true for most smaller fields. The relative cost effectiveness of automated cutting is dependent on the percentage of computer designed blocks which are generated in the clinical setting. At the present time, the traditional manual method is still favored

HERMES II experimenters' manual (revised)

International Nuclear Information System (INIS)

Schuch, R.L.

1977-04-01

The HERMES II is a high-intensity laboratory photon source for gamma-ray radiation effects experiments as well as a high-energy pulsed electron beam generator for a variety of potential applications. The purpose of this manual is to serve as a basic source of information for prospective users of HERMES. Included is a brief discussion of the design and operation of the accelerator system as well as a summary of environmental data for x-ray operation and output characteristics for electron beam modes. The manual also contains a description of the HERMES experimental facilities, including geometry of the test cell, instrumentation and data collection capabilities, and services and support available to experimenters

SRS Station 2.3 manual

International Nuclear Information System (INIS)

Tang, C.; Miller, M.; MacLean, E.

1998-01-01

The objective of this manual is to effectively provide assistance to users so that they can perform successful experiments at Station 2.3 during their visits. In order to compile a comprehensive document, the functions of the instrument hardware and software are described in detail. Where appropriate it also contains useful information and other documentation for help and/or reference. In addition, suggestions and instructions are available to overcome problems which inevitably face the users in the performing of complex experimental tasks. This document can provide help as part of the overall user support facility, and it is therefore intended that the manual is readily available in hard copy as well as in electronic form. (author)

Computer usage among nurses in rural health-care facilities in South Africa: obstacles and challenges.

Science.gov (United States)

Asah, Flora

2013-04-01

This study discusses factors inhibiting computer usage for work-related tasks among computer-literate professional nurses within rural healthcare facilities in South Africa. In the past two decades computer literacy courses have not been part of the nursing curricula. Computer courses are offered by the State Information Technology Agency. Despite this, there seems to be limited use of computers by professional nurses in the rural context. Focus group interviews held with 40 professional nurses from three government hospitals in northern KwaZulu-Natal. Contributing factors were found to be lack of information technology infrastructure, restricted access to computers and deficits in regard to the technical and nursing management support. The physical location of computers within the health-care facilities and lack of relevant software emerged as specific obstacles to usage. Provision of continuous and active support from nursing management could positively influence computer usage among professional nurses. A closer integration of information technology and computer literacy skills into existing nursing curricula would foster a positive attitude towards computer usage through early exposure. Responses indicated that change of mindset may be needed on the part of nursing management so that they begin to actively promote ready access to computers as a means of creating greater professionalism and collegiality. © 2011 Blackwell Publishing Ltd.

PFP MICON maintenance manual. Revision 1

International Nuclear Information System (INIS)

Silvan, G.R.

1995-01-01

This manual covers the use of maintenance displays, maintenance procedures, system alarms and common system failures. This manual is intended to supplement the MICON maintenance training not replace it. It also assumes that the user is familiar with the normal operation of the MICON A/S system. The MICON system is a distributed control computer and, among other things, controls the HVAC system for the Plutonium Finishing Plant

Input/output routines for a hybrid computer

International Nuclear Information System (INIS)

Izume, Akitada; Yodo, Terutaka; Sakama, Iwao; Sakamoto, Akira; Miyake, Osamu

1976-05-01

This report is concerned with data processing programs for a hybrid computer system. Especially pre-data processing of magnetic tapes which are recorded during the dynamic experiment by FACOM 270/25 data logging system in the 50 MW steam generator test facility is described in detail. The magnetic tape is a most effective recording medium for data logging, but recording formats of the magnetic tape are different between data logging systems. In our section, the final data analyses are performed by data in the disk of EAI-690 hybrid computer system, and to transfer all required information in magnetic tapes to the disk, the magnetic tape editing and data transit are necessary by sub-computer NEAC-3200 system. This report is written for users as a manual and reference hand book of pre-data processing between different type computers. (auth.)

Shielding Calculations for Positron Emission Tomography - Computed Tomography Facilities

Energy Technology Data Exchange (ETDEWEB)

Baasandorj, Khashbayar [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Yang, Jeongseon [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-10-15

Integrated PET-CT has been shown to be more accurate for lesion localization and characterization than PET or CT alone, and the results obtained from PET and CT separately and interpreted side by side or following software based fusion of the PET and CT datasets. At the same time, PET-CT scans can result in high patient and staff doses; therefore, careful site planning and shielding of this imaging modality have become challenging issues in the field. In Mongolia, the introduction of PET-CT facilities is currently being considered in many hospitals. Thus, additional regulatory legislation for nuclear and radiation applications is necessary, for example, in regulating licensee processes and ensuring radiation safety during the operations. This paper aims to determine appropriate PET-CT shielding designs using numerical formulas and computer code. Since presently there are no PET-CT facilities in Mongolia, contact was made with radiological staff at the Nuclear Medicine Center of the National Cancer Center of Mongolia (NCCM) to get information about facilities where the introduction of PET-CT is being considered. Well-designed facilities do not require additional shielding, which should help cut down overall costs related to PET-CT installation. According to the results of this study, building barrier thicknesses of the NCCM building is not sufficient to keep radiation dose within the limits.

ARDS User Manual

Science.gov (United States)

Fleming, David P.

2001-01-01

Personal computers (PCs) are now used extensively for engineering analysis. their capability exceeds that of mainframe computers of only a few years ago. Programs originally written for mainframes have been ported to PCs to make their use easier. One of these programs is ARDS (Analysis of Rotor Dynamic Systems) which was developed at Arizona State University (ASU) by Nelson et al. to quickly and accurately analyze rotor steady state and transient response using the method of component mode synthesis. The original ARDS program was ported to the PC in 1995. Several extensions were made at ASU to increase the capability of mainframe ARDS. These extensions have also been incorporated into the PC version of ARDS. Each mainframe extension had its own user manual generally covering only that extension. Thus to exploit the full capability of ARDS required a large set of user manuals. Moreover, necessary changes and enhancements for PC ARDS were undocumented. The present document is intended to remedy those problems by combining all pertinent information needed for the use of PC ARDS into one volume.

Evolution of facility layout requirements and CAD [computer-aided design] system development

International Nuclear Information System (INIS)

Jones, M.

1990-06-01

The overall configuration of the Superconducting Super Collider (SSC) including the infrastructure and land boundary requirements were developed using a computer-aided design (CAD) system. The evolution of the facility layout requirements and the use of the CAD system are discussed. The emphasis has been on minimizing the amount of input required and maximizing the speed by which the output may be obtained. The computer system used to store the data is also described

PETSc Users Manual Revision 3.7

Energy Technology Data Exchange (ETDEWEB)

Balay, S.; Brune, P.; Buschelman, K.; Gropp, W.; Karpeyev, D.; Kaushik, D.; Knepley, M.; McInnes, L. Curfman; Rupp, K.; Smith, B.; Zhang, H.; Abhyankar, S.; Adams, M.; Dalcin, L.; Zampini, S.; Zhang, H.

2016-04-01

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication.

PETSc Users Manual Revision 3.8

Energy Technology Data Exchange (ETDEWEB)

Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Abhyankar, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Adams, M. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Brune, P. [Argonne National Lab. (ANL), Argonne, IL (United States); Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Dalcin, L. D. [King Abdullah Univ. of Science and Technology, Thuwal (Saudi Arabia); Eijkhout, V. [Univ. of Texas, Austin, TX (United States); Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States); Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States); Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States); May, D. [ETH Zurich (Switzerland); McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States); Munson, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Rupp, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Sanan, P. [Univ. of Italian Switzerland, Lugano (Switzerland); Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Zampini, S. [King Abdullah Univ. of Science and Technology, Thuwal (Saudi Arabia); Zhang, H. [Illinois Inst. of Technology, Chicago, IL (United States); Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-01

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication.

Hazard Baseline Downgrade Effluent Treatment Facility

International Nuclear Information System (INIS)

Blanchard, A.

1998-01-01

This Hazard Baseline Downgrade reviews the Effluent Treatment Facility, in accordance with Department of Energy Order 5480.23, WSRC11Q Facility Safety Document Manual, DOE-STD-1027-92, and DOE-EM-STD-5502-94. It provides a baseline grouping based on the chemical and radiological hazards associated with the facility. The Determination of the baseline grouping for ETF will aid in establishing the appropriate set of standards for the facility

PUNCH. GENIE MK.2.2 manual

International Nuclear Information System (INIS)

David, W.I.F.; Johnson, M.W.; Knowles, K.J.; Crosbie, G.D.; Graham, S.P.; Campbell, E.P.; Lyall, J.S.

1986-01-01

GENIE is a language for spectrum manipulation and display, that has been developed to satisfy the data-analysis requirements for all the neutron-scattering instruments at the spallation neutron source. The manual contains: the GENIE 'keyboard' commands, GENIE 'GCL' commands, command file examples, and the adding of non-standard facilities. (U.K.)

A Course on Operational Considerations in Wastewater Treatment Plant Design. Student Manual.

Science.gov (United States)

Stottler, Stag and Associates, San Antonio, TX.

This manual was designed to furnish information for upgrading the design of wastewater treatment plant facilities and to serve as a resource for establishing criteria for upgrading these plants. The manual also furnishes information for modifying plant design to compensate for current organic and hydraulic overloads and/or to meet more stringent…

Dynamic link: user's manual

International Nuclear Information System (INIS)

Harada, Hiroo; Asai, Kiyoshi; Kihara, Kazuhisa.

1981-09-01

The purpose of dynamic link facility is to link a load module dynamically only when it is used in execution time. The facility is very useful for development, execution and maintenance of a large scale computer program which is too big to be saved as one load module in main memory, or it is poor economy to save it due to many unused subroutines depending on an input. It is also useful for standardization and common utilization of programs. Standard usage of dynamic link facility of FACOM M-200 computer system, a software tool which analyzes the effect of dynamic link facility and application of dynamic link to nuclear codes are described. (author)

In Data We Trust? Comparison of Electronic Versus Manual Abstraction of Antimicrobial Prescribing Quality Metrics for Hospitalized Veterans With Pneumonia.

Science.gov (United States)

Jones, Barbara E; Haroldsen, Candace; Madaras-Kelly, Karl; Goetz, Matthew B; Ying, Jian; Sauer, Brian; Jones, Makoto M; Leecaster, Molly; Greene, Tom; Fridkin, Scott K; Neuhauser, Melinda M; Samore, Matthew H

2018-07-01

Electronic health records provide the opportunity to assess system-wide quality measures. Veterans Affairs Pharmacy Benefits Management Center for Medication Safety uses medication use evaluation (MUE) through manual review of the electronic health records. To compare an electronic MUE approach versus human/manual review for extraction of antibiotic use (choice and duration) and severity metrics. Retrospective. Hospitalizations for uncomplicated pneumonia occurring during 2013 at 30 Veterans Affairs facilities. We compared summary statistics, individual hospitalization-level agreement, facility-level consistency, and patterns of variation between electronic and manual MUE for initial severity, antibiotic choice, daily clinical stability, and antibiotic duration. Among 2004 hospitalizations, electronic and manual abstraction methods showed high individual hospitalization-level agreement for initial severity measures (agreement=86%-98%, κ=0.5-0.82), antibiotic choice (agreement=89%-100%, κ=0.70-0.94), and facility-level consistency for empiric antibiotic choice (anti-MRSA r=0.97, P<0.001; antipseudomonal r=0.95, P<0.001) and therapy duration (r=0.77, P<0.001) but lower facility-level consistency for days to clinical stability (r=0.52, P=0.006) or excessive duration of therapy (r=0.55, P=0.005). Both methods identified widespread facility-level variation in antibiotic choice, but we found additional variation in manual estimation of excessive antibiotic duration and initial illness severity. Electronic and manual MUE agreed well for illness severity, antibiotic choice, and duration of therapy in pneumonia at both the individual and facility levels. Manual MUE showed additional reviewer-level variation in estimation of initial illness severity and excessive antibiotic use. Electronic MUE allows for reliable, scalable tracking of national patterns of antimicrobial use, enabling the examination of system-wide interventions to improve quality.

WAM-E user's manual

International Nuclear Information System (INIS)

Rayes, L.G.; Riley, J.E.

1986-07-01

The WAM-E series of mainframe computer codes have been developed to efficiently analyze the large binary models (e.g., fault trees) used to represent the logic relationships within and between the systems of a nuclear power plant or other large, multisystem entity. These codes have found wide application in reliability and safety studies of nuclear power plant systems. There are now nine codes in the WAM-E series, with six (WAMBAM/WAMTAP, WAMCUT, WAMCUT-II, WAMFM, WAMMRG, and SPASM) classified as Type A Production codes and the other three (WAMFTP, WAMTOP, and WAMCONV) classified as Research codes. This document serves as a combined User's Guide, Programmer's Manual, and Theory Reference for the codes, with emphasis on the Production codes. To that end, the manual is divided into four parts: Part I, Introduction; Part II, Theory and Numerics; Part III, WAM-E User's Guide; and Part IV, WAMMRG Programmer's Manual

Opportunities for artificial intelligence application in computer- aided management of mixed waste incinerator facilities

International Nuclear Information System (INIS)

Rivera, A.L.; Ferrada, J.J.; Singh, S.P.N.

1992-01-01

The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site. It is designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). This facility, known as the TSCA Incinerator, services seven DOE/OR installations. This incinerator was recently authorized for production operation in the United States for the processing of mixed (radioactively contaminated-chemically hazardous) wastes as regulated under TSCA and RCRA. Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. These requirements impact the characteristics and disposition of incinerator residues, limits the quality of liquid and gaseous effluents, limit the characteristics and rates of waste feeds and operating conditions, and restrict the handling of the waste feed inventories. This incinerator facility presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. Demonstrated computer-aided management systems could be transferred to future mixed waste incinerator facilities

Trauma facilities in Denmark - a nationwide cross-sectional benchmark study of facilities and trauma care organisation.

Science.gov (United States)

Weile, Jesper; Nielsen, Klaus; Primdahl, Stine C; Frederiksen, Christian A; Laursen, Christian B; Sloth, Erik; Mølgaard, Ole; Knudsen, Lars; Kirkegaard, Hans

2018-03-27

Trauma is a leading cause of death among adults aged facilities and the use multidisciplinary trauma teams. Because knowledge is sparse on the existing distribution of trauma facilities and the organisation of trauma care in Denmark, the aim of this study was to identify all Danish facilities that care for traumatized patients and to investigate the diversity in organization of trauma management. We conducted a systematic observational cross-sectional study. First, all hospitals in Denmark were identified via online services and clarifying phone calls to each facility. Second, all trauma care manuals on all facilities that receive traumatized patients were gathered. Third, anesthesiologists and orthopedic surgeons on call at all trauma facilities were contacted via telephone for structured interviews. A total of 22 facilities in Denmark were found to receive traumatized patients. All facilities used a trauma care manual and all had a multidisciplinary trauma team. The study found three different trauma team activation criteria and nine different compositions of teams who participate in trauma care. Training was heterogeneous and, beyond the major trauma centers, databases were only maintained in a few facilities. The study established an inventory of the existing Danish facilities that receive traumatized patients. The trauma team activation criteria and the trauma teams were heterogeneous in both size and composition. A national database for traumatized patients, research on nationwide trauma team activation criteria, and team composition guidelines are all called for.

Field manual for reclamation of salt contaminated soils

International Nuclear Information System (INIS)

Burley, M.J.; Lesky, M.; Warren, R.J.

1988-01-01

Saltwater is often produced with crude oil and must be separated from it at a processing facility prior to deep-well injection. Increasing volumes of saltwater have led to pipeline corrosion and an increasing frequency of saltwater spills. A field manual for treating saltwater-contaminated soil was prepared by the Production Research Department of Esso Resources Canada Limited and Husky Oil Operations Limited. The purpose of the manual is to provide field and plant operations with a practical guide for reclaiming brine spills on mineral (agricultural) soil. The manual covers background scientific theory about how saltwater affects the soil, initial steps for treating new spills, site assessment, and reclamation program design, implementation and monitoring. A sample spill site assessment form is included. 8 refs

A User's Manual for the NRN Shield Design Method

Energy Technology Data Exchange (ETDEWEB)

Hjaerne, Leif [ed.; Aalto, E; Fraeki, R; Leimdoerfer, M; Lindblom, K; Linde, S; Malen, K; Nyman, K

1964-06-15

This report describes a code system for bulk shield design written for a Ferranti Mercury computer and is intended as a manual for those using the programme. The idea of an 'almost direct' flux, as in the removal theory serves as a basis for further development of the theory. An important aspiration has been to minimize the manual work of administering the codes. The codes concerned are: NECO, computing necessary group constants from primary data, REFUSE and REBOX (infinite plane or cylindrical, and box geometry, respectively), computing removal flux, NEDI a one-dimensional (plane, spherical, cylindrical) diffusion multigroup code, and SALOME a Monte Carlo code computing the gamma flux. Output tapes are constructed for direct use as input tapes, when required, for a following code.

A User's Manual for the NRN Shield Design Method

International Nuclear Information System (INIS)

Hjaerne, Leif; Aalto, E.; Fraeki, R.; Leimdoerfer, M.; Lindblom, K.; Linde, S.; Malen, K.; Nyman, K.

1964-06-01

This report describes a code system for bulk shield design written for a Ferranti Mercury computer and is intended as a manual for those using the programme. The idea of an 'almost direct' flux, as in the removal theory serves as a basis for further development of the theory. An important aspiration has been to minimize the manual work of administering the codes. The codes concerned are: NECO, computing necessary group constants from primary data, REFUSE and REBOX (infinite plane or cylindrical, and box geometry, respectively), computing removal flux, NEDI a one-dimensional (plane, spherical, cylindrical) diffusion multigroup code, and SALOME a Monte Carlo code computing the gamma flux. Output tapes are constructed for direct use as input tapes, when required, for a following code

Effectiveness of an automatic manual wheelchair braking system in the prevention of falls.

Science.gov (United States)

Martorello, Laura; Swanson, Edward

2006-01-01

The purpose of this study was to evaluate the effectiveness of an automatic manual wheelchair braking system in the reduction of falls for patients at high risk of falls while transferring to and from a manual wheelchair. The study design was a normative survey carried out through the use of a written questionnaire sent to 60 skilled nursing facilities to collect data from the medical charts, which identified patients at high risk for falls who used an automatic wheelchair braking system. The facilities participating in the study identified a frequency of falls of high-risk patients while transferring to and from the wheelchair ranging from 2 to 10 per year, with a median fall rate per facility of 4 falls. One year after the installation of the automatic wheelchair braking system, participating facilities demonstrated a reduction of zero to three falls during transfers by high-risk patients, with a median fall rate of zero falls. This represents a statistically significant reduction of 78% in the fall rate of high-risk patients while transferring to and from the wheelchair, t (18) = 6.39, p braking system for manual wheelchairs was installed. The application of the automatic braking system allows clients, families/caregivers, and facility personnel an increased safety factor for the reduction of falls from the wheelchair.

Waste Management Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Buckingham, J.S. [ed.

1967-08-31

This Manual has been prepared to provide a documented compendium of the technical bases and general physical features of Isochem Incorporated`s Waste Management Program. The manual is intended to be used as a means of training and as a reference handbook for use by personnel responsible for executing the Waste Management Program. The material in this manual was assembled by members of Isochem`s Chemical Processing Division, Battelle Northwest Laboratory, and Hanford Engineering Services between September 1965 and March 1967. The manual is divided into the following parts: Introduction, contains a summary of the overall Waste Management Program. It is written to provide the reader with a synoptic view and as an aid in understanding the subsequent parts; Feed Material, contains detailed discussion of the type and sources of feed material used in the Waste Management Program, including a chapter on nuclear reactions and the formation of fission products; Waste Fractionization Plant Processing, contains detailed discussions of the processes used in the Waste Fractionization Plant with supporting data and documentation of the technology employed; Waste Fractionization Plant Product and Waste Effluent Handling, contains detailed discussions of the methods of handling the product and waste material generated by the Waste Fractionization Plant; Plant and Equipment, describes the layout of the Waste Management facilities, arrangement of equipment, and individual equipment pieces; Process Control, describes the instruments and analytical methods used for process control; and Safety describes process hazards and the methods used to safeguard against them.

Explotation of irradiation facilities. Safety handbook

International Nuclear Information System (INIS)

Prieto Miranda, Enrique Franscisco; Melo Crespo, Jose Carlos

1997-01-01

At present in the world there are more of 160 gamma radiation facilities and more of 600 electron bean accelerators in operation, at least one in each member state of International Atomic Energy Agency. In this paper is elaborated a Manual with the security criteria to operation of these facility types

The CT Scanner Facility at Stellenbosch University: An open access X-ray computed tomography laboratory

Science.gov (United States)

du Plessis, Anton; le Roux, Stephan Gerhard; Guelpa, Anina

2016-10-01

The Stellenbosch University CT Scanner Facility is an open access laboratory providing non-destructive X-ray computed tomography (CT) and a high performance image analysis services as part of the Central Analytical Facilities (CAF) of the university. Based in Stellenbosch, South Africa, this facility offers open access to the general user community, including local researchers, companies and also remote users (both local and international, via sample shipment and data transfer). The laboratory hosts two CT instruments, i.e. a micro-CT system, as well as a nano-CT system. A workstation-based Image Analysis Centre is equipped with numerous computers with data analysis software packages, which are to the disposal of the facility users, along with expert supervision, if required. All research disciplines are accommodated at the X-ray CT laboratory, provided that non-destructive analysis will be beneficial. During its first four years, the facility has accommodated more than 400 unique users (33 in 2012; 86 in 2013; 154 in 2014; 140 in 2015; 75 in first half of 2016), with diverse industrial and research applications using X-ray CT as means. This paper summarises the existence of the laboratory's first four years by way of selected examples, both from published and unpublished projects. In the process a detailed description of the capabilities and facilities available to users is presented.

The CT Scanner Facility at Stellenbosch University: An open access X-ray computed tomography laboratory

Energy Technology Data Exchange (ETDEWEB)

Plessis, Anton du, E-mail: anton2@sun.ac.za [CT Scanner Facility, Central Analytical Facilities, Stellenbosch University, Stellenbosch (South Africa); Physics Department, Stellenbosch University, Stellenbosch (South Africa); Roux, Stephan Gerhard le, E-mail: lerouxsg@sun.ac.za [CT Scanner Facility, Central Analytical Facilities, Stellenbosch University, Stellenbosch (South Africa); Guelpa, Anina, E-mail: aninag@sun.ac.za [CT Scanner Facility, Central Analytical Facilities, Stellenbosch University, Stellenbosch (South Africa)

2016-10-01

The Stellenbosch University CT Scanner Facility is an open access laboratory providing non-destructive X-ray computed tomography (CT) and a high performance image analysis services as part of the Central Analytical Facilities (CAF) of the university. Based in Stellenbosch, South Africa, this facility offers open access to the general user community, including local researchers, companies and also remote users (both local and international, via sample shipment and data transfer). The laboratory hosts two CT instruments, i.e. a micro-CT system, as well as a nano-CT system. A workstation-based Image Analysis Centre is equipped with numerous computers with data analysis software packages, which are to the disposal of the facility users, along with expert supervision, if required. All research disciplines are accommodated at the X-ray CT laboratory, provided that non-destructive analysis will be beneficial. During its first four years, the facility has accommodated more than 400 unique users (33 in 2012; 86 in 2013; 154 in 2014; 140 in 2015; 75 in first half of 2016), with diverse industrial and research applications using X-ray CT as means. This paper summarises the existence of the laboratory’s first four years by way of selected examples, both from published and unpublished projects. In the process a detailed description of the capabilities and facilities available to users is presented.

Sodium safety manual

International Nuclear Information System (INIS)

Hayes, D.J.; Gardiner, R.L.

1980-09-01

The sodium safety manual is based upon more than a decade of experience with liquid sodium at Berkeley Nuclear Laboratories (BNL). It draws particularly from the expertise and experience developed in the course of research work into sodium fires and sodium water reactions. It draws also on information obtained from the UKAEA and other sodium users. Many of the broad principles will apply to other Establishments but much of the detail is specific to BNL and as a consequence its application at other sites may well be limited. Accidents with sodium are at best unpleasant and at worst lethal in an extremely painful way. The object of this manual is to help prevent sodium accidents. It is not intended to give detailed advice on specific precautions for particular situations, but rather to set out the overall strategy which will ensure that sodium activities will be pursued safely. More detail is generally conveyed to staff by the use of local instructions known as Sodium Working Procedures (SWP's) which are not reproduced in this manual although a list of current SWP's is included. Much attention is properly given to the safe design and operation of larger facilities; nevertheless evidence suggests that sodium accidents most frequently occur in small-scale work particularly in operations associated with sodium cleaning and special care is needed in all such cases. (U.K.)

User's manual of Tokamak Simulation Code

International Nuclear Information System (INIS)

Nakamura, Yukiharu; Nishino, Tooru; Tsunematsu, Toshihide; Sugihara, Masayoshi.

1992-12-01

User's manual for use of Tokamak Simulation Code (TSC), which simulates the time-evolutional process of deformable motion of axisymmetric toroidal plasma, is summarized. For the use at JAERI computer system, the TSC is linked with the data management system GAEA. This manual is forcused on the procedure for the input and output by using the GAEA system. Model equations to give axisymmetric motion, outline of code system, optimal method to get the well converged solution are also described. (author)

Trauma facilities in Denmark

DEFF Research Database (Denmark)

Weile, Jesper; Nielsen, Klaus; Primdahl, Stine C

2018-01-01

Background: Trauma is a leading cause of death among adults aged challenge. Evidence supports the centralization of trauma facilities and the use multidisciplinary trauma teams. Because knowledge is sparse on the existing distribution of trauma facilities...... and the organisation of trauma care in Denmark, the aim of this study was to identify all Danish facilities that care for traumatized patients and to investigate the diversity in organization of trauma management. Methods: We conducted a systematic observational cross-sectional study. First, all hospitals in Denmark...... were identified via online services and clarifying phone calls to each facility. Second, all trauma care manuals on all facilities that receive traumatized patients were gathered. Third, anesthesiologists and orthopedic surgeons on call at all trauma facilities were contacted via telephone...

Building a capacity building manual

CSIR Research Space (South Africa)

Clinton, DD

2010-02-01

Full Text Available Organizations 2010 Building a capacity building manual Daniel D. Clinton, Jr., P.E., F.NSPE Chair, WFEO Capacity Building Committee Dr Andrew Cleland, FIPENZ, Chief Executive, IPENZ, NZ Eng David Botha, FSAICE, Executive Director, SAICE, SA Dawit... 2010 Tertiary level University curricula Coaches and mentors Facilities EXCeeD Remuneration of Academics Experiential training Outreach to Students Students chapters Young members forum World Federation of Engineering Organizations 2010 Post...

Automation of a cryogenic facility by commercial process-control computer

International Nuclear Information System (INIS)

Sondericker, J.H.; Campbell, D.; Zantopp, D.

1983-01-01

To insure that Brookhaven's superconducting magnets are reliable and their field quality meets accelerator requirements, each magnet is pre-tested at operating conditions after construction. MAGCOOL, the production magnet test facility, was designed to perform these tests, having the capacity to test ten magnets per five day week. This paper describes the control aspects of MAGCOOL and the advantages afforded the designers by the implementation of a commercial process control computer system

Environmental Measurements Laboratory (EML) procedures manual

International Nuclear Information System (INIS)

Chieco, N.A.; Bogen, D.C.; Knutson, E.O.

1990-11-01

Volume 1 of this manual documents the procedures and existing technology that are currently used by the Environmental Measurements Laboratory. A section devoted to quality assurance has been included. These procedures have been updated and revised and new procedures have been added. They include: sampling; radiation measurements; analytical chemistry; radionuclide data; special facilities; and specifications. 228 refs., 62 figs., 37 tabs. (FL)

Development of the computer code to monitor gamma radiation in the nuclear facility environment

International Nuclear Information System (INIS)

Akhmad, Y. R.; Pudjiyanto, M.S.

1998-01-01

Computer codes for gamma radiation monitoring in the vicinity of nuclear facility which have been developed could be introduced to the commercial potable gamma analyzer. The crucial stage of the first year activity was succeeded ; that is the codes have been tested to transfer data file (pulse high distribution) from Micro NOMAD gamma spectrometer (ORTEC product) and the convert them into dosimetry and physics quantities. Those computer codes are called as GABATAN (Gamma Analyzer of Batan) and NAGABAT (Natural Gamma Analyzer of Batan). GABATAN code can isable to used at various nuclear facilities for analyzing gamma field up to 9 MeV, while NAGABAT could be used for analyzing the contribution of natural gamma rays to the exposure rate in the certain location

Generic communications index: User's manual

International Nuclear Information System (INIS)

Dean, R.S.; Steinbrecher, D.H.; Hennick, A.

1987-12-01

This report is a manual for providing information required to use a special computer program developed by the NRC for indexing generic communications. The program is written in a user-friendly menu driven form using dBASE III programming language. It facilitates use of the required dBASE III search and sort capabilities to access records in a database called Generic Communications Index. This index is made up of one record each for all bulletins, circulars, and information notices, including revisions and supplements, from 1971, when such documentation started, through 1986 (or to the latest update). The program is designed for use by anyone modestly acquainted with the general use of IBM-compatible personal computers. The manual contains both a brief overview and a detailed description of the program, as well as detailed instructions for getting started using the program on a personal computer with either a two-floppy disk or a hard disk system. Included at the end are a brief description of how to handle problems which might occur, and notes on the makeup of the program and database files for help in adding records of communications for future years

The Interactive Electronic Technical Manual: Requirements, Current Status, and Implementation. Strategy Considerations.

Science.gov (United States)

1991-07-01

authoring systems. Concurrently, great strides in computer-aided design and computer-aided maintenance have contributed to this capability. 12 Junod ...J.; William A. Nugent; and L. John Junod . Plan for the Navy/Air Force Test of the Interactive Electronic Technical Manual (IETM) at Cecil Field...AFHRL Logistics and Human Factors Division, WPAFB. Aug 1990. 12. Junod , John L. PY90 Interactive Electronic Technical Manual (IETM) Portable Delivery

Computer analysis of digital sky surveys using citizen science and manual classification

Science.gov (United States)

Kuminski, Evan; Shamir, Lior

2015-01-01

As current and future digital sky surveys such as SDSS, LSST, DES, Pan-STARRS and Gaia create increasingly massive databases containing millions of galaxies, there is a growing need to be able to efficiently analyze these data. An effective way to do this is through manual analysis, however, this may be insufficient considering the extremely vast pipelines of astronomical images generated by the present and future surveys. Some efforts have been made to use citizen science to classify galaxies by their morphology on a larger scale than individual or small groups of scientists can. While these citizen science efforts such as Zooniverse have helped obtain reasonably accurate morphological information about large numbers of galaxies, they cannot scale to provide complete analysis of billions of galaxy images that will be collected by future ventures such as LSST. Since current forms of manual classification cannot scale to the masses of data collected by digital sky surveys, it is clear that in order to keep up with the growing databases some form of automation of the data analysis will be required, and will work either independently or in combination with human analysis such as citizen science. Here we describe a computer vision method that can automatically analyze galaxy images and deduce galaxy morphology. Experiments using Galaxy Zoo 2 data show that the performance of the method increases as the degree of agreement between the citizen scientists gets higher, providing a cleaner dataset. For several morphological features, such as the spirality of the galaxy, the algorithm agreed with the citizen scientists on around 95% of the samples. However, the method failed to analyze some of the morphological features such as the number of spiral arms, and provided accuracy of just ~36%.

The JOSHUA (J80) system programmer`s manual

Energy Technology Data Exchange (ETDEWEB)

Smetana, A.O.; McCort, J.T.; Westmoreland, B.W.

1993-08-01

The JOSHUA system routines (JS routines) can be used to manage a JOSHUA data base and execute JOSHUA modules on VAX/VMS and IBM/MVS computer systems. This manual provides instructions for using the JS routines and information about the internal data structures and logic used by the routines. It is intended for use primarily by JOSHUA systems programmers, however, advanced applications programmers may also find it useful. The JS routines are, as far as possible, written in ANSI FORTRAN 77 so that they are easily maintainable and easily portable to different computer systems. Nevertheless, the JOSHUA system provides features that are not available in ANSI FORTRAN 77, notably dynamic module execution and a data base of named, variable length, unformatted records, so some parts of the routines are coded in nonstandard FORTRAN or assembler (as a last resort). In most cases, the nonstandard sections of code are different for each computer system. To make it easy for programmers using the JS routines to avoid naming conflicts, the JS routines and common block all have six character names that begin with the characters {open_quotes}JS.{close_quotes} Before using this manual, one should be familiar with the JOSHUA system as described in {open_quotes}The JOSHUA Users` Manual,{close_quotes} ANSI FORTRAN 77, and at least one of the computer systems for which the JS routines have been implemented.

Operation, Maintenance and Management of Wastewater Treatment Facilities: A Bibliography of Technical Documents.

Science.gov (United States)

Himes, Dottie

This is an annotated bibliography of wastewater treatment manuals. Fourteen manuals are abstracted including: (1) A Planned Maintenance Management System for Municipal Wastewater Treatment Plants; (2) Anaerobic Sludge Digestion, Operations Manual; (3) Emergency Planning for Municipal Wastewater Treatment Facilities; (4) Estimating Laboratory Needs…

Procedures manual for the Oak Ridge Electron Linear Accelerator

International Nuclear Information System (INIS)

Todd, H.A.

1979-01-01

The Procedures Manual for the Oak Ridge Electron Linear Accelerator contains specific information pertaining to operation and safety of the facility. Items such as the interlock system, radiation monitoring, emergency procedures, night shift and weekend operation, and maintenance are discussed in detail

Algebraic computing program for studying the gauge theory

International Nuclear Information System (INIS)

Zet, G.

2005-01-01

An algebraic computing program running on Maple V platform is presented. The program is devoted to the study of the gauge theory with an internal Lie group as local symmetry. The physical quantities (gauge potentials, strength tensors, dual tensors etc.) are introduced either as equations in terms of previous defined quantities (tensors), or by manual entry of the component values. The components of the strength tensor and of its dual are obtained with respect to a given metric of the space-time used for describing the gauge theory. We choose a Minkowski space-time endowed with spherical symmetry and give some example of algebraic computing that are adequate for studying electroweak or gravitational interactions. The field equations are also obtained and their solutions are determined using the DEtools facilities of the Maple V computing program. (author)

RADTRAN 4: Volume 4, Programmer's manual

International Nuclear Information System (INIS)

Kanipe, F.L.; Neuhauser, K.S.

1992-07-01

The RADTRAN 4 computer code is designed to analyze radiological consequences and accident risks of transporting radioactive material. This manual provides information useful for interpreting, troubleshooting, or debugging components of the code during development or revision of the program

Integration of distributed plant process computer systems to nuclear power generation facilities

International Nuclear Information System (INIS)

Bogard, T.; Finlay, K.

1996-01-01

Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation ampersand control are evident from variations of design features

Estimating pressurized water reactor decommissioning costs: A user's manual for the PWR Cost Estimating Computer Program (CECP) software

International Nuclear Information System (INIS)

Bierschbach, M.C.; Mencinsky, G.J.

1993-10-01

With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the US Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user's manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personnel computer, provides estimates for the cost of decommissioning PWR plant stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning

Computer-based data acquisition system in the Large Coil Test Facility

International Nuclear Information System (INIS)

Gould, S.S.; Layman, L.R.; Million, D.L.

1983-01-01

The utilization of computers for data acquisition and control is of paramount importance on large-scale fusion experiments because they feature the ability to acquire data from a large number of sensors at various sample rates and provide for flexible data interpretation, presentation, reduction, and analysis. In the Large Coil Test Facility (LCTF) a Digital Equipment Corporation (DEC) PDP-11/60 host computer with the DEC RSX-11M operating system coordinates the activities of five DEC LSI-11/23 front-end processors (FEPs) via direct memory access (DMA) communication links. This provides host control of scheduled data acquisition and FEP event-triggered data collection tasks. Four of the five FEPs have no operating system

Electronic Commerce user manual

Energy Technology Data Exchange (ETDEWEB)

1992-04-10

This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD`s Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases & Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

Electronic Commerce user manual

Energy Technology Data Exchange (ETDEWEB)

1992-04-10

This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD's Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

SERA: Simulation Environment for Radiotherapy Applications - Users Manual Version 1CO

International Nuclear Information System (INIS)

Venhuizen, James Robert; Wessol, Daniel Edward; Wemple, Charles Alan; Wheeler, Floyd J; Harkin, G. J.; Frandsen, M. W.; Albright, C. L.; Cohen, M.T.; Rossmeier, M.; Cogliati, J.J.

2002-01-01

This document is the user manual for the Simulation Environment for Radiotherapy Applications (SERA) software program developed for boron-neutron capture therapy (BNCT) patient treatment planning by researchers at the Idaho National Engineering and Environmental Laboratory (INEEL) and students and faculty at Montana State University (MSU) Computer Science Department. This manual corresponds to the final release of the program, Version 1C0, developed to run under the RedHat Linux Operating System (version 7.2 or newer) or the Solaris Operating System (version 2.6 or newer). SERA is a suite of command line or interactively launched software modules, including graphical, geometric reconstruction, and execution interface modules for developing BNCT treatment plans. The program allows the user to develop geometric models of the patient as derived from Computed Tomography (CT) and Magnetic Resonance Imaging (MRI) images, perform dose computation for these geometric models, and display the computed doses on overlays of the original images as three dimensional representations. This manual provides a guide to the practical use of SERA, but is not an exhaustive treatment of each feature of the code

SERA: Simulation Environment for Radiotherapy Applications - Users Manual Version 1CO

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, James Robert; Wessol, Daniel Edward; Wemple, Charles Alan; Wheeler, Floyd J; Harkin, G. J.; Frandsen, M. W.; Albright, C. L.; Cohen, M.T.; Rossmeier, M.; Cogliati, J.J.

2002-06-01

This document is the user manual for the Simulation Environment for Radiotherapy Applications (SERA) software program developed for boron-neutron capture therapy (BNCT) patient treatment planning by researchers at the Idaho National Engineering and Environmental Laboratory (INEEL) and students and faculty at Montana State University (MSU) Computer Science Department. This manual corresponds to the final release of the program, Version 1C0, developed to run under the RedHat Linux Operating System (version 7.2 or newer) or the Solaris™ Operating System (version 2.6 or newer). SERA is a suite of command line or interactively launched software modules, including graphical, geometric reconstruction, and execution interface modules for developing BNCT treatment plans. The program allows the user to develop geometric models of the patient as derived from Computed Tomography (CT) and Magnetic Resonance Imaging (MRI) images, perform dose computation for these geometric models, and display the computed doses on overlays of the original images as three dimensional representations. This manual provides a guide to the practical use of SERA, but is not an exhaustive treatment of each feature of the code.

Ford motor company NDE facility shielding design

International Nuclear Information System (INIS)

Metzger, R. L.; Van Riper, K. A.; Jones, M. H.

2005-01-01

Ford Motor Company proposed the construction of a large non-destructive evaluation laboratory for radiography of automotive power train components. The authors were commissioned to design the shielding and to survey the completed facility for compliance with radiation doses for occupationally and non-occupationally exposed personnel. The two X-ray sources are Varian Linatron 3000 accelerators operating at 9-11 MV. One performs computed tomography of automotive transmissions, while the other does real-time radiography of operating engines and transmissions. The shield thickness for the primary barrier and all secondary barriers were determined by point-kernel techniques. Point-kernel techniques did not work well for skyshine calculations and locations where multiple sources (e.g. tube head leakage and various scatter fields) impacted doses. Shielding for these areas was determined using transport calculations. A number of MCNP [Briesmeister, J. F. MCNPCA general Monte Carlo N-particle transport code version 4B. Los Alamos National Laboratory Manual (1997)] calculations focused on skyshine estimates and the office areas. Measurements on the operational facility confirmed the shielding calculations. (authors)

Ford Motor Company NDE facility shielding design.

Science.gov (United States)

Metzger, Robert L; Van Riper, Kenneth A; Jones, Martin H

2005-01-01

Ford Motor Company proposed the construction of a large non-destructive evaluation laboratory for radiography of automotive power train components. The authors were commissioned to design the shielding and to survey the completed facility for compliance with radiation doses for occupationally and non-occupationally exposed personnel. The two X-ray sources are Varian Linatron 3000 accelerators operating at 9-11 MV. One performs computed tomography of automotive transmissions, while the other does real-time radiography of operating engines and transmissions. The shield thickness for the primary barrier and all secondary barriers were determined by point-kernel techniques. Point-kernel techniques did not work well for skyshine calculations and locations where multiple sources (e.g. tube head leakage and various scatter fields) impacted doses. Shielding for these areas was determined using transport calculations. A number of MCNP [Briesmeister, J. F. MCNPCA general Monte Carlo N-particle transport code version 4B. Los Alamos National Laboratory Manual (1997)] calculations focused on skyshine estimates and the office areas. Measurements on the operational facility confirmed the shielding calculations.

KAFEPA-II program users' manual and description

International Nuclear Information System (INIS)

Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

1992-04-01

KAFEPA-II is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computes the one-dimensional temperature distribution and thermal expansion of the fuel pellets. The amount of gas released during irradiation of the fuel is also computed. Thermal expansion and gas pressure inside the fuel element are then used to compute the strains and stresses in the sheath. This document is intended as a user's manual and description for KAFEPA-II. (Author)

SES2D user's manual

International Nuclear Information System (INIS)

Johnson, J.D.; Lyon, S.P.

1982-04-01

SES2D is an interactive graphics code designed to generate plots of equation of state data from the Los Alamos National Laboratory Group T-4 computer libraries. This manual discusses the capabilities of the code. It describes the prompts and commands and illustrates their use with a sample run

Inter-observer and inter-examination variability of manual vertebral bone attenuation measurements on computed tomography

International Nuclear Information System (INIS)

Pompe, Esther; Lammers, Jan-Willem J.; Jong, Pim A. de; Jong, Werner U. de; Takx, Richard A.P.; Eikendal, Anouk L.M.; Willemink, Martin J.; Mohamed Hoesein, Firdaus A.A.; Oudkerk, Matthijs; Budde, Ricardo P.J.

2016-01-01

To determine inter-observer and inter-examination variability of manual attenuation measurements of the vertebrae in low-dose unenhanced chest computed tomography (CT). Three hundred and sixty-seven lung cancer screening trial participants who underwent baseline and repeat unenhanced low-dose CT after 3 months because of an indeterminate lung nodule were included. The CT attenuation value of the first lumbar vertebrae (L1) was measured in all CTs by one observer to obtain inter-examination reliability. Six observers performed measurements in 100 randomly selected CTs to determine agreement with limits of agreement and Bland-Altman plots and reliability with intraclass correlation coefficients (ICCs). Reclassification analyses were performed using a threshold of 110 HU to define osteoporosis. Inter-examination reliability was excellent with an ICC of 0.92 (p < 0.001). Inter-examination limits of agreement ranged from -26 to 28 HU with a mean difference of 1 ± 14 HU. Inter-observer reliability ICCs ranged from 0.70 to 0.91. Inter-examination variability led to 11.2 % reclassification of participants and inter-observer variability led to 22.1 % reclassification. Vertebral attenuation values can be manually quantified with good to excellent inter-examination and inter-observer reliability on unenhanced low-dose chest CT. This information is valuable for early detection of osteoporosis on low-dose chest CT. (orig.)

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

Energy Technology Data Exchange (ETDEWEB)

Drewmark Communications; Sartor, Dale; Wilson, Mark

2010-07-01

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

Trauma facilities in Denmark - A nationwide cross-sectional benchmark study of facilities and trauma care organisation

DEFF Research Database (Denmark)

Weile, Jesper; Nielsen, Klaus; Primdahl, Stine C.

2018-01-01

Background: Trauma is a leading cause of death among adults aged trauma facilities and the use multidisciplinary trauma teams. Because knowledge is sparse on the existing distribution of trauma facilities...... and the organisation of trauma care in Denmark, the aim of this study was to identify all Danish facilities that care for traumatized patients and to investigate the diversity in organization of trauma management. Methods: We conducted a systematic observational cross-sectional study. First, all hospitals in Denmark...... were identified via online services and clarifying phone calls to each facility. Second, all trauma care manuals on all facilities that receive traumatized patients were gathered. Third, anesthesiologists and orthopedic surgeons on call at all trauma facilities were contacted via telephone...

Applying Minimal Manual Principles for Documentation of Graphical User Interfaces.

Science.gov (United States)

Nowaczyk, Ronald H.; James, E. Christopher

1993-01-01

Investigates the need to include computer screens in documentation for software using a graphical user interface. Describes the uses and purposes of "minimal manuals" and their principles. Studies student reaction to their use of one of three on-screen manuals: screens, icon, and button. Finds some benefit for including icon and button…

Maintenance Personnel Performance Simulation (MAPPS) model. Users' Manual

International Nuclear Information System (INIS)

Kopstein, F.F.; Wolf, J.J.

1985-09-01

This report (MAPPS User's Manual) is the last report to be published from this program and provides detailed guidelines for utilization of the MAPPS model. Although the model has been developed to be highly user-friendly and provides interactive means for controlling and running of the model, the user's manual is provided as a guide for the user in the event clarification or direction is required. The user will find that in general the model requires primarily user input that is self explanatory. Once initial familiarization with the model has been achieved by the user, the amount of interaction between the user's manual and the computer model will be minimal. It is suggested however that even the experienced user keep the user's manual handy for quick reference. 5 refs., 10 figs., 7 tabs

In vitro comparative study of manual and mechanical rotary instrumentation of root canals using computed tomography.

Science.gov (United States)

Limongi, Orlando; de Albuquerque, Diana Santana; Baratto Filho, Flares; Vanni, José Roberto; de Oliveira, Elias P Motcy; Barletta, Fernando Branco

2007-01-01

This in vitro study compared, using computed tomography (CT), the amount of dentin removed from root canal walls by manual and mechanical rotary instrumentation techniques. Forty mandibular incisors with dental crown and a single canal were selected. The teeth were randomly assigned to two groups, according to the technique used for root canal preparation: Group I - manual instrumentation with stainless steel files; Group II - mechanical instrumentation with RaCe rotary nickel-titanium instruments. In each tooth, root dentin thickness of the buccal, lingual, mesial and distal surfaces in the apical, middle and cervical thirds of the canal was measured (in mm) using a multislice CT scanner (Siemens Emotion, Duo). Data were stored in the SPSS v. 11.5 and SigmaPlot 2001 v. 7.101 softwares. After crown opening, working length was determined, root canals were instrumented and new CT scans were taken for assessment of root dentin thickness. Pre- and post-instrumentation data were compared and analyzed statistically by ANOVA and Tukey's post-hoc test for significant differences (p=0.05). Based on the findings of this study, it may be concluded that regarding dentin removal from root canal walls during instrumentation, neither of the techniques can be considered more effective than the other.

DESIGN OF MANUAL MATERIAL HANDLING SYSTEM THROUGH COMPUTER AIDED ERGONOMICS: A CASE STUDY AT BDTSC TEXTILE FIRM

Directory of Open Access Journals (Sweden)

Amare Matebu

2014-12-01

Full Text Available Designing of lifting, pushing and pulling activities based on the physical and physiological capabilities of the operators is essential. The purpose of this study is to analyze manual material handling (MMH working posture of the operators using 3D Static Strength Prediction Program (3DSSPP software and to identify major areas causing long last injury of operators. The research has investigated the fit between the demands of tasks and the capabilities of operators. At the existing situations, the actual capabilities of operators have been computed with the help of 3DSSPP software and compared with NIOSH standards. Accordingly, operators' working posture is at an unacceptable position that exposes them for musculoskeletal disorders. Then, after the improvement of the design of MMH device (cart's roller, the result showed that the forces required by the operators to push and pull the sliver cans have been reduced from 931.77 Newton to 194.23 Newton. Furthermore, improvement of MMH cart's roller has reduced the awkward posture of operators and the risk of musculoskeletal disorders. The improved manual material handling design also saves about 1828.40 ETB per month for the company.

Zooplankton Methodology, Collection & identyification - A field manual

Digital Repository Service at National Institute of Oceanography (India)

Goswami, S.C.

and productivity would largely depend upon the use of correct methodology which involves collection of samples, fixation, preservation, analysis and computation of data. The detailed procedures on all these aspects are given in this manual....

Computer-based guidelines for concrete pavements : HIPERPAV III : user manual

Science.gov (United States)

2009-10-01

This user manual provides guidance on how to use the new High PERformance PAVing (HIPERPAV) III software program for the analysis of early-age Portland cement concrete pavement (PCCP) behavior. HIPERPAV III includes several improvements over prev...

Typewriting 10-20-30. Senior High School Teacher Resource Manual.

Science.gov (United States)

Alberta Dept. of Education, Edmonton. Curriculum Branch.

This manual is designed to assist typewriting teachers in the implementation of the Alberta, Canada, Typewriting 10-20-30 Curriculum (1985). Many ideas contained in the handbook can also be used in curricula that address keyboarding or the skill of typing in computer keyboarding, dictaphone typing, or word processing. The manual is organized in…

The HEPCloud Facility: elastic computing for High Energy Physics - The NOvA Use Case

Science.gov (United States)

Fuess, S.; Garzoglio, G.; Holzman, B.; Kennedy, R.; Norman, A.; Timm, S.; Tiradani, A.

2017-10-01

The need for computing in the HEP community follows cycles of peaks and valleys mainly driven by conference dates, accelerator shutdown, holiday schedules, and other factors. Because of this, the classical method of provisioning these resources at providing facilities has drawbacks such as potential overprovisioning. As the appetite for computing increases, however, so does the need to maximize cost efficiency by developing a model for dynamically provisioning resources only when needed. To address this issue, the HEPCloud project was launched by the Fermilab Scientific Computing Division in June 2015. Its goal is to develop a facility that provides a common interface to a variety of resources, including local clusters, grids, high performance computers, and community and commercial Clouds. Initially targeted experiments include CMS and NOvA, as well as other Fermilab stakeholders. In its first phase, the project has demonstrated the use of the “elastic” provisioning model offered by commercial clouds, such as Amazon Web Services. In this model, resources are rented and provisioned automatically over the Internet upon request. In January 2016, the project demonstrated the ability to increase the total amount of global CMS resources by 58,000 cores from 150,000 cores - a 38 percent increase - in preparation for the Recontres de Moriond. In March 2016, the NOvA experiment has also demonstrated resource burst capabilities with an additional 7,300 cores, achieving a scale almost four times as large as the local allocated resources and utilizing the local AWS s3 storage to optimize data handling operations and costs. NOvA was using the same familiar services used for local computations, such as data handling and job submission, in preparation for the Neutrino 2016 conference. In both cases, the cost was contained by the use of the Amazon Spot Instance Market and the Decision Engine, a HEPCloud component that aims at minimizing cost and job interruption. This paper

Comparison of Intensity-Modulated Radiotherapy Planning Based on Manual and Automatically Generated Contours Using Deformable Image Registration in Four-Dimensional Computed Tomography of Lung Cancer Patients

International Nuclear Information System (INIS)

Weiss, Elisabeth; Wijesooriya, Krishni; Ramakrishnan, Viswanathan; Keall, Paul J.

2008-01-01

Purpose: To evaluate the implications of differences between contours drawn manually and contours generated automatically by deformable image registration for four-dimensional (4D) treatment planning. Methods and Materials: In 12 lung cancer patients intensity-modulated radiotherapy (IMRT) planning was performed for both manual contours and automatically generated ('auto') contours in mid and peak expiration of 4D computed tomography scans, with the manual contours in peak inspiration serving as the reference for the displacement vector fields. Manual and auto plans were analyzed with respect to their coverage of the manual contours, which were assumed to represent the anatomically correct volumes. Results: Auto contours were on average larger than manual contours by up to 9%. Objective scores, D 2% and D 98% of the planning target volume, homogeneity and conformity indices, and coverage of normal tissue structures (lungs, heart, esophagus, spinal cord) at defined dose levels were not significantly different between plans (p = 0.22-0.94). Differences were statistically insignificant for the generalized equivalent uniform dose of the planning target volume (p = 0.19-0.94) and normal tissue complication probabilities for lung and esophagus (p = 0.13-0.47). Dosimetric differences >2% or >1 Gy were more frequent in patients with auto/manual volume differences ≥10% (p = 0.04). Conclusions: The applied deformable image registration algorithm produces clinically plausible auto contours in the majority of structures. At this stage clinical supervision of the auto contouring process is required, and manual interventions may become necessary. Before routine use, further investigations are required, particularly to reduce imaging artifacts

Specialized computer architectures for computational aerodynamics

Science.gov (United States)

Stevenson, D. K.

1978-01-01

In recent years, computational fluid dynamics has made significant progress in modelling aerodynamic phenomena. Currently, one of the major barriers to future development lies in the compute-intensive nature of the numerical formulations and the relative high cost of performing these computations on commercially available general purpose computers, a cost high with respect to dollar expenditure and/or elapsed time. Today's computing technology will support a program designed to create specialized computing facilities to be dedicated to the important problems of computational aerodynamics. One of the still unresolved questions is the organization of the computing components in such a facility. The characteristics of fluid dynamic problems which will have significant impact on the choice of computer architecture for a specialized facility are reviewed.

A valiant little terminal: A VLT user's manual

Energy Technology Data Exchange (ETDEWEB)

Weinstein, A.

1990-12-01

This report is a manual for the valiant little terminal. Information covered in this report is as follow: an introduction to VLT; installation; starting up; text screen menus; graphics screen menus; introduction to VLT's scripting facility; quick reference section; and troubleshooting.

IAEA safeguards technical manual

International Nuclear Information System (INIS)

1982-03-01

Part F of the Safeguards Technical Manual is being issued in three volumes. Volume 1 was published in 1977 and revised slightly in 1979. Volume 1 discusses basic probability concepts, statistical inference, models and measurement errors, estimation of measurement variances, and calibration. These topics of general interest in a number of application areas, are presented with examples drawn from nuclear materials safeguards. The final two chapters in Volume 1 deal with problem areas unique to safeguards: calculating the variance of MUF and of D respectively. Volume 2 continues where Volume 1 left off with a presentation of topics of specific interest to Agency safeguards. These topics include inspection planning from a design and effectiveness evaluation viewpoint, on-facility site inspection activities, variables data analysis as applied to inspection data, preparation of inspection reports with respect to statistical aspects of the inspection, and the distribution of inspection samples to more than one analytical laboratory. Volume 3 covers generally the same material as Volumes 1 and 2 but with much greater unity and cohesiveness. Further, the cook-book style of the previous two volumes has been replaced by one that makes use of equations and formulas as opposed to computational steps, and that also provides the bases for the statistical procedures discussed. Hopefully, this will help minimize the frequency of misapplications of the techniques

SRS station guide. Station 2.3 manual

International Nuclear Information System (INIS)

Tang, C.; Miller, M.; Laundy, D.

1996-06-01

The object of the manual is to effectively provide assistance to users so that they can perform successful experiments at station 2.3 during their visits. In order to compile a comprehensive document, the functions of the instrument hardware and software are described in detail. Where appropriate it also contains useful information and other documentation for help and/or reference. In addition, suggestions and instructions are available to overcome problems which inevitably face the users as the instrument is quite advanced in the performing of complex experimental tasks. This document can provide help as part of the overall user support facility and it is therefore intended that the manual is readily available in hardcopy as well as in electronic form. (author)

Computer program for storage of historical and routine safety data related to radiologically controlled facilities

International Nuclear Information System (INIS)

Marsh, D.A.; Hall, C.J.

1984-01-01

A method for tracking and quick retrieval of radiological status of radiation and industrial safety systems in an active or inactive facility has been developed. The system uses a mini computer, a graphics plotter, and mass storage devices. Software has been developed which allows input and storage of architectural details, radiological conditions such as exposure rates, current location of safety systems, and routine and historical information on exposure and contamination levels. A blue print size digitizer is used for input. The computer program retains facility floor plans in three dimensional arrays. The software accesses an eight pen color plotter for output. The plotter generates color plots of the floor plans and safety systems on 8 1/2 x 11 or 20 x 30 paper or on overhead transparencies for reports and presentations

Atmospheric dispersion calculation for posturated accident of nuclear facilities and the computer code: PANDA

International Nuclear Information System (INIS)

Kitahara, Yoshihisa; Kishimoto, Yoichiro; Narita, Osamu; Shinohara, Kunihiko

1979-01-01

Several Calculation methods for relative concentration (X/Q) and relative cloud-gamma dose (D/Q) of the radioactive materials released from nuclear facilities by posturated accident are presented. The procedure has been formulated as a Computer program PANDA and the usage is explained. (author)

Health physics manual of good practices for tritium facilities

International Nuclear Information System (INIS)

Blauvelt, R.K.; Deaton, M.R.; Gill, J.T.

1991-12-01

The purpose of this document is to provide written guidance defining the generally accepted good practices in use at Department of Energy (DOE) tritium facilities. A open-quotes good practiceclose quotes is an action, policy, or procedure that enhances the radiation protection program at a DOE site. The information selected for inclusion in this document should help readers achieve an understanding of the key radiation protection issues at tritium facilities and provide guidance as to what characterizes excellence from a radiation protection point of view. The ALARA (As Low as Reasonable Achievable) program at DOE sites should be based, in part, on following the good practices that apply to their operations

RADTRAN 4: Volume 4, Programmer`s manual

Energy Technology Data Exchange (ETDEWEB)

Kanipe, F L [GRAM, Inc., Albuquerque, NM (United States); Neuhauser, K S [Sandia National Labs., Albuquerque, NM (United States)

1992-07-01

The RADTRAN 4 computer code is designed to analyze radiological consequences and accident risks of transporting radioactive material. This manual provides information useful for interpreting, troubleshooting, or debugging components of the code during development or revision of the program.

Manual for implementing residual radioactivity guidelines

International Nuclear Information System (INIS)

Gilbert, T.L.; Eckerman, K.F.; Hansen, W.R.; Healy, J.W.; Kennedy, W.E.; Napier, B.A.; Solday, J.K.

1986-01-01

The US Department of Energy (DOE) has recently issued guidelines for residual radioactivity at Formerly Utilized Sites Remedial Action Program (FUSRAP) and remote Surplus Facilities Management Program (SFMP) sites. A manual for implementing these guidelines has been prepared jointly by four DOE laboratories (ANL, LANL, ORNL, and PNL) and is being issued as a supplement to the guidelines. The manual presents procedures and tables for deriving site-specific guidelines for levels of residual radionuclide concentrations in soil that must not be exceeded if a site is to be released for unrestricted use. Guidance for implementing DOE ALARA policy for remedial actions is also included. The concentration factor method is used in the pathway analysis for deriving soil guidelines. The analysis has been structured in a manner that explicitly identifies all of the factors involved. Tables are provided for dose-conversion factors and pathway factors from which environmental transport factors for each radionuclide and pathway may be calculated. The scenarios used for deriving the environmental transport factors and dose conversion factors, and the manner in which the information provided in the manual is used to derive site-specific soil guidelines will be presented

Estimation of Aboveground Biomass Using Manual Stereo Viewing of Digital Aerial Photographs in Tropical Seasonal Forest

Directory of Open Access Journals (Sweden)

Katsuto Shimizu

2014-11-01

Full Text Available The objectives of this study are to: (1 evaluate accuracy of tree height measurements of manual stereo viewing on a computer display using digital aerial photographs compared with airborne LiDAR height measurements; and (2 develop an empirical model to estimate stand-level aboveground biomass with variables derived from manual stereo viewing on the computer display in a Cambodian tropical seasonal forest. We evaluate observation error of tree height measured from the manual stereo viewing, based on field measurements. RMSEs of tree height measurement with manual stereo viewing and LiDAR were 1.96 m and 1.72 m, respectively. Then, stand-level aboveground biomass is regressed against tree height indices derived from the manual stereo viewing. We determined the best model to estimate aboveground biomass in terms of the Akaike’s information criterion. This was a model of mean tree height of the tallest five trees in each plot (R2 = 0.78; RMSE = 58.18 Mg/ha. In conclusion, manual stereo viewing on the computer display can measure tree height accurately and is useful to estimate aboveground stand biomass.

INES: The International Nuclear Event Scale user's manual

International Nuclear Information System (INIS)

1992-09-01

The revised and extended addition of the International Nuclear Event Scale is presented. The manual is comprised of four parts. Part 1 contains a summary of the basis of the scale and of the procedure to be used for rating events. Part 2 contains the detailed guidance required to rate events in terms of off-site and on-site impact. These two parts are applicable to all nuclear facilities. Parts 3 and 4 contain the detailed guidance required to rate events in terms of defence in depth for reactors and other facilities, respectively. 5 figs, 2 tabs

Interlibrary Loan Communications Subsystem: Users Manual.

Science.gov (United States)

OCLC Online Computer Library Center, Inc., Dublin, OH.

The OCLC Interlibrary Loan (ILL) Communications Subsystem provides participating libraries with on-line control of ILL transactions. This user manual includes a glossary of terms related to the procedures in using the system. Sections describe computer entry, searching, loan request form, loan response form, ILL procedures, the special message…

Taking the classical large audience university lecture online using tablet computer and webconferencing facilities

DEFF Research Database (Denmark)

Brockhoff, Per B.

2011-01-01

During four offerings (September 2008 – May 2011) of the course 02402 Introduction to Statistics for Engineering students at DTU, with an average of 256 students, the lecturing was carried out 100% through a tablet computer combined with the web conferencing facility Adobe Connect (version 7...

User's manual for the computer-aided plant transient data compilation

International Nuclear Information System (INIS)

Langenbuch, S.; Gill, R.; Lerchl, G.; Schwaiger, R.; Voggenberger, T.

1984-01-01

The objective of this project is the compilation of data for nuclear power plants needed for transient analyses. The concept has been already described. This user's manual gives a detailed description of all functions of the dialogue system that supports data acquisition and retrieval. (orig.) [de

Techniques for controlling air pollution from the operation of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

1966-03-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level. Refs, 24 figs, 5 tabs.

Animal facilities

International Nuclear Information System (INIS)

Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

1981-01-01

The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

Interactive hypermedia training manual for spent-fuel bundle counters

International Nuclear Information System (INIS)

Basso, R.A.

1990-07-01

Spent-fuel bundle counters, developed by the Canadian Safeguards Support Program for the International Atomic Energy Agency, provide a secure and independent means of counting the number of irradiated fuel bundles discharged into the fuel storage bays at CANDU nuclear power stations. Paper manuals have been traditionally used to familiarize IAEA inspectors with the operation, maintenance and extensive reporting capabilities of the bundle counters. To further assist inspectors, an interactive training manual has been developed on an Apple Macintosh computer using hypermedia software. The manual uses interactive animation and sound, in conjunction with the traditional text and graphics, to simulate the underlying operation and logic of the bundle counters. This paper presents the key features of the interactive manual and highlights the advantages of this new technology for training

Teaching ergonomics to nursing facility managers using computer-based instruction.

Science.gov (United States)

Harrington, Susan S; Walker, Bonnie L

2006-01-01

This study offers evidence that computer-based training is an effective tool for teaching nursing facility managers about ergonomics and increasing their awareness of potential problems. Study participants (N = 45) were randomly assigned into a treatment or control group. The treatment group completed the ergonomics training and a pre- and posttest. The control group completed the pre- and posttests without training. Treatment group participants improved significantly from 67% on the pretest to 91% on the posttest, a gain of 24%. Differences between mean scores for the control group were not significant for the total score or for any of the subtests.

Health physics manual of good practices for tritium facilities

Energy Technology Data Exchange (ETDEWEB)

Blauvelt, R.K.; Deaton, M.R.; Gill, J.T. [and others

1991-12-01

The purpose of this document is to provide written guidance defining the generally accepted good practices in use at Department of Energy (DOE) tritium facilities. A {open_quotes}good practice{close_quotes} is an action, policy, or procedure that enhances the radiation protection program at a DOE site. The information selected for inclusion in this document should help readers achieve an understanding of the key radiation protection issues at tritium facilities and provide guidance as to what characterizes excellence from a radiation protection point of view. The ALARA (As Low as Reasonable Achievable) program at DOE sites should be based, in part, on following the good practices that apply to their operations.

Computational Science Facility (CSF)

Data.gov (United States)

Federal Laboratory Consortium — PNNL Institutional Computing (PIC) is focused on meeting DOE's mission needs and is part of PNNL's overarching research computing strategy. PIC supports large-scale...

ENDF/B-5 formats manual 1984

Energy Technology Data Exchange (ETDEWEB)

Kinsey, R; Magurno, B A

1986-09-01

The ENDF-5 Format, originally the format of the US Evaluated Nuclear Data File ENDF/B-5, was internationally recommended for the computer storage, processing and exchange of evaluated neutron nuclear data. The present document contains the original Formats Manual of 1979, updated with revisions of Nov. 1983. (author) Figs, tabs

RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation

International Nuclear Information System (INIS)

1976-09-01

This portion of the RELAP4/MOD5 User's Manual presents the details of setting up and entering the reactor model to be evaluated. The input card format and arrangement is presented in depth, including not only cards for data but also those for editing and restarting. Problem initalization including pressure distribution and energy balance is discussed. A section entitled ''User Guidelines'' is included to provide modeling recommendations, analysis and verification techniques, and computational difficulty resolution. The section is concluded with a discussion of the computer output form and format

ELESTRES.M11K program users'manual and description

International Nuclear Information System (INIS)

Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

1992-12-01

ELESTRES.M11K is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computers the one-dimensional temperature distribution and thermal expansion of the fuel pellets, and computes two-dimensional pellet deformation using FEM. The amount of fission gas released and sheath strain/stress are also computed. This document is intended as a users' manual and description for ELESTRES.M11K program. (Author)

Investigation of Storage Options for Scientific Computing on Grid and Cloud Facilities

International Nuclear Information System (INIS)

Garzoglio, Gabriele

2012-01-01

In recent years, several new storage technologies, such as Lustre, Hadoop, OrangeFS, and BlueArc, have emerged. While several groups have run benchmarks to characterize them under a variety of configurations, more work is needed to evaluate these technologies for the use cases of scientific computing on Grid clusters and Cloud facilities. This paper discusses our evaluation of the technologies as deployed on a test bed at FermiCloud, one of the Fermilab infrastructure-as-a-service Cloud facilities. The test bed consists of 4 server-class nodes with 40 TB of disk space and up to 50 virtual machine clients, some running on the storage server nodes themselves. With this configuration, the evaluation compares the performance of some of these technologies when deployed on virtual machines and on “bare metal” nodes. In addition to running standard benchmarks such as IOZone to check the sanity of our installation, we have run I/O intensive tests using physics-analysis applications. This paper presents how the storage solutions perform in a variety of realistic use cases of scientific computing. One interesting difference among the storage systems tested is found in a decrease in total read throughput with increasing number of client processes, which occurs in some implementations but not others.

How to Investigate Drug Use in Health Facilities. Selected Drug Use ...

African Journals Online (AJOL)

This short WHO manual outlines methods for evaluating drug use indicators in health facilities. The broad areas of ... Washington: American Psychiatric Press, Inc. 1991. ISBN 0-88048-114-5. This book is ... discussion of different symptom categories using the DSM. (Diagnostic Statistical Manual) as a base. The definition of.

The HEPCloud Facility: elastic computing for High Energy Physics – The NOvA Use Case

Energy Technology Data Exchange (ETDEWEB)

Fuess, S. [Fermilab; Garzoglio, G. [Fermilab; Holzman, B. [Fermilab; Kennedy, R. [Fermilab; Norman, A. [Fermilab; Timm, S. [Fermilab; Tiradani, A. [Fermilab

2017-03-15

The need for computing in the HEP community follows cycles of peaks and valleys mainly driven by conference dates, accelerator shutdown, holiday schedules, and other factors. Because of this, the classical method of provisioning these resources at providing facilities has drawbacks such as potential overprovisioning. As the appetite for computing increases, however, so does the need to maximize cost efficiency by developing a model for dynamically provisioning resources only when needed. To address this issue, the HEPCloud project was launched by the Fermilab Scientific Computing Division in June 2015. Its goal is to develop a facility that provides a common interface to a variety of resources, including local clusters, grids, high performance computers, and community and commercial Clouds. Initially targeted experiments include CMS and NOvA, as well as other Fermilab stakeholders. In its first phase, the project has demonstrated the use of the “elastic” provisioning model offered by commercial clouds, such as Amazon Web Services. In this model, resources are rented and provisioned automatically over the Internet upon request. In January 2016, the project demonstrated the ability to increase the total amount of global CMS resources by 58,000 cores from 150,000 cores - a 25 percent increase - in preparation for the Recontres de Moriond. In March 2016, the NOvA experiment has also demonstrated resource burst capabilities with an additional 7,300 cores, achieving a scale almost four times as large as the local allocated resources and utilizing the local AWS s3 storage to optimize data handling operations and costs. NOvA was using the same familiar services used for local computations, such as data handling and job submission, in preparation for the Neutrino 2016 conference. In both cases, the cost was contained by the use of the Amazon Spot Instance Market and the Decision Engine, a HEPCloud component that aims at minimizing cost and job interruption. This paper

Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases

Energy Technology Data Exchange (ETDEWEB)

Vincent, A.W. III

2001-01-03

This manual documents a recommended methodology for determining the ingestion pathway consequences of hypothetical accidental airborne radiological releases from facilities at the Savannah River Site. Both particulate and tritiated radioactive contaminants are addressed. Other approaches should be applied for evaluation of routine releases.

GMS 3: A users manual for an improved generalised multigroup scheme using WDSN MK2 for the KDF9 computer

International Nuclear Information System (INIS)

Barnett, M.R.; Ward, J.A.

1968-08-01

GMS 3 is an extension of GMS1 written for the KDF9 computer. An improved DSN routine has been incorporated, with consequent reduction in running time in many instances. Three alternative nuclear data libraries are now available, the latest of these being entirely consistent with that of WIMS. A treatment of neutron streaming in simple voids is now incorporated in the routine which prepares few-group macroscopic parameters. This report is primarily a Users Manual, but in addition includes details of theory and programming. (author)

Follow 1.1 - a program for visualization of Thermal-Hydraulic computer simulations. User's manual

International Nuclear Information System (INIS)

Hyvarinen, J.

1990-04-01

FOLLOW is a computer program designed to function as an analyst's aid when performing large thermalhydraulic and related safety calculations using the well known simulation codes RELAP5, MELCOR, SMABRE and TRAB. The code is a by-product of the effort to improve the analysis capabilities of the Finnish Centre for Radiation and Nuclear Safety (STUK). FOLLOW's most important application is as an on-line 'window' into the progress of the simulation calculation. The thermal-hydraulic analyses related to nuclear safety routinely require very long calculation times. FOLLOW provides a possibility to follow the course of the simulation and thus make observations of the results already during the simulation. FOLLOW's various outputs have been designed to mimic those available at nuclear power plant operators' console. Thus FOLLOW can also be used much like a nuclear power plant simulator. This manual describes the usages, features and input requirements of FOLLOW version 1.1, including a sample problem input and various outputs. (orig.)

Data acquisition for X ray microprobe. User's manual

International Nuclear Information System (INIS)

2002-01-01

A modified data acquisition software for X ray microprobe was developed by the Physics Group, Instrumentation Unit, IAEA Laboratories at Seibersdorf, with assistance from M. Bogovac, Croatia. The software consists of data acquisition (scanning and calibration), automatic positioning and micro-movement of sample, data reduction and evaluation. The acquisition software was designed in order to support different measurement set-ups which are applied in low-energy nuclear physics. The modification was done in 1999-2000 under the projects Nuclear Spectrometry and Utilization of Particle Accelerators. The manual supersedes the first version entitled Microanalysis Data Acquisition and Control Program published under Computer Manual Series, No. 9 in 1996. The software described in this manual is freely available from the IAEA upon request

Management Information System Project. Data Processors Manual to the Program Oriented Accounting System: The Budgetary Process.

Science.gov (United States)

Foley, Walter; Harr, Gordon

The purpose of this manual is to serve the needs of a data processing facility in the operation of a management information system (MIS). Included in the manual are system flowcharts, job control language, and system documentation. The system has been field tested and operates under IBM System 360/Model 65-05-MVT-HASP. The programing language is…

User Manual for SSG Power Simulation 2

DEFF Research Database (Denmark)

Jensen, Palle Meinert; Gilling, Lasse; Kofoed, Jens Peter

This manual gives a detailed description of the use of the computer program SSG Power Simulation 2. Furthermore, the underlying mathematics and algorithms are briefly described. The program is based on experimental data from model testing of Seawave Slot-Cone Generator (SSG) presented in Kofoed...

SPARK Version 1.1 user manual

International Nuclear Information System (INIS)

Weissenburger, D.W.

1988-01-01

This manual describes the input required to use Version 1.1 of the SPARK computer code. SPARK 1.1 is a library of FORTRAN main programs and subprograms designed to calculate eddy currents on conducting surfaces where current flow is assumed zero in the direction normal to the surface. Surfaces are modeled with triangular and/or quadrilateral elements. Lorentz forces produced by the interaction of eddy currents with background magnetic fields can be output at element nodes in a form compatible with most structural analysis codes. In addition, magnetic fields due to eddy currents can be determined at points off the surface. Version 1.1 features eddy current streamline plotting with optional hidden-surface-removal graphics and topological enhancements that allow essentially any orientable surface to be modeled. SPARK also has extensive symmetry specification options. In order to make the manual as self-contained as possible, six appendices are included that present summaries of the symmetry options, topological options, coil options and code algorithms, with input and output examples. An edition of SPARK 1.1 is available on the Cray computers at the National Magnetic Fusion Energy Computer Center at Livermore, California. Another more generic edition is operational on the VAX computers at the Princeton Plasma Physics Laboratory and is available on magnetic tape by request. The generic edition requires either the GKS or PLOT10 graphics package and the IMSL or NAG mathematical package. Requests from outside the United States will be subject to applicable federal regulations regarding dissemination of computer programs. 22 refs

SPARK Version 1. 1 user manual

Energy Technology Data Exchange (ETDEWEB)

Weissenburger, D.W.

1988-01-01

This manual describes the input required to use Version 1.1 of the SPARK computer code. SPARK 1.1 is a library of FORTRAN main programs and subprograms designed to calculate eddy currents on conducting surfaces where current flow is assumed zero in the direction normal to the surface. Surfaces are modeled with triangular and/or quadrilateral elements. Lorentz forces produced by the interaction of eddy currents with background magnetic fields can be output at element nodes in a form compatible with most structural analysis codes. In addition, magnetic fields due to eddy currents can be determined at points off the surface. Version 1.1 features eddy current streamline plotting with optional hidden-surface-removal graphics and topological enhancements that allow essentially any orientable surface to be modeled. SPARK also has extensive symmetry specification options. In order to make the manual as self-contained as possible, six appendices are included that present summaries of the symmetry options, topological options, coil options and code algorithms, with input and output examples. An edition of SPARK 1.1 is available on the Cray computers at the National Magnetic Fusion Energy Computer Center at Livermore, California. Another more generic edition is operational on the VAX computers at the Princeton Plasma Physics Laboratory and is available on magnetic tape by request. The generic edition requires either the GKS or PLOT10 graphics package and the IMSL or NAG mathematical package. Requests from outside the United States will be subject to applicable federal regulations regarding dissemination of computer programs. 22 refs.

LCS Users Manual

International Nuclear Information System (INIS)

Redd, A.J.; Ignat, D.W.

1998-01-01

The Lower Hybrid Simulation Code (LSC) is a computational model of lower hybrid current drive in the presence of an electric field. Details of geometry, plasma profiles, and circuit equations are treated. Two-dimensional velocity space effects are approximated in a one-dimensional Fokker-Planck treatment. The LSC was originally written to be a module for lower hybrid current drive called by the Tokamak Simulation Code (TSC), which is a numerical model of an axisymmetric tokamak plasma and the associated control systems. The TSC simulates the time evolution of a free boundary plasma by solving the MHD equations on a rectangular computational grid. The MHD equations are coupled to the external circuits (representing poloidal field coils) through the boundary conditions. The code includes provisions for modeling the control system, external heating, and fusion heating. The LSC module can also be called by the TRANSP code. TRANSP represents the plasma with an axisymmetric, fixed-boundary model and focuses on calculation of plasma transport to determine transport coefficients from data on power inputs and parameters reached. This manual covers the basic material needed to use the LSC. If run in conjunction with TSC, the ''TSC Users Manual'' should be consulted. If run in conjunction with TRANSP, on-line documentation will be helpful. A theoretical background of the governing equations and numerical methods is given. Information on obtaining, compiling, and running the code is also provided

Specialized, multi-user computer facility for the high-speed, interactive processing of experimental data

International Nuclear Information System (INIS)

Maples, C.C.

1979-05-01

A proposal has been made at LBL to develop a specialized computer facility specifically designed to deal with the problems associated with the reduction and analysis of experimental data. Such a facility would provide a highly interactive, graphics-oriented, multi-user environment capable of handling relatively large data bases for each user. By conceptually separating the general problem of data analysis into two parts, cyclic batch calculations and real-time interaction, a multilevel, parallel processing framework may be used to achieve high-speed data processing. In principle such a system should be able to process a mag tape equivalent of data through typical transformations and correlations in under 30 s. The throughput for such a facility, for five users simultaneously reducing data, is estimated to be 2 to 3 times greater than is possible, for example, on a CDC7600. 3 figures

Specialized, multi-user computer facility for the high-speed, interactive processing of experimental data

International Nuclear Information System (INIS)

Maples, C.C.

1979-01-01

A proposal has been made to develop a specialized computer facility specifically designed to deal with the problems associated with the reduction and analysis of experimental data. Such a facility would provide a highly interactive, graphics-oriented, multi-user environment capable of handling relatively large data bases for each user. By conceptually separating the general problem of data analysis into two parts, cyclic batch calculations and real-time interaction, a multi-level, parallel processing framework may be used to achieve high-speed data processing. In principle such a system should be able to process a mag tape equivalent of data, through typical transformations and correlations, in under 30 sec. The throughput for such a facility, assuming five users simultaneously reducing data, is estimated to be 2 to 3 times greater than is possible, for example, on a CDC7600

MAN-004 Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

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

2014-07-01

protection, mechanical, electrical, telecommunications, and security features is expected to ensure compatibility with planned functional equipment and to facilitate constructability. If portions of the design are subcontracted to specialists, delivery of the finished design documents must not be considered complete until the subcontracted portions are also submitted for review. You must, along with support consultants, perform functional analyses and programming in developing design solutions. These solutions must reflect coordination of the competing functional, budgetary, and physical requirements for the project. During design phases, meetings between you and the SNL/NM Project Team to discuss and resolve design issues are required. These meetings are a normal part of the design process. For specific design-review requirements, see the project-specific Design Criteria. In addition to the design requirements described in this manual, instructive information is provided to explain the sustainable building practice goals for design, construction, operation, and maintenance of SNL/NM facilities. Please notify SNL/NM personnel of design best practices not included in this manual, so they can be incorporated in future updates.

A computer controlled tele-cobalt unit

International Nuclear Information System (INIS)

Brace, J.A.

1982-01-01

A computer controlled cobalt treatment unit was commissioned for treating patients in January 1980. Initially the controlling computer was a minicomputer, but now the control of the therapy unit is by a microcomputer. The treatment files, which specify the movement and configurations necessary to deliver the prescribed dose, are produced on the minicomputer and then transferred to the microcomputer using minitape cartridges. The actual treatment unit is based on a standard cobalt unit with a few additional features e.g. the drive motors can be controlled either by the computer or manually. Since the treatment unit is used for both manual and automatic treatments, the operational procedure under computer control is made to closely follow the manual procedure for a single field treatment. The necessary safety features which protect against human, hardware and software errors as well as the advantages and disadvantages of computer controlled radiotherapy are discussed

Application of personal computer to development of entrance management system for radiating facilities

International Nuclear Information System (INIS)

Suzuki, Shogo; Hirai, Shouji

1989-01-01

The report describes a system for managing the entrance and exit of personnel to radiating facilities. A personal computer is applied to its development. Major features of the system is outlined first. The computer is connected to the gate and two magnetic card readers provided at the gate. The gate, which is installed at the entrance to a room under control, opens only for those who have a valid card. The entrance-exit management program developed is described next. The following three files are used: ID master file (random file of the magnetic card number, name, qualification, etc., of each card carrier), entrance-exit management file (random file of time of entrance/exit, etc., updated everyday), and entrance-exit record file (sequential file of card number, name, date, etc.), which are stored on floppy disks. A display is provided to show various lists including a list of workers currently in the room and a list of workers who left the room at earlier times of the day. This system is useful for entrance management of a relatively small facility. Though small in required cost, it requires only a few operators to perform effective personnel management. (N.K.)

CP-50 calibration facility radiological safety assessment document

International Nuclear Information System (INIS)

Chilton, M.W.; Hill, R.L.; Eubank, B.F.

1980-03-01

The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

EURDYN: computer programs for the nonlinear transient analysis of structures submitted to dynamic loading. EURDYN (Release 3): users' manual

International Nuclear Information System (INIS)

Halleux, J.P.

1983-01-01

The EURDYN computer codes are mainly designed for the simulation of nonlinear dynamic response of fast-reactor compoments submitted to impulse loading due to abnormal working conditions. Two releases of the structural computer codes EURDYN 01 (2-D beams and triangles and axisymmetric conical shells and triangular tores), 02 (axisymmetric and 2-D quadratic isoparametric elements) and 03 (triangular plate elements) have already been produced. They include material (elasto-plasticity using the classical flow theory approach) and geometrical (large displacements and rotations treated by a corotational technique) nonlinearities. The new features of Release 3 roughly consist in: full large strain capability for 9-node isoparametric elements, generalized array dimensions, introduction of the radial return algorithm for elasto-plastic material modelling, extension of the energy check facility to the case of prescribed displacements, and, possible interface to a post-processing package including time plot facilities

BIGIF: fracture mechanics code for structures. Manual 1: introduction and theoretical background

International Nuclear Information System (INIS)

Besuner, P.M.; Rau, S.A.; Davis, C.S.; Rogers, G.W.; Grover, J.L.; Peters, D.C.

1981-04-01

This report is a general description manual documenting the current version of BIGIF, a computer program designed to calculate cracked growth in a flawed structure. The first of three, this manual provides a general understanding of the program's present capabilities and includes enough information to decide whether or not to use BIGIF

User's manual for SPLPLOT-2: a computer code for data plotting and editing in conversational mode

International Nuclear Information System (INIS)

Muramatsu, Ken; Matsumoto, Kiyoshi; Kohsaka, Atsuo; Maniwa, Masaki.

1985-07-01

The computer code SPLPLOT-2 for plotting and data editing has been developed as a part of the code package: SPLPACK-1. The SPLPLOT-2 code has capabilities of both conversational and batch processings. This report describes the user's manual for SPLPLOT-2. The following improvements have been made in the SPLPLOT-2. (1) It has capabilities of both conversational and batch processings, (2) function of conversion of files from the input SPL (Standard PLotter) files to internal work files have been implemented to reduce number of time consuming access to the input SPL files, (3) user supplied subroutines can be assigned for data editing from the SPL files, (4) in addition to the two-dimensional graphs, streamline graphs, contour line graphs and bird's-eye view graphs can be drawn. (author)

Computer programs for capital cost estimation, lifetime economic performance simulation, and computation of cost indexes for laser fusion and other advanced technology facilities

International Nuclear Information System (INIS)

Pendergrass, J.H.

1978-01-01

Three FORTRAN programs, CAPITAL, VENTURE, and INDEXER, have been developed to automate computations used in assessing the economic viability of proposed or conceptual laser fusion and other advanced-technology facilities, as well as conventional projects. The types of calculations performed by these programs are, respectively, capital cost estimation, lifetime economic performance simulation, and computation of cost indexes. The codes permit these three topics to be addressed with considerable sophistication commensurate with user requirements and available data

Manual for reactor produced radioisotopes

International Nuclear Information System (INIS)

2003-01-01

numerous new developments that have taken place since then. Hence in this manual it was decided to focus only on reactor produced radioisotopes. This manual contains procedures for 48 important reactor-produced isotopes. These were contributed by major radioisotope producers from different parts of the world and are based on their practical experience. In case of widely used radioisotopes such as 131 I, 32 P and 99 Mo, information from more than one centre is included so that the users can compare the procedures. As in the earlier two versions, a general introductory write-up is included covering basic information on related aspects such as target irradiation, handling facilities, radiation protection and transportation, but in less detail. Relevant IAEA publications on such matters, particularly related to radiation protection and transportation, should be referred to for guidelines. Similarly, the nuclear data contained in the manual are only indicative and the relevant databases should be referred to for more authentic values. It is hoped that the manual will be a useful source of information for those working in radioisotope production laboratories as well as those intending to initiate such activities

FFTF fission gas monitor computer system

International Nuclear Information System (INIS)

Hubbard, J.A.

1987-01-01

The Fast Flux Test Facility (FFTF) is a liquid-metal-cooled test reactor located on the Hanford site. A dual computer system has been developed to monitor the reactor cover gas to detect and characterize any fuel or test pin fission gas releases. The system acquires gamma spectra data, identifies isotopes, calculates specific isotope and overall cover gas activity, presents control room alarms and displays, and records and prints data and analysis reports. The fission gas monitor system makes extensive use of commercially available hardware and software, providing a reliable and easily maintained system. The design provides extensive automation of previous manual operations, reducing the need for operator training and minimizing the potential for operator error. The dual nature of the system allows one monitor to be taken out of service for periodic tests or maintenance without interrupting the overall system functions. A built-in calibrated gamma source can be controlled by the computer, allowing the system to provide rapid system self tests and operational performance reports

Airport Information Retrieval System (AIRS) System Support Manual

Science.gov (United States)

1973-01-01

This handbook is a support manual for prototype air traffic flow control automation system developed for the FAA's Systems Command Center. The system is implemented on a time-sharing computer and is designed to provide airport traffic load prediction...

Computer-aided and manual quantifications of MRI synovitis, bone marrow edema-like lesions, erosion and cartilage loss in rheumatoid arthritis of the wrist

Energy Technology Data Exchange (ETDEWEB)

Yang, Haitao [The First Affiliated Hospital of Chongqing Medical University, Department of Radiology, Chongqing (China); University of California, San Francisco (UCSF), Department of Radiology and Biomedical Imaging, San Francisco, CA (United States); Rivoire, Julien; Hoppe, Michael; Link, Thomas M.; Li, Xiaojuan [University of California, San Francisco (UCSF), Department of Radiology and Biomedical Imaging, San Francisco, CA (United States); Srikhum, Waraporn [University of California, San Francisco (UCSF), Department of Radiology and Biomedical Imaging, San Francisco, CA (United States); Thammasat University, Department of Radiology, Pathumthani (Thailand); Imboden, John [San Francisco General Hospital, University of California, Department of Medicine, San Francisco and Division of Rheumatology, San Francisco, CA (United States)

2014-12-10

To investigate the reliability and validity of computer-aided automated and manual quantification as well as semiquantitative analysis for MRI synovitis, bone marrow edema-like lesions, erosion and cartilage loss of the wrist in rheumatoid arthritis (RA) compared to the OMERACT-RAMRIS. Wrist MRI was performed at 3 T in 16 patients with RA. Synovial volume and perfusion, bone marrow edema-like lesion (BMEL) volume, signal intensity and perfusion, and erosion dimensions were measured manually and using an in-house-developed automated software algorithm; findings were correlated with the OMERAC-RAMRIS gradings. In addition, a semiquantitative MRI cartilage loss score system was developed. Intraclass correlation coefficients (ICCs) were used to test the reproducibility of these quantitative and semiquantitative techniques. Spearman correlation coefficients were calculated between lesion quantifications and RAMRIS and between the MRI cartilage score and radiographic Sharp van der Heijde joint space narrowing scores. The intra- and interobserver ICCs were excellent for synovial, BMEL and erosion quantifications and cartilage loss grading (all >0.89). The synovial volume, BMEL volume and signal intensity, and erosion dimensions were significantly correlated with the corresponding RAMRIS (r = 0.727 to 0.900, p < 0.05). Synovial perfusion parameter maximum enhancement (Emax) was significantly correlated with synovitis RAMRIS (r = 0.798). BMEL perfusion parameters were not correlated with the RAMRIS BME score. Cartilage loss gradings from MRI were significantly correlated with the Sharp joint space narrowing scores (r = 0.635, p = 0.008). The computer-aided, manual and semiquantitative methods presented in this study can be used to evaluate MRI pathologies in RA with excellent reproducibility. Significant correlations with standard RAMRIS were found in the measurements using these methods. (orig.)

User's manual for computer program BASEPLOT

Science.gov (United States)

Sanders, Curtis L.

2002-01-01

The checking and reviewing of daily records of streamflow within the U.S. Geological Survey is traditionally accomplished by hand-plotting and mentally collating tables of data. The process is time consuming, difficult to standardize, and subject to errors in computation, data entry, and logic. In addition, the presentation of flow data on the internet requires more timely and accurate computation of daily flow records. BASEPLOT was developed for checking and review of primary streamflow records within the U.S. Geological Survey. Use of BASEPLOT enables users to (1) provide efficiencies during the record checking and review process, (2) improve quality control, (3) achieve uniformity of checking and review techniques of simple stage-discharge relations, and (4) provide a tool for teaching streamflow computation techniques. The BASEPLOT program produces tables of quality control checks and produces plots of rating curves and discharge measurements; variable shift (V-shift) diagrams; and V-shifts converted to stage-discharge plots, using data stored in the U.S. Geological Survey Automatic Data Processing System database. In addition, the program plots unit-value hydrographs that show unit-value stages, shifts, and datum corrections; input shifts, datum corrections, and effective dates; discharge measurements; effective dates for rating tables; and numeric quality control checks. Checklist/tutorial forms are provided for reviewers to ensure completeness of review and standardize the review process. The program was written for the U.S. Geological Survey SUN computer using the Statistical Analysis System (SAS) software produced by SAS Institute, Incorporated.

Revegetation manual for the environmental restoration contractor

International Nuclear Information System (INIS)

McLendon, T.; Redente, E.F.

1997-02-01

The purpose of this manual is to provide guidance and general guidelines for the revegetation of remediation waste sites and other disturbed areas on the Hanford Site. Specific revegetation plans will be developed using guidance from this manual. Locations, resources, and funding will dictate the specific revegetation design at each disturbed area. Disturbances have occurred to some of the ecological communities of the Hanford Site. Many of these disturbances are the result of operations of the Hanford Site, including Comprehensive Environmental Response, Compensation, and Liability Act of 1980 waste sites on small portions of the Hanford Site. There were, however, extensive disturbances to the native vegetation prior to operations of the facility. These resulted from cultivation, grazing, fire, and the introduction of exotics. Revegetation planning must take into account these early disturbances, as well as the later ones

Revegetation manual for the environmental restoration contractor

Energy Technology Data Exchange (ETDEWEB)

McLendon, T.; Redente, E.F.

1997-02-01

The purpose of this manual is to provide guidance and general guidelines for the revegetation of remediation waste sites and other disturbed areas on the Hanford Site. Specific revegetation plans will be developed using guidance from this manual. Locations, resources, and funding will dictate the specific revegetation design at each disturbed area. Disturbances have occurred to some of the ecological communities of the Hanford Site. Many of these disturbances are the result of operations of the Hanford Site, including Comprehensive Environmental Response, Compensation, and Liability Act of 1980 waste sites on small portions of the Hanford Site. There were, however, extensive disturbances to the native vegetation prior to operations of the facility. These resulted from cultivation, grazing, fire, and the introduction of exotics. Revegetation planning must take into account these early disturbances, as well as the later ones.

Computer Security at Nuclear Facilities (French Edition)

International Nuclear Information System (INIS)

2013-01-01

category of the IAEA Nuclear Security Series, and deals with computer security at nuclear facilities. It is based on national experience and practices as well as publications in the fields of computer security and nuclear security. The guidance is provided for consideration by States, competent authorities and operators. The preparation of this publication in the IAEA Nuclear Security Series has been made possible by the contributions of a large number of experts from Member States. An extensive consultation process with all Member States included consultants meetings and open-ended technical meetings. The draft was then circulated to all Member States for 120 days to solicit further comments and suggestions. The comments received from Member States were reviewed and considered in the final version of the publication.

Information Manual: Procedures, Planning Concepts, Subsystems. ABS Publication No. 3.

Science.gov (United States)

California Univ., Berkeley.

This report, the third in a series which presents the results of a systems analysis of the problem of providing science and engineering buildings at the university level, is a technical manual for using the Academic Building Systems (ABS) approach in programing, designing, and constructing such facilities. The document presents (1) planning…

Laboratory training manual on radioimmunoassay in animal reproduction

International Nuclear Information System (INIS)

1984-01-01

Reproduction must always be regarded as one of the major limiting factors in animal production and many of the modern methods for improving reproduction rely heavily on the ability to measure hormone levels in blood and milk. This has produced a world-wide demand for laboratory facilities to carry out hormone assays and the need for specialist training to allow these assays to be undertaken. The need to measure nanogram and picogram quantities and the use of radionuclides require a good deal of skill and care and this Manual has been prepared to aid training and provide the sort of information that rarely appears in scientific papers. It represents a further step in the Joint FAO/IAEA Division's series of Laboratory Training Manuals, and has been designed to aid training programmes of the type carried out during the Joint FAO/IAEA Interregional Training Course on Radioimmunoassay and its Application in Research on Animal Reproduction at Cornell University in July 1982. Many of the laboratory exercises described in this Manual are based on those conducted during the course

Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

International Nuclear Information System (INIS)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E.; Tills, J.

1997-12-01

The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions

Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

Energy Technology Data Exchange (ETDEWEB)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E. [Sandia National Labs., Albuquerque, NM (United States); Tills, J. [J. Tills and Associates, Inc., Sandia Park, NM (United States)

1997-12-01

The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions.

FIRAC - a computer code to predict fire accident effects in nuclear facilities

International Nuclear Information System (INIS)

Bolstad, J.W.; Foster, R.D.; Gregory, W.S.

1983-01-01

FIRAC is a medium-sized computer code designed to predict fire-induced flows, temperatures, and material transport within the ventilating systems and other airflow pathways in nuclear-related facilities. The code is designed to analyze the behavior of interconnected networks of rooms and typical ventilation system components. This code is one in a family of computer codes that is designed to provide improved methods of safety analysis for the nuclear industry. The structure of this code closely follows that of the previously developed TVENT and EVENT codes. Because a lumped-parameter formulation is used, this code is particularly suitable for calculating the effects of fires in the far field (that is, in regions removed from the fire compartment), where the fire may be represented parametrically. However, a fire compartment model to simulate conditions in the enclosure is included. This model provides transport source terms to the ventilation system that can affect its operation and in turn affect the fire. A basic material transport capability that features the effects of convection, deposition, entrainment, and filtration of material is included. The interrelated effects of filter plugging, heat transfer, gas dynamics, and material transport are taken into account. In this paper the authors summarize the physical models used to describe the gas dynamics, material transport, and heat transfer processes. They also illustrate how a typical facility is modeled using the code

Potential applications of artificial intelligence in computer-based management systems for mixed waste incinerator facility operation

International Nuclear Information System (INIS)

Rivera, A.L.; Singh, S.P.N.; Ferrada, J.J.

1991-01-01

The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site, designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conversion and Recovery Act (RCRA). Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. This presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. This paper describes mixed waste incinerator facility performance-oriented tasks that could be assisted by Artificial Intelligence (AI) and the requirements for AI tools that would implement these algorithms in a computer-based system. 4 figs., 1 tab

Comparison of manual and automatic MR-CT registration for radiotherapy of prostate cancer.

Science.gov (United States)

Korsager, Anne Sofie; Carl, Jesper; Riis Østergaard, Lasse

2016-05-08

In image-guided radiotherapy (IGRT) of prostate cancer, delineation of the clini-cal target volume (CTV) often relies on magnetic resonance (MR) because of its good soft-tissue visualization. Registration of MR and computed tomography (CT) is required in order to add this accurate delineation to the dose planning CT. An automatic approach for local MR-CT registration of the prostate has previously been developed using a voxel property-based registration as an alternative to a manual landmark-based registration. The aim of this study is to compare the two registration approaches and to investigate the clinical potential for replacing the manual registration with the automatic registration. Registrations and analysis were performed for 30 prostate cancer patients treated with IGRT using a Ni-Ti prostate stent as a fiducial marker. The comparison included computing translational and rotational differences between the approaches, visual inspection, and computing the overlap of the CTV. The computed mean translational difference was 1.65, 1.60, and 1.80mm and the computed mean rotational difference was 1.51°, 3.93°, and 2.09° in the superior/inferior, anterior/posterior, and medial/lateral direction, respectively. The sensitivity of overlap was 87%. The results demonstrate that the automatic registration approach performs registrations comparable to the manual registration.

Transuranic waste characterization sampling and analysis methods manual. Revision 1

International Nuclear Information System (INIS)

Suermann, J.F.

1996-04-01

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits

The insertion device magnetic measurement facility: Prototype and operational procedures

International Nuclear Information System (INIS)

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

1993-03-01

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

Peace Corps Aquaculture Training Manual. Training Manual T0057.

Science.gov (United States)

Peace Corps, Washington, DC. Information Collection and Exchange Div.

This Peace Corps training manual was developed from two existing manuals to provide a comprehensive training program in fish production for Peace Corps volunteers. The manual encompasses the essential elements of the University of Oklahoma program that has been training volunteers in aquaculture for 25 years. The 22 chapters of the manual are…

Micro computed tomography features of laryngeal fractures in a case of fatal manual strangulation.

Science.gov (United States)

Fais, Paolo; Giraudo, Chiara; Viero, Alessia; Miotto, Diego; Bortolotti, Federica; Tagliaro, Franco; Montisci, Massimo; Cecchetto, Giovanni

2016-01-01

Cases of subtle fatal neck compression are often complicated by the lack of specificity of the post-mortem signs of asphyxia and by the lack of clear signs of neck compression. Herein we present a forensic case of a 45-year-old schizophrenic patient found on the floor of the bedroom of a psychiatric ward in cardiopulmonary arrest and who died after two days in a vegetative state. The deposition of the roommate of the deceased, who claimed responsibility for the killing of the victim by neck compression, was considered unreliable by the prosecutor. Autopsy, toxicological analyses, and multi-slice computed tomography (MSCT), micro computed tomography (micro-CT) and histology of the larynx complex were performed. Particularly, micro-CT analysis of the thyroid cartilage revealed the bilateral presence of ossified triticeous cartilages and the complete fragmentation of the right superior horn of the thyroid, but it additionally demonstrated a fracture on the contralateral superior horns, which was not clearly diagnosable at MSCT. On the basis of the evidence of intracartilaginous laryngeal hemorrhages and bilateral microfracture at the base of the superior horns of the larynx, the death was classified as a case of asphyxia due to manual strangulation. Micro-CT was confirmed as a useful tool in cases of subtle fatal neck compression, for the detection of minute laryngeal cartilage fractures, especially in complex cases with equivocal findings on MSCT. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

Dounreay Shuffler diagnostic software operations manual

International Nuclear Information System (INIS)

Eccleston, G.W.; Stuewe, B.; Klosterbuer, S.; Van Lyssel, T.

1985-07-01

This operations manual describes the test software for the Dounreay Shuffler. The Shuffler is an assay system, controlled by a Commodore PET computer, that measures the plutonium content in leached hulls at the fuel reprocessing plant in Dounreay, Scotland. The Shuffler contains a 252 Cf neutron source that is moved between storage and irradiation locations to obtain measurement data. A stepping motor control (SMC) module operates the Shuffler and accepts commands from the PET to move the source. This manual briefly describes the Shuffler and provides details on running and using the diagnostic software program. The communications protocol for message transmittal between the PET and SMC is defined and a detailed example of message sending is presented in an appendix

Burnup calculations for KIPT accelerator driven subcritical facility using Monte Carlo computer codes-MCB and MCNPX

International Nuclear Information System (INIS)

Gohar, Y.; Zhong, Z.; Talamo, A.

2009-01-01

Argonne National Laboratory (ANL) of USA and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the conceptual design development of an electron accelerator driven subcritical (ADS) facility, using the KIPT electron accelerator. The neutron source of the subcritical assembly is generated from the interaction of 100 KW electron beam with a natural uranium target. The electron beam has a uniform spatial distribution and electron energy in the range of 100 to 200 MeV. The main functions of the subcritical assembly are the production of medical isotopes and the support of the Ukraine nuclear power industry. Neutron physics experiments and material structure analyses are planned using this facility. With the 100 KW electron beam power, the total thermal power of the facility is ∼375 kW including the fission power of ∼260 kW. The burnup of the fissile materials and the buildup of fission products reduce continuously the reactivity during the operation, which reduces the neutron flux level and consequently the facility performance. To preserve the neutron flux level during the operation, fuel assemblies should be added after long operating periods to compensate for the lost reactivity. This process requires accurate prediction of the fuel burnup, the decay behavior of the fission produces, and the introduced reactivity from adding fresh fuel assemblies. The recent developments of the Monte Carlo computer codes, the high speed capability of the computer processors, and the parallel computation techniques made it possible to perform three-dimensional detailed burnup simulations. A full detailed three-dimensional geometrical model is used for the burnup simulations with continuous energy nuclear data libraries for the transport calculations and 63-multigroup or one group cross sections libraries for the depletion calculations. Monte Carlo Computer code MCNPX and MCB are utilized for this study. MCNPX transports the electrons and the

High resolution muon computed tomography at neutrino beam facilities

International Nuclear Information System (INIS)

Suerfu, B.; Tully, C.G.

2016-01-01

X-ray computed tomography (CT) has an indispensable role in constructing 3D images of objects made from light materials. However, limited by absorption coefficients, X-rays cannot deeply penetrate materials such as copper and lead. Here we show via simulation that muon beams can provide high resolution tomographic images of dense objects and of structures within the interior of dense objects. The effects of resolution broadening from multiple scattering diminish with increasing muon momentum. As the momentum of the muon increases, the contrast of the image goes down and therefore requires higher resolution in the muon spectrometer to resolve the image. The variance of the measured muon momentum reaches a minimum and then increases with increasing muon momentum. The impact of the increase in variance is to require a higher integrated muon flux to reduce fluctuations. The flux requirements and level of contrast needed for high resolution muon computed tomography are well matched to the muons produced in the pion decay pipe at a neutrino beam facility and what can be achieved for momentum resolution in a muon spectrometer. Such an imaging system can be applied in archaeology, art history, engineering, material identification and whenever there is a need to image inside a transportable object constructed of dense materials

Computer control and monitoring of neutral beam injectors on the 2XIIB CTR experiment at LLL

International Nuclear Information System (INIS)

Pollock, G.G.

1975-01-01

The original manual control system for the 12 neutral beam injectors on the 2XIIB Machine is being integrated with a computer control system. This, in turn, is a part of a multiple computer network comprised of the three computers which are involved in the operation and instrumentation of the 2XIIB experiment. The computer control system simplifies neutral beam operation and centralizes it to a single operating position. A special purpose console utilizes computer generated graphics and interactive function entry buttons to optimize the human/machine interface. Through the facilities of the computer network, a high level control function will be implemented for the use of the experimenter in a remotely located experiment diagnositcs area. In addition to controlling the injectors in normal operation, the computer system provides automatic conditioning of the injectors, bringing rebuilt units back to full energy output with minimum loss of useful life. The computer system also provides detail archive data recording

QRev—Software for computation and quality assurance of acoustic doppler current profiler moving-boat streamflow measurements—Technical manual for version 2.8

Science.gov (United States)

Mueller, David S.

2016-06-21

The software program, QRev applies common and consistent computational algorithms combined with automated filtering and quality assessment of the data to improve the quality and efficiency of streamflow measurements and helps ensure that U.S. Geological Survey streamflow measurements are consistent, accurate, and independent of the manufacturer of the instrument used to make the measurement. Software from different manufacturers uses different algorithms for various aspects of the data processing and discharge computation. The algorithms used by QRev to filter data, interpolate data, and compute discharge are documented and compared to the algorithms used in the manufacturers’ software. QRev applies consistent algorithms and creates a data structure that is independent of the data source. QRev saves an extensible markup language (XML) file that can be imported into databases or electronic field notes software. This report is the technical manual for version 2.8 of QRev.

A personal computer code for seismic evaluations of nuclear power plant facilities

International Nuclear Information System (INIS)

Xu, J.; Graves, H.

1991-01-01

In the process of review and evaluation of licensing issues related to nuclear power plants, it is essential to understand the behavior of seismic loading, foundation and structural properties and their impact on the overall structural response. In most cases, such knowledge could be obtained by using simplified engineering models which, when properly implemented, can capture the essential parameters describing the physics of the problem. Such models do not require execution on large computer systems and could be implemented through a personal computer (PC) based capability. Recognizing the need for a PC software package that can perform structural response computations required for typical licensing reviews, the US Nuclear Regulatory Commission sponsored the development of a PC operated computer software package CARES (Computer Analysis for Rapid Evaluation of Structures) system. This development was undertaken by Brookhaven National Laboratory (BNL) during FY's 1988 and 1989. A wide range of computer programs and modeling approaches are often used to justify the safety of nuclear power plants. It is often difficult to assess the validity and accuracy of the results submitted by various utilities without developing comparable computer solutions. Taken this into consideration, CARES is designed as an integrated computational system which can perform rapid evaluations of structural behavior and examine capability of nuclear power plant facilities, thus CARES may be used by the NRC to determine the validity and accuracy of analysis methodologies employed for structural safety evaluations of nuclear power plants. CARES has been designed to operate on a PC, have user friendly input/output interface, and have quick turnaround. This paper describes the various features which have been implemented into the seismic module of CARES version 1.0

A personal computer code for seismic evaluations of nuclear power plant facilities

International Nuclear Information System (INIS)

Xu, J.; Graves, H.

1990-01-01

A wide range of computer programs and modeling approaches are often used to justify the safety of nuclear power plants. It is often difficult to assess the validity and accuracy of the results submitted by various utilities without developing comparable computer solutions. Taken this into consideration, CARES is designed as an integrated computational system which can perform rapid evaluations of structural behavior and examine capability of nuclear power plant facilities, thus CARES may be used by the NRC to determine the validity and accuracy of analysis methodologies employed for structural safety evaluations of nuclear power plants. CARES has been designed to: operate on a PC, have user friendly input/output interface, and have quick turnaround. The CARES program is structured in a modular format. Each module performs a specific type of analysis. The basic modules of the system are associated with capabilities for static, seismic and nonlinear analyses. This paper describes the various features which have been implemented into the Seismic Module of CARES version 1.0. In Section 2 a description of the Seismic Module is provided. The methodologies and computational procedures thus far implemented into the Seismic Module are described in Section 3. Finally, a complete demonstration of the computational capability of CARES in a typical soil-structure interaction analysis is given in Section 4 and conclusions are presented in Section 5. 5 refs., 4 figs

Internal environmental protection audits: a suggested guide for US Department of Energy facilities

International Nuclear Information System (INIS)

Barisas, S.; Polich, J.; Habegger, L.; Surles, T.

1983-08-01

This manual has been prepared for use by any DOE facility as an aid for conducting an internal environmental-protection audit. The manual is organized in modular format, with each module covering a separate area of environmental protection. The questions within each module were developed from existing DOE orders, executive orders, federal statutes, and Environmental Protection Agency (EPA) regulations issued pursuant to specific environmental legislation. A bibliography of such legislation is included at the end of this section. Each module also includes questions about a facility's use of industrial standards of practice

APUD - User's manual

International Nuclear Information System (INIS)

Vamanu, D.

1989-04-01

APUD is a computed code designed for rough, expeditious assessments of the dispersal of airborne radioactivity discharged, either normally or accidentally, from nuclear facilities. In particular codes such as APUD may aptly complement the tool-kit required in the adoption of informed contingency plans in case of abnormal nuclear occurences that are accompanied by atmospheric releases of radioactivity. Apart from such extreme circumstances, APUD may profitable be used a a simulation/drill facility. Given adequate inputs, APUD may also work on any sort of industrial atmospheric emissions.(author)

Savannah River Plant californium-252 Shuffler electronics manual

International Nuclear Information System (INIS)

Bourret, S.C.; Crane, T.W.; Eccleston, G.W.; Gallegos, E.A.; Garcia, D.L.

1980-03-01

Detailed information is presented in this report, an electronics manual for the Savannah River Plant Shuffler, about the electronics associated with the various control and data acquisition functions of the Shuffler subsystems. Circuit diagrams, interconnection information, and details about computer control and programming are included

Manual on JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

1977-05-01

A manual on the revised JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI which complements the library installed for FACOM 230-75 computer. It is subject to further extension in the future, since the present one is still insufficient for scientific calculations. (auth.)

NJOY nuclear data processing system: user's manual

International Nuclear Information System (INIS)

MacFarlane, R.E.; Barrett, R.J.; Muir, D.W.; Boicourt, R.M.

1978-12-01

The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections for neutron and photon transport calculations from ENDF/B-IV and -V evaluated nuclear data. This user's manual provides a concise description of the code, input instructions, sample problems, and installation instructions. 1 figure, 3 tables

Upgrading of the AMS facility at the Koffler 14UD Pelletron accelerator

CERN Document Server

Berkovits, D; Bordeanu, C; Ghelberg, S; Hass, M; Heber, O; Paul, M; Shahar, Y; Verri, G; 10.1016/j.nimb.2004.04.033

2004-01-01

The AMS facility based on a 14UD Pelletron tandem accelerator has been upgraded in recent years to support an active and diversified research program. A new dedicated AMS ion source beam line merging at 45 degrees with the existing injection line through a 45 degrees electrostatic deflector is in operation. The multi-sample high- intensity Cs sputter ion source stands on a separate 120 kV platform and is remote-controlled through a hybrid infrared-fiber-optics link operated either manually or by the accelerator-control computer, ensuring safe and reliable operation. Independent current preamplifiers are used in Faraday cup current readings down to the pA range. The accelerator computer-control system was upgraded to Lab View 6.1, allowing a PC server to control and read out all hardware components while one or more remote PC clients run the AMS software. Ad hoc sequences of commands, written in a script macro language, are run from a client computer to perform an automated AMS measurement. The present capabil...

Towards full automation of accelerators through computer control

CERN Document Server

Gamble, J; Kemp, D; Keyser, R; Koutchouk, Jean-Pierre; Martucci, P P; Tausch, Lothar A; Vos, L

1980-01-01

The computer control system of the Intersecting Storage Rings (ISR) at CERN has always laid emphasis on two particular operational aspects, the first being the reproducibility of machine conditions and the second that of giving the operators the possibility to work in terms of machine parameters such as the tune. Already certain phases of the operation are optimized by the control system, whilst others are automated with a minimum of manual intervention. The authors describe this present control system with emphasis on the existing automated facilities and the features of the control system which make it possible. It then discusses the steps needed to completely automate the operational procedure of accelerators. (7 refs).

Towards full automation of accelerators through computer control

International Nuclear Information System (INIS)

Gamble, J.; Hemery, J.-Y.; Kemp, D.; Keyser, R.; Koutchouk, J.-P.; Martucci, P.; Tausch, L.; Vos, L.

1980-01-01

The computer control system of the Intersecting Storage Rings (ISR) at CERN has always laid emphasis on two particular operational aspects, the first being the reproducibility of machine conditions and the second that of giving the operators the possibility to work in terms of machine parameters such as the tune. Already certain phases of the operation are optimized by the control system, whilst others are automated with a minimum of manual intervention. The paper describes this present control system with emphasis on the existing automated facilities and the features of the control system which make it possible. It then discusses the steps needed to completely automate the operational procedure of accelerators. (Auth.)

GASFLOW-MPI. A scalable computational fluid dynamics code for gases, aerosols and combustion. Vol. 2. Users' manual (Revision 1.0)

Energy Technology Data Exchange (ETDEWEB)

Xiao, Jianjun; Travis, Jack; Royl, Peter; Necker, Gottfried; Svishchev, Anatoly; Jordan, Thomas

2016-07-01

Karlsruhe Institute of Technology (KIT) is developing the parallel computational fluid dynamics code GASFLOW-MPI as a best-estimate tool for predicting transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facility buildings. GASFLOW-MPI is a finite-volume code based on proven computational fluid dynamics methodology that solves the compressible Navier-Stokes equations for three-dimensional volumes in Cartesian or cylindrical coordinates.

RADTRAN 6 Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Weiner, Ruth F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Neuhauser, Karen Sieglinde [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Heames, Terence John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); O' Donnell, Brandon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dennis, Matthew L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-01-01

This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

RADTRAN 6 technical manual.

Energy Technology Data Exchange (ETDEWEB)

Weiner, Ruth F.; Neuhauser, Karen Sieglinde; Heames, Terence John; O' Donnell, Brandon M.; Dennis, Matthew L.

2014-01-01

This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

Research Facilities | Wind | NREL

Science.gov (United States)

Research Facilities Research Facilities NREL's state-of-the-art wind research facilities at the Research Facilities Photo of five men in hard hards observing the end of a turbine blade while it's being tested. Structural Research Facilities A photo of two people silhouetted against a computer simulation of

BRIT manual after loading brachytherapy kit for intracavitary: initial experience

International Nuclear Information System (INIS)

Aggarwal, Lalit M.; Mandal, Abhijit; Asthana, Anupam K.; Shahi, Uday P.; Pradhan, Satyajit

2007-01-01

Brachytherapy continues to serve as an important and rapidly evolving tool in the management of cancer. Technological developments in the last two decades have dramatic impact on the safe practice of brachytherapy. A wide range of brachytherapy sources and equipment are available for new therapeutic possibilities. However, decision making with regard to new brachytherapy facilities are need based and depend on the patient load, socioeconomic status of the patients, and funds available with the institution. Remote afterloading equipments are fast replacing the Manual After Loading (MAL) systems. However, keeping in view the large number of patients, who can not afford expensive treatment, the utility of manual after loading system which is inexpensive, cannot be ignored

COMPUTING

CERN Multimedia

I. Fisk

2011-01-01

Introduction CMS distributed computing system performed well during the 2011 start-up. The events in 2011 have more pile-up and are more complex than last year; this results in longer reconstruction times and harder events to simulate. Significant increases in computing capacity were delivered in April for all computing tiers, and the utilisation and load is close to the planning predictions. All computing centre tiers performed their expected functionalities. Heavy-Ion Programme The CMS Heavy-Ion Programme had a very strong showing at the Quark Matter conference. A large number of analyses were shown. The dedicated heavy-ion reconstruction facility at the Vanderbilt Tier-2 is still involved in some commissioning activities, but is available for processing and analysis. Facilities and Infrastructure Operations Facility and Infrastructure operations have been active with operations and several important deployment tasks. Facilities participated in the testing and deployment of WMAgent and WorkQueue+Request...

Techniques for controlling air pollution from the operation of nuclear facilities. Report of a panel

International Nuclear Information System (INIS)

1966-01-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level.

Comparison of manual and automatic MR‐CT registration for radiotherapy of prostate cancer

Science.gov (United States)

Carl, Jesper; Østergaard, Lasse Riis

2016-01-01

In image‐guided radiotherapy (IGRT) of prostate cancer, delineation of the clinical target volume (CTV) often relies on magnetic resonance (MR) because of its good soft‐tissue visualization. Registration of MR and computed tomography (CT) is required in order to add this accurate delineation to the dose planning CT. An automatic approach for local MR‐CT registration of the prostate has previously been developed using a voxel property‐based registration as an alternative to a manual landmark‐based registration. The aim of this study is to compare the two registration approaches and to investigate the clinical potential for replacing the manual registration with the automatic registration. Registrations and analysis were performed for 30 prostate cancer patients treated with IGRT using a Ni‐Ti prostate stent as a fiducial marker. The comparison included computing translational and rotational differences between the approaches, visual inspection, and computing the overlap of the CTV. The computed mean translational difference was 1.65, 1.60, and 1.80 mm and the computed mean rotational difference was 1.51°, 3.93°, and 2.09° in the superior/inferior, anterior/posterior, and medial/lateral direction, respectively. The sensitivity of overlap was 87%. The results demonstrate that the automatic registration approach performs registrations comparable to the manual registration. PACS number(s): 87.57.nj, 87.61.‐c, 87.57.Q‐, 87.56.J‐ PMID:27167285

High School and Beyond Transcripts Survey (1982). Data File User's Manual. Contractor Report.

Science.gov (United States)

Jones, Calvin; And Others

This data file user's manual documents the procedures used to collect and process high school transcripts for a large sample of the younger cohort (1980 sophomores) in the High School and Beyond survey. The manual provides the user with the technical assistance needed to use the computer file and also discusses the following: (1) sample design for…

SYVAC3 manual

International Nuclear Information System (INIS)

Andres, T.H.

2000-01-01

SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and describes their argument lists. It also gives an overview of how routines in the File Reading Package, the Parameter Sampling Package and the Time Series Package can be used by programs outside of SYVAC3. (author)

SYVAC3 manual

Energy Technology Data Exchange (ETDEWEB)

Andres, T.H

2000-07-01

SYVAC3 (Systems Variability Analysis Code, generation 3) is a computer program that implements a method called systems variability analysis to analyze the behaviour of a system in the presence of uncertainty. This method is based on simulating the system many times to determine the variation in behaviour it can exhibit. SYVAC3 specializes in systems representing the transport of contaminants, and has several features to simplify the modelling of such systems. It provides a general tool for estimating environmental impacts from the dispersal of contaminants. This report describes the use and structure of SYVAC3. It is intended for modellers, programmers, operators and reviewers who deal with simulation codes based on SYVAC3. From this manual they can learn how to link a model with SYVAC3, how to set up an input file, and how to extract results from output files. The manual lists the subroutines of SYVAC3 that are available for use by models, and describes their argument lists. It also gives an overview of how routines in the File Reading Package, the Parameter Sampling Package and the Time Series Package can be used by programs outside of SYVAC3. (author)

DOSEFU: Computer application for dose calculation and effluent management in normal operation

International Nuclear Information System (INIS)

Martin Garcia, J. E.; Gonzalvo Manovel, A.; Revuelta Garcia, L.

2002-01-01

DOSEFU is a computer application on Windows that develops the methodology of nuclear power plant Exterior Dose Calculation Manuals (Manuals de Calculo de Dosis al Exterior-MACADE) for calculating doses in normal operation caused by radioactive liquid and gaseous effluents, for the purpose of enforcing the new Spanish Regulation on Health Protection against Ionizing Radiations, Royal Decree 783/2001 resulting from transposition of Directive 96/29/Euratom whereby the basic rules regarding health protection of workers and the population against risks resulting from ionizing radiations are established. In addition to making dose calculations, DOSEFU generates, on a magnetic support, the information regarding radioactive liquid and gaseous effluents that plants must periodically send to the CSN (ELGA format). The computer application has been developed for the specific case of Jose Cabrera NPP, which is called DOEZOR. This application can be easily implemented in any other nuclear or radioactive facility. The application is user-friendly, as the end user inputs data and executes the different modules through keys and dialogue boxes that are enabled by clicking on the mouse (see figures 2, 3, 4 and 5 ), The application runs under Windows 95. Digital Visual Fortran has been used as the development program, as this does not require additional libraries (DLLs), it can be installed in any computer without affecting other programs that are already installed. (Author)

PC/FRAM, Version 3.2 User Manual

International Nuclear Information System (INIS)

Kelley, T.A.; Sampson, T.E.

1999-01-01

This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descenies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S 'chn' and 'SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added in the future. Support for reading and writing CAM files will also be forthcoming. A versatile parameter fde database structure governs all facets of the data analysis. User editing of the parameter sets allows great flexibility in handling data with different isotopic distributions, interfering isotopes, and different acquisition parameters such as energy calibration, and detector type. This manual is intended for the system supervisor or the local user who is to be the resident expert. Excerpts from this manual may also be appropriate for the system operator who will routinely use the instrument

GASFLOW: A computational model to analyze accidents in nuclear containment and facility buildings

International Nuclear Information System (INIS)

Travis, J.R.; Nichols, B.D.; Wilson, T.L.; Lam, K.L.; Spore, J.W.; Niederauer, G.F.

1993-01-01

GASFLOW is a finite-volume computer code that solves the time-dependent, compressible Navier-Stokes equations for multiple gas species. The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting liquids or gases to simulate diffusion or propagating flames in complex geometries of nuclear containment or confinement and facilities' buildings. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. The ventilation system may consist of extensive ductwork, filters, dampers or valves, and fans. Condensation and heat transfer to walls, floors, ceilings, and internal structures are calculated to model the appropriate energy sinks. Solid and liquid aerosol behavior is simulated to give the time and space inventory of radionuclides. The solution procedure of the governing equations is a modified Los Alamos ICE'd-ALE methodology. Complex facilities can be represented by separate computational domains (multiblocks) that communicate through overlapping boundary conditions. The ventilation system is superimposed throughout the multiblock mesh. Gas mixtures and aerosols are transported through the free three-dimensional volumes and the restricted one-dimensional ventilation components as the accident and fluid flow fields evolve. Combustion may occur if sufficient fuel and reactant or oxidizer are present and have an ignition source. Pressure and thermal loads on the building, structural components, and safety-related equipment can be determined for specific accident scenarios. GASFLOW calculations have been compared with large oil-pool fire tests in the 1986 HDR containment test T52.14, which is a 3000-kW fire experiment. The computed results are in good agreement with the observed data

A Computer Simulation to Assess the Nuclear Material Accountancy System of a MOX Fuel Fabrication Facility

International Nuclear Information System (INIS)

Portaix, C.G.; Binner, R.; John, H.

2015-01-01

SimMOX is a computer programme that simulates container histories as they pass through a MOX facility. It performs two parallel calculations: · the first quantifies the actual movements of material that might be expected to occur, given certain assumptions about, for instance, the accumulation of material and waste, and of their subsequent treatment; · the second quantifies the same movements on the basis of the operator's perception of the quantities involved; that is, they are based on assumptions about quantities contained in the containers. Separate skeletal Excel computer programmes are provided, which can be configured to generate further accountancy results based on these two parallel calculations. SimMOX is flexible in that it makes few assumptions about the order and operational performance of individual activities that might take place at each stage of the process. It is able to do this because its focus is on material flows, and not on the performance of individual processes. Similarly there are no pre-conceptions about the different types of containers that might be involved. At the macroscopic level, the simulation takes steady operation as its base case, i.e., the same quantity of material is deemed to enter and leave the simulated area, over any given period. Transient situations can then be superimposed onto this base scene, by simulating them as operational incidents. A general facility has been incorporated into SimMOX to enable the user to create an ''act of a play'' based on a number of operational incidents that have been built into the programme. By doing this a simulation can be constructed that predicts the way the facility would respond to any number of transient activities. This computer programme can help assess the nuclear material accountancy system of a MOX fuel fabrication facility; for instance the implications of applying NRTA (near real time accountancy). (author)

GADRAS-DRF 18.5 User's Manual.

Energy Technology Data Exchange (ETDEWEB)

Horne, Steven M.; Thoreson, Gregory G; Theisen, Lisa A.; Mitchell, Dean J.; Harding, Lee; Amai, Wendy A.

2014-12-01

The Gamma Detector Response and Analysis Software - Detector Response Function (GADRAS-DRF) application computes the response of gamma-ray and neutron detectors to incoming radiation. This manual provides step-by-step procedures to acquaint new users with the use of the application. The capabilities include characterization of detector response parameters, plotting and viewing measured and computed spectra, analyzing spectra to identify isotopes, and estimating source energy distributions from measured spectra. GADRAS-DRF can compute and provide detector responses quickly and accurately, giving users the ability to obtain usable results in a timely manner (a matter of seconds or minutes).

GADRAS-DRF 18.6 User's Manual

Energy Technology Data Exchange (ETDEWEB)

Horne, Steve M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Threat Science; Thoreson, Greg G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Threat Science; Theisen, Lisa A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Threat Science; Mitchell, Dean J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Threat Science; Harding, Lee [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Threat Science; Amai, Wendy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Robotic Security Systems

2016-05-01

The Gamma Detector Response and Analysis Software–Detector Response Function (GADRAS-DRF) application computes the response of gamma-ray and neutron detectors to incoming radiation. This manual provides step-by-step procedures to acquaint new users with the use of the application. The capabilities include characterization of detector response parameters, plotting and viewing measured and computed spectra, analyzing spectra to identify isotopes, and estimating source energy distributions from measured spectra. GADRAS-DRF can compute and provide detector responses quickly and accurately, giving users the ability to obtain usable results in a timely manner (a matter of seconds or minutes).

The users manual and concepts of nuclear materials accounting system

International Nuclear Information System (INIS)

Lee, Byung Du; Jeon, In

1996-03-01

This report is to describe the concepts, operation status and user's manuals of nuclear materials accounting system which was developed to not only make out, report and manage the IAEA accounting reports but also maintain the accounting information. Therefore, facility operator could effectively make use of the accounting system without a special training by using this report. 3 tabs., 15 figs., (Author) .new

Health workers' knowledge of and attitudes towards computer applications in rural African health facilities.

Science.gov (United States)

Sukums, Felix; Mensah, Nathan; Mpembeni, Rose; Kaltschmidt, Jens; Haefeli, Walter E; Blank, Antje

2014-01-01

The QUALMAT (Quality of Maternal and Prenatal Care: Bridging the Know-do Gap) project has introduced an electronic clinical decision support system (CDSS) for pre-natal and maternal care services in rural primary health facilities in Burkina Faso, Ghana, and Tanzania. To report an assessment of health providers' computer knowledge, experience, and attitudes prior to the implementation of the QUALMAT electronic CDSS. A cross-sectional study was conducted with providers in 24 QUALMAT project sites. Information was collected using structured questionnaires. Chi-squared tests and one-way ANOVA describe the association between computer knowledge, attitudes, and other factors. Semi-structured interviews and focus groups were conducted to gain further insights. A total of 108 providers responded, 63% were from Tanzania and 37% from Ghana. The mean age was 37.6 years, and 79% were female. Only 40% had ever used computers, and 29% had prior computer training. About 80% were computer illiterate or beginners. Educational level, age, and years of work experience were significantly associated with computer knowledge (pworkplace. Given the low levels of computer knowledge among rural health workers in Africa, it is important to provide adequate training and support to ensure the successful uptake of electronic CDSSs in these settings. The positive attitudes to computers found in this study underscore that also rural care providers are ready to use such technology.

ASSERT-4 user's manual

International Nuclear Information System (INIS)

Judd, R.A.; Tahir, A.; Carver, M.B.; Stewart, D.G.; Thibeault, P.R.; Rowe, D.S.

1984-09-01

ASSERT-4 is an advanced subchannel code being developed primarily to model single- and two-phase flow and heat transfer in horizontal rod bundles. This manual is intended to facilitate the application of this code to the analysis of flow in reactor fuel channels. It contains a brief description of the thermalhydraulic model and ASSERT-4 solution scheme, and other information required by users. This other information includes a detailed discussion of input data requirements, a sample problem and solution, and information describing how to access and run ASSERT-4 on the Chalk River computers

Nevada Test Site Radiological Control Manual, Revision 1

International Nuclear Information System (INIS)

2010-01-01

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. The NTS is located in Nye County, Nevada. The NTS is located approximately 105 kilometers (65 miles) northwest of Las Vegas. It is a remote facility that covers approximately 3,500 square kilometers (1,375 square miles) of land. The dimensions of the NTS vary from 46 to 56 kilometers (28 to 35 miles) in width (eastern to western border) and from 64 to 88 kilometers (40 to 55 miles) in length (northern to southern border). The NTS is surrounded to the west, north, and east by additional thousands of acres of land withdrawn from the public domain for use as a protected wildlife range and as a military gunnery range. These public exclusion areas comprise the Nellis Air Force Range complex, previously designated as the Nellis Air Force Base Bombing and Gunnery Range, and the Tonopah Test Range. These two areas provide a buffer zone between the test areas and public lands administered by the Federal Bureau of Land

Thoracic manual therapy is not more effective than placebo thoracic manual therapy in patients with shoulder dysfunctions: A systematic review with meta-analysis.

Science.gov (United States)

Bizzarri, Paolo; Buzzatti, Luca; Cattrysse, Erik; Scafoglieri, Aldo

2018-02-01

Manual treatments targeting different regions (shoulder, cervical spine, thoracic spine, ribs) have been studied to deal with patients complaining of shoulder pain. Thoracic manual treatments seem able to produce beneficial effects on this group of patients. However, it is not clear whether the patient improvement is a consequence of thoracic manual therapy or a placebo effect. To compare the efficacy of thoracic manual therapy and placebo thoracic manual treatment for patients with shoulder dysfunction. Electronic databases (MEDLINE, CENTRAL, PEDro, CINAHL, WoS, EMBASE, ERIC) were searched through November 2016. Randomized Controlled Trials assessing pain, mobility and function were selected. The Cochrane bias estimation tool was applied. Outcome results were either extracted or computed from raw data. Meta-analysis was performed for outcomes with low heterogeneity. Four studies were included in the review. The methodology of the included studies was generally good except for one study that was rated as high risk of bias. Meta-analysis showed no significant effect for "pain at present" (SMD -0.02; 95% CI: -0.35, 0.32) and "pain during movement" (SMD -0.12; 95% CI: -0.45, 0.21). There is very low to low quality of evidence that a single session of thoracic manual therapy is not more effective than a single session of placebo thoracic manual therapy in patients with shoulder dysfunction at immediate post-treatment. Copyright © 2017 Elsevier Ltd. All rights reserved.

TRANSWRAP II: problem definition manual

International Nuclear Information System (INIS)

Knittle, D.E.

1981-02-01

The TRANSWRAP II computer code, written in Fortran IV and described in this Problem Definition Manual, was developed to analytically predict the magnitude of pressure pulses of large scale sodium-wate reactions in LMFBR secondary systems. It is currently being used for the Clinch River Breeder Reactor Program. The code provides the options, flexibility and features necessary to consider any system configuration. The code methodology has been validated with the aid of extensive sodium-water reaction test programs

GASFLOW: A Computational Fluid Dynamics Code for Gases, Aerosols, and Combustion, Volume 1: Theory and Computational Model

International Nuclear Information System (INIS)

Nichols, B.D.; Mueller, C.; Necker, G.A.; Travis, J.R.; Spore, J.W.; Lam, K.L.; Royl, P.; Redlinger, R.; Wilson, T.L.

1998-01-01

Los Alamos National Laboratory (LANL) and Forschungszentrum Karlsruhe (FzK) are developing GASFLOW, a three-dimensional (3D) fluid dynamics field code as a best-estimate tool to characterize local phenomena within a flow field. Examples of 3D phenomena include circulation patterns; flow stratification; hydrogen distribution mixing and stratification; combustion and flame propagation; effects of noncondensable gas distribution on local condensation and evaporation; and aerosol entrainment, transport, and deposition. An analysis with GASFLOW will result in a prediction of the gas composition and discrete particle distribution in space and time throughout the facility and the resulting pressure and temperature loadings on the walls and internal structures with or without combustion. A major application of GASFLOW is for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facilities. It has been applied to situations involving transporting and distributing combustible gas mixtures. It has been used to study gas dynamic behavior (1) in low-speed, buoyancy-driven flows, as well as sonic flows or diffusion dominated flows; and (2) during chemically reacting flows, including deflagrations. The effects of controlling such mixtures by safety systems can be analyzed. The code version described in this manual is designated GASFLOW 2.1, which combines previous versions of the United States Nuclear Regulatory Commission code HMS (for Hydrogen Mixing Studies) and the Department of Energy and FzK versions of GASFLOW. The code was written in standard Fortran 90. This manual comprises three volumes. Volume I describes the governing physical equations and computational model. Volume II describes how to use the code to set up a model geometry, specify gas species and material properties, define initial and boundary conditions, and specify different outputs, especially graphical displays. Sample problems are included

Conceptual design of an ALICE Tier-2 centre. Integrated into a multi-purpose computing facility

Energy Technology Data Exchange (ETDEWEB)

Zynovyev, Mykhaylo

2012-06-29

This thesis discusses the issues and challenges associated with the design and operation of a data analysis facility for a high-energy physics experiment at a multi-purpose computing centre. At the spotlight is a Tier-2 centre of the distributed computing model of the ALICE experiment at the Large Hadron Collider at CERN in Geneva, Switzerland. The design steps, examined in the thesis, include analysis and optimization of the I/O access patterns of the user workload, integration of the storage resources, and development of the techniques for effective system administration and operation of the facility in a shared computing environment. A number of I/O access performance issues on multiple levels of the I/O subsystem, introduced by utilization of hard disks for data storage, have been addressed by the means of exhaustive benchmarking and thorough analysis of the I/O of the user applications in the ALICE software framework. Defining the set of requirements to the storage system, describing the potential performance bottlenecks and single points of failure and examining possible ways to avoid them allows one to develop guidelines for selecting the way how to integrate the storage resources. The solution, how to preserve a specific software stack for the experiment in a shared environment, is presented along with its effects on the user workload performance. The proposal for a flexible model to deploy and operate the ALICE Tier-2 infrastructure and applications in a virtual environment through adoption of the cloud computing technology and the 'Infrastructure as Code' concept completes the thesis. Scientific software applications can be efficiently computed in a virtual environment, and there is an urgent need to adapt the infrastructure for effective usage of cloud resources.

Conceptual design of an ALICE Tier-2 centre. Integrated into a multi-purpose computing facility

International Nuclear Information System (INIS)

Zynovyev, Mykhaylo

2012-01-01

This thesis discusses the issues and challenges associated with the design and operation of a data analysis facility for a high-energy physics experiment at a multi-purpose computing centre. At the spotlight is a Tier-2 centre of the distributed computing model of the ALICE experiment at the Large Hadron Collider at CERN in Geneva, Switzerland. The design steps, examined in the thesis, include analysis and optimization of the I/O access patterns of the user workload, integration of the storage resources, and development of the techniques for effective system administration and operation of the facility in a shared computing environment. A number of I/O access performance issues on multiple levels of the I/O subsystem, introduced by utilization of hard disks for data storage, have been addressed by the means of exhaustive benchmarking and thorough analysis of the I/O of the user applications in the ALICE software framework. Defining the set of requirements to the storage system, describing the potential performance bottlenecks and single points of failure and examining possible ways to avoid them allows one to develop guidelines for selecting the way how to integrate the storage resources. The solution, how to preserve a specific software stack for the experiment in a shared environment, is presented along with its effects on the user workload performance. The proposal for a flexible model to deploy and operate the ALICE Tier-2 infrastructure and applications in a virtual environment through adoption of the cloud computing technology and the 'Infrastructure as Code' concept completes the thesis. Scientific software applications can be efficiently computed in a virtual environment, and there is an urgent need to adapt the infrastructure for effective usage of cloud resources.

Hanford Environmental Information System (HEIS) user's manual

International Nuclear Information System (INIS)

1991-10-01

The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. Data stored in the HEIS are collected under several regulatory programs. Currently these include the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the Resource Conservation and Recovery Act of 1976 (RCRA); and the Ground-Water Environmental Surveillance Project, managed by the Pacific Northwest Laboratory. The HEIS is an information system with an inclusive database. The manual, the HEIS User's Manual, describes the facilities available to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines

Estimating boiling water reactor decommissioning costs. A user's manual for the BWR Cost Estimating Computer Program (CECP) software: Draft report for comment

International Nuclear Information System (INIS)

Bierschbach, M.C.

1994-12-01

With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the U.S. Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user's manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personal computer, provides estimates for the cost of decommissioning BWR power stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning

General fire protection guidelines for egyptian nuclear facilities. Vol. 4

Energy Technology Data Exchange (ETDEWEB)

Radhad, S; Hussien, A Z; Hammad, F H [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

The purpose of this paper is to establish the regulatory requirements of that will provide and ensure fire protection of egyptian nuclear facilities. Those facilities that use, handle and store low and/or medium radioactive substances are included. Two or more classes of occupancy are considered to occur in the same building or structure. Fir protection measures and systems were reviewed for three of the egyptian Nuclear facilities. These are egypt first nuclear reactor (ETRR-1) building and systems, hot laboratories buildings and facilities, and the building including the AECL type Is-6500 industrial cobalt-60 gamma irradiator {sup E}gypt`s mega gamma I{sup .} The study includes the outlines of the various aspects of fire protection with a view to define the relevant highlights and scope of egyptian guideline for nuclear installations. The study considers fire protection aspects including the following items: 1- Site selection. 2- General facility design. 3- Fire alarm, detection and suppression systems. (4- Protection for specific areas/control room, cable spreading room, computer room) 5- Fire emergency response planning. 6- Fire water supply. 7- Emergency lighting and communication. 8- Rescue and escape routes. 9- Explosion protection. 10-Manual fire fighting. 11- Security consideration in the interest of fire protection. 12- quality assurance programme. Therefore, first of all the design stage, then during the construction stage, and later during the operation stage, measures must be taken to forestall the risks associated with the outbreak of fire and to ensure that consequences of fire accidents remain limited.

General fire protection guidelines for egyptian nuclear facilities. Vol. 4

International Nuclear Information System (INIS)

Radhad, S.; Hussien, A.Z.; Hammad, F.H.

1996-01-01

The purpose of this paper is to establish the regulatory requirements of that will provide and ensure fire protection of egyptian nuclear facilities. Those facilities that use, handle and store low and/or medium radioactive substances are included. Two or more classes of occupancy are considered to occur in the same building or structure. Fir protection measures and systems were reviewed for three of the egyptian Nuclear facilities. These are egypt first nuclear reactor (ETRR-1) building and systems, hot laboratories buildings and facilities, and the building including the AECL type Is-6500 industrial cobalt-60 gamma irradiator E gypt's mega gamma I . The study includes the outlines of the various aspects of fire protection with a view to define the relevant highlights and scope of egyptian guideline for nuclear installations. The study considers fire protection aspects including the following items: 1- Site selection. 2- General facility design. 3- Fire alarm, detection and suppression systems. 4- Protection for specific areas/control room, cable spreading room, computer room) 5- Fire emergency response planning. 6- Fire water supply. 7- Emergency lighting and communication. 8- Rescue and escape routes. 9- Explosion protection. 10-Manual fire fighting. 11- Security consideration in the interest of fire protection. 12- quality assurance programme. Therefore, first of all the design stage, then during the construction stage, and later during the operation stage, measures must be taken to forestall the risks associated with the outbreak of fire and to ensure that consequences of fire accidents remain limited

Working paper on public steering of privately owned sports facilities

DEFF Research Database (Denmark)

Iversen, Evald Bundgård

This short paper discusses how municipalities can steer privately owned sports facilities. Firstly I analyse why steering of privately owned facilities is an interesting subject. Secondly I discuss what the advantages and drawbacks of using different approaches for steering sports facilities are........ Finally I discuss the methodological challenges of measuring activities in sports facilities – and take a closer look at the advantages and drawbacks of using manual and thermal techniques for registering activity.......This short paper discusses how municipalities can steer privately owned sports facilities. Firstly I analyse why steering of privately owned facilities is an interesting subject. Secondly I discuss what the advantages and drawbacks of using different approaches for steering sports facilities are...

3D-CDTI User Manual v2.1

Science.gov (United States)

Johnson, Walter; Battiste, Vernol

2016-01-01

The 3D-Cockpit Display of Traffic Information (3D-CDTI) is a flight deck tool that presents aircrew with: proximal traffic aircraft location, their current status and flight plan data; strategic conflict detection and alerting; automated conflict resolution strategies; the facility to graphically plan manual route changes; time-based, in-trail spacing on approach. The CDTI is manipulated via a touchpad on the flight deck, and by mouse when presented as part of a desktop flight simulator.

Computer Profile of School Facilities Energy Consumption.

Science.gov (United States)

Oswalt, Felix E.

This document outlines a computerized management tool designed to enable building managers to identify energy consumption as related to types and uses of school facilities for the purpose of evaluating and managing the operation, maintenance, modification, and planning of new facilities. Specifically, it is expected that the statistics generated…

Neuromantic - from semi manual to semi automatic reconstruction of neuron morphology

Directory of Open Access Journals (Sweden)

Darren eMyatt

2012-03-01

Full Text Available The ability to create accurate geometric models of neuronal morphologyis important for understanding the role of shape in informationprocessing. Despite a significant amount of research on automating neuronreconstructions from image stacks obtained via microscopy, in practice mostdata are still collected manually.This paper describes Neuromantic, an open source system for threedimensional digital tracing of neurites. Neuromantic reconstructions arecomparable in quality to those of existing commercial and freeware systemswhile balancing speed and accuracy of manual reconstruction. Thecombination of semi-automatic tracing, intuitive editing, and ability ofvisualising large image stacks on standard computing platforms providesa versatile tool that can help address the reconstructions availabilitybottleneck. Practical considerations for reducing the computational time andspace requirements of the extended algorithm are also discussed.

Development and Evaluation of an Interactive Electronic Laboratory Manual for Cooperative Learning of Medical Histology

Science.gov (United States)

Khalil, Mohammed K.; Kirkley, Debbie L.; Kibble, Jonathan D.

2013-01-01

This article describes the development of an interactive computer-based laboratory manual, created to facilitate the teaching and learning of medical histology. The overarching goal of developing the manual is to facilitate self-directed group interactivities that actively engage students during laboratory sessions. The design of the manual…

PROSA version 4.0 manual

International Nuclear Information System (INIS)

Bicking, U.; Golly, W.; Peter, N.; Seifert, R.

1991-05-01

This report includes a comprehensive manual of the computer program PROSA which illustrate the handling and functioning of PROSA. The manual PROSA 4.0 (FORTRAN 77) describes the PC Version of PROSA including its program moduls. The PROSA program package is a statistical tool to decide on the basis of statistical assumptions whether in a given sequence of material balance periods a loss of material might have occurred. The evaluation of the material balance data is based on statistical test procedures. In the present PROSA Version 4.0 the three tests CUMUF test, PAGE's test and GEMUF test are applied to a sequence of material balances. PROSA Version 4.0 supports a real sequential evaluation. That means, PROSA is not only able to evaluate a series of MUF values sequentially after the campaign has finished, but also real sequentially during the campaign. PROSA Version 4.0 is a menu-guided computer program. Data input can be performed either by diskette or by key-enter. Result output is primarily an information whether or not an alarm is indicated. This information can be displayed either numerically or graphically. Therefore, a comfortable graphical output utility is attached to PROSA 4.0. The program moduls are compiled and linked with the Ryan Mc-Farland Compiler. The PROSA graphical utility uses the PLOT88 Library of Plotworks, Inc. (orig./HP) [de

Environment, safety and health progress assessment manual

International Nuclear Information System (INIS)

1992-12-01

On June 27, 1989, the Secretary of Energy announced a 10-Point Initiative to strengthen environment, safety, and health (ES ampersand H) programs, and waste management activities at DOE production, research, and testing facilities. One of the points involved conducting dent Tiger Team Assessments of DOE operating facilities. The Office of Special independent Projects (OSP), EH-5, in the Office of the Assistant Secretary for Environment, Safety and Health, EH-1, was assigned the responsibility to conduct the Tiger Team Assessments. Through June 1992, a total of 35 Tiger Team Assessments were completed. The Secretary directed that Corrective Action Plans be developed and implemented to address the concerns identified by the Tiger Teams. In March 1991, the Secretary approved a plan for assessments that are ''more focused, concentrating on ES ampersand H management, ES ampersand H corrective actions, self-assessment programs, and root-cause related issues.'' In July 1991, the Secretary approved the initiation of ES ampersand H Progress Assessments, as a followup to the Tiger Team Assessments, and in the continuing effort to institutionalize the self-assessment process and line management accountability in the ES ampersand H areas. This manual documents the processes to be used to perform the ES ampersand H Progress Assessments. It was developed based upon the lessons learned from Tiger Team Assessments, the two pilot Progress Assessments, and Progress Assessments that have been completed. The manual will be updated periodically to reflect lessons learned or changes in policy

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-17

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

Future Computer Requirements for Computational Aerodynamics

Science.gov (United States)

1978-01-01

Recent advances in computational aerodynamics are discussed as well as motivations for and potential benefits of a National Aerodynamic Simulation Facility having the capability to solve fluid dynamic equations at speeds two to three orders of magnitude faster than presently possible with general computers. Two contracted efforts to define processor architectures for such a facility are summarized.

Licence applications for low and intermediate level waste predisposal facilities: A manual for operators

International Nuclear Information System (INIS)

2009-07-01

This publication covers all predisposal waste management facilities and practices for receipt, pretreatment (sorting, segregation, characterization), treatment, conditioning, internal relocation and storage of low and intermediate level radioactive waste, including disused sealed radioactive sources. The publication contains an Annex presenting the example of a safety assessment for a small radioactive waste storage facility. Facilities dealing with both short lived and long lived low and intermediate level waste generated from nuclear applications and from operation of small nuclear research reactors are included in the scope. Processing and storage facilities for high activity disused sealed sources and sealed sources containing long lived radionuclides are also covered. The publication does not cover facilities processing or storing radioactive waste from nuclear power plants or any other industrial scale nuclear fuel cycle facilities. Disposal facilities are excluded from the scope of this publication. Authorization process can be implemented in several stages, which may start at the site planning and the feasibility study stage and will continue through preliminary design, final design, commissioning, operation and decommissioning stages. This publication covers primarily the authorization needed to take the facility into operation

Surface Water Modeling Using an EPA Computer Code for Tritiated Waste Water Discharge from the heavy Water Facility

International Nuclear Information System (INIS)

Chen, K.F.

1998-06-01

Tritium releases from the D-Area Heavy Water Facilities to the Savannah River have been analyzed. The U.S. EPA WASP5 computer code was used to simulate surface water transport for tritium releases from the D-Area Drum Wash, Rework, and DW facilities. The WASP5 model was qualified with the 1993 tritium measurements at U.S. Highway 301. At the maximum tritiated waste water concentrations, the calculated tritium concentration in the Savannah River at U.S. Highway 301 due to concurrent releases from D-Area Heavy Water Facilities varies from 5.9 to 18.0 pCi/ml as a function of the operation conditions of these facilities. The calculated concentration becomes the lowest when the batch releases method for the Drum Wash Waste Tanks is adopted

Development of Parallel Computing Framework to Enhance Radiation Transport Code Capabilities for Rare Isotope Beam Facility Design

Energy Technology Data Exchange (ETDEWEB)

Kostin, Mikhail [Michigan State Univ., East Lansing, MI (United States); Mokhov, Nikolai [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Niita, Koji [Research Organization for Information Science and Technology, Ibaraki-ken (Japan)

2013-09-25

A parallel computing framework has been developed to use with general-purpose radiation transport codes. The framework was implemented as a C++ module that uses MPI for message passing. It is intended to be used with older radiation transport codes implemented in Fortran77, Fortran 90 or C. The module is significantly independent of radiation transport codes it can be used with, and is connected to the codes by means of a number of interface functions. The framework was developed and tested in conjunction with the MARS15 code. It is possible to use it with other codes such as PHITS, FLUKA and MCNP after certain adjustments. Besides the parallel computing functionality, the framework offers a checkpoint facility that allows restarting calculations with a saved checkpoint file. The checkpoint facility can be used in single process calculations as well as in the parallel regime. The framework corrects some of the known problems with the scheduling and load balancing found in the original implementations of the parallel computing functionality in MARS15 and PHITS. The framework can be used efficiently on homogeneous systems and networks of workstations, where the interference from the other users is possible.

Computational Simulations of the NASA Langley HyMETS Arc-Jet Facility

Science.gov (United States)

Brune, A. J.; Bruce, W. E., III; Glass, D. E.; Splinter, S. C.

2017-01-01

The Hypersonic Materials Environmental Test System (HyMETS) arc-jet facility located at the NASA Langley Research Center in Hampton, Virginia, is primarily used for the research, development, and evaluation of high-temperature thermal protection systems for hypersonic vehicles and reentry systems. In order to improve testing capabilities and knowledge of the test article environment, an effort is underway to computationally simulate the flow-field using computational fluid dynamics (CFD). A detailed three-dimensional model of the arc-jet nozzle and free-jet portion of the flow-field has been developed and compared to calibration probe Pitot pressure and stagnation-point heat flux for three test conditions at low, medium, and high enthalpy. The CFD model takes into account uniform pressure and non-uniform enthalpy profiles at the nozzle inlet as well as catalytic recombination efficiency effects at the probe surface. Comparing the CFD results and test data indicates an effectively fully-catalytic copper surface on the heat flux probe of about 10% efficiency and a 2-3 kpa pressure drop from the arc heater bore, where the pressure is measured, to the plenum section, prior to the nozzle. With these assumptions, the CFD results are well within the uncertainty of the stagnation pressure and heat flux measurements. The conditions at the nozzle exit were also compared with radial and axial velocimetry. This simulation capability will be used to evaluate various three-dimensional models that are tested in the HyMETS facility. An end-to-end aerothermal and thermal simulation of HyMETS test articles will follow this work to provide a better understanding of the test environment, test results, and to aid in test planning. Additional flow-field diagnostic measurements will also be considered to improve the modeling capability.

Primary Health Care Software-A Computer Based Data Management System

Directory of Open Access Journals (Sweden)

Tuli K

1990-01-01

Full Text Available Realising the duplication and time consumption in the usual manual system of data collection necessitated experimentation with computer based management system for primary health care in the primary health centers. The details of the population as available in the existing manual system were used for computerizing the data. Software was designed for data entry and analysis. It was written in Dbase III plus language. It was so designed that a person with no knowledge about computer could use it, A cost analysis was done and the computer system was found more cost effective than the usual manual system.

The Overview of the National Ignition Facility Distributed Computer Control System

International Nuclear Information System (INIS)

Lagin, L.J.; Bettenhausen, R.C.; Carey, R.A.; Estes, C.M.; Fisher, J.M.; Krammen, J.E.; Reed, R.K.; VanArsdall, P.J.; Woodruff, J.P.

2001-01-01

The Integrated Computer Control System (ICCS) for the National Ignition Facility (NIF) is a layered architecture of 300 front-end processors (FEP) coordinated by supervisor subsystems including automatic beam alignment and wavefront control, laser and target diagnostics, pulse power, and shot control timed to 30 ps. FEP computers incorporate either VxWorks on PowerPC or Solaris on UltraSPARC processors that interface to over 45,000 control points attached to VME-bus or PCI-bus crates respectively. Typical devices are stepping motors, transient digitizers, calorimeters, and photodiodes. The front-end layer is divided into another segment comprised of an additional 14,000 control points for industrial controls including vacuum, argon, synthetic air, and safety interlocks implemented with Allen-Bradley programmable logic controllers (PLCs). The computer network is augmented asynchronous transfer mode (ATM) that delivers video streams from 500 sensor cameras monitoring the 192 laser beams to operator workstations. Software is based on an object-oriented framework using CORBA distribution that incorporates services for archiving, machine configuration, graphical user interface, monitoring, event logging, scripting, alert management, and access control. Software coding using a mixed language environment of Ada95 and Java is one-third complete at over 300 thousand source lines. Control system installation is currently under way for the first 8 beams, with project completion scheduled for 2008

The procedures manual of the Environmental Measurements Laboratory. Volume 1, 28. edition

Energy Technology Data Exchange (ETDEWEB)

Chieco, N.A. [ed.

1997-02-01

This manual covers procedures and technology currently in use at the Environmental Measurements Laboratory. An attempt is made to be sure that all work carried out will be of the highest quality. Attention is focused on the following areas: quality assurance; sampling; radiation measurements; analytical chemistry; radionuclide data; special facilities; and specifications.

The procedures manual of the Environmental Measurements Laboratory. Volume 1, 28. edition

International Nuclear Information System (INIS)

Chieco, N.A.

1997-02-01

This manual covers procedures and technology currently in use at the Environmental Measurements Laboratory. An attempt is made to be sure that all work carried out will be of the highest quality. Attention is focused on the following areas: quality assurance; sampling; radiation measurements; analytical chemistry; radionuclide data; special facilities; and specifications

Tank farms criticality safety manual

International Nuclear Information System (INIS)

FORT, L.A.

2003-01-01

This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR-), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR- 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type

Hanford whole body counting manual

International Nuclear Information System (INIS)

Palmer, H.E.; Rieksts, G.A.; Lynch, T.P.

1990-06-01

This document describes the Hanford Whole Body Counting Program as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy--Richland Operations Office (DOE-RL) and its Hanford contractors. Program services include providing in vivo measurements of internally deposited radioactivity in Hanford employees (or visitors). Specific chapters of this manual deal with the following subjects: program operational charter, authority, administration, and practices, including interpreting applicable DOE Orders, regulations, and guidance into criteria for in vivo measurement frequency, etc., for the plant-wide whole body counting services; state-of-the-art facilities and equipment used to provide the best in vivo measurement results possible for the approximately 11,000 measurements made annually; procedures for performing the various in vivo measurements at the Whole Body Counter (WBC) and related facilities including whole body counts; operation and maintenance of counting equipment, quality assurance provisions of the program, WBC data processing functions, statistical aspects of in vivo measurements, and whole body counting records and associated guidance documents. 16 refs., 48 figs., 22 tabs

Computer Access and Flowcharting as Variables in Learning Computer Programming.

Science.gov (United States)

Ross, Steven M.; McCormick, Deborah

Manipulation of flowcharting was crossed with in-class computer access to examine flowcharting effects in the traditional lecture/laboratory setting and in a classroom setting where online time was replaced with manual simulation. Seventy-two high school students (24 male and 48 female) enrolled in a computer literacy course served as subjects.…

Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

International Nuclear Information System (INIS)

Young, Michael F.

1999-01-01

The integrated fuel-coolant interaction (IFCI) computer code is being developed at Sandia National Laboratories to investigate the fuel-coolant interaction (FCI) problem at large scale using a two-dimensional, three-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. This document is a description of IFCI 7.0. The user's manual describes the hydrodynamic method and physical models used in IFCI 7.0. Appendix A is an input manual provided for the creation of working decks

FIRAC: a computer code to predict fire-accident effects in nuclear facilities

International Nuclear Information System (INIS)

Bolstad, J.W.; Krause, F.R.; Tang, P.K.; Andrae, R.W.; Martin, R.A.; Gregory, W.S.

1983-01-01

FIRAC is a medium-sized computer code designed to predict fire-induced flows, temperatures, and material transport within the ventilating systems and other airflow pathways in nuclear-related facilities. The code is designed to analyze the behavior of interconnected networks of rooms and typical ventilation system components. This code is one in a family of computer codes that is designed to provide improved methods of safety analysis for the nuclear industry. The structure of this code closely follows that of the previously developed TVENT and EVENT codes. Because a lumped-parameter formulation is used, this code is particularly suitable for calculating the effects of fires in the far field (that is, in regions removed from the fire compartment), where the fire may be represented parametrically. However, a fire compartment model to simulate conditions in the enclosure is included. This model provides transport source terms to the ventilation system that can affect its operation and in turn affect the fire

MULTIPLE PROJECTIONS SYSTEM (MPS) - USER'S MANUAL VERSION 1.0

Science.gov (United States)

The report is a user's manual for version 1.0 of the Multiple Projections Systems (MPS), a computer system that can perform "what if" scenario analysis and report the final results (i.e., Rate of Further Progress - ROP - inventories) to EPA (i.e., the Aerometric Information Retri...

A deterministic-probabilistic model for contaminant transport. User manual

Energy Technology Data Exchange (ETDEWEB)

Schwartz, F W; Crowe, A

1980-08-01

This manual describes a deterministic-probabilistic contaminant transport (DPCT) computer model designed to simulate mass transfer by ground-water movement in a vertical section of the earth's crust. The model can account for convection, dispersion, radioactive decay, and cation exchange for a single component. A velocity is calculated from the convective transport of the ground water for each reference particle in the modeled region; dispersion is accounted for in the particle motion by adding a readorn component to the deterministic motion. The model is sufficiently general to enable the user to specify virtually any type of water table or geologic configuration, and a variety of boundary conditions. A major emphasis in the model development has been placed on making the model simple to use, and information provided in the User Manual will permit changes to the computer code to be made relatively easily for those that might be required for specific applications. (author)

Mac OS X : Tiger edition the missing manual

CERN Document Server

Pogue, David

2005-01-01

You can set your watch to it: As soon as Apple comes out with another version of Mac OS X, David Pogue hits the streets with another meticulous Missing Manual to cover it with a wealth of detail. The new Mac OS X 10.4, better known as Tiger, is faster than its predecessors, but nothing's too fast for Pogue and Mac OS X: The Missing Manual. There are many reasons why this is the most popular computer book of all time. With its hallmark objectivity, the Tiger Edition thoroughly explores the latest features to grace the Mac OS. Which ones work well and which do not? What should you look for? Th

Citham-2 computer code-User manual

International Nuclear Information System (INIS)

Batista, J.L.

1984-01-01

The procedures and the input data for the Citham-2 computer code are described. It is a subroutine that modifies the nuclide concentration taking in account its burn and prepares cross sections library in 2,3 or 4 energy groups, to the used for Citation program. (E.G.) [pt

Training manual on food irradiation technology and techniques. 2. ed.

International Nuclear Information System (INIS)

1982-01-01

The objective of the revised Training Manual is to help scientists to acquire the necessary knowledge needed for performing proper research and development work in the field of food irradiation. The Manual presents an up-to-date picture of the current state of food irradiation and reflects the important advances made in the technology of food irradiation, in the radiation chemistry of foods, in the microbiology of irradiated foods, in wholesomeness and standardization. It contains the following chapters: (1) Radionuclides and radiation; (2) Radiation detection and measurement; (3) Radiation protection; (4) Radiation chemistry; (5) Effects of radiation on living organisms; (6) Preservation of foods; (7) Radiation preservation of foods; (8) Packaging; (9) Combination processes; (10) Limitations of food irradiation; (11) Wholesomeness of irradiated foods; (12) Government regulation of irradiated foods; (13) Food irradiation facilities; (14) Commercial aspects of food irradiation; (15) Literature sources. The practical part of the Manual contains a revised and expanded series of detailed laboratory exercises in the use of ionizing radiation for food processing

NASCAP programmer's reference manual

Science.gov (United States)

Mandell, M. J.; Stannard, P. R.; Katz, I.

1993-05-01

The NASA Charging Analyzer Program (NASCAP) is a computer program designed to model the electrostatic charging of complicated three-dimensional objects, both in a test tank and at geosynchronous altitudes. This document is a programmer's reference manual and user's guide. It is designed as a reference to experienced users of the code, as well as an introduction to its use for beginners. All of the many capabilities of NASCAP are covered in detail, together with examples of their use. These include the definition of objects, plasma environments, potential calculations, particle emission and detection simulations, and charging analysis.

INSPECT: a package of computer programs for planning and evaluating safeguards inspections

International Nuclear Information System (INIS)

Mullen, M.F.

1980-01-01

As part of the US Program of Technical Assistance to IAEA Safeguards, PNL has developed a package of computer programs, called INSPECT, that can be used in planning and evaluating safeguards inspections of various types of nuclear facilities. The programs are based on the statistical methods described in Part F of the IAEA Safeguards Technical Manual and can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, and a measure of the effectiveness of the inspection plan. The paper describes the programs, reviews a number of applications, and indicates areas for future work

Synfuel program analysis. Volume 2: VENVAL users manual

Science.gov (United States)

Muddiman, J. B.; Whelan, J. W.

1980-07-01

This volume is intended for program analysts and is a users manual for the VENVAL model. It contains specific explanations as to input data requirements and programming procedures for the use of this model. VENVAL is a generalized computer program to aid in evaluation of prospective private sector production ventures. The program can project interrelated values of installed capacity, production, sales revenue, operating costs, depreciation, investment, dent, earnings, taxes, return on investment, depletion, and cash flow measures. It can also compute related public sector and other external costs and revenues if unit costs are furnished.

Manual Therapy

OpenAIRE

Hakgüder, Aral; Kokino, Siranuş

2002-01-01

Manual therapy has been used in the treatment of pain and dysfunction of spinal and peripheral joints for more than a hundred years. Manual medicine includes manipulation, mobilization, and postisometric relaxation techniques. The aim of manual therapy is to enhance restricted movement caused by blockage of joints keeping postural balance, restore function and maintain optimal body mechanics. Anatomic, biomechanical, and neurophysiological evaluations of the leucomotor system is essential for...

Design/CPN. A Reference Manual

DEFF Research Database (Denmark)

Jensen et. al, Kurt

/CPN WWW pages. To speed up the access to the Design/CPN manuals we recommend to keep a local copy - which may be shared by all users in your organisation. In this way you do not need to go via our WWW server each time you need to look in a manual. For some of the largest manuals, we also supply files......Note: The manuals are available as PDF files . There are two sets of manuals - one for the Unix platform and another for the Mac platform. Each set of manual consists of: Tutorial (for the Design/CPN editor and simulator) Reference Manual (for the Design/CPN editor and simulator) Programmer......'s Manual (with Design/OA functions and Charts) Occurrence Graph Manual (integrated tutorial and reference manual) OE/OS Graph Manual (integrated tutorial and reference manual) Other Manuals (e.g. a short overview of CPN ML).   The Tutorial, Reference Manual and Programmer's Manual are made for Design...

Mass Balance. Operational Control Tests for Wastewater Treatment Facilities. Instructor's Manual [and] Student Workbook.

Science.gov (United States)

Carnegie, John W.

This module describes the process used to determine solids mass and location throughout a waste water treatment plant, explains how these values are used to determine the solids mass balance around single treatment units and the entire system, and presents calculations of solids in pounds and sludge units. The instructor's manual contains a…

Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

International Nuclear Information System (INIS)

Carter, R.L. Jr.

1994-01-01

The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS)

CSNI Integral Test Facility Matrices for Validation of Best-Estimate Thermal-Hydraulic Computer Codes

International Nuclear Information System (INIS)

Glaeser, H.

2008-01-01

Internationally agreed Integral Test Facility (ITF) matrices for validation of realistic thermal hydraulic system computer codes were established. ITF development is mainly for Pressurised Water Reactors (PWRs) and Boiling Water Reactors (BWRs). A separate activity was for Russian Pressurised Water-cooled and Water-moderated Energy Reactors (WWER). Firstly, the main physical phenomena that occur during considered accidents are identified, test types are specified, and test facilities suitable for reproducing these aspects are selected. Secondly, a list of selected experiments carried out in these facilities has been set down. The criteria to achieve the objectives are outlined. In this paper some specific examples from the ITF matrices will also be provided. The matrices will be a guide for code validation, will be a basis for comparisons of code predictions performed with different system codes, and will contribute to the quantification of the uncertainty range of code model predictions. In addition to this objective, the construction of such a matrix is an attempt to record information which has been generated around the world over the last years, so that it is more accessible to present and future workers in that field than would otherwise be the case.

Caltrans : construction manual

Science.gov (United States)

2009-08-01

Caltrans intends this manual as a resource for all personnel engaged in contract administration. The manual establishes policies and procedures for the construction phase of Caltrans projects. However, this manual is not a contract document. It impos...

Computer facilities for ISABELLE data handling

International Nuclear Information System (INIS)

Kramer, M.A.; Love, W.A.; Miller, R.J.; Zeller, M.

1977-01-01

The analysis of data produced by ISABELLE experiments will need a large system of computers. An official group of prospective users and operators of that system should begin planning now. Included in the array will be a substantial computer system at each ISABELLE intersection in use. These systems must include enough computer power to keep experimenters aware of the health of the experiment. This will require at least one very fast sophisticated processor in the system, the size depending on the experiment. Other features of the intersection systems must be a good, high speed graphic display, ability to record data on magnetic tape at 500 to 1000 KB, and a high speed link to a central computer. The operating system software must support multiple interactive users. A substantially larger capacity computer system, shared by the six intersection region experiments, must be available with good turnaround for experimenters while ISABELLE is running. A computer support group will be required to maintain the computer system and to provide and maintain software common to all experiments. Special superfast computing hardware or special function processors constructed with microprocessor circuitry may be necessary both in the data gathering and data processing work. Thus both the local and central processors should be chosen with the possibility of interfacing such devices in mind

Automatic beam position control at Los Alamos Spallation Radiation Effects Facility (LASREF)

International Nuclear Information System (INIS)

Oothoudt, M.; Pillai, C.; Zumbro, M.

1997-01-01

Historically the Los Alamos Spallation Radiation Effects Facility (LASREF) has used manual methods to control the position of the 800 kW, 800 MeV proton beam on targets. New experiments, however, require more stringent position control more frequently than can be done manually for long periods of time. Data from an existing harp is used to automatically adjust steering magnets to maintain beam position to required tolerances

PROTEUS-SN User Manual

Energy Technology Data Exchange (ETDEWEB)

Shemon, Emily R. [Argonne National Lab. (ANL), Argonne, IL (United States); Smith, Micheal A. [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, Changho [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-02-16

PROTEUS-SN is a three-dimensional, highly scalable, high-fidelity neutron transport code developed at Argonne National Laboratory. The code is applicable to all spectrum reactor transport calculations, particularly those in which a high degree of fidelity is needed either to represent spatial detail or to resolve solution gradients. PROTEUS-SN solves the second order formulation of the transport equation using the continuous Galerkin finite element method in space, the discrete ordinates approximation in angle, and the multigroup approximation in energy. PROTEUS-SN’s parallel methodology permits the efficient decomposition of the problem by both space and angle, permitting large problems to run efficiently on hundreds of thousands of cores. PROTEUS-SN can also be used in serial or on smaller compute clusters (10’s to 100’s of cores) for smaller homogenized problems, although it is generally more computationally expensive than traditional homogenized methodology codes. PROTEUS-SN has been used to model partially homogenized systems, where regions of interest are represented explicitly and other regions are homogenized to reduce the problem size and required computational resources. PROTEUS-SN solves forward and adjoint eigenvalue problems and permits both neutron upscattering and downscattering. An adiabatic kinetics option has recently been included for performing simple time-dependent calculations in addition to standard steady state calculations. PROTEUS-SN handles void and reflective boundary conditions. Multigroup cross sections can be generated externally using the MC2-3 fast reactor multigroup cross section generation code or internally using the cross section application programming interface (API) which can treat the subgroup or resonance table libraries. PROTEUS-SN is written in Fortran 90 and also includes C preprocessor definitions. The code links against the PETSc, METIS, HDF5, and MPICH libraries. It optionally links against the MOAB library and

Traditional Engineering Graphics versus Computer-Aided Drafting: A View from Academe.

Science.gov (United States)

Foster, Robert J.

1987-01-01

Argues for a legitimate role of manually expressed engineering graphics within engineering education as a needed support for computer-assisted drafting work. Discusses what and how students should learn as well as trends in engineering graphics education. Compares and contrasts manual and computer drafting methods. (CW)

DOE Radiological Control Manual Core Training Program

International Nuclear Information System (INIS)

Scott, H.L.; Maisler, J.

1993-01-01

Over the past year, the Department of Energy (DOE) Office of Health (EH-40) has taken a leading role in the development of new standardized radiological control training programs for use throughout the DOE complex. The Department promulgated its Radiological Control (RadCon) Manual in June 1992. To ensure consistent application of the criteria presented in the RadCon Manual, standardized radiological control core training courses and training materials have been developed for implementation at all DOE facilities. In producing local training programs, standardized core courses are to be supplemented with site-specific lesson plans, viewgraphs, student handbooks, qualification standards, question banks, and wallet-sized training certificates. Training programs for General Employee Radiological Training, Radiological Worker I and II Training, and Radiological Control Technician Training have been disseminated. Also, training committees under the direction of the Office of Health (EH-40) have been established for the development of additional core training courses, development of examination banks, and the update of the existing core training courses. This paper discusses the current activities and future direction of the DOE radiological control core training program

High-throughput measurement of rice tillers using a conveyor equipped with x-ray computed tomography

Science.gov (United States)

Yang, Wanneng; Xu, Xiaochun; Duan, Lingfeng; Luo, Qingming; Chen, Shangbin; Zeng, Shaoqun; Liu, Qian

2011-02-01

Tillering is one of the most important agronomic traits because the number of shoots per plant determines panicle number, a key component of grain yield. The conventional method of counting tillers is still manual. Under the condition of mass measurement, the accuracy and efficiency could be gradually degraded along with fatigue of experienced staff. Thus, manual measurement, including counting and recording, is not only time consuming but also lack objectivity. To automate this process, we developed a high-throughput facility, dubbed high-throughput system for measuring automatically rice tillers (H-SMART), for measuring rice tillers based on a conventional x-ray computed tomography (CT) system and industrial conveyor. Each pot-grown rice plant was delivered into the CT system for scanning via the conveyor equipment. A filtered back-projection algorithm was used to reconstruct the transverse section image of the rice culms. The number of tillers was then automatically extracted by image segmentation. To evaluate the accuracy of this system, three batches of rice at different growth stages (tillering, heading, or filling) were tested, yielding absolute mean absolute errors of 0.22, 0.36, and 0.36, respectively. Subsequently, the complete machine was used under industry conditions to estimate its efficiency, which was 4320 pots per continuous 24 h workday. Thus, the H-SMART could determine the number of tillers of pot-grown rice plants, providing three advantages over the manual tillering method: absence of human disturbance, automation, and high throughput. This facility expands the application of agricultural photonics in plant phenomics.

User manual for PACTOLUS: a code for computing power costs.

Energy Technology Data Exchange (ETDEWEB)

Huber, H.D.; Bloomster, C.H.

1979-02-01

PACTOLUS is a computer code for calculating the cost of generating electricity. Through appropriate definition of the input data, PACTOLUS can calculate the cost of generating electricity from a wide variety of power plants, including nuclear, fossil, geothermal, solar, and other types of advanced energy systems. The purpose of PACTOLUS is to develop cash flows and calculate the unit busbar power cost (mills/kWh) over the entire life of a power plant. The cash flow information is calculated by two principal models: the Fuel Model and the Discounted Cash Flow Model. The Fuel Model is an engineering cost model which calculates the cash flow for the fuel cycle costs over the project lifetime based on input data defining the fuel material requirements, the unit costs of fuel materials and processes, the process lead and lag times, and the schedule of the capacity factor for the plant. For nuclear plants, the Fuel Model calculates the cash flow for the entire nuclear fuel cycle. For fossil plants, the Fuel Model calculates the cash flow for the fossil fuel purchases. The Discounted Cash Flow Model combines the fuel costs generated by the Fuel Model with input data on the capital costs, capital structure, licensing time, construction time, rates of return on capital, tax rates, operating costs, and depreciation method of the plant to calculate the cash flow for the entire lifetime of the project. The financial and tax structure for both investor-owned utilities and municipal utilities can be simulated through varying the rates of return on equity and debt, the debt-equity ratios, and tax rates. The Discounted Cash Flow Model uses the principal that the present worth of the revenues will be equal to the present worth of the expenses including the return on investment over the economic life of the project. This manual explains how to prepare the input data, execute cases, and interpret the output results. (RWR)

User manual for PACTOLUS: a code for computing power costs

International Nuclear Information System (INIS)

Huber, H.D.; Bloomster, C.H.

1979-02-01

PACTOLUS is a computer code for calculating the cost of generating electricity. Through appropriate definition of the input data, PACTOLUS can calculate the cost of generating electricity from a wide variety of power plants, including nuclear, fossil, geothermal, solar, and other types of advanced energy systems. The purpose of PACTOLUS is to develop cash flows and calculate the unit busbar power cost (mills/kWh) over the entire life of a power plant. The cash flow information is calculated by two principal models: the Fuel Model and the Discounted Cash Flow Model. The Fuel Model is an engineering cost model which calculates the cash flow for the fuel cycle costs over the project lifetime based on input data defining the fuel material requirements, the unit costs of fuel materials and processes, the process lead and lag times, and the schedule of the capacity factor for the plant. For nuclear plants, the Fuel Model calculates the cash flow for the entire nuclear fuel cycle. For fossil plants, the Fuel Model calculates the cash flow for the fossil fuel purchases. The Discounted Cash Flow Model combines the fuel costs generated by the Fuel Model with input data on the capital costs, capital structure, licensing time, construction time, rates of return on capital, tax rates, operating costs, and depreciation method of the plant to calculate the cash flow for the entire lifetime of the project. The financial and tax structure for both investor-owned utilities and municipal utilities can be simulated through varying the rates of return on equity and debt, the debt-equity ratios, and tax rates. The Discounted Cash Flow Model uses the principal that the present worth of the revenues will be equal to the present worth of the expenses including the return on investment over the economic life of the project. This manual explains how to prepare the input data, execute cases, and interpret the output results with the updated version of PACTOLUS. 11 figures, 2 tables

On a new method to compute photon skyshine doses around radiotherapy facilities

Energy Technology Data Exchange (ETDEWEB)

Falcao, R.; Facure, A. [Comissao Nacional de Eenrgia Nuclear, Rio de Janeiro (Brazil); Xavier, A. [PEN/Coppe -UFRJ, Rio de Janeiro (Brazil)

2006-07-01

Full text of publication follows: Nowadays, in a great number of situations constructions are raised around radiotherapy facilities. In cases where the constructions would not be in the primary x-ray beam, 'skyshine' radiation is normally accounted for. The skyshine method is commonly used to to calculate the dose contribution from scattered radiation in such circumstances, when the roof shielding is projected considering there will be no occupancy upstairs. In these cases, there will be no need to have the usual 1,5-2,0 m thick ceiling, and the construction costs can be considerably reduced. The existing expression to compute these doses do not accomplish to explain mathematically the existence of a shadow area just around the outer room walls, and its growth, as we get away from these walls. In this paper we propose a new method to compute photon skyshine doses, using geometrical considerations to find the maximum dose point. An empirical equation is derived, and its validity is tested using M.C.N.P. 5 Monte Carlo calculation to simulate radiotherapy rooms configurations. (authors)

Operation and maintenance manual for data acquisition system of MIDAS

International Nuclear Information System (INIS)

Lee, D. Y.; Park, W. M.; Kim, J. T.; Euh, D. J.

2001-09-01

This report describes an operation and maintenance manual of the data acquisition system and the data processing system for the DVI performance evaluation facility, MIDAS. The data acquisition system is implemented with VXI based system of Kinetic Systems TM , and the data processing PC. This report presents the configuration method and operation procedure for the operator. The modification procedure and method for functional extension and performance modification are also included for the future demand

User manual for version 4.3 of the Tripoli-4 Monte-Carlo method particle transport computer code

International Nuclear Information System (INIS)

Both, J.P.; Mazzolo, A.; Peneliau, Y.; Petit, O.; Roesslinger, B.

2003-01-01

This manual relates to Version 4.3 TRIPOLI-4 code. TRIPOLI-4 is a computer code simulating the transport of neutrons, photons, electrons and positrons. It can be used for radiation shielding calculations (long-distance propagation with flux attenuation in non-multiplying media) and neutronic calculations (fissile medium, criticality or sub-criticality basis). This makes it possible to calculate k eff (for criticality), flux, currents, reaction rates and multi-group cross-sections. TRIPOLI-4 is a three-dimensional code that uses the Monte-Carlo method. It allows for point-wise description in terms of energy of cross-sections and multi-group homogenized cross-sections and features two modes of geometrical representation: surface and combinatorial. The code uses cross-section libraries in ENDF/B format (such as JEF2-2, ENDF/B-VI and JENDL) for point-wise description cross-sections in APOTRIM format (from the APOLLO2 code) or a format specific to TRIPOLI-4 for multi-group description. (authors)

Reliability and reproducibility analysis of the Cobb angle and assessing sagittal plane by computer-assisted and manual measurement tools.

Science.gov (United States)

Wu, Weifei; Liang, Jie; Du, Yuanli; Tan, Xiaoyi; Xiang, Xuanping; Wang, Wanhong; Ru, Neng; Le, Jinbo

2014-02-06

Although many studies on reliability and reproducibility of measurement have been performed on coronal Cobb angle, few results about reliability and reproducibility are reported on sagittal alignment measurement including the pelvis. We usually use SurgimapSpine software to measure the Cobb angle in our studies; however, there are no reports till date on its reliability and reproducible measurements. Sixty-eight standard standing posteroanterior whole-spine radiographs were reviewed. Three examiners carried out the measurements independently under the settings of manual measurement on X-ray radiographies and SurgimapSpine software on the computer. Parameters measured included pelvic incidence, sacral slope, pelvic tilt, Lumbar lordosis (LL), thoracic kyphosis, and coronal Cobb angle. SPSS 16.0 software was used for statistical analyses. The means, standard deviations, intraclass and interclass correlation coefficient (ICC), and 95% confidence intervals (CI) were calculated. There was no notable difference between the two tools (P = 0.21) for the coronal Cobb angle. In the sagittal plane parameters, the ICC of intraobserver reliability for the manual measures varied from 0.65 (T2-T5 angle) to 0.95 (LL angle). Further, for SurgimapSpine tool, the ICC ranged from 0.75 to 0.98. No significant difference in intraobserver reliability was found between the two measurements (P > 0.05). As for the interobserver reliability, measurements with SurgimapSpine tool had better ICC (0.71 to 0.98 vs 0.59 to 0.96) and Pearson's coefficient (0.76 to 0.99 vs 0.60 to 0.97). The reliability of SurgimapSpine measures was significantly higher in all parameters except for the coronal Cobb angle where the difference was not significant (P > 0.05). Although the differences between the two methods are very small, the results of this study indicate that the SurgimapSpine measurement is an equivalent measuring tool to the traditional manual in coronal Cobb angle, but is advantageous in spino

Recommended practice for the design of a computer driven Alarm Display Facility for central control rooms of nuclear power generating stations

International Nuclear Information System (INIS)

Ben-Yaacov, G.

1984-01-01

This paper's objective is to explain the process by which design can prevent human errors in nuclear plant operation. Human factor engineering principles, data, and methods used in the design of computer driven alarm display facilities are discussed. A ''generic'', advanced Alarm Display Facility is described. It considers operator capabilities and limitations in decision-making processes, response dynamics, and human memory limitations. Highlighted are considerations of human factor criteria in the designing and layout of alarm displays. Alarm data sources are described, and their use within the Alarm Display Facility are illustrated

The grand challenge of managing the petascale facility.

Energy Technology Data Exchange (ETDEWEB)

Aiken, R. J.; Mathematics and Computer Science

2007-02-28

This report is the result of a study of networks and how they may need to evolve to support petascale leadership computing and science. As Dr. Ray Orbach, director of the Department of Energy's Office of Science, says in the spring 2006 issue of SciDAC Review, 'One remarkable example of growth in unexpected directions has been in high-end computation'. In the same article Dr. Michael Strayer states, 'Moore's law suggests that before the end of the next cycle of SciDAC, we shall see petaflop computers'. Given the Office of Science's strong leadership and support for petascale computing and facilities, we should expect to see petaflop computers in operation in support of science before the end of the decade, and DOE/SC Advanced Scientific Computing Research programs are focused on making this a reality. This study took its lead from this strong focus on petascale computing and the networks required to support such facilities, but it grew to include almost all aspects of the DOE/SC petascale computational and experimental science facilities, all of which will face daunting challenges in managing and analyzing the voluminous amounts of data expected. In addition, trends indicate the increased coupling of unique experimental facilities with computational facilities, along with the integration of multidisciplinary datasets and high-end computing with data-intensive computing; and we can expect these trends to continue at the petascale level and beyond. Coupled with recent technology trends, they clearly indicate the need for including capability petascale storage, networks, and experiments, as well as collaboration tools and programming environments, as integral components of the Office of Science's petascale capability metafacility. The objective of this report is to recommend a new cross-cutting program to support the management of petascale science and infrastructure. The appendices of the report document current and projected

Spatio-temporal Facility Utilization Analysis from Exhaustive WiFi Monitoring

DEFF Research Database (Denmark)

Prentow, Thor Siiger; Ruiz-Ruiz, Antonio; Blunck, Henrik

2015-01-01

The optimization of logistics in large building complexes with many resources, such as hospitals, require realistic facility management and planning. Current planning practices rely foremost on manual observations or coarse unverified assumptions and therefore do not properly scale or provide rea...

Computer surety: computer system inspection guidance. [Contains glossary

Energy Technology Data Exchange (ETDEWEB)

1981-07-01

This document discusses computer surety in NRC-licensed nuclear facilities from the perspective of physical protection inspectors. It gives background information and a glossary of computer terms, along with threats and computer vulnerabilities, methods used to harden computer elements, and computer audit controls.

EMSL Operations Manual

Energy Technology Data Exchange (ETDEWEB)

Foster, Nancy S.

2009-06-18

This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

EMSL Operations Manual

Energy Technology Data Exchange (ETDEWEB)

Foster, Nancy S.

2009-03-25

This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

Towards the Automatic Detection of Efficient Computing Assets in a Heterogeneous Cloud Environment

OpenAIRE

Iglesias, Jesus Omana; Stokes, Nicola; Ventresque, Anthony; Murphy, Liam, B.E.; Thorburn, James

2013-01-01

peer-reviewed In a heterogeneous cloud environment, the manual grading of computing assets is the first step in the process of configuring IT infrastructures to ensure optimal utilization of resources. Grading the efficiency of computing assets is however, a difficult, subjective and time consuming manual task. Thus, an automatic efficiency grading algorithm is highly desirable. In this paper, we compare the effectiveness of the different criteria used in the manual gr...

Fluor Hanford Nuclear Material Stabilization Project Welding Manual

International Nuclear Information System (INIS)

BERKEY, J.R.

2000-01-01

The purpose of this section of the welding manual is to: (1) Provide a general description of the major responsibilities of the organizations involved with welding. (2) Provide general guidance concerning the application of codes related to welding. This manual contains requirements for welding for all Fluor Hanford (FH) welding operators working on the W460 Project, in the Plutonium Finishing Plant (PFP) at the U. S. Department of Energy (DOE) Hanford facilities. These procedures and any additional requirements for these joining processes can be used by all FH welding operators that are qualified. The Welding Procedure Specifications (WPS) found in this document were established from Procedure Qualification Records (PQR) qualified by FH specifically for the W460 Project. PQRs are permanent records of the initial testing and qualification program and are used to backup, and support, the WPS. The identification numbers of the supporting PQR(s) are recorded on each WPS. All PQRs are permanently stored under the supervision of the Fluor Hanford Welding Engineer (FHWE). New PQRs and WPSs will continue to be developed as necessary. The qualification of welders, welding operators and welding procedures will be performed for FH under supervision and concurrent of the FHWE. All new welding procedures to be entered in this manual or welder personnel to be added to the welder qualification database, shall be approved by the FHWE

Concept of an immersive assistance system with augmented reality for the support of manual activities in radioactive production environments

International Nuclear Information System (INIS)

Eursch, Andreas A.

2010-01-01

The thesis on an immersive assistance system concept with augmented reality for the support of manual activities in radioactive production environments covers the following topics: analysis of the situation: production and use of radioactive materials, problem analysis of the work in the production facilities, necessity of manual activities, automation, prediction in hot cells; status of research and development; assistance system concept, immersive camera system; augmented reality support in hot cells; economic evaluation and generalization.

Solution In-Line Alpha Counter (SILAC) Instruction Manual-Version 4.00

International Nuclear Information System (INIS)

Alferink, Steven M.; Farnham, Joel E.; Fowler, Malcolm M.; Wong, Amy S.

2002-01-01

The Solution In-Line Alpha Counter (SILAC) provides near real-time alpha activity measurements of aqueous solutions in gloveboxes located in the Plutonium Facility (TA-55) at Los Alamos National Laboratory (LANL). The SILAC detector and its interface software were first developed by Joel Farnham at LANL [1]. This instruction manual describes the features of the SILAC interface software and contains the schematic and fabrication instructions for the detector

Dosimetry and health effects self-teaching curriculum: illustrative problems to supplement the user's manual for the Dosimetry and Health Effects Computer Code

International Nuclear Information System (INIS)

Runkle, G.E.; Finley, N.C.

1983-03-01

This document contains a series of sample problems for the Dosimetry and Health Effects Computer Code to be used in conjunction with the user's manual (Runkle and Cranwell, 1982) for the code. This code was developed at Sandia National Laboratories for the Risk Methodology for Geologic Disposal of Radioactive Waste program (NRC FIN A-1192). The purpose of this document is to familiarize the user with the code, its capabilities, and its limitations. When the user has finished reading this document, he or she should be able to prepare data input for the Dosimetry and Health Effects code and have some insights into interpretation of the model output

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

Aquifer thermal energy storage reference manual: seasonal thermal energy storage program

Energy Technology Data Exchange (ETDEWEB)

Prater, L.S.

1980-01-01

This is the reference manual of the Seasonal Thermal Energy Storage (STES) Program, and is the primary document for the transfer of technical information of the STES Program. It has been issued in preliminary form and will be updated periodically to include more technical data and results of research. As the program progresses and new technical data become available, sections of the manual will be revised to incorporate these data. This primary document contains summaries of: the TRW, incorporated demonstration project at Behtel, Alaska, Dames and Moore demonstration project at Stony Brook, New York, and the University of Minnesota demonstration project at Minneapolis-St. Paul, Minnesota; the technical support programs including legal/institutional assessment; economic assessment; environmental assessment; field test facilities; a compendia of existing information; numerical simulation; and non-aquifer STES concepts. (LCL)

EPRI fuel performance data base: user's manual. Final report

International Nuclear Information System (INIS)

Simpson, J.; Lee, S.; Rumble, E.

1980-10-01

This user's manual provides instructions for accessing the data in the EPRI fuel performance data base (FPDB) and manipulating that data to solve specific problems that the user wishes to specify. The user interacts with the FPDB through the Relational Information Management System (RIMS) computer program. The structure and format of the FPDB and the general syntax of the data base commands are described. Instructions follow for the use of each command. Appendixes provide more detailed information about the FPDB and its software. The FPDB currently resides on a PRIME-750 computer

INTRA/Mod3.2. Manual and code description. Volume 2 - User's manual

International Nuclear Information System (INIS)

Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

1999-01-01

The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the physical modelling of INTRA and the ruling numerics, and volume II, the User's Manual is an input description. This document, the User's Manual, Volume II, contains a detailed description of how to use INTRA, how to set up an input file, how to run INTRA and also post-processing

I need to know! Timely accessing of perioperative user manuals.

Science.gov (United States)

Landreneau, Raphael

2010-12-01

Ready access to equipment or product information is essential for the safe operation of the many items that a perioperative nurse is asked to use, troubleshoot, or maintain. One institution's solution for making manufacturer information available in the practice setting was to create a facility intranet site dedicated to OR equipment manuals. This site provides information access to perioperative nurses and support staff members and, ultimately, helps improve patient care. Published by Elsevier Inc. All rights reserved.

User Manual for the NASA Glenn Ice Accretion Code LEWICE: Version 2.0

Science.gov (United States)

Wright, William B.

1999-01-01

A research project is underway at NASA Glenn to produce a computer code which can accurately predict ice growth under a wide range of meteorological conditions for any aircraft surface. This report will present a description of the code inputs and outputs from version 2.0 of this code, which is called LEWICE. This version differs from previous releases due to its robustness and its ability to reproduce results accurately for different spacing and time step criteria across computing platform. It also differs in the extensive effort undertaken to compare the results against the database of ice shapes which have been generated in the NASA Glenn Icing Research Tunnel (IRT) 1. This report will only describe the features of the code related to the use of the program. The report will not describe the inner working of the code or the physical models used. This information is available in the form of several unpublished documents which will be collectively referred to as a Programmers Manual for LEWICE 2 in this report. These reports are intended as an update/replacement for all previous user manuals of LEWICE. In addition to describing the changes and improvements made for this version, information from previous manuals may be duplicated so that the user will not need to consult previous manuals to use this code.

Structures manual

Science.gov (United States)

2001-01-01

This manual was written as a guide for use by design personnel in the Vermont Agency of Transportation Structures Section. This manual covers the design responsibilities of the Section. It does not cover other functions that are a part of the Structu...

Ciencias 2. Manual do Professor (Science Teacher's Manual).

Science.gov (United States)

Raposo, Lucilia

This is the teacher's manual for Ciencias 2, the second in a series of elementary science textbooks for Portuguese-speaking students. The student textbook contains 10 chapters and 57 activities. The teacher's manual presents an explanation of the educational goals and the organization of the content, Topics included are environment, the human,…

Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

Radiological Control Manual

International Nuclear Information System (INIS)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

Computing, Environment and Life Sciences | Argonne National Laboratory

Science.gov (United States)

Computing, Environment and Life Sciences Research Divisions BIOBiosciences CPSComputational Science DSLData Argonne Leadership Computing Facility Biosciences Division Environmental Science Division Mathematics and Computer Science Division Facilities and Institutes Argonne Leadership Computing Facility News Events About

Self-study manual for introduction to computational fluid dynamics

OpenAIRE

Nabatov, Andrey

2017-01-01

Computational Fluid Dynamics (CFD) is the branch of Fluid Mechanics and Computational Physics that plays a decent role in modern Mechanical Engineering Design process due to such advantages as relatively low cost of simulation comparing with conduction of real experiment, an opportunity to easily correct the design of a prototype prior to manufacturing of the final product and a wide range of application: mixing, acoustics, cooling and aerodynamics. This makes CFD particularly and Computation...

Egyptian Mythological Manuals

DEFF Research Database (Denmark)

Jørgensen, Jens Kristoffer Blach

From the hands of Greek mythographers a great number of myths have survived along with philosophical discussions of their meaning and relevance for the Greeks. It is little known that something similar existed in ancient Egypt where temple libraries and archives held scholarly literature used...... by the native priesthood, much of which has only been published in recent years. As part of this corpus of texts, the ancient Egyptian mythological manuals offer a unique perspective on how the Egyptian priesthood structured and interpreted Egyptian myths. The thesis looks at the different interpretative...... techniques used in the Tebtunis Mythological Manual (Second century CE) and the Mythological Manual of the Delta (Sixth century BCE) and the place of these manuals within the larger corpus of priestly scholarly literature from ancient Egypt. To organize the wealth of local myths the manuals use model...

UQTk version 2.0 user manual

Energy Technology Data Exchange (ETDEWEB)

Debusschere, Bert J. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sargsyan, Khachik [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Safta, Cosmin [Sandia National Lab. (SNL-CA), Livermore, CA (United States)