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Sample records for technical basis manual

Internal dosimetry technical basis manual

International Nuclear Information System (INIS)

1990-01-01

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs
Internal dosimetry technical basis manual

Energy Technology Data Exchange (ETDEWEB)

1990-12-20

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2006-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records & Information Capture Architecture (ERICA) database
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2005-02-25

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2009-08-28

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-04-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2011-04-04

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2007-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records and Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2007-03-12

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor
Sandia National Laboratories Internal Dosimetry Technical Basis Manual (Rev 4)

Energy Technology Data Exchange (ETDEWEB)

Goke, Sarah Hayes [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Elliott, Nathan Ryan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-09-01

The Sandia National Laboratories’ Internal Dosimetry Technical Basis Manual is intended to provide extended technical discussion and justification of the internal dosimetry program at SNL. It serves to record the approach to evaluating internal doses from radiobioassay data, and where appropriate, from workplace monitoring data per the Department of Energy Internal Dosimetry Program Guide DOE G 441.1C. The discussion contained herein is directed primarily to current and future SNL internal dosimetrists. In an effort to conserve space in the TBM and avoid duplication, it contains numerous references providing an entry point into the internal dosimetry literature relevant to this program. The TBM is not intended to act as a policy or procedure statement, but will supplement the information normally found in procedures or policy documents. The internal dosimetry program outlined in this manual is intended to meet the requirements of Federal Rule 10CFR835 for monitoring the workplace and for assessing internal radiation doses to workers.
Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the
Danglers in Patient Information Leaflets and Technical Manuals

DEFF Research Database (Denmark)

Køhler Simonsen, Henrik

2014-01-01

in fact been proved. The analysis and the discussion showed that dangling participles are not very frequent in PILs, but much more common in technical manuals. The data showed that there were no “ludicrous” danglers,(see Matthews and Matthews 2008:146), in PILcorp. However, the analysis showed that both......Dangling participles and other types of ambiguous or unclear sentence constructions in directive and informative medical and technical texts, such as patient information leaflets (PILs) and technical manuals, render instructions unclear and potentially dangerous for the layman reader, i......, and readability on the basis of two corpora: a corpus of PILs (PILcorp) and a corpus of technical manuals (TECHcorp). The hypothesis is that patient information leaflets will contain fewer dangling constructions than technical manuals because of the strict regulations on product information texts including PILs...
Technical Basis Document for PFP Area Monitoring Dosimetry Program

CERN Document Server

Cooper, J R

2000-01-01

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.
Technical Basis Document for PFP Area Monitoring Dosimetry Program

International Nuclear Information System (INIS)

COOPER, J.R.

2000-01-01

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual
Technical Basis Document for PFP Area Monitoring Dosimetry Program

Energy Technology Data Exchange (ETDEWEB)

COOPER, J.R.

2000-04-17

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.
Fuel Element Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Burley, H.H. [ed.

1956-08-01

It is the purpose of the Fuel Element Technical Manual to Provide a single document describing the fabrication processes used in the manufacture of the fuel element as well as the technical bases for these processes. The manual will be instrumental in the indoctrination of personnel new to the field and will provide a single data reference for all personnel involved in the design or manufacture of the fuel element. The material contained in this manual was assembled by members of the Engineering Department and the Manufacturing Department at the Hanford Atomic Products Operation between the dates October, 1955 and June, 1956. Arrangement of the manual. The manual is divided into six parts: Part I--introduction; Part II--technical bases; Part III--process; Part IV--plant and equipment; Part V--process control and improvement; and VI--safety.
Technical Manual. The ACT®

Science.gov (United States)

ACT, Inc., 2014

2014-01-01

This manual contains technical information about the ACT® college readiness assessment. The principal purpose of this manual is to document the technical characteristics of the ACT in light of its intended purposes. ACT regularly conducts research as part of the ongoing formative evaluation of its programs. The research is intended to ensure that…
Technical basis and evaluation criteria for an air sampling/monitoring program

International Nuclear Information System (INIS)

Gregory, D.C.; Bryan, W.L.; Falter, K.G.

1993-01-01

Air sampling and monitoring programs at DOE facilities need to be reviewed in light of revised requirements and guidance found in, for example, DOE Order 5480.6 (RadCon Manual). Accordingly, the Oak Ridge National Laboratory (ORNL) air monitoring program is being revised and placed on a sound technical basis. A draft technical basis document has been written to establish placement criteria for instruments and to guide the ''retrospective sampling or real-time monitoring'' decision. Facility evaluations are being used to document air sampling/monitoring needs, and instruments are being evaluated in light of these needs. The steps used to develop this program and the technical basis for instrument placement are described
Technical basis for the internal dosimetry program at the Y-12 Plant

International Nuclear Information System (INIS)

Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

1992-01-01

Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document
ACT Plan: Technical Manual. 2013/2014

Science.gov (United States)

ACT, Inc., 2013

2013-01-01

This manual contains information about the American College Test (ACT) Plan® program. The principal focus of this manual is to document the Plan program's technical adequacy in light of its intended purposes. This manual supersedes the 2011 edition. The content of this manual responds to requirements of the testing industry as established in the…

Technical Manual: 2002 Series GED Tests

Science.gov (United States)

Ezzelle, Carol; Setzer, J. Carl

2009-01-01

This manual was written to provide technical information regarding the 2002 Series GED (General Educational Development) Tests. Throughout this manual, documentation is provided regarding the development of the GED Tests, data collection activities, as well as reliability and validity evidence. The purpose of this manual is to provide evidence…
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
Technical Manual: easyCBM. Technical Report #1408

Science.gov (United States)

Anderson, Daniel; Alonzo, Julie; Tindal, Gerald; Farley, Dan; Irvin, P. Shawn; Lai, Cheng-Fei; Saven, Jessica L.; Wray, Kraig A.

2014-01-01

Since the easyCBM© learning system was first published in 2006, over $8 million of federal funding (both from the Office of Special Education Programs and more recently from the Institute of Education Sciences) has been used to develop, study, and refine the assessments available on the system. This Technical Manual summarizes the ongoing research…
Technical reference manual for TIME4. Vol. 2

International Nuclear Information System (INIS)

Wilmot, R.D.; Ringrose, P.S.; Larkin, J.P.A.; Kleissen, F.A.T.

1991-07-01

This document is the Technical Reference Manual for the TIME4 model. TIME4 is the environmental change model developed for use in the probabilistic risk analysis of deep disposal of radioactive waste. The Technical Reference Manual describes the theoretical background to the model. The modelling method is described, followed by a review of related work and a detailed description for each sub-model. (author)
OSH technical reference manual

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

In an evaluation of the Department of Energy (DOE) Occupational Safety and Health programs for government-owned contractor-operated (GOCO) activities, the Department of Labor`s Occupational Safety and Health Administration (OSHA) recommended a technical information exchange program. The intent was to share written safety and health programs, plans, training manuals, and materials within the entire DOE community. The OSH Technical Reference (OTR) helps support the secretary`s response to the OSHA finding by providing a one-stop resource and referral for technical information that relates to safe operations and practice. It also serves as a technical information exchange tool to reference DOE-wide materials pertinent to specific safety topics and, with some modification, as a training aid. The OTR bridges the gap between general safety documents and very specific requirements documents. It is tailored to the DOE community and incorporates DOE field experience.
River Corridor Project Workplace Air Monitoring Technical Basis

International Nuclear Information System (INIS)

MANTOOTH, D.S.

2001-01-01

This document provides the technical basis by which the workplace air monitoring and sampling program is operated in the River Corridor Project (RCP). Revision 2 addresses and incorporates changes in the air monitoring program drivers and implementing documents which occurred after the previous revision was issued. This revision also includes an additional RCP project to make Revision 2 applicable to the entire RCP. These changes occurred in the following areas: (1) Changes resulting from the conversion of the Hanford Site Radiological Control Manual (HSRCM-1) into the Project Hanford Radiological Control Manual (F-5173). HNF-5173 is now the implementing document for 10CFR835. (2) Changes resulting from the issue of new and revised Hanford Site implementing procedures. (3) Changes resulting from the issue of new and revised, as well as the cancellation of RCP implementing procedures. (4) Addition of the 200 Area Accelerated Deactivation Project (ADP). (5) Modification of some air sampling/monitoring locations to better meet the needs of facility operations. (6) Changes resulting from the RCP reorganization
Pollutant Assessments Group procedures manual: Volume 2, Technical procedures

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

This is volume 2 of the manuals that describes the technical procedures currently in use by the Pollution Assessments Group. This manual incorporates new developments in hazardous waste assessment technology and administrative policy. Descriptions of the equipment, procedures and operations of such things as radiation detection, soil sampling, radionuclide monitoring, and equipment decontamination are included in this manual. (MB)
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.
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.
MCO loading and cask loadout technical manual

International Nuclear Information System (INIS)

PRAGA, A.N.

1998-01-01

A compilation of the technical basis for loading a multi-canister overpack (MCO) with spent nuclear fuel and then placing the MCO into a cask for shipment to the Cold Vacuum Drying Facility. The technical basis includes a description of the process, process technology that forms the basis for loading alternatives, process control considerations, safety considerations, equipment description, and a brief facility structure description
Technical reference manual for TIME4. Version 1.0, Volume 1

International Nuclear Information System (INIS)

Wilmot, R.D.; Ringrose, P.S.; Larkin, J.P.A.; Kleissen, F.A.T.

1991-07-01

This document is the Technical Reference Manual for the TIME4 model. TIME4 is the environmental change model developed for use in the probabilistic risk analysis of deep disposal of radioactive waste. The Technical Reference Manual describes the theoretical background to the model. The modelling method is described, followed by a review of related work and a detailed description for each sub-model. (author)
Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

International Nuclear Information System (INIS)

Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

1978-10-01

The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems
Dose measurements with a HPGe detector - a technical manual

Energy Technology Data Exchange (ETDEWEB)

Lidstroem, K.; Nordenfors, C.; Aagren, G

2000-06-01

This paper is a technical manual for estimations of dose based on a gamma spectrum. The method used is based on the Monte Carlo code EGS4. Since dose estimations from spectra are specific for each detector, this work is performed on two mobile HPGe detectors at FOA NBC Defence in Umeaa. This technical manual describes the method used in three steps: Part 1 explains how to construct a model of the detector geometry and the specific material for a new detector. Part 2 describes the underlying work of Monte Carlo simulations of a detector given geometry and material. Part 3 describes dose estimations from a gamma spectrum.
Amplification in Technical Manuals: Theory and Practice.

Science.gov (United States)

Killingsworth, M. Jimmie; And Others

1989-01-01

Examines how amplification (rhetorical techniques by which discourse is extended to enhance its appeal and information value) tends to increase and improve the coverage, rationale, warnings, behavioral alternatives, examples, previews, and general emphasis of technical manuals. Shows how classical and modern rhetorical theories can be applied to…
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
Technical Manual for the SAM Biomass Power Generation Model

Energy Technology Data Exchange (ETDEWEB)

Jorgenson, J.; Gilman, P.; Dobos, A.

2011-09-01

This technical manual provides context for the implementation of the biomass electric power generation performance model in the National Renewable Energy Laboratory's (NREL's) System Advisor Model (SAM). Additionally, the report details the engineering and scientific principles behind the underlying calculations in the model. The framework established in this manual is designed to give users a complete understanding of behind-the-scenes calculations and the results generated.
Research and Development Issues for Interactive Electronic Technical Manuals

National Research Council Canada - National Science Library

Ricci, Katrina

2002-01-01

.... While there is a wide range of research issues associated with technical manuals, the focus of the Intelligent Performance Support and Training effort is the development and evaluation of various...
Research and Development Issues for Interactive Electronic Technical Manuals

National Research Council Canada - National Science Library

Ricci, Katrina

2002-01-01

... technologies to support Interactive Electronic Technical Manuals (IETMs). A workshop was conducted at the NAVAIR Orlando, Training Systems Division to discuss the domain and to present current research in this area...

TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

International Nuclear Information System (INIS)

KRIPPS, L.J.

2006-01-01

This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls
TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

Energy Technology Data Exchange (ETDEWEB)

BERGLIN, E J

2003-06-23

This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.
Technical manual for calculating cooling pond performance

International Nuclear Information System (INIS)

Krstulovich, S.F.

1988-01-01

This manual is produced in response to a growing number of requests for a technical aid to explain methods for simulating cooling pond performance. As such, it is a compilation of reports, charts and graphs developed through the years for use in analyzing situations. Section II contains a report summarizing the factors affecting cooling pond performance and lists statistical parameters used in developing performance simulations. Section III contains the graphs of simulated cooling pond performance on an hourly basis for various combinations of criteria (wind, solar, depth, air temperature and humidity) developed from the report in Section II. Section IV contains correspondence describing how to develop further data from the graphs in Section III, as well as mathematical models for the system of performance calculation. Section V contains the formulas used to simulate cooling pond performances in a cascade arrangement, such as the Fermilab Main Ring ponds. Section VI contains the calculations currently in use to evaluate the Main Ring pond performance based on current flows and Watts loadings. Section VII contains the overall site drawing of the Main Ring cooling ponds with thermal analysis and physical data
Radioactive Waste Management Basis

International Nuclear Information System (INIS)

Perkins, B.K.

2009-01-01

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.
FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

KRIPPS, L.J.

2005-03-03

This document describes the qualitative evaluation of frequency and consequences for DST and SST representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant structures, systems and components (SSCs) and/or technical safety requirements (TSRs) were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support WP-13033, Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.
Technical basis document for natural event hazards

International Nuclear Information System (INIS)

CARSON, D.M.

2003-01-01

This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for natural event hazards (NEH)-initiated representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report
The Job Training and Job Satisfaction Survey Technical Manual

Science.gov (United States)

Schmidt, Steven W.

2004-01-01

Job training has become an important aspect of an employee's overall job experience. However, it is not often called out specifically on instruments measuring job satisfaction. This technical manual details the processes used in the development and validation of a survey instrument to measure job training satisfaction and overall job…
Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; Brion Bennett

2011-09-01

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 Fuels Complex 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.
Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

International Nuclear Information System (INIS)

Harvego, Lisa; Bennett, Brion

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 Fuels Complex 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.
Radioactive Waste Management BasisApril 2006

Energy Technology Data Exchange (ETDEWEB)

Perkins, B K

2011-08-31

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.
Radiological control manual. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Kloepping, R.

1996-05-01

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.
Radiological control manual. Revision 1

International Nuclear Information System (INIS)

Kloepping, R.

1996-05-01

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP
ITER technical basis

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.
ITER technical basis

International Nuclear Information System (INIS)

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties
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.
Technical basis for tumbleweed survey requirements and disposal criteria

International Nuclear Information System (INIS)

J. D. Arana

2000-01-01

This technical basis document describes the technique for surveying potentially contaminated tumbleweeds in areas where the Environmental Restoration Contractor has jurisdiction and the disposal criteria based on these survey results. The report also discusses the statistical basis for surveys and the historical basis for the assumptions that are used to interpret the surveys
Technical Basis for Tumbleweed Survey Requirements and Disposal Criteria

International Nuclear Information System (INIS)

Arana, J.D.

2000-01-01

This technical basis document describes the technique for surveying potentially contaminated tumbleweeds in areas where the Environmental Restoration Contractor has jurisdiction and the disposal criteria based on these survey results. The report also discusses the statistical basis for surveys and the historical basis for the assumptions that are used to interpret the surveys
Technical basis document for external events

International Nuclear Information System (INIS)

OBERG, B.D.

2003-01-01

This document supports the Tank Farms Documented Safety Analysis and presents the technical basis for the FR-equencies of externally initiated accidents. The consequences of externally initiated events are discussed in other documents that correspond to the accident that was caused by the external event. The external events include aircraft crash, vehicle accident, range fire, and rail accident
FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

KRIPPS, L.J.

2005-02-18

This document describes the qualitative evaluation of frequency and consequences for double shell tank (DST) and single shell tank (SST) representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant SSCs and/or TSRS were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support of the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.
Writing Performance Goals: Strategy and Prototypes. A Manual for Vocational and Technical Educators.

Science.gov (United States)

McGraw-Hill Book Co., New York, NY. Gregg Div.

The result of a cooperative project of the Center for Vocational and Technical Education at the Ohio State University and the McGraw-Hill Book Company, this manual was prepared to develop prototypes of performance goals for use by curriculum specialists and developers of instructional materials in vocational and technical education and to provide…

Technical basis for the aboveground structure failure and associated represented hazardous conditions

International Nuclear Information System (INIS)

GOETZ, T.G.

2003-01-01

This technical basis document describes the risk binning process and the technical basis for assigning risk bins for the aboveground structure failure representative accident and associated represented hazardous conditions. This document was developed to support the documented safety analysis
ALWR utility requirements - A technical basis for updated emergency planning

International Nuclear Information System (INIS)

Leaver, David E.W.; DeVine, John C. Jr.; Santucci, Joseph

2004-01-01

U.S. utilities, with substantial support from international utilities, are developing a comprehensive set of design requirements in the form of a Utility Requirements Document (URD) as part of an industry wide effort to establish a technical foundation for the next generation of light water reactors. A key aspect of the URD is a set of severe accident-related design requirements which have been developed to provide a technical basis for updated emergency planning for the ALWR. The technical basis includes design criteria for containment performance and offsite dose during severe accident conditions. An ALWR emergency planning concept is being developed which reflects this severe accident capability. The main conclusion from this work is that the likelihood and consequences of a severe accident for an ALWR are fundamentally different from that assumed in the technical basis for existing emergency planning requirements, at least in the U.S. The current technical understanding of severe accident risk is greatly improved compared to that available when the existing U.S. emergency planning requirements were established nearly 15 years ago, and the emerging ALWR designs have superior core damage prevention and severe accident mitigation capability. Thus, it is reasonable and prudent to reflect this design capability in the emergency planning requirements for the ALWR. (author)
Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system

International Nuclear Information System (INIS)

Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

1993-03-01

The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data
Cost-Benefit Analysis of a Bridge to Integrate the Management of Technical Information for Producing Technical Manuals and Training Courses

Science.gov (United States)

2010-11-01

Philadelphia, and all Computer-Based Training (CBT) courses delivered by Navy eLearning (NeL), a part of the Naval Education and Training Command (NETC...concentrated exclu- sively on the benefit side—whether the Bridge would save money in producing future technical manuals and training courses. It...of $78.1 million in 10-year costs: a savings of $86.8 million in producing future HM&E manuals and NeL-delivered courses less $8.7 million in
Technical basis for the ITER-FEAT outline design

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-11-01

This ITER EDA Documentation Series issue summarizes the results of the ITER Engineering Design Activities on the technical basis for the ITER-FEAT outline design. This issue also comprises some physical analysis activities as well as structure and goals of the Physics Expert Group activities.
Technical basis for the ITER-FEAT outline design

International Nuclear Information System (INIS)

2000-01-01

This ITER EDA Documentation Series issue summarizes the results of the ITER Engineering Design Activities on the technical basis for the ITER-FEAT outline design. This issue also comprises some physical analysis activities as well as structure and goals of the Physics Expert Group activities
RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

International Nuclear Information System (INIS)

KOZLOWSKI, S.D.

2007-01-01

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below
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
TASS code topical report. V.1 TASS code technical manual

International Nuclear Information System (INIS)

Sim, Suk K.; Chang, W. P.; Kim, K. D.; Kim, H. C.; Yoon, H. Y.

1997-02-01

TASS 1.0 code has been developed at KAERI for the initial and reload non-LOCA safety analysis for the operating PWRs as well as the PWRs under construction in Korea. TASS code will replace various vendor's non-LOCA safety analysis codes currently used for the Westinghouse and ABB-CE type PWRs in Korea. This can be achieved through TASS code input modifications specific to each reactor type. The TASS code can be run interactively through the keyboard operation. A simimodular configuration used in developing the TASS code enables the user easily implement new models. TASS code has been programmed using FORTRAN77 which makes it easy to install and port for different computer environments. The TASS code can be utilized for the steady state simulation as well as the non-LOCA transient simulations such as power excursions, reactor coolant pump trips, load rejections, loss of feedwater, steam line breaks, steam generator tube ruptures, rod withdrawal and drop, and anticipated transients without scram (ATWS). The malfunctions of the control systems, components, operator actions and the transients caused by the malfunctions can be easily simulated using the TASS code. This technical report describes the TASS 1.0 code models including reactor thermal hydraulic, reactor core and control models. This TASS code models including reactor thermal hydraulic, reactor core and control models. This TASS code technical manual has been prepared as a part of the TASS code manual which includes TASS code user's manual and TASS code validation report, and will be submitted to the regulatory body as a TASS code topical report for a licensing non-LOCA safety analysis for the Westinghouse and ABB-CE type PWRs operating and under construction in Korea. (author). 42 refs., 29 tabs., 32 figs
Technical Basis for PNNL Beryllium Inventory

Energy Technology Data Exchange (ETDEWEB)

Johnson, Michelle Lynn

2014-07-09

The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.
Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

1993-03-01

The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data.
Radioactive Waste Management BasisSept 2001

International Nuclear Information System (INIS)

Goodwin, S.S.

2011-01-01

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.
Mixing of incompatible materials in waste tanks technical basis document

International Nuclear Information System (INIS)

SANDGREN, K.R.

2003-01-01

This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process, the technical basis for assigning risk bins, and the controls selected for the mixing of incompatible materials representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSCs) and/or technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the FR-equency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report
Understanding and capturing NSSS design basis

International Nuclear Information System (INIS)

Palo, W.J.; Miller, B.

1993-01-01

Changes to, and technical evaluations of nuclear generating station designs are often warranted. Comprehensive documentation and understanding of the NSSS Design Basis are essential to support these activities. Effective configuration management tools are also needed to maintain the plant within design basis limits. Efficient design basis reconstitution can be realized via: In-depth understanding of the design process; Utilization of effective data collection methodology; State of the art data basing tools. A database can be created to generate a Design Basis Manual (DBM). This database can communicate electronically with other plant databases. A living document vice a static snapshot of the plant design is the goal. A design basis database can serve as the cornerstone for a global electronic information control system
Technical Basis to Describe the Use of the Eberline E-600

International Nuclear Information System (INIS)

Brehm, D.M.

1998-03-01

This technical basis document describes the parameters and conditions under which the Eberline E-600 rate meter and the associated detectors can be operated to quantify ionizing radiation and radiological contamination
77 FR 39800 - Nondiscrimination on the Basis of Disability in Air Travel: Draft Technical Assistance Manual

Science.gov (United States)

2012-07-05

.... Italics and Bold Text Italics and boldfaced type are used throughout the manual to draw attention to a... procedures which affect or may affect the types of accommodations and services provided to passengers with... a memory aid to Ask, Call, Check, Evaluate, Solve, and Satisfy, for use when resolving complaints...
Technical basis for removal of 221-T tunnel from airborne radiological area status

International Nuclear Information System (INIS)

Geuther, W.J.

1996-01-01

This document provides the technical basis for removal of the 221-T Tunnel from airborne radiological control. T Plant Radiological Control has evaluated air sampling data and engineering controls, and determined the necessary administrative controls to make this transition. With these administrative controls (specified within document) in place, the tunnel can be removed from Airborne Radioactive Area status. The removal of the tunnel from airborne status will allow work to be performed within the tunnel under controlled conditions, as outlined in this technical basis, without the use of respiratory protection equipment
Tools to support important technical decisions during accident conditions

International Nuclear Information System (INIS)

Tenschert, J.; Bergiers, C.

2008-01-01

To handle design basis and beyond design basis accidents with intact reactor core, Nuclear Power Plants are using Emergency Operating Procedures (EOP) that they may have developed based on the generic Westinghouse Emergency Response Guidelines. Even though the EOPs are very directive, some questions are left to external support, i.e. to a team of persons constituting the so-called Technical Support Center (TSC). The Pressurized Water Reactor Owner Group (PWROG, previously Westinghouse Owner Group, WOG) has developed a TSC manual to support this group in their decision making process. Because of the specific and particular design of the Beznau NPP (KKB) Safety Systems, development of a plant-specific TSC manual required a lot of additions compared to the generic material. This plant-specific TSC manual is a helpful tool for the Site Emergency Director (SED) of the KKB to better evaluate issues and potential concerns arising while executing the EOPs. The majority of considered issues are relevant for beyond design basis accidents and external events. (orig.)
Flammable gas tank safety program: Technical basis for gas analysis and monitoring

International Nuclear Information System (INIS)

Estey, S.D.

1998-01-01

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms
Technical Basis for Implementation of the PCM-1B for Personnel Release at Tank Farms

International Nuclear Information System (INIS)

BROWN, R.L.

1999-01-01

The purpose of this document is to define the technical basis and implementing guidelines for using automated personnel contamination monitors, such as the PCM-1B, at the River Protection Project (RPP) in lieu of performing a hand-held instrument followed by a PCM-1B survey for personnel release from contamination areas requiring a beta-gamma whole body survey. This document provides the basis for full implementation of the PCM-1B release survey, without the supplemental hand and foot survey, as currently implemented at RPP. This document applies only to RPP facilities. This document does not provide the technical basis for determining the equivalency of an automated system to hand-held instruments, or to the effective counting capability of automated systems as such technical determinations are contained in TBTN: GDGH-9604-RLS-0015

IAEA safeguards technical manual

International Nuclear Information System (INIS)

1980-02-01

The necessity for statistical inference procedures arises because of time and cost limitations imposed on inspection activities, and also because of inherent limitations of inspection measurement instruments and techniques. This manual produces statistical concepts and techniques in the field of nuclear material control
Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.
Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.
Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs
Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs
Manual on indoor air quality

International Nuclear Information System (INIS)

Diamond, R.C.; Grimsrud, D.T.

1983-12-01

This reference manual was prepared to assist electric utilities in helping homeowners, builders, and new home buyers to understand a broad range of issues related to indoor air quality. The manual is directed to technically knowledgeable persons employed by utility companies - the customer service or marketing representative, applications engineer, or technician - who may not have specific expertise in indoor air quality issues. In addition to providing monitoring and control techniques, the manual summarizes the link between pollutant concentrations, air exchange, and energy conservation and describes the characteristics and health effects of selected pollutants. Where technical information is too lengthy or complex for inclusion in this volume, reference sources are given. Information for this manual was gathered from technical studies, manufacturers' information, and other materials from professional societies, institutes, and associations. The aim has been to provide objective technical and descriptive information that can be used by utility personnel to make informed decisions about indoor air quality issues
Manual on indoor air quality

Energy Technology Data Exchange (ETDEWEB)

Diamond, R.C.; Grimsrud, D.T.

1983-12-01

This reference manual was prepared to assist electric utilities in helping homeowners, builders, and new home buyers to understand a broad range of issues related to indoor air quality. The manual is directed to technically knowledgeable persons employed by utility companies - the customer service or marketing representative, applications engineer, or technician - who may not have specific expertise in indoor air quality issues. In addition to providing monitoring and control techniques, the manual summarizes the link between pollutant concentrations, air exchange, and energy conservation and describes the characteristics and health effects of selected pollutants. Where technical information is too lengthy or complex for inclusion in this volume, reference sources are given. Information for this manual was gathered from technical studies, manufacturers' information, and other materials from professional societies, institutes, and associations. The aim has been to provide objective technical and descriptive information that can be used by utility personnel to make informed decisions about indoor air quality issues.
General Drafting. Technical Manual.

Science.gov (United States)

Department of the Army, Washington, DC.

The manual provides instructional guidance and reference material in the principles and procedures of general drafting and constitutes the primary study text for personnel in drafting as a military occupational specialty. Included is information on drafting equipment and its use; line weights, conventions and formats; lettering; engineering charts…
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.
Independent Electricity Market Operator integration management participant technical reference manual

International Nuclear Information System (INIS)

1999-01-01

The document provides potential participants with the essential technical information to permit them to participate in the IMO-administered markets, and is not intended to be a complete technical reference manual for all issues within the realm of electricity production, distribution, or consumption. Written for the participants, it provides only that information which is relevant to the participant for interfacing with the IMO and participating in the market. Written as a generic guide, all the information contained within it may not be relevant to all the participants. The document's intent is to provide participants with a description of the various facilities and interfaces required by market participants to take part in the IMO-administered markets. The document supplements the market rules and provides installation, set-up, and configuration information for the various tools and facilities that will be required for market participation as a supplier, carrier/delivery (transmitter/distributor), generator, or consumer in the market. Aspects considered include: participant workstation specifications, dispatch workstation specification, message exchange, remote terminal unit specification, AGC operational RTU specification, real time network connection specification, telephone connection specification, revenue administration specification, funds administration specification, data catalogues, market information, power grid connection requirements, and appendices
Emergency preparedness in Germany. Development of manuals for emergency exercises

International Nuclear Information System (INIS)

Bath, N.; Berg, H.P.

2001-01-01

Extensive technical and administrative measures are taken in the German nuclear power plants in order to be able to perform effective on-site accident management in case that an event actually occurs. Because of the 'beyond-design-basis' character of these accidents, there are no detailed regulations and guidelines for the development of emergency preparedness in Germany. However, it has become common practice to perform at least one emergency exercise per year in every German nuclear plant. Bundesamt fuer Strahlenschutz has launched a project for the development of a manual for planning, co-ordination, and assessment of on-site accident management exercises. The objective is to establish an approach with a sound technical basis harmonized on federal level. The current status of this project and further activities are described.(author)
Functional imaging in oncology. Biophysical basis and technical approaches. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Luna, Antonio [Health Time Group, Jaen (Spain); University Hospitals, Case Western Reserve Univ., Cleveland, OH (United States). Dept. of Radiology; Vilanova, Joan C. [Clinica Girona - Hospital Sta. Caterina, Girona (Spain); Hygino da Cruz, L. Celso Jr. [CDPI and IRM, Rio de Janeiro, RJ (Brazil). Dept. of Radiology; Rossi, Santiago E. (ed.) [Centro de Diagnostico, Buenos Aires (Argentina)

2014-07-01

Easy-to-read manual on new functional imaging techniques in oncology. Explains current clinical applications and outlines future avenues. Includes numerous high-quality illustrations to highlight the major teaching points. In the new era of functional and molecular imaging, both currently available imaging biomarkers and biomarkers under development are expected to lead to major changes in the management of oncological patients. This well-illustrated two-volume book is a practical manual on the various imaging techniques capable of delivering functional information on cancer, including preclinical and clinical imaging techniques, based on US, CT, MRI, PET and hybrid modalities. This first volume explains the biophysical basis for these functional imaging techniques and describes the techniques themselves. Detailed information is provided on the imaging of cancer hallmarks, including angiogenesis, tumor metabolism, and hypoxia. The techniques and their roles are then discussed individually, covering the full range of modalities in clinical use as well as new molecular and functional techniques. The value of a multiparametric approach is also carefully considered.
Functional imaging in oncology. Biophysical basis and technical approaches. Vol. 1

International Nuclear Information System (INIS)

Luna, Antonio; Hygino da Cruz, L. Celso Jr.

2014-01-01

Easy-to-read manual on new functional imaging techniques in oncology. Explains current clinical applications and outlines future avenues. Includes numerous high-quality illustrations to highlight the major teaching points. In the new era of functional and molecular imaging, both currently available imaging biomarkers and biomarkers under development are expected to lead to major changes in the management of oncological patients. This well-illustrated two-volume book is a practical manual on the various imaging techniques capable of delivering functional information on cancer, including preclinical and clinical imaging techniques, based on US, CT, MRI, PET and hybrid modalities. This first volume explains the biophysical basis for these functional imaging techniques and describes the techniques themselves. Detailed information is provided on the imaging of cancer hallmarks, including angiogenesis, tumor metabolism, and hypoxia. The techniques and their roles are then discussed individually, covering the full range of modalities in clinical use as well as new molecular and functional techniques. The value of a multiparametric approach is also carefully considered.
High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

International Nuclear Information System (INIS)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report
High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

Energy Technology Data Exchange (ETDEWEB)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.
Technical basis document for internal dosimetry

CERN Document Server

Hickman, D P

1991-01-01

This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosi...
SEE Action Guide for States: Guidance on Establishing and Maintaining Technical Reference Manuals for Energy Efficiency Measures

Energy Technology Data Exchange (ETDEWEB)

None

2017-06-01

The goal of this guide is to support the development, maintenance, and use of accurate and reliable Technical Reference Manuals (TRMs). TRMs provide information primarily used for estimating the energy and demand savings of end-use energy efficiency measures associated with utility customer-funded efficiency programs.
TECHNICAL SUPPORT AS A BASIS OF HIGH AVAILABILITY LEVEL AND IT SYSTEM SERVICE QUALITY

Directory of Open Access Journals (Sweden)

Dejan Vidojevic

2007-06-01

Full Text Available This work presents the development and implementation methodology of technical support in IT1system operation. Methodology is developed and applied in realistic system (Information system of the Tax administration - DIS 2003, which is technically very complex and highly distributed. The results of IT system availability assessment and identification of the critical components are input parameters in the process of establishing of the technical support. The importance of technical support for achieving optimal IT system availability and IT service quality is assessed according to its operation during one year. The history of technical support system operation is a basis for further continuous improvement.
High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

International Nuclear Information System (INIS)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report
Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors

Science.gov (United States)

Gordon, Barry; Garcia, Susan

Boiling water reactors (BWRs) operate with very high purity water. However, even the utilization of near theoretical conductivity water cannot prevent intergranular stress corrosion cracking (IGSCC) of sensitized stainless steel, wrought nickel alloys and nickel weld metals under oxygenated conditions. IGSCC can be further accelerated by the presence of certain impurities dissolved in the coolant. The goal of this paper is to present the technical basis for controlling various impurities under both oxygenated, i.e., normal water chemistry (NWC) and deoxygenated, i.e., hydrogen water chemistry (HWC) conditions for mitigation of IGSCC. More specifically, the effects of typical BWR ionic impurities (e.g., sulfate, chloride, nitrate, borate, phosphate, etc.) on IGSCC propensities in both NWC and HWC environments will be discussed. The technical basis for zinc addition to the BWR coolant will also provided along with an in-plant example of the most severe water chemistry transient to date.

Technical Basis for Electromagnetic Compatibility Regulatory Guidance Update

Energy Technology Data Exchange (ETDEWEB)

Ewing, Paul D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Korsah, Kofi [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard Thomas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mays, Gary T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-03-01

The objective of this report is to serve as the technical basis document for the next, planned revision of this RG that highlights and provides the rationale for the recommended changes. The structure of this document follows and summarizes the several assessment activities undertaken during the course of this project to evaluate new and updated electromagnetic compatibility (EMC) standards, testing methods and limits, and relevant technology developments being incorporated into plant activities that may have EMI/RFI implications, as well as other specific issues, including impacts of electrostatic discharge (ESD) on safety equipment and impacts on increased usage of wireless devices in nuclear power plants.
TECHNICAL BASIS DOCUMENT FOR AT-POWER SIGNIFICANCE DETERMINATION PROCESS (SDP) NOTEBOOKS

International Nuclear Information System (INIS)

AZARM, M.A.; SMANTA, P.K.; MARTINEZ-GURIDI, G.; HIGGINS, J.

2004-01-01

To support the assessment of inspection findings as part of the risk-informed inspection in the United States Nuclear Regulatory Commission's (USNRC's) Reactor Oversight Process (ROP), risk inspection notebooks, also called significance determination process (SDP) notebooks, have been developed for each of the operating plants in the United States. These notebooks serve as a tool for assessing risk significance of inspection findings along with providing an engineering understanding of the significance. Plant-specific notebooks are developed to capture plant-specific features, characteristics, and analyses that influence the risk profile of the plant. At the same time, the notebooks follow a consistent set of assumptions and guidelines to assure consistent treatment of inspection findings across the plants. To achieve these objectives, notebooks are designed to provide specific information that are unique both in the manner in which the information is provided and in the way the screening risk assessment is carried out using the information provided. The unique features of the SDP notebooks, the approaches used to present the information for assessment of inspection findings, the assumptions used in consistent modeling across different plants with due credit to plant-specific features and analyses form the technical basis of the SDP notebooks. In this document, the unique features and the technical basis for the notebooks are presented. The types of information that are included and the reasoning/basis for including that information are discussed. The rules and basis for developing the worksheets that are used by the inspectors in the assessment of inspection findings are presented. The approach to modeling plants' responses to different initiating events and specific assumptions/considerations used for each of the reactor types are also discussed
Manual of engineering drawing technical product specification and documentation to British and international standards

CERN Document Server

Simmons, Colin H; Simmons, Colin

2012-01-01

Manual of Engineering Drawing is a comprehensive guide for experts and novices for producing engineering drawings and annotated 3D models that meet the recent BSI and ISO standards of technical product documentation and specifications. This fourth edition of the text has been updated in line with recent standard revisions and amendments. The book has been prepared for international use, and includes a comprehensive discussion of the fundamental differences between the ISO and ASME standards, as well as recent updates regarding legal components, such as copyright, patents, and other legal considerations. The text is applicable to CAD and manual drawing, and it covers the recent developments in 3D annotation and surface texture specifications. Its scope also covers the concepts of pictorial and orthographic projections, geometrical, dimensional and surface tolerancing, and the principle of duality. The text also presents numerous examples of hydraulic and electrical diagrams, applications, bearings, adhesives, ...
Technical Basis - Spent Nuclear Fuels (SNF) Project Radiation and Contamination Trending Program

International Nuclear Information System (INIS)

ELGIN, J.C.

2000-01-01

This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas
Technical Basis Document (TBD) and user guides

International Nuclear Information System (INIS)

Chiaro, P.J. Jr.

1998-09-01

A Technical Basis Document (TBD) should provide the background information for establishment of an instrument's operational requirements. Due to the amount and location of DOE facilities, no one set of requirements is possible. Operational requirements will vary based on the local environments and missions at each facility. Environmental conditions that can affect an instrument's operations are ambient temperature, humidity, and radio frequency, and to a lesser extent, magnetic fields, and interfering ionizing radiations. Consideration should also be made regarding how an instrument is to be used. If an instrument will be transported around the facility, vibration and shock can cause problems if they are not addressed in the TBD. This document provides guidance for the development of a TBD. This document applies to radiation instruments used for personnel and equipment contamination monitoring, dose rate monitoring, and air monitoring
Technical basis for exemption from alpha surveys for personnel, material, and equipment in the 324 facility

International Nuclear Information System (INIS)

RIDDELLE, J.G.

1998-01-01

The purpose of this document is to establish the technical basis for characterizing grouted B-Cell waste for disposal at the Hanford Burial Grounds using the 3-82B shipping cask. The scope of this document includes establishing the technical basis for loading the shipping package, an HN-200 Grout Container, to ensure that: (1) the amount of material in the grout container does not exceed the 100 nCl alpha/g limit that would cause the waste to be designated as ''greater that Category 3'' (GC3) or transuranic (TRU) waste (2) the amount of heat generated by the waste in the grout container does not exceed the 60 Watt heat generation limit established in the 3-82B shipping cask Safety Analysis Report (SAR); and (3) the dose rate on the surface of the shipping cask after loading does not exceed the 200 mrem/h limit established in the cask SAR. This document establishes the technical basis for performing measurements and analyses that will ensure that none of these three limits are exceeded
Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Bradley, E.W.; Wu, C.F.; Goff, T.E.

1993-01-01

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report
Providing a Scientific and Technical Basis for Repository Decisions

International Nuclear Information System (INIS)

2001-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 directed the U. S. Department of Energy (DOE) to research sites and design a deep geologic repository for the disposal of our nation's spent nuclear fuel and high-level radioactive waste. In 1987, Congress amended the NWPA and directed the DOE to focus only on Yucca Mountain, Nevada, to determine whether it is a suitable site for a repository. For more than 15 years, the DOE has been studying Yucca Mountain and has accumulated an enormous amount of scientific and technical information about the mountain and the area surrounding it. The secretary of energy will decide whether to recommend Yucca Mountain to the president as a suitable site for a repository. This decision will be based on the scientific and technical information resulting from the Department of Energy's studies of Yucca Mountain and on the views and comments submitted by other governmental groups and the public. One required basis for the secretary's decision will be a scientific analysis called a total system performance assessment
Spray Calciner/In-Can Melter high-level waste solidification technical manual

International Nuclear Information System (INIS)

Larson, D.E.

1980-09-01

This technical manual summarizes process and equipment technology developed at Pacific Northwest Laboratory over the last 20 years for vitrification of high-level liquid waste by the Spray Calciner/In-Can Melter process. Pacific Northwest Laboratory experience includes process development and demonstration in laboratory-, pilot-, and full-scale equipment using nonradioactive synthetic wastes. Also, laboratory- and pilot-scale process demonstrations have been conducted using actual high-level radioactive wastes. In the course of process development, more than 26 tonnes of borosilicate glass have been produced in 75 canisters. Four of these canisters contained radioactive waste glass. The associated process and glass chemistry is discussed. Technology areas described include calciner feed treatment and techniques, calcination, vitrification, off-gas treatment, glass containment (the canister), and waste glass chemistry. Areas of optimization and site-specific development that would be needed to adapt this base technology for specific plant application are indicated. A conceptual Spray Calciner/In-Can Melter system design and analyses are provided in the manual to assist prospective users in evaluating the process for plant application, to provide equipment design information, and to supply information for safety analyses and environmental reports. The base (generic) technology for the Spray Calciner/In-Can Melter process has been developed to a point at which it is ready for plant application
Combating illicit trafficking in nuclear and other radioactive material. Technical guidance. Reference manual. (Chinese Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation
The development of nuclear material accountability system - software user's manual

International Nuclear Information System (INIS)

Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

1999-07-01

We have developed the near-real time nuclear material accountability system, named by DMAS, for DUPIC Test Facility in the basis of the survey of DUPIC process and activities for the accountability of the system, and the review of the rules and regulations related to the nuclear material accounting. Our system adopts the structure and technologies used in COREMAS which was developed by LANL. This technical report illustrates the system structure and program usage as a user manual for DMAS. (author). 56 tabs., 1 fig
Establishment of the technical basis to apply the viscous damper in nuclear power plant

International Nuclear Information System (INIS)

Nakajima, J.; Suezono, N.; Higuchi, T.; Katayama, H.

2014-01-01

In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)
Establishment of the technical basis to apply the viscous damper in nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Nakajima, J.; Suezono, N.; Higuchi, T. [Toshiba Corp., Isogo Nuclear Engineering Center, Isogo-ku, Yokohama (Japan); Katayama, H. [Toshiba Corp., Power and Industrial Systems Research and Development Center, Isogo-ku, Yokohama (Japan)

2014-07-01

In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)
The Neural Basis of Speech Perception through Lipreading and Manual Cues: Evidence from Deaf Native Users of Cued Speech

Science.gov (United States)

Aparicio, Mario; Peigneux, Philippe; Charlier, Brigitte; Balériaux, Danielle; Kavec, Martin; Leybaert, Jacqueline

2017-01-01

We present here the first neuroimaging data for perception of Cued Speech (CS) by deaf adults who are native users of CS. CS is a visual mode of communicating a spoken language through a set of manual cues which accompany lipreading and disambiguate it. With CS, sublexical units of the oral language are conveyed clearly and completely through the visual modality without requiring hearing. The comparison of neural processing of CS in deaf individuals with processing of audiovisual (AV) speech in normally hearing individuals represents a unique opportunity to explore the similarities and differences in neural processing of an oral language delivered in a visuo-manual vs. an AV modality. The study included deaf adult participants who were early CS users and native hearing users of French who process speech audiovisually. Words were presented in an event-related fMRI design. Three conditions were presented to each group of participants. The deaf participants saw CS words (manual + lipread), words presented as manual cues alone, and words presented to be lipread without manual cues. The hearing group saw AV spoken words, audio-alone and lipread-alone. Three findings are highlighted. First, the middle and superior temporal gyrus (excluding Heschl’s gyrus) and left inferior frontal gyrus pars triangularis constituted a common, amodal neural basis for AV and CS perception. Second, integration was inferred in posterior parts of superior temporal sulcus for audio and lipread information in AV speech, but in the occipito-temporal junction, including MT/V5, for the manual cues and lipreading in CS. Third, the perception of manual cues showed a much greater overlap with the regions activated by CS (manual + lipreading) than lipreading alone did. This supports the notion that manual cues play a larger role than lipreading for CS processing. The present study contributes to a better understanding of the role of manual cues as support of visual speech perception in the framework
QUALIS OF TECHNICAL PRODUCTION: METRIC DEVELOPMENT FOR MANUALS.

Science.gov (United States)

Pacheco, Adhemar Monteiro; Mendes, Carlos José Lazzarini

2015-01-01

There are few authors focused on the study of preparing manuals criteria, often criticized for methodological rigor of the information. However, it is interesting to understand what is going wrong; to understand prognosis in self-handling; in prevention of complications; in identifying better services and information; in encouraging the pursuit of excellence in the healthcare. In its preparation should be valued the basic requirements of a manual, which are: 1) wrote in simple words, being concise, efficient, clear with index or table of contents; 2) using the existing institutional rules; 3) being flexible; and 4) having ongoing process of review, update and distribution. In the process of evaluation of Medicine III manuals may have the following stratification: M4 - 100 points: when there is ISBN registration and disclosure in other languages; M3 - 75 points: registration with the ISBN only in our country; M2 - 50 points: registered in regional libraries; M1 - 25 points: manual use for inter-departmental or intra-institutional groups; M0 - 0 point: use of manual in intra-departmental teaching. In conclusion, it is known that the use of manuals is focused to the ones who do not know the subject; however, it is also an important tool that can minimize errors, avoid professional misconduct, optimize resources, and at the end allowing assessment of the subject at hand. Poucos são os autores que se debruçam no estudo dos critérios de elaboração de manuais, sendo muitas vezes criticados pelo rigor metodológico das informações. Contudo, eles são interessantes no entender o que é errado, compreender prognóstico, na autoassistência, na prevenção de complicações, para identificar melhores serviços e informações, motivando a busca pela excelência no atendimento assistencial. Em sua elaboração devem ser valorizados os requisitos básicos de um manual, que são: 1) conter redação simples, concisa, eficiente e clara, contendo índice ou sumário; 2
Program Management System manual

International Nuclear Information System (INIS)

1986-01-01

The Program Management System (PMS), as detailed in this manual, consists of all the plans, policies, procedure, systems, and processes that, taken together, serve as a mechanism for managing the various subprograms and program elements in a cohesive, cost-effective manner. The PMS is consistent with the requirements of the Nuclear Waste Policy Act of 1982 and the ''Mission Plan for the Civilian Radioactive Waste Management Program'' (DOE/RW-0005). It is based on, but goes beyond, the Department of Energy (DOE) management policies and procedures applicable to all DOE programs by adapting these directives to the specific needs of the Civilian Radioactive Waste Management program. This PMS Manual describes the hierarchy of plans required to develop and maintain the cost, schedule, and technical baselines at the various organizational levels of the Civilian Radioactive Waste Management Program. It also establishes the management policies and procedures used in the implementation of the Program. These include requirements for internal reports, data, and other information; systems engineering management; regulatory compliance; safety; quality assurance; and institutional affairs. Although expanded versions of many of these plans, policies, and procedures are found in separate documents, they are an integral part of this manual. The PMS provides the basis for the effective management that is needed to ensure that the Civilian Radioactive Waste Management Program fulfills the mandate of the Nuclear Waste Policy Act of 1982. 5 figs., 2 tabs
Technical basis document for internal dosimetry

International Nuclear Information System (INIS)

Hickman, D.P.

1991-01-01

This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission
Technical basis for a minimum hydroxide concentration in tanks containing dilute waste

International Nuclear Information System (INIS)

Zapp, P.E.

1995-05-01

Laboratory tests were performed to address the protection of waste tank steel from corrosion in situations of elevated temperatures up to 75 C (hot spots) in the sludge layer of Extended Sludge Processing (ESP) tanks. Coupon immersion tests were conducted at 75 C in two ESP simulants at four hydroxide (or pH) levels. The nitrite concentrations of the simulants were calculated from the ESP technical standards based on a temperature of 40 C. The results showed that a hydroxide concentration of at least 0.01 M prevented significant corrosion of the steel at the elevated temperature. This conclusion provides the technical basis for the revised minimum hydroxide concentration of 0.01 M in the draft WSRC 241-82H Control Room Process Requirements, for the ESP tanks
GRACE manual

International Nuclear Information System (INIS)

Ishikawa, T.; Kawabata, S.; Shimizu, Y.; Kaneko, T.; Kato, K.; Tanaka, H.

1993-02-01

This manual is composed of three kinds of objects, theoretical background for calculating the cross section of elementary process, usage and technical details of the GRACE system. Throughout this manual we take the tree level process e + e - → W + W - γ as an example, including the e ± -scalar boson interactions. The real FORTRAN source code for this process is attached in the relevant sections as well as the results of calculation, which might be a great help for understanding the practical use of the system. (J.P.N.)
Interiors Construction Manual integrated planning, finishing and fitting out, technical servcies

CERN Document Server

Hausladen, Gerhard

2010-01-01

Soccer stadiums, airports, theaters, museums it falls to very few architects to tackle spectacular building tasks like these. The everyday work of most architects is more often focused on ""manageable"" projects like the renovation, remodeling, or rebuilding of single- and multi-family houses, schools, and offices. Whatever the nature of the building task, interior construction is always a significant design and qualitative challenge that calls for highly detailed technical expertise. After all, it affects the realm that will be brought to life and utilized by the user when the task is finished, and whose aesthetic and functional serviceability will be put to the test each and every day. The Interior Construction Manual supports planners in their daily work as a practical planning aid and reference work with the relevant standards, guidelines, reference details, and constructional solutions, all illustrated by built example projects. It brings together the crucial facts on all aspects of interior construction...

Technical basis for the preparation of emergency plans relating to pressurized water reactors

International Nuclear Information System (INIS)

L'Homme, A.; Manesse, D.; Gauvain, J.; Crabol, B.

1989-01-01

The paper begins by summarizing the standard French approach to management of severe accidents at PWR plants. It goes on to define the source term used as a general basis for emergency plans for protection of the civil population. The paper describes the impact this source term has on both the site and the environment, which is subsequently used as a technical basis for determining the response of the utility and the public authorities concerned. The discussion concludes with a brief outline of the current status of various emergency plans and a description of additional work currently in progress and aimed at improving these plans [fr
Technical basis of safeguards

International Nuclear Information System (INIS)

Buechler, C.

1975-01-01

Definition of nuclear materials control. Materials accountancy and physical control as technical possibilities. Legal possibilities and levels of responsibility: material holders, national and international authority. Detection vs. prevention. Physical security and containment surveillance. Accountancy: materials balance concept. Materials measurement: inventory taking, flow determination. IAEA safeguards; verification of operator's statement. (HP) [de
Process Technical Basis Documentation Diagram for a solid-waste processing facility

International Nuclear Information System (INIS)

Benar, C.J.; Petersen, C.A.

1994-02-01

The Process Technical Basis Documentation Diagram is for a solid-waste processing facility that could be designed to treat, package, and certify contact-handled mixed low-level waste for permanent disposal. The treatment processes include stabilization using cementitious materials and immobilization using a polymer material. The Diagram identifies several engineering/demonstration activities that would confirm the process selection and process design. An independent peer review was conducted at the request of Westinghouse Hanford Company to determine the technical adequacy of the technical approach for waste form development. The peer review panel provided comments and identified documents that it felt were needed in the Diagram as precedence for Title I design. The Diagram is a visual tool to identify traceable documentation of key activities, including those documents suggested by the peer review, and to show how they relate to each other. The Diagram is divided into three sections: (1) the Facility section, which contains documents pertaining to the facility design, (2) the Process Demonstration section, which contains documents pertaining to the process engineering/demonstration work, and 3) the Regulatory section, which contains documents describing the compliance strategy for each acceptance requirement for each feed type, and how this strategy will be implemented
Solar control window film: report and manual

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

A method has been developed by which the energy and energy cost savings associated with application of solar control film to windows of commercial and institutional buildings can be calculated. This method has been prepared as a separate, self-contained user's manual. It is simple and essentially non-technical, based on Toronto conditions, and is sufficiently accurate to provide a basis for economic feasibility analysis. The report explains the method in depth and compares it to alternate methods developed by the solar film industry. Variables which affect film performance, the savings that result, and limitations on the use of solar film as an energy conserving method are discussed. 8 refs., 2 figs., 1 tab.
TADS Needs Assessment Procedures Manual, Summer 1980.

Science.gov (United States)

Black, Talbot; And Others

The TADS (Technical Assistance Development System) Needs Assessment Manual is designed to guide the comprehensive review of Handicapped Children's Early Education Program (HCEEP) demonstration projects in identifying technical assistance needs. An introduction reviews the TADS technical assistance model which includes program planning, needs…
Technical report writing

Science.gov (United States)

Vidoli, Carol A.

1992-01-01

This manual covers the fundamentals of organizing, writing, and reviewing NASA technical reports. It was written to improve the writing skills of LeRC technical authors and the overall quality of their reports.
Technical basis for nuclear accident dosimetry at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kerr, G.D.; Mei, G.T.

1993-08-01

The Oak Ridge National Laboratory (ORNL) Environmental, Safety, and Health Emergency Response Organization has the responsibility of providing analyses of personnel exposures to neutrons and gamma rays from a nuclear accident. This report presents the technical and philosophical basis for the dose assessment aspects of the nuclear accident dosimetry (NAD) system at ORNL. The issues addressed are regulatory guidelines, ORNL NAD system components and performance, and the interpretation of dosimetric information that would be gathered following a nuclear accident
Offsite dose calculation manual guidance: Standard radiological effluent controls for boiling water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-- 01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft form for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. 11 tabs
LLCEDATA and LLCECALC for Windows version 1.0, Volume 2: Technical manual

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of databases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank from which it originates. LLCECALC reads the EDF and the gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDA TA, and LLCECALC. Documentation for LLCEDA TA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, which documents LLCEDATA and LLCECALCs methodology, structure, and format, provides sample calculations; discusses system limitations; and provides recommendations to the LLCE process. Volume 3 is a software verification and validation document LLCEDATA and LLCECALC for Windows are sponsored by the U.S.Department of Energy. They were developed and are maintained by Engineering, Waste Management Federal Services, Inc., Northwest Operations. Copies of the software and documentation are available by contacting Engineering, Waste Management Federal Services, Inc., Northwest Operations, Richland, Washington.
The development of nuclear material accountability system - software user's manual

Energy Technology Data Exchange (ETDEWEB)

Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

1999-07-01

We have developed the near-real time nuclear material accountability system, named by DMAS, for DUPIC Test Facility in the basis of the survey of DUPIC process and activities for the accountability of the system, and the review of the rules and regulations related to the nuclear material accounting. Our system adopts the structure and technologies used in COREMAS which was developed by LANL. This technical report illustrates the system structure and program usage as a user manual for DMAS. (author). 56 tabs., 1 fig.
Resource Manual for Functional Vision Evaluation. Technical Assistance Bulletin.

Science.gov (United States)

Texas Education Agency, Austin. Div. of Special Education.

The manual was intended to help school personnel (either an educator of the visually handicapped and/or a certified orientation and mobility instructor) evaluate the functional use of residual vision. The manual is organized in three major sections, which cover the following: (1) the general areas addressed in functional vision evaluation (such as…
Technical basis to describe and document the use of the E-600 and SHP-380 detector

International Nuclear Information System (INIS)

Hensley, J.R.

1997-06-01

This technical basis document describes and documents the parameters under which the Eberline E-600 ratemeter and the associated SHP-380 detector can be operated to quantify alpha and beta contamination levels. 3 refs., 3 tabs
Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document

International Nuclear Information System (INIS)

ADAMS, M.R.

2000-01-01

The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables
Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants
Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.
Technical meeting on progress in managing, and limiting the consequences of events exceeding the design basis

International Nuclear Information System (INIS)

Fabian, H.

2004-01-01

The Technical Groups on 'Reactor Safety' and 'Thermodynamics and Fluid Dynamics' of the Kerntechnische Gesellschaft e.V. organized a joint technical meeting on 'Progress in Managing, and Limiting the Consequences of, Events Exceeding the Design Basis' at the FTU Training Center of the Karlsruhe Research Center. The topic chosen, the papers presented, the presenters, and the non-technical part of the program met with lively interest on the part of institutions in the nuclear field. These were the objectives of the technical meeting: - Establishing a forum for communicating relevant topics. - In-depth discussion of the main topic, i.e. the advanced development of reactor safety, research in the field, and its application, in twenty selected papers presented by speakers from different institutions. - Presentation of topical work in a nuclear technology institution, the Karlsruhe Research Center. (orig.) [de
Safety Basis Report

International Nuclear Information System (INIS)

R.J. Garrett

2002-01-01

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities
Safety Basis Report

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2002-01-14

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.
The operation and maintenance manual

International Nuclear Information System (INIS)

Stoll, A.; Krotil, H.; Klein, W.

1976-01-01

The operating manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the operating manual. The operating manual is an essential element in bringing man and machine in harmony. This is necessary for safe and, as far as possible, uninterrupted operation of the power plant. The operating manual is the only document containing binding instructions for plant operation. All the tasks of plant operation which are carried out by plant staff are described in the operating manual in a form which is as clear and comprehensible as possible. A considerable number of these tasks can only be carried out by man, namely: 1) tasks concerning operational organization, 2) all non-automated areas of plant operation. (orig./TK) [de
KEIMS utility manual (edition 1.0)

International Nuclear Information System (INIS)

Kim, Yeun Seung; Eom, Young Sam; Choi, Jin Yeup; Nam, Ji Hwa

1996-06-01

Since 1987 when KAERI had started Yonggwang 3 and 4 NSSS system design project, KAERI has carried out so many NSSS system design projects such as Ulchin 3 and 4, Wolsong 2, 3 and 4 and Yonggwang 5 and 6 with fixed members that necessity of increasing productivity has been raised. To improve design work efficiency, it was considered that computerization of workflow which took so much man-power and business time. As result of investigation of design workflow to reduce man-power loss. It was suggested that DDA (Document Distribution for Agreement) workflow, design document stored in DDCD (Document Distribution and Control Center), IOC (Interoffice Correspondence) document, Letter, PM Memo should be preferentially computerized. On the basis of these computerization requirements, MEDIS (Modular Engineering Document Imaging System) was selected. Prototype had been implemented during 1995.9 -1995.12, and from 1996.1 KEIMS (KAERI Engineering Information Management System) has been operated. This MEDIS system utility manual was composed of several technical memos which has been described on customization of MEDIS fit to KEIMS, program development for system check, and information control of database. Further edition would be released as utility technical memo added. (Author) .new

KEIMS utility manual (edition 1.0)

Energy Technology Data Exchange (ETDEWEB)

Kim, Yeun Seung; Eom, Young Sam; Choi, Jin Yeup; Nam, Ji Hwa [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-06-01

Since 1987 when KAERI had started Yonggwang 3 and 4 NSSS system design project, KAERI has carried out so many NSSS system design projects such as Ulchin 3 and 4, Wolsong 2, 3 and 4 and Yonggwang 5 and 6 with fixed members that necessity of increasing productivity has been raised. To improve design work efficiency, it was considered that computerization of workflow which took so much man-power and business time. As result of investigation of design workflow to reduce man-power loss. It was suggested that DDA (Document Distribution for Agreement) workflow, design document stored in DDCD (Document Distribution and Control Center), IOC (Interoffice Correspondence) document, Letter, PM Memo should be preferentially computerized. On the basis of these computerization requirements, MEDIS (Modular Engineering Document Imaging System) was selected. Prototype had been implemented during 1995.9 -1995.12, and from 1996.1 KEIMS (KAERI Engineering Information Management System) has been operated. This MEDIS system utility manual was composed of several technical memos which has been described on customization of MEDIS fit to KEIMS, program development for system check, and information control of database. Further edition would be released as utility technical memo added. (Author) .new.
Writing Clinic for Business and Technical Writers.

Science.gov (United States)

Mercer County Community Coll., Trenton, NJ.

This document offers brief lesson plans for four courses: (1) an 8-hour refresher course for employees who write memos, short reports, and letters; (2) an 8-hour refresher course on creating a short document; (3) a 16-hour course on technical manual writing; and (4) an 8-hour course on technical manual writing. The courses were part of a workplace…
Offsite dose calculation manual guidance: Standard radiological effluent controls for pressurized water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effect Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft from (NUREG-0471 and -0473) for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of generic Letter 89-01
Rotor Wake/Stator Interaction Noise Prediction Code Technical Documentation and User's Manual

Science.gov (United States)

Topol, David A.; Mathews, Douglas C.

2010-01-01

This report documents the improvements and enhancements made by Pratt & Whitney to two NASA programs which together will calculate noise from a rotor wake/stator interaction. The code is a combination of subroutines from two NASA programs with many new features added by Pratt & Whitney. To do a calculation V072 first uses a semi-empirical wake prediction to calculate the rotor wake characteristics at the stator leading edge. Results from the wake model are then automatically input into a rotor wake/stator interaction analytical noise prediction routine which calculates inlet aft sound power levels for the blade-passage-frequency tones and their harmonics, along with the complex radial mode amplitudes. The code allows for a noise calculation to be performed for a compressor rotor wake/stator interaction, a fan wake/FEGV interaction, or a fan wake/core stator interaction. This report is split into two parts, the first part discusses the technical documentation of the program as improved by Pratt & Whitney. The second part is a user's manual which describes how input files are created and how the code is run.
Technical basis and radiological release plan for Trackhoes used at 100 BC-1 and 100 DR-1

International Nuclear Information System (INIS)

De Mers, S.K.

1997-06-01

To develop a method for the radiological release of tracked heavy equipment vehicles used in the excavation of the 100-BC-1 and 100-DR remedial action sites, including the technical basis for selection of release criteria and the instrumentation to be used for surveys
Microbial ecology laboratory procedures manual NASA/MSFC

Science.gov (United States)

Huff, Timothy L.

1990-01-01

An essential part of the efficient operation of any microbiology laboratory involved in sample analysis is a standard procedures manual. The purpose of this manual is to provide concise and well defined instructions on routine technical procedures involving sample analysis and methods for monitoring and maintaining quality control within the laboratory. Of equal importance is the safe operation of the laboratory. This manual outlines detailed procedures to be followed in the microbial ecology laboratory to assure safety, analytical control, and validity of results.
Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

Energy Technology Data Exchange (ETDEWEB)

Curtis Smith; James Knudsen; Bentley Harwood

2013-08-01

The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk – as a function of different configurations – in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.
Hanford Engineer Works technical manual

Energy Technology Data Exchange (ETDEWEB)

1944-05-01

The uranium metal, as discharged from the piles in the 100 Areas, contains the alpha emitting product, plutonium, in concentration in the neighborhood of 150--250 grams per metric ton, along with similar amounts of beta and gamma fission elements. It is the purpose of the Separations Plant to effect the separation of this product from the uranium metal and fission elements, and to prepare a concentrated, relatively pure solution of plutonium nitrate as the final product of the Hanford Plant. This section of the manual discusses the chemistry of the separations process, describes the buildings and equipment provided for carrying out the various steps in the operation, and presents the detailed operating procedures used. There are included, in many instances, references to other documents presenting a more detailed view of a specific point in the process.
Marketing information: The technical report as product

Science.gov (United States)

Stoher, F. F.; Pinelli, T. E.

1981-01-01

Technical reports constitute a product, the primary means for communicating the results of research to the user. The Langley scientific and technical information (STI) review and evaluation project undertook a review of the technical report as an effective product for information communication. Style manuals describing theory and practice in technical report preparation; publication manuals covering such factors as design, layout, and type style; and copies of technical reports were obtained from industrial, academic, governmental, and research organizations. Based on an analysis of this material, criteria will be established for the report components, for the relationship of the components within the report context, and for the overall report organization. The criteria will be used as bench marks and compared with the publication standards currently used to prepare NASA technical reports.
Energy statistics manual

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The Manual is written in a question-and-answer format. The points developed are introduced with a basic question, such as: What do people mean by 'fuels' and 'energy'? What units are used to express oil? How are energy data presented? Answers are given in simple terms and illustrated by graphs, charts and tables. More technical explanations are found in the annexes. The Manual contains seven chapters. The first one presents the fundamentals of energy statistics, five chapters deal with the five different fuels (electricity and heat; natural gas; oil; solid fuels and manufactured gases; renewables and waste) and the last chapter explains the energy balance. Three technical annexes and a glossary are also included. For the five chapters dedicated to the fuels, there are three levels of reading: the first one contains general information on the subject, the second one reviews issues which are specific to the joint IEA/OECD-Eurostat-UNECE questionnaires and the third one focuses on the essential elements of the subject. 43 figs., 22 tabs., 3 annexes.
Creating Web Sites The Missing Manual

CERN Document Server

MacDonald, Matthew

2006-01-01

Think you have to be a technical wizard to build a great web site? Think again. For anyone who wants to create an engaging web site--for either personal or business purposes--Creating Web Sites: The Missing Manual demystifies the process and provides tools, techniques, and expert guidance for developing a professional and reliable web presence. Like every Missing Manual, you can count on Creating Web Sites: The Missing Manual to be entertaining and insightful and complete with all the vital information, clear-headed advice, and detailed instructions you need to master the task at hand. Autho
The operation and maintenance manual

International Nuclear Information System (INIS)

Klein, W.; Krotil, H.; Stoll, A.

1975-01-01

The Operating Manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the Operating Manual. It contains, appropriately arranged, the necessary system and other diagrams, drawings, lists, licensing documents and similar material, which are necessary for understanding the design, for testing, for obtaining the operating licence and for the operation of individual systems and of the entire plant. (orig./RW) [de
HFBR: Review of the technical specifications against the FSAR

International Nuclear Information System (INIS)

Rao, D.V.; Boss, S.B.; Claiborne, E.R.; Darby, J.L.; Clark, R.A.

1990-01-01

The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart
Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2015-11-01

The demands on nuclear fuel have recently been increasing, and include transient regimes, higher discharge burnup and longer fuel cycles. This has resulted in an increase of loads on fuel and core internals. In order to satisfy these demands while ensuring compliance with safety criteria, new national and international programmes have been launched and advanced modelling codes are being developed. The Fukushima Daiichi accident has particularly demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure and also to predict fuel behaviour were an accident to occur.This publication presents the Proceedings of the Technical Meeting on Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents, which was hosted by the Nuclear Power Institute of China (NPIC) in Chengdu, China, following the recommendation made in 2013 at the IAEA Technical Working Group on Fuel Performance and Technology. This recommendation was in agreement with IAEA mid-term initiatives, linked to the post-Fukushima IAEA Nuclear Safety Action Plan, as well as the forthcoming Coordinated Research Project (CRP) on Fuel Modelling in Accident Conditions. At the technical meeting in Chengdu, major areas and physical phenomena, as well as types of code and experiment to be studied and used in the CRP, were discussed. The technical meeting provided a forum for international experts to review the state of the art of code development for modelling fuel performance of nuclear fuel for water cooled reactors with regard to steady state and transient conditions, and for design basis and early phases of severe accidents, including experimental support for code validation. A round table discussion focused on the needs and perspectives on fuel modelling in accident conditions. This meeting was the ninth in a series of IAEA meetings, which reflects Member States’ continuing interest in nuclear fuel issues. The previous meetings were held in 1980 (jointly with
Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A., Westinghouse Hanford

1996-07-17

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.
Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A.

1996-09-20

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.
Technical Support for the development of DCS

International Nuclear Information System (INIS)

Oh, In Seok; Lee, Cheol Kwon; Kim, Dong Hoon; Kim, Jung Taek; Hwang, In Koo; Park, Jae Chang; Lee, Dong Young; Park, Won Man

2008-05-01

The objective of this project is to provide a technical support to Woori Tech Co. in its design and manufacture process of the DCS as a part of KNICS development program to promote the technology self-reliance for non-safety equipment for NPPs(Nuclear Power Plants). We support Woori Tech Co. to develop a DCS which satisfies the requirements for Shinkori 3 and 4 NPPs in the aspects of reliability, applicability and technical competitiveness. As the results of this project the following items were developed and/or implemented; · Design basis and requirements for a DCS system · Design requirements for control communication networks · Architecture of control networks · Design requirements of EWS(Engineering Workstation) · Plan of software verification and validation · Operation display design · Soft control functions · Application development tools of DCS · Analysis and V/V activities on DCS control network protocols · Software verification and validation and documentation guidelines · User manual documents
Wastes power generation introduction manual. Material edition; Haikibutsu hatsuden donyu manual. Shiryohen

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

This paper collects and puts into order the materials used in preparing the manual. The materials were classified into the power generation system database related to discussion of the economic performance, case studies, technical materials, other referential materials and glossary. The database shows power generation efficiency, auxiliary power ratio, construction cost, utility cost and number of operators. The case studies present examples of economy calculations on the five recommended power generation systems at a wastes treatment capacity of 180 tons a day. Technical materials put into order the technological discussions on efficiency improvement, environmental measures (suppression of discharge of dioxins, measures for their removal, and the effects thereof), refuse derived fuel (RDF) and power plant operating techniques. The other referential materials collect laws, notifications, and guidelines related to the Welfare Ministry, laws, notifications, criteria and related to the Ministry of International Trade and Industry, and materials related to LCA, forms of power generation business entities, general wastes disposal business, and electric business bonds. The glossary explains terms required for operation and understanding of the manual. (NEDO)
UMTRA [Uranium Mill Tailings Remedial Action] Project site management manual

International Nuclear Information System (INIS)

1990-10-01

The purpose of this manual is to summarize the organizational interfaces and the technical approach used to manage the planning, design development, National Environmental Policy Act (NEPA) compliance, engineering, and remedial action required to stabilize and control the designated Uranium Mill Tailings Remedial Action (UMTRA) Project sites. This manual describes the Project's objective, participants' roles and responsibilities, technical approach for accomplishing the objective, and planning and managerial controls to be used in performing the site work. The narrative follows the flow of activities depicted in Figure 1.1, which provides the typical sequence of key Project activities. A list of acronyms used is presented at the end of the manual. The comparable manual for UMTRA Project vicinity properties is the ''Vicinity Properties Management and Implementation Manual'' (VPMIM) (UMTRA-DOE/AL-050601). Together, the two manuals cover the remedial action activities associated with UMTRA Project sites. The UMTRA Project's objective is to stabilize and control the uranium mill tailings, vicinity property materials, and other residual radioactive materials at the designated sites (Figure 1.2) in a safe and environmentally sound manner in order to minimize radiation health hazards to the public. 26 figs., 6 tabs
Technical basis for acceptance criteria on the susceptibility of digital systems to electromagnetic interference

International Nuclear Information System (INIS)

Ewing, P.D.; Korsah, K.; Antonescu, C.

1992-01-01

This paper discusses the development of the technical basis for establishing acceptance criteria on the susceptibility of digital systems to electromagnetic interference (EMI). The effort is sponsored by the US Nuclear Regulatory Commission and stems from the safety-related issues that need to be addressed with the application of digital instrumentation and controls systems in nuclear power plants. Designers of digital circuits are incorporating increasingly higher clock frequencies and lower logic voltage levels, thereby leading to the risk of susceptibility when spurious interference is misinterpreted as legitimate logic. Development of the technical basis for acceptance criteria centers around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems. First, good EMC design and installation practices are needed to control the emissions from interference sources and their impact on other nearby circuits and systems. Then, a test and evaluation program is needed to outline the EMI tests to be performed, the associated test methods to be followed, and adequate test limits to ensure that the circuit or system under test meets the recommended guidelines. Test and evaluation should be followed by periodic maintenance to assess whether the recommended EMI control practices continue to be adhered to as part of the routine operation of the nuclear power plant. By following these steps, the probability of encountering safety-related problems associated with EMI will be greatly reduced

Preparing Payroll Register, Employee Earnings' Records, and Paychecks. Student's Manual and Instructor's Manual.

Science.gov (United States)

McElveen, Peggy C.

Supporting performance objective 28 of the V-TECS (Vocational-Technical Education Consortium of States) Secretarial Catalog, both a set of student materials and an instructor's manual on preparing a payroll register, employee earnings' records, and paychecks are included in this packet, which is one in a series. The student materials include a…
Scientific and technical basis for the near surface disposal of low and intermediate level waste

International Nuclear Information System (INIS)

2002-01-01

This report presents an overview of the scientific and technical basis for the disposal of low- and intermediate-level radioactive waste in near surface repositories. The focus is on basic principles, approaches, methodologies and technical criteria that can be used to develop and assess the performance of a disposal facility, and for building confidence in repository safety. This includes consideration of the multiple barrier concept, the performance of engineered barriers, the role of natural barriers and the development of a safety case. The emphasis is on defining the conditions relevant to the containment of the radionuclides in the repository and the processes that may affect the integrity of the engineered barriers. Both generic and specific data requirements for repository development and the assurance of safety are addressed. A large number of bibliographical references are given to support the information provided in this report
Technical guide to criticality alarm system design

International Nuclear Information System (INIS)

Greenfield, B.

2009-01-01

An instructional manual was created to guide criticality safety engineers through the technical aspects of designing a criticality alarm system (CAS) for Dept. of Energy (DOE) hazard class 1 and 2 facilities. The manual was structured such that it can be used by engineers designing completely new systems and by those who are working with existing facilities. Major design tasks are thoroughly analyzed to provide concise direction for how to complete the analysis. Regulatory and technical performance requirements were both addressed. (authors)
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)
A prescribed wake rotor inflow and flow field prediction analysis, user's manual and technical approach

Science.gov (United States)

Egolf, T. A.; Landgrebe, A. J.

1982-01-01

A user's manual is provided which includes the technical approach for the Prescribed Wake Rotor Inflow and Flow Field Prediction Analysis. The analysis is used to provide the rotor wake induced velocities at the rotor blades for use in blade airloads and response analyses and to provide induced velocities at arbitrary field points such as at a tail surface. This analysis calculates the distribution of rotor wake induced velocities based on a prescribed wake model. Section operating conditions are prescribed from blade motion and controls determined by a separate blade response analysis. The analysis represents each blade by a segmented lifting line, and the rotor wake by discrete segmented trailing vortex filaments. Blade loading and circulation distributions are calculated based on blade element strip theory including the local induced velocity predicted by the numerical integration of the Biot-Savart Law applied to the vortex wake model.
Audit Manual release 3.0

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

This manual consolidates into one document the policies, procedures, standards, technical guidance and other techniques to be followed by the Assistant Inspector General for Audits and staff in planning and conducting audit work within DOE and in preparing related reports on behalf of the Office of Inspector General.
OASIS User Manual

CERN Document Server

Bojtar, L

2009-01-01

The OASIS system has been operational for years now. After a long development the project has reached a state where the number of features it provides exceeds largely what most of its users knows about. The author felt it was time to write a user manual explaining all the functionality of the viewer application. This document is a user manual, concentrating on the functionality of the viewer from the user’s point of view. There are already documents available on the project’s web site about the technical aspects at http://project-oasis.web.cern.ch/project-oasis/presentations.htm . There was an attempt to produce a tutorial on the viewer, but it didn’t get much further than the table of contents, that however is well thought. The structure of this user manual follows the same principle, the basic and most often used features are grouped together. Advanced or less often used features are described in a separate chapter. There is a second organizational principle, features belong to different levels: chann...
Welding engineering manual for constructing engineers. Pt. 2

International Nuclear Information System (INIS)

Neumann, A.

1986-01-01

The manual is a real treasure trove of knowledge and experience for the statics expert, the constructing engineer, and the welding engineer, who have to do with design and dimensioning of welding engineering work for steel structures, bridges, boilers, vessels, and pipes. Many practical examples are given together with numerous data that provide helpful information for the task of technical and economic design and dimensioning. Determination of efficient and appropriate cross-sectional dimensions and materials is the main goal of the manual. Structural steel engineering and installations subject to monitoring and inspection such as boilers, pipings, pressure vessels, and nuclear installations are the subject fields dealt with in separate chapters. The dimensioning rules presented are based on the regulations and technical codes valid in the GDR and the FRG. The catalogue of technical rules of the FRG concerning structural steel engineering and installations as above are given in supplementary chapters. (orig./HP) [de
Creating a goaltending development manual for Belgium Ice Hockey

OpenAIRE

Guay, Eddy

2014-01-01

The objective of the thesis and was to create a goalie development manual for the Royal Belgian Ice Hockey Federation (RBIHF). The manual will provide goalies and coaches a guide for developing players in the position. The manual aims to provide a technical resources for goalies and coaches on the skills that goalies need to focus on to allow them to improve their play. ! “The backbone of a hockey team”or “The most important position in sports” are two of many phrases that i...
Technical Support for the development of DCS

Energy Technology Data Exchange (ETDEWEB)

Oh, In Seok; Lee, Cheol Kwon; Kim, Dong Hoon; Kim, Jung Taek; Hwang, In Koo; Park, Jae Chang; Lee, Dong Young; Park, Won Man

2008-05-15

The objective of this project is to provide a technical support to Woori Tech Co. in its design and manufacture process of the DCS as a part of KNICS development program to promote the technology self-reliance for non-safety equipment for NPPs(Nuclear Power Plants). We support Woori Tech Co. to develop a DCS which satisfies the requirements for Shinkori 3 and 4 NPPs in the aspects of reliability, applicability and technical competitiveness. As the results of this project the following items were developed and/or implemented; {center_dot} Design basis and requirements for a DCS system {center_dot} Design requirements for control communication networks {center_dot} Architecture of control networks {center_dot} Design requirements of EWS(Engineering Workstation) {center_dot} Plan of software verification and validation {center_dot} Operation display design {center_dot} Soft control functions {center_dot} Application development tools of DCS {center_dot} Analysis and V/V activities on DCS control network protocols {center_dot} Software verification and validation and documentation guidelines {center_dot} User manual documents.
Improving the technical preparation of football players on the basis of the control of discriminative characteristics when performing combinations of techniques during a game

Directory of Open Access Journals (Sweden)

Mitova Olena

2016-06-01

Full Text Available The paper examines the issue of improving the technical preparation of football players during initial basic training. A special attention is paid to the development and experimental substantiation of the methods of technical preparation of young football players in an annual cycle at the stage of initial basic training on the basis of the control of discriminative characteristics when performing inseparable combinations of techniques during a game. An attempt was made to uncover the underlying causes of a low technical preparedness of football players at different stages of multi-year training and to implement an integrated scientific approach to improvement of the process of technical preparation of 10-11 years old football players in an annual cycle at the stage of initial basic training on the basis of the control of discriminative characteristics when performing inseparable combinations of techniques during competitive activity, along with the peculiarities of psychophysical condition and a level of development of physical qualities. This approach in teaching technical skills will be of interest to specialists and coaches in football, since the pedagogical experiment has determined the effectiveness of the developed methodology.
Ensuring the conflict sustainability of the information systems on the basis of technical means

Directory of Open Access Journals (Sweden)

L. E. Mistrov

2016-01-01

Full Text Available The analysis of the purposes, tasks, functions and ways of ensuring conflict stability of func-tioning of information systems on the ba-sis of application of a complex of technical means is carried out. The main contours of management of elements of the organizational and technical systems (OTS in various forms of actions are defined. It is noted that a basis of functioning of OTS, infor-mation sup-port makes, classes of the data making him are defined. It is shown that ensuring conflict stability of functioning of the information sys-tems (IS is carried out by the complex of technical means (CTM, as a part of subsystems of reception / transfer, collecting and de-struction / distortion of information, their main functions are defined. Wednesday in which KTS function, is defined as an information and target situation which is understood as the part of a social and economic situa-tion characterized by existence of KTS providing functioning with IS, their location, operating modes, parameters of the information streams (IS, characteristics of technical means of processing, storage, submission of information realized by ways of the information security (IS for the solution of tasks in dynamics of information conflict. At the same time the information conflict is part target (the difficult conflict OTS representing information ex-change of KTS providing conflict steady functioning of IS at realization of processes of collection of information, transfer and counter-action to carrying out similar actions by the competing party with means of the destroying / distorting in-fluences (RIV. The special at-tention is paid to research of actions of a subsystem of collection of information, methods of collection of information are defined, con-ditions of application of methods of processing of the collected data are shown, features of functioning of subsystems of KTS at vari-ous stages of application are considered. The conclusion is drawn that
Conceptual framework and technical basis for clearance of materials with residual radioactivity

International Nuclear Information System (INIS)

Chen, S.Y.

1997-01-01

The primary impediment to the release of materials containing residual radioactivity from a controlled environment is the lack of a suitable framework within which release standards can be developed. Recently, the 'risk-based' approach has been proposed as an appropriate means of setting standards. The term 'clearance' has been introduced by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial risks. A 'trivial' risk level has been determined to be on the order of 10[sup -6] to 10[sup -7] annual risk to an exposed individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk (or dose) constraints
(ICT) to Technical Services in Libraries

African Journals Online (AJOL)

The term technical services is used in this paper to refer to the major operations that are common to all Technical Services Divisions in libraries – namely, cataloguing, classification, indexing and abstracting. These activities have many repetitive components which used to be done manually. But today the new technology ...
Tank waste remediation system process engineering instruction manual

International Nuclear Information System (INIS)

ADAMS, M.R.

1998-01-01

The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees
U.S. Department of Energy Vehicle Technologies Program: Battery Test Manual For Plug-In Hybrid Electric Vehicles

Energy Technology Data Exchange (ETDEWEB)

Christophersen, Jon P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

This battery test procedure manual was prepared for the United States Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy (EERE), Vehicle Technologies Office. It is based on technical targets for commercial viability established for energy storage development projects aimed at meeting system level DOE goals for Plug-in Hybrid Electric Vehicles (PHEV). The specific procedures defined in this manual support the performance and life characterization of advanced battery devices under development for PHEV’s. However, it does share some methods described in the previously published battery test manual for power-assist hybrid electric vehicles. Due to the complexity of some of the procedures and supporting analysis, future revisions including some modifications and clarifications of these procedures are expected. As in previous battery and capacitor test manuals, this version of the manual defines testing methods for full-size battery systems, along with provisions for scaling these tests for modules, cells or other subscale level devices. The DOE-United States Advanced Battery Consortium (USABC), Technical Advisory Committee (TAC) supported the development of the manual. Technical Team points of contact responsible for its development and revision are Renata M. Arsenault of Ford Motor Company and Jon P. Christophersen of the Idaho National Laboratory. The development of this manual was funded by the Unites States Department of Energy, Office of Energy Efficiency and Renewable Energy, Vehicle Technologies Office. Technical direction from DOE was provided by David Howell, Energy Storage R&D Manager and Hybrid Electric Systems Team Leader. Comments and questions regarding the manual should be directed to Jon P. Christophersen at the Idaho National Laboratory (jon.christophersen@inl.gov).
System requirements and design description for the document basis database interface (DocBasis)

International Nuclear Information System (INIS)

Lehman, W.J.

1997-01-01

This document describes system requirements and the design description for the Document Basis Database Interface (DocBasis). The DocBasis application is used to manage procedures used within the tank farms. The application maintains information in a small database to track the document basis for a procedure, as well as the current version/modification level and the basis for the procedure. The basis for each procedure is substantiated by Administrative, Technical, Procedural, and Regulatory requirements. The DocBasis user interface was developed by Science Applications International Corporation (SAIC)
Technical specifications for the Pajarito Site Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.; Paxton, H.C.

1980-12-01

This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility
Technical basis for the ITER-FEAT outline design. Progress in resolving open design issues from the outline design report

International Nuclear Information System (INIS)

2000-01-01

In this publication the technical basis for the ITER-FEAT outline design is presented. It comprises the Plant Design Specifications, the Safety Principles and Environmental Criteria, the Site Requirements and Site Design Assumptions. The outline of the key features of the ITER-FEAT design includes main physical parameters and assessment, design overview and preliminary safety assessment, cost and schedule
Manual for the operation of research reactors

International Nuclear Information System (INIS)

1965-01-01

The great majority of the research reactors in newly established centres are light-water cooled and are often also light-water moderated. Consequently, the IAEA has decided to publish in its Technical Reports Series a manual dealing with the technical and practical problems associated with the safe and efficient operation of this type of reactor. Even though this manual is limited to light-water reactors in its direct application and presents the practices and experience at one specific reactor centre, it may also be useful for other reactor types because of the general relevance of the problems discussed and the long experience upon which it is based. It has, naturally, no regulatory character but it is hoped that it will be found helpful by staff occupied in all phases of the practical operation of research reactors, and also by those responsible for planning their experimental use. 23 refs, tabs

Conversion of NEK standard technical specifications into improved technical specifications

International Nuclear Information System (INIS)

Glaser, B.

2003-01-01

Neck is currently using a standard format of operation's Technical Specifications - STS (based on NUREG-0452), which are planned to be converted into Improved Technical Specifications - ITS (based on NUREG-1431). To facilitate the development of individual ITS, each reactor vendor owners group (OG) and the NRC staff developed improved standard TS (ISTS). For Westinghouse plants, the ISTS are published as NUREG-1431, and this document is going to be the basis for the new NEK ITS. It has been recognized that nuclear safety in all plants would benefit from improvement and standardization of ITS, so this was also addressed and recognized by the NRC. There are several plants around Europe and US, which have replaced the format into ITS which brings a lot of improvements and practical value in operations. The main objective of conversion is to completely rewrite, reformat, and streamline the existing STS. Emphasis is placed on human factors principles to improve clarity and understanding. The Bases section will be significantly expanded to clarify and better explain the purpose and foundation of each specification. There might be some proposed changes to the existing STS that deviated from the ITS in NUREG-1431 and constitute a relaxation of the existing STS. Each of these additional proposed changes will be described and evaluated in amendment application and justified on a case-by-case basis. Since the NEK is going to operate for more than 20 year without considering life extension, such conversion will be beneficial for operation personnel as well as regulation, surveillance and focus on operation's safety. At the present, only preliminary plan of STS conversion exists, showing the time frame of approximately 2 years of conversion process and numerous tasks that need to be performed. The plan is to begin with process in year 2004 and finish project in 2006, which means use of new ITS in main control room in year 2007. Beside the main process of conversion, there are
The way to bio heat. A manual on production of heat from bio fuel; Veien til biovarme. Manual for produksjon av ferdigvarme fra biobrensel

Energy Technology Data Exchange (ETDEWEB)

Breen, Tor; Liodden, Ole Joergen; Farsund Oeystein; Martinsen, Arnold Kyrre

2008-09-26

The manual is a tool in the process of planning and establishing a bio heat company. It focuses on both technical, administrative, and economic aspects. Part 1 of the manual briefly reviews the production of bio fuel and bio heat, part 2 considers the organizational aspects of the project, and part 3 is a tool box containing laws and regulations, templates for contracts/agreements etc
Manual for reactor produced radioisotopes

International Nuclear Information System (INIS)

2003-01-01

Radioisotopes find extensive applications in several fields including medicine, industry, agriculture and research. Radioisotope production to service different sectors of economic significance constitutes an important ongoing activity of many national nuclear programmes. Radioisotopes, formed by nuclear reactions on targets in a reactor or cyclotron, require further processing in almost all cases to obtain them in a form suitable for use. Specifications for final products and testing procedures for ensuring quality are also an essential part of a radioisotope production programme. The International Atomic Energy Agency (IAEA) has compiled and published such information before for the benefit of laboratories of Member States. The first compilation, entitled Manual of Radioisotope Production, was published in 1966 (Technical Reports Series No. 63). A more elaborate and comprehensive compilation, entitled Radioisotope Production and Quality Control, was published in 1971 (Technical Reports Series No. 128). Both served as useful reference sources for scientists working in radioisotope production worldwide. The 1971 publication has been out of print for quite some time. The IAEA convened a consultants meeting to consider the need for compiling an updated manual. The consultants recommended the publication of an updated manual taking the following into consideration: significant changes have taken place since 1971 in many aspects of radioisotope production; many radioisotopes have been newly introduced while many others have become gradually obsolete; considerable experience and knowledge have been gained in production of important radioisotopes over the years, which can be preserved through compilation of the manual; there is still a need for a comprehensive manual on radioisotope production methods for new entrants to the field, and as a reference. It was also felt that updating all the subjects covered in the 1971 manual at a time may not be practical considering the
Contents Development of Library Signage Manual in Korea

OpenAIRE

In-Ja Ahn

2011-01-01

There is an increase in the need of an unified manual for library signage system, due to recent increase in library construction or remodeling. This paper, therefore, can be a basic research to develop library signage system manual. Based on an anual released from KLA and the sum of opinions of expert groups, this research proposes a concrete list of contents for library signage system manual as follows. First, there is a need of theoretical basis of library signage system. Second, for the ac...
Technical basis for high-level waste repository land control requirements for Palo Duro Basin, Paradox Basin, and Richton Dome

International Nuclear Information System (INIS)

Chen, C.P.; Raines, G.E.

1987-02-01

Three sites, the Palo Duro Basin in Texas, the Paradox Basin in Utah, and the Richton Dome in Mississippi, are being investigated by the US Department of Energy for high-level radioactive-waste disposal in mined, deep geologic repositories in salt. This report delineates the use of regulatory, engineering, and performance assessment information to establish the technical basis for controlled area requirements. Based on the size of the controlled area determined, plus that of the geologic repository operations area, recommendations of possible land control or ownership area requirements for each locale are provided. On a technical basis, the following minimum land control or ownership requirements are recommended, assuming repository operations area of 2240 ac (907 ha), or 3.5 mi 2 (9.1 km 2 ): Palo Duro Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); Paradox Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); and Richton Dome - 5000 ac (2024 ha), or 7.8 mi 2 (20.2 km 2 ). Of the factors used to determine the technically based recommendations, one was found to dominate each locale. For the Palo Duro and Paradox Basins, the dominant factor was the need to limit potential radionuclide release by ground-water flow to the accessible environment. For the Richton Dome, the dominant factor was the need to limit the potential effects of solution mining on dome and repository integrity
Laboratory biosafety manual

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

This book is in three sections; basic standards of laboratory design and equipment; procedures for safe laboratory practice; and the selection and use of essential biosafety equipment. The intention is that the guidance given in the book should have a broad basis and international application, and that it should be a source from which manuals applicable to local and special conditions can be usefully derived.
The research project on technical information basis for aging management in Fukui and Kinki area. Final report

International Nuclear Information System (INIS)

Fujimura, Kimiya; Nagayama, Shigeru; Watarumi, Chikae; Toudou, Tsugihiko

2011-01-01

The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI) as a five-year program effectively, to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the technical strategy map for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants, 2) The development of inspection techniques to monitor the initiation and propagation of defects, 3) The development of a guideline for evaluating weld repair methods, 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2010, 11 continuing research subjects were proposed for this project and all were accepted. Of these, 5 subjects were related to the first topic (pipe thinning), 4 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)
Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines
IAEA publishes first health and safety manual

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-01-15

A 'Manual on the Safe Handling of Radioisotopes' was published in English on 15 Dec ember 1958 by the International Atomic Energy Agency. This is a comprehensive handbook of internationally compiled recommendations for users of radioisotopes. It covers organizational, medical and technical aspects of radiation safety practices. It is also the Agency's first technical publication. French, Russian and Spanish editions will appear shortly. The Manual should prove useful to all users of radioisotopes in industry, medicine, research, etc., but is directed mainly to small scale users who may not have access to other sources of information. The recommendations apply only to radioactivity surpassing the limit of 0,002 microcurie concentration per gram of material; or a total activity of more than 0,1 microcuries in the working areas; this limit is based on the most dangerous radioisotopes. The experts state that the limiting level might be higher for less dangerous isotopes, but recommend that all be treated as potentially dangerous. This would have educational value and avoid accidents caused by misidentification. The Manual also stressed that good radiation safety practices depend on effective organization and warns that even very competent workers sometimes ignore or forget important health and safety requirements.
IAEA publishes first health and safety manual

International Nuclear Information System (INIS)

1959-01-01

A 'Manual on the Safe Handling of Radioisotopes' was published in English on 15 Dec ember 1958 by the International Atomic Energy Agency. This is a comprehensive handbook of internationally compiled recommendations for users of radioisotopes. It covers organizational, medical and technical aspects of radiation safety practices. It is also the Agency's first technical publication. French, Russian and Spanish editions will appear shortly. The Manual should prove useful to all users of radioisotopes in industry, medicine, research, etc., but is directed mainly to small scale users who may not have access to other sources of information. The recommendations apply only to radioactivity surpassing the limit of 0,002 microcurie concentration per gram of material; or a total activity of more than 0,1 microcuries in the working areas; this limit is based on the most dangerous radioisotopes. The experts state that the limiting level might be higher for less dangerous isotopes, but recommend that all be treated as potentially dangerous. This would have educational value and avoid accidents caused by misidentification. The Manual also stressed that good radiation safety practices depend on effective organization and warns that even very competent workers sometimes ignore or forget important health and safety requirements
Manual on laboratory testing for uranium ore processing

International Nuclear Information System (INIS)

1990-01-01

Laboratory testing of uranium ores is an essential step in the economic evaluation of uranium occurrences and in the development of a project for the production of uranium concentrates. Although these tests represent only a small proportion of the total cost of a project, their proper planning, execution and interpretation are of crucial importance. The main purposes of this manual are to discuss the objectives of metallurgical laboratory ore testing, to show the specific role of these tests in the development of a project, and to provide practical instructions for performing the tests and for interpreting their results. Guidelines on the design of a metallurgical laboratory, on the equipment required to perform the tests and on laboratory safety are also given. This manual is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. A report on the Significance of Mineralogy in the Development of Flowsheets for Processing Uranium Ores (Technical Reports Series No. 196, 1980) and an instruction manual on Methods for the Estimation of Uranium Ore Reserves (No. 255, 1985) have already been published. 17 refs, 40 figs, 17 tabs
Applicability of EPRI Decommissioning Pre-Planning Manual to International Decommissioning Projects

International Nuclear Information System (INIS)

Lessard, Leo; Kay, Jim; Lefrancois, Donald; Furr, Richard; Lucas, Matthieu; Schauer, Konrad

2016-01-01

Industry models for planning the efficient decommissioning of a nuclear power plant continue to evolve. Effective planning is a key to cost control, a critical aspect of decommissioning. In 2001, the Electric Power Research Institute (EPRI) published the 'Decommissioning Pre-Planning Manual', referred to as the 'Manual'. The goal of the Manual was to develop a framework for use in pre-planning the decommissioning of a nuclear power plant. The original research was based on information collected during the active decommissioning of power reactors in New England, and the ongoing decommissioning planning of another reactor still in operation. The research team identified thirty-two (32) major Decommissioning Tasks that support the strategic and tactical planning that can be conducted in advance of plant shutdown. The Decommissioning Tasks were organized in a logical sequence of execution, and sorted in common discipline groupings. Owners of U.S. nuclear plants that have shut down prematurely during the past 5 years have found the EPRI Decommissioning Pre-Planning Manual useful in developing their transition plans from an operating to shutdown facility. Concurrently, during the past 15 years, the IAEA has published numerous technical and safety reports on nuclear reactor decommissioning planning and execution. IAEA's goal is to provide its global members with useful and timely guidance for the planning and execution of nuclear decommissioning projects. This information has been used extensively by international nuclear plant operators. One of the key objectives will be to develop a road-map linking the 32 EPRI Decommissioning Tasks with the comparable (or equivalent) topics covered in the IAEA library of decommissioning knowledge. The logical and convenient structure of the Manual will be cross-referenced to the IAEA topics to aid in organizing the development of decommissioning plans. The road-map will serve to provide a basis for improved
Field manual for stream water and sediment reconnaissance

International Nuclear Information System (INIS)

Ferguson, R.B.; Price, V.; Baucom, E.I.

1977-11-01

A manual is presented that is intended to direct and coordinate field operations, site selection, sample collection, and information codes for the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. The manual provides technical direction and public relations information for field sampling teams. The program is being conducted to evaluate domestic uranium resources and to identify favorable areas for commercial exploration. The NURE program is expected to increase the activity of commercial exploration for uranium in the United States
Technical basis for storage of elastomer-sealed produce cans in the DOE-STD-3013-94 package

International Nuclear Information System (INIS)

Horrell, D.R.; Stakebake, J.L.; Szempruch, R.W.

1996-11-01

Department of Energy standard DOE-STD-3013-94 establishes criteria for the long-term packaging of plutonium metal and oxide. The inclusion of organic materials in sealed packages of plutonium may produce gases that contribute to container pressurization. To expedite processing, it would be desirable to permit, within the DOE-outlined criteria, limited amounts of organic materials to be used as a sealing gasket in some packaging containers. This paper presents a technical basis for allowing elastomer-sealed cans to be packaged inside the sealed inner container of a double weld-sealed DOE-STD-3013-94 container system
Technical basis for dose reconstruction

International Nuclear Information System (INIS)

Anspaugh, L.R.

1996-01-01

The purpose of this paper is to consider two general topics: Technical considerations of why dose-reconstruction studies should or should not be performed and methods of dose reconstruction. The first topic is of general and growing interest as the number of dose-reconstruction studies increases, and one asks the question whether it is necessary to perform a dose reconstruction for virtually every site at which, for example, the Department of Energy (DOE) has operated a nuclear-related facility. And there is the broader question of how one might logically draw the line at performing or not performing dose-reconstruction (radiological and chemical) studies for virtually every industrial complex in the entire country. The second question is also of general interest. There is no single correct way to perform a dose-reconstruction study, and it is important not to follow blindly a single method to the point that cheaper, faster, more accurate, and more transparent methods might not be developed and applied. 90 refs., 4 tabs
Technical basis for dose reconstruction

International Nuclear Information System (INIS)

Anspaugh, L.R.

1996-01-01

The purpose of this paper is to consider two general topics: technical considerations of why dose-reconstruction studies should or should not be performed and methods of dose reconstruction. The first topic is of general and growing interest as the number of dose-reconstruction studies increases, and one asks the question whether it is necessary to perform a dose reconstruction for virtually every site at which, for example, the Department of Energy (DOE) has operated a nuclear-related facility. And there is the broader question of how one might logically draw the line at performing or not performing dose-reconstruction (radiological and chemical) studies for virtually every industrial complex in the entire country. The second question is also of general interest. There is no single correct way to perform a dose-reconstruction study, and it is important not to follow blindly a single method to the point that cheaper, faster, more accurate, and more transparent methods might not be developed and applied
Contents Development of Library Signage Manual in Korea

Directory of Open Access Journals (Sweden)

In-Ja Ahn

2011-12-01

Full Text Available There is an increase in the need of an unified manual for library signage system, due to recent increase in library construction or remodeling. This paper, therefore, can be a basic research to develop library signage system manual. Based on an anual released from KLA and the sum of opinions of expert groups, this research proposes a concrete list of contents for library signage system manual as follows. First, there is a need of theoretical basis of library signage system. Second, for the actual practices of signage system, planning, check list, and standard terms shall be necessary.
Requirements to be met by the operation manual

International Nuclear Information System (INIS)

1981-03-01

The rule applies to the contents and the lay-out of the operating manual for stationary nuclear power plants. The draft contains: 1. General requirement to be met by the contents of the operating manual. The operating manual to be arranged in 4 parts (part 1: internal rules and regulations; part 2: operation overall plant; part 3: incidents; part 4: operation systems). Safety specifications to be included in the manual, the exemption being the system of technical documentation. 2. General requirements to be met by the lay-out of the operating manual. Comprehensibility; legibility; structure and subdivisions; arrangement of the instructions and design of the manuals cover. 3. Requirements to be met by part 1. Defining the various internal rules and regulations (personnel management); rules and regulations concerning inspections and shift work; maintenance and repair; radiation protection; guard duty and admission; alarm; fire protection; first aid. 4. Requirements to be met by part 2. Provisions and operational limitations; limit values important from the point of view of safety; normal operation; anomalous operation; in-service inspections. 6. Requirements to be met by part 3. 7. Annex: Rules, regulations and stipulations mentioned in the rule draft. (orig.)
NUSC Technical Publications Guide.

Science.gov (United States)

1985-05-01

Facility personnel especially that of A. Castelluzzo, E. Deland, J. Gesel , and E. Szlosek (all of Code 4343). Reviewed and Approved: 14 July 1980 D...their technical content and format. Review and approve the manual outline, the review manuscript, and the final camera - reproducible copy. Conduct in
Administrators' Perceptions of Career and Technical Education

Science.gov (United States)

Haussman, Charles E.

2012-01-01

Career and technical education was founded on the common practice of apprenticeships integrated into the public schools at the beginning of the 20th century as manual arts, which continued to evolve into a culture and practice of its own as vocational education, and into what is now career and technical education, with an evolving focus on college…

Nuclear medicine. 1 part. Manual

International Nuclear Information System (INIS)

Shlygina, O.E.; Borisenko, A.R.

2006-01-01

Current manual is urged to give wide-scale readers a submission on a key principles and methods of nuclear medicine, and it opportunities and restrictions in diagnostics and treatment of different diseases. Nuclear medicine is differing first of all by combination of diverse knowledge fields: special knowledge of a doctor, knowledge of physical processes bases, related with radiation, grounds of radiopharmaceutics, dosimetry. In the base of the book the 5th edition of 'Nuclear medicine' manual in 2 parts of German authors - Schicha, G.; Schober, O. is applied. In the book publishing the stuff of the Institute of Nuclear Physics of the National Nuclear Center of Republic of Kazakhstan has been worked. Modifications undergo practically all chapters: especially the second one, forth and sixth was enlarged. The 1 part of the book was published due to support of IAEA within the Technical cooperation project 'Implementation of Nuclear Medicine and Biophysics Center' (KAZ/6/007). The manual second part - devoted to applications of nuclear medicine methods for diagnostics and treatment - will be published in 2007
Bio-energy in the wood processing industry. Manual for energy production from residual matter for the wood processing industry

International Nuclear Information System (INIS)

Van Halen, C.J.G.; Arninkhof, M.J.C.; Rommens, P.J.M.; Karsch, P.

2000-04-01

This manual is published within the framework of a project, financed by Novem (EWAB programme) and the European Commission (Altener programme). Similar manuals were drafted in Germany, England and Sweden. The basis of the project was the manual 'Quality manual for small-scale wood incineration and wood gasification', published by Novem in 1998. That quality manual was drafted on the basis of an evaluation of a number of wood combustion and wood gasification projects. The original manual has been improved as a result of comments made by experts in the field of bio-energy. Updated information was added with respect to legislation, financing options and new technology. Also the manual is focused more on the wood processing industry
Technical document characterization by data analysis

International Nuclear Information System (INIS)

Mauget, A.

1993-05-01

Nuclear power plants possess documents analyzing all the plant systems, which represents a vast quantity of paper. Analysis of textual data can enable a document to be classified by grouping the texts containing the same words. These methods are used on system manuals for feasibility studies. The system manual is then analyzed by LEXTER and the terms it has selected are examined. We first classify according to style (sentences containing general words, technical sentences, etc.), and then according to terms. However, it will not be possible to continue in this fashion for the 100 system manuals existing, because of lack of sufficient storage capacity. Another solution is being developed. (author)
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
Manual on maintenance of systems and components important to safety

International Nuclear Information System (INIS)

1986-01-01

The Manual should serve as guidance at the plant management level for the maintenance of systems and components important to safety. It includes a detailed description of management systems, administrative controls and procedures. The Annexes contain examples of documents and practices adopted by Operating Organizations of some Member States. It is not the intention of this Manual to address the technical problem of how to maintain a particular component but rather to cover the programmatic aspects of maintenance. It also contains some aspects of surveillance and verification activities. The Manual makes only general statements about radiation protection provisions in connection with maintenance; detailed guidance can be found in other IAEA documents
Field manual for ground water reconnaissance. Savannah River Laboratory National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Ferguson, R.B.; Price, V.; Baucom, E.I.

1977-01-01

A manual is presented that is intended to direct and coordinate field operations, site selection, groundwater sample collection, and information codes for the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. The manual provides public relations information for field sampling teams as well as technical direction
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…
Technical basis for staffing levels at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Shurberg, D.A.; Haber, S.B. [Brookhaven National Lab., Upton, NY (United States); Morisseau, D. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

1995-04-01

The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.
Accident beyond the design basis management with the coolant loss at the NPP with WWER

International Nuclear Information System (INIS)

Skalozubov, V.I.; Klyuchnikov, A.A.; Kolykhanov, V.N.

2010-01-01

The analysis of status and experience of development on modelling and accident beyond the design basis management, including the severe accidents, at the nuclear power plants is carried out. The methodical providing of manuals on the accident beyond the design basis management with the coolant loss on the basis of simulated critical system configurations providing the necessary safety function performance on reactor unit is proposed. The project of symptom-oriented manuals on accident beyond the design basis management with the coolant loss on the serial power unit with WWER-1000 on the basis of developed methodical providing and well known results of deepened safety analysis is presented.
The design of operating procedures manuals for nuclear power plants

International Nuclear Information System (INIS)

Bohr, E.; Preuss, W.; Reinartz, G.; Thau, G.

1977-03-01

This report describes the findings of a research on the desirable design of operating procedures manuals for nuclear power plants. The work was supported by a grant of the Federal Department of the Interior. Information was acquired from different sources. Interviews and discussions on manual design were carried out with manual users in nuclear power plants. Moreover, tasks carried out using procedures were either observed or, alternatively, the manner of using procedures was elicited by interviews. In addition, manual writers, managers from manufacturers and utilities, nuclear experts, and individuals involved in manual specification activities were interviewed. A major source of information has been the pertinent scientific and technical findings scattered in the literature on topics such as instructional technology, engineering psychology, psycholinguistics, and typography. A comprehensive bibliography is included. General rules are established on designing instructional material for use on the job, aiming at increasing their legability, comprehensibility, and suitability to guide human performance. The application of these rules to the design of individual operating procedures is demonstrated. Recommendations are given on the design, layout, development and implementation of manuals. (orig.) [de
PRIS-WEDAS. User’s Manual to the Web Enabled Data Acquisition System for PRIS

International Nuclear Information System (INIS)

2015-01-01

The user manual for the Web Enabled Data Acquisition System (WEDAS), a system that supports the Power Reactor Information System (PRIS), provides instructions, guidelines and detailed definitions for each of the data items required for PRIS. The purpose of this manual is to ensure PRIS performance data are collected consistently and that the required quality of data collection is ensured. This PRIS-WEDAS user’s manual replaces reporting instructions published in the IAEA Technical Reports Series No. 428
Parallel Algorithms for Groebner-Basis Reduction

Science.gov (United States)

1987-09-25

22209 ELEMENT NO. NO. NO. ACCESSION NO. 11. TITLE (Include Security Classification) * PARALLEL ALGORITHMS FOR GROEBNER -BASIS REDUCTION 12. PERSONAL...All other editions are obsolete. Productivity Engineering in the UNIXt Environment p Parallel Algorithms for Groebner -Basis Reduction Technical Report
Field manual for stream sediment reconnaissance. Savannah River Laboratory National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Ferguson, R.B.; Price, V.; Baucom, E.I.

1976-07-01

A manual is presented that is intended to direct and coordinate field operations, site selection, stream sediment sample collection, water sample collection, and information codes for the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. The manual provides public relations information for field sampling teams as well as technical direction
Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 February 2007

International Nuclear Information System (INIS)

2007-01-01

The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear or radiological emergency, with the aim of minimizing the consequences. The International Atomic Energy Agency has specific functions assigned to it under these Conventions, to which, in addition to a large number of States, the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. The arrangements provided between the IAEA, States that are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of these Conventions - specifically concerning those articles that are operational in nature - are documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). ENATOM was first issued on 18 January 1989. Member States, Parties to the Early Notification and Assistance Conventions, relevant international organizations and other States have since then regularly received updates to the manual. In 2000, a complete revision of ENATOM was reissued as EPR-ENATOM (2000) to reflect technological developments, changes in operational concepts, views on standards in the area of emergency preparedness and response, and Member States' expectations. Since then ENATOM has been reviewed and reissued biennially in line with the review cycle of the Joint Radiation Emergency Management Plan of the International Organizations (the 'Joint Plan'). Since the last edition of ENATOM in 2004, several factors have warranted some modifications to
Technical basis for evaluating electromagnetic and radio-frequency interference in safety-related I ampersand C systems

International Nuclear Information System (INIS)

Ewing, P.D.; Korsah, K.

1994-04-01

This report discusses the development of the technical basis for the control of upsets and malfunctions in safety-related instrumentation and control (I ampersand C) systems caused by electromagnetic and radio-frequency interference (EMI/RFI) and power surges. The research was performed at the Oak Ridge National Laboratory (ORNL) and was sponsored by the USNRC Office of Nuclear Regulatory Research (RES). The motivation for research stems from the safety-related issues that need to be addressed with the application of advanced I ampersand C systems to nuclear power plants. Development of the technical basis centered around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems known to be the source(s) of EMI/RFI and power surges. First, good EMC design and installation practices need to be established to control the impact of interference sources on nearby circuits and systems. These EMC good practices include circuit layouts, terminations, filtering, grounding, bonding, shielding, and adequate physical separation. Second, an EMI/RFI test and evaluation program needs to be established to outline the tests to be performed, the associated test methods to be followed, and carefully formulated acceptance criteria based on the intended environment to ensure that the circuit or system under test meets the recommended guidelines. Third, a program needs to be developed to perform confirmatory tests and evaluate the surge withstand capability (SWC) and of I ampersand C equipment connected to or installed in the vicinity of power circuits within the nuclear power plant. By following these three steps, the design and operability of safety-related I ampersand C systems against EMI/RFI and power surges can be evaluated, acceptance criteria can be developed, and appropriate regulatory guidance can be provided
Nuclear electronics laboratory manual 1989 edition

International Nuclear Information System (INIS)

1989-10-01

This manual is a joint product of several electronics experts who have been associated with IAEA activity in this field for many years. It is based on the experience of conducting twenty-three training courses on nuclear electronics. Compared with the first edition, published 1984, this edition contains many new experiments, mainly on the advanced technical level. The total number of experiments and special projects is 58. Tabs and figs
Acquisition and Development of System Command (SYSCOM) Technical Manuals

National Research Council Canada - National Science Library

2003-01-01

... (NAVSEA) and Space and Naval Warfare Systems Command (SPAWAR). TMs are the primary information source for technical training, installation, operation, testing, maintenance, and repair associated with NAVSEA/SPAWAR systems or equipment...
Operators Manual and Technical Reference for the Z-Beamlet Phase Modulation Failsafe System: Version 1.

Energy Technology Data Exchange (ETDEWEB)

Armstrong, Darrell J.

2014-09-01

The need for pulse energies exceeding 4 kJ and pulse lengths [?] 2 ns in Sandia's Z-Beamlet laser (ZBL) requires that the single-frequency spectrum of its fiber-laser master oscillator be converted to a phase modulated spectrum with a modulation in dex [?] 5. Because accidental injection of single-frequency light into ZBL could result i n damage to optical materials from transverse stimulated Brillouin scattering, the presence of phase modulated (PM) light must be monitored by a reliable failsafe system that can stop a las er shot within of a few 10's of ns following a failure of the PM system. This requirement is met by combining optical heterodyne detection with high-speed electronics to indicate the pres ence or absence of phase modulated light. The transition time for the failsafe signal resultin g from a sudden failure using this technique is approximately 35 ns. This is sufficiently short to safely stop a single-frequency laser pulse from leaving ZBL's regenerative amplifier with a n approximately 35 ns margin of safety. This manual and technical reference contains detai led instructions for daily use of the PM failsafe system and provides enough additional informat ion for its maintenance and repair.
Revision of the protective action guides manual for nuclear incidents

International Nuclear Information System (INIS)

DeCair, S.; MacKinney, J.

2007-01-01

EPA's 1992 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, referred to as the PAG Manual, is a radiological emergency planning and response tool for emergency management officials at the Federal, state, tribal, and local levels. A Protective Action Guide is defined as, the projected dose to reference man, or other defined individual, from a release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended'. The updated version of the PAG Manual accomplishes these key objectives: applying the existing 1992 protective action guides and protective actions to new radiological and nuclear scenarios of concern; updating the dosimetry basis; lowering the recommended dose for administration of stable iodine; providing new guidance concerning consumption of drinking water during or after a radiological emergency; updating the dosimetry basis for all derived levels, and, adding guidance for dealing with long-term site restoration following a major radiological release. (author)
Analysis and evaluation of the ASTEC model basis. Relevant experiments. Technical report

International Nuclear Information System (INIS)

Koppers, V.; Koch, M.K.

2015-12-01

The present report is a Technical Report within the research project ''ASMO'', funded by the German Federal Ministry of Economics and Technology (BMWi 1501433) and projected at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at the Ruhr-Universitaet Bochum (RUB). The project deals with the analysis of the model basis of the Accident Source Term Evaluation Code (ASTEC). This report focuses on the containment part of ASTEC (CPA) and presents the simulation results of the experiment TH20.7. The experimental series TH20 was performed in the test vessel THAI (Thermal-hydraulics, Aerosols, Iodine) to investigate the erosion of a helium layer by a blower generated air jet. Helium is used as a substitute for hydrogen. In the experiment TH20.7 a light-gas layer is established and eroded by a momentum driven jet. The simulation of momentum driven jets is challenging for CPA because there is no model to simulate the kinetic momentum transfer. Subject of this report is the analysis of the capability of the code with the current model basis to model momentum driven phenomena. The jet is modelled using virtual ventilation systems, so called FAN-Systems. The FAN-Systems are adapted to the erosion velocity. The simulation results are compared to the experimental results and a basic calculation using FAN-Systems without any adjustments. For further improvement, different variation calculations are performed. At first, the vertical nodalization is refined. Subsequently, the resistance coefficients are adjusted to support the jet flow pattern and the number of the FAN-Systems is reduced. The analysis shows that the simulation of a momentum driven light-gas layer erosion is possible using adjusted FAN-Systems. A fine selected vertical nodalization and adaption of the resistance coefficients improves the simulation results.

Fire and blast safety manual for fuel element manufacture

International Nuclear Information System (INIS)

Ensinger, U.; Koehler, B.; Mester, W.; Riotte, H.G.; Sehrbrock, H.W.

1988-01-01

The manual aims to enable people involved in the planning, operation, supervision, licensing or appraisal of fuel element factories to make a quick and accurate assessment of blast safety. In Part A, technical plant principles are shown, and a summary lists the flammable materials and ignition sources to be found in fuel element factories, together with theoretical details of what happens during a fire or a blast. Part B comprises a list of possible fires and explosions in fuel element factories and ways of preventing them. Typical fire and explosion scenarios are analysed more closely on the basis of experiments. Part B also contains a list and an assessment of actual fires and explosions which have occurred in fuel element factories. Part C contains safety measures to protect against fire and explosion, in-built fire safety, fire safety in plant design, explosion protection and measures to protect people from radiation and other hazards when fighting fires. A distinction is drawn between UO 2 , MOX and HTR fuel elements. (orig./DG) [de
Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

International Nuclear Information System (INIS)

James, L.A.

1997-01-01

The Section 11 Working Group on Flaw Evaluation of the ASME B and PV Code Committee is considering a Code Case to allow the determination of the conditions under which environmentally-assisted cracking of low-alloy steels could occur in PWR primary environments. This paper provides the technical support basis for such an EAC Initiation and Cessation Criterion by reviewing the theoretical and experimental information in support of the proposed Code Case
Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

Energy Technology Data Exchange (ETDEWEB)

James, L.A.

1997-10-01

The Section 11 Working Group on Flaw Evaluation of the ASME B and PV Code Committee is considering a Code Case to allow the determination of the conditions under which environmentally-assisted cracking of low-alloy steels could occur in PWR primary environments. This paper provides the technical support basis for such an EAC Initiation and Cessation Criterion by reviewing the theoretical and experimental information in support of the proposed Code Case.
Computerized creation of interactive electronic technical manuals (IETM)

International Nuclear Information System (INIS)

Galin, I.Yu.

2011-01-01

The author informs that the automated system of developing and maintaining the operational documentation (OD) (Technical Guide Builder) has been first developed and experimentally tested. The obtained result raises the competitiveness of Russian aircraft in international markets. The author offers methods and technology of OD formation, allowing to produce interactive OD for domestic aircraft industry, issued according to international standards in several languages [ru
Technical basis for PWR emergency plans forming

International Nuclear Information System (INIS)

L'Homme, A.; Manesse, D.; Gauvain, J.; Crabol, B.

1989-10-01

Our speech first summarizes the french approach concerning the management of severe accidents which could occur on PWR stations. Then it defines the source-term which is being used as a general support for elaborating the emergency plans devoted to the protection of the population. It describes next the consequences of this source-term on the site and in the environment, which constitute the technical bases for defining actions of utilities and concerned authorities. It gives lastly information on the present status of the different emergency plans and the complementary work undertaken to improve them [fr
Simplified Procedures for Eutrophication Assessment and Prediction: User Manual

Science.gov (United States)

1996-09-01

1975), for use in the Lake Erie Wastewater Management Study and is described by Verhoff, Yaksich, and Melfi (1980) and Westerdahl et al. (1981). This...manual," Technical Re- port E-81-9, U.S. Army Engineer Waterways Experiment Station, Vicksburg, MS. Westerdahl , H. E., Ford, W. B., Harris, J., and
Factors increasing the risk of inactivity among administrative, technical, and manual workers in Warszawa public institutions.

Science.gov (United States)

Biernat, Elżbieta

2015-01-01

The research aims to assess the level of physical activity among administrative, technical, and manual workers employed in Warszawa public institutions and to analyze the factors that increase the risk of failing to meet World Health Organization (WHO) recommendations. The study comprised 373 employees of randomly selected institutions. A short version of International Physical Activity Questionnaire (IPAQ) was applied. The correlation between the mean values of duration, days, MET-min/week of efforts, gender, and type of work was analyzed using the Tukey's honest significant difference (HSD) test, while the correlation between the level of physical activity and the socio-demographic characteristics was assessed with the Chi2 test. The strength of the relationship between socio-demographic characteristics and fulfilment of WHO standards was expressed by the odds ratio (OR) and 95% confidence interval (95% CI). The significance level was p = 0.05. High levels of physical activity were declared by 41.8% of the manual workers, 14.7% of the administration staff, and 7.3% of the technicians; 19%, 31.5% and 54.5%, respectively, reported low levels of physical activity. Factors determining the fulfilment of the WHO recommendations include: the nature of work (p = 0.003), education (p = 0.004), and income (p = 0.003). The risk of being inactive nearly doubles in the case of administration staff (31.5%) and increases more than 4 times in the case of technicians (54.5%). Respondents with secondary school education (31.6%) are exposed to a 3-fold higher risk of inactivity, while in respondents with higher education (37.2%), the level of the risk is 4-fold higher. Compared to those in the highest income group (23.4%), people who earn less (34.1%) are inactive almost twice as often. Urgent intervention is necessary in all studied groups: increased energy expenditure for recreation and locomotion, educational offers of employers to promote healthy lifestyle, management of
California Publicly-Owned Utilities (POUs) – LBNL ‘Beyond Widgets’ Project. Task: ambient lighting and occupancy-based plug load control. System Program Manual

Energy Technology Data Exchange (ETDEWEB)

Robinson, Alastair; Mathew, Paul A.; Regnier, Cynthia; Schwartz, Peter; Schakelford, Jordan; Walter, Travis

2017-09-01

This program manual contains detailed technical information for implementing an incentive program for task-ambient lighting and occupancy-based plug load control. This manual was developed by Lawrence Berkeley National Laboratory, in collaboration with the California Publicly-Owned Utilities (CA POUs) as a partner in the ‘Beyond Widgets’ program funded by the U.S. Department of Energy Building Technologies Office. The primary audience for this manual is the program staff of the various CA POUs. It may also be used by other utility incentive programs to help develop similar programs. It is anticipated that the content of this manual be utilized by the CA POU staff for developing related documents such as the Technical Resource Manual and other filings pertaining to the rollout of an energy systems-based rebate incentive program.
Rural Gas Program manual

Energy Technology Data Exchange (ETDEWEB)

1987-11-01

The intent and purpose of this manual is to describe the various guideliness and administrative procedures associated with the Alberta Rural Gas Program and to consolidate and expand upon the legislation under which the Program has been developed. It is intended primarily for the use and information of rural gas distributors, their agents, and other private or government parties having an interest in the Rural Gas Program. Information is presented on: rural gas franchises, technical applications, contracts and tenders, determination of system capital costs for grant support, grants, Gas Alberta brokerage arrangements, insurance coverage, utility rights-of-way, and lien notes.
Transportation management center data capture for performance and mobility measures reference manual.

Science.gov (United States)

2013-03-01

The Guide to Transportation Management Center (TMC) Data Capture for Performance and Mobility Measures is a two-volume document consisting of a summary Guidebook and this Reference Manual. These documents provide technical guidance and recommended pr...
Calibration of dosimeters used in radiotherapy. A manual

International Nuclear Information System (INIS)

1994-01-01

The present manual is a revision of IAEA Technical Reports Series No.185, published in 1979. This manual is intended for use by the network of Secondary Standard Dosimetry Laboratories (SSDLs) which was set up by the IAEA and the World Health Organization (WHO). The objectives of the SSDL network are to: calibrate radiation dosimeters and ancillary instruments; serve as a link between primary standard laboratories and radiation users; and provide advice and assistance in all aspects of radiation metrology. The various calibration procedures are described, their relative advantages and disadvantages are discussed, and criteria are put forward to help an SSDL decide which procedure is the best to use in order to meet a particular requirement. The information in this manual should also be of value to other similar laboratories, usually associated with hospitals, which are not formally part of the IAEA/WHO network of SSDLs. 26 refs, 6 figs, 6 tabs
Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

International Nuclear Information System (INIS)

O'Hara, J.M.; Higgins, J.C.

2010-01-01

Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.
Field and in-situ rock-mechanics testing manual. Technical report

International Nuclear Information System (INIS)

Shuri, F.S.; Feves, M.L.; Peterson, G.L.; Foster, K.M.; Kienle, C.F. Jr.

1981-10-01

Standardized field and in situ rock mechanics testing procedures have been prepared for use in the National Terminal Waste Storage Program. The procedures emphasize equipment performance specifications, documentation and reporting, and Quality Assurance acceptance criteria. Sufficient theoretical background is included to allow the user to perform the necessary data reduction. These procedures incorporate existing standards when possible, otherwise they represent the current state of the art. Maximum flexibility in equipment design has been incorporated to allow use of this manual by existing groups and to encourage future improvements
Introduction to the Social Sciences: Teacher's Manual.

Science.gov (United States)

Blum, Mark E.; Spangehl, Stephen D.

A competency-based, introductory social science course for college students is described. Objectives of the manual are twofold--first, to present the complete set of materials which have served as the basis of a one semester social sciences course at the University of Louisville over three years, and, second, to offer suggestions regarding…
Calculation of the effectiveness of manual control rods for the reactor of Ignalina NPP Unit 2

International Nuclear Information System (INIS)

Bubelis, E.; Pabarcius, R.

2001-01-01

On the basis of one of the recent databases of the reactor of Ignalina NPP Unit 2, calculations of the effectiveness of separate manual control rods, groups of manual control rods and axial characteristic of effectiveness of separate manual control rods were performed. The results of the calculations indicated, that all analyzed separate manual control rods have approximately the same effectiveness, which doesn't depend on the location of a control rod in the reactor core layout Manual control rod of the new design has about 10% greater effectiveness than manual control rod of the old design. (author)
Proceedings of the joint CSNI/CNRA workshop on redefining the large break LOCA: technical basis and its implications

International Nuclear Information System (INIS)

2003-01-01

-informing technical requirement. In the third paper, the European reactor vendor gave its view on LB-LOCA definition for new reactors (EPR). The proposed concept take into account the LB-LOCA (of the main coolant line) for designing the ECCS and the containment but not for mechanical design of the main coolant lines itself. An important prerequisite for LBB and break exclusion in the EPR is also reliable monitoring and inspection. 2. Does adequate technical basis exist to support a redefinition of the LB-LOCA? None of the participants suggested that the probability of LB LOCA could be so high that it represents a significant contribution to the overall risk. There was a general confidence that the probability of a fast occurring large leak from the main reactor coolant circuit can be made insignificant with the right corrective measures. This is true at least in the new plants where lessons learned during the last 30 years have been implemented. The session had a well coordinated set of four complementary presentations aimed at measuring the technical basis to support a redefinition of the LB-LOCA, through the potential development of a spectrum of break sizes, their expected frequencies and the corresponding consequences. With that aim, the four papers presented, in a sequential manner: the critical issues and technical approaches to the subject from the risk requirements point of view, the known and potential aging mechanisms in primary pipes, the technical and administrative developments to prevent pressure boundary fractures through in service inspections and the new developments to detect such fractures through advanced leak detection technologies. The NRC presentation identified issues related to materials engineering, risk considerations, and plant response analysis, and discussed NRC's ongoing technical approaches to address these issues and develop a technical basis for the risk-informed revision of the rule. The EDF presentation was very insightful as it reflected
Solar Simulation Laboratory Description and Manual.

Science.gov (United States)

1985-06-01

2000 was sent back to Cyborg Corp. three times over a five month period for repairs. The solar lab is presently using a loaner from Cyborg Corp. The IBM...PC/XT is connected to the ISAAC 2000 by a RS232 connection. All programs were written in advanced basic ("BASICA"). BASICA was used because Cyborg ...2067 CH/P Temperature.Control Bath TechnicalManual, November. 1980. A 30. Cyborg Corporation, Version 1.2, IS..AC.....Co..mpiut.er.liz e.d Data
TMI cable tracer operation and maintenance manual for assembly 417910

International Nuclear Information System (INIS)

Sumstine, R.L.

1983-11-01

This manual provides technical information and instructions to operate and maintain the cable tracer designed for the Three Mile Island (TMI) Unit 2 Reactor Building. The TMI cable tracer was developed to allow TMI personnel to trace cables in cable trays that may be tested or sectioned for destructive examination
Controlatron Neutron Tube Test Suite Software Manual - Operation Manual (V2.2)

CERN Document Server

Noel, W P; Hertrich, R J; Martinez, M L; Wallace, D L

2002-01-01

The Controlatron Software Suite is a custom built application to perform automated testing of Controlatron neutron tubes. The software package was designed to allowing users to design tests and to run a series of test suites on a tube. The data is output to ASCII files of a pre-defined format for data analysis and viewing with the Controlatron Data Viewer Application. This manual discusses the operation of the Controlatron Test Suite Software and a brief discussion of state machine theory, as state machine is the functional basis of the software.
Los Alamos Scientific Laboratory x-ray survey manual

International Nuclear Information System (INIS)

Olsher, R.H.

1980-02-01

A manual has been developed by the Health Physics Group to establish procedures for routine testing of industrial and analytical x-ray equipment for compliance with applicable LASL administrative requirements and technical bulletins. Radiation protection survey procedures were developed for the following types of equipment: x-ray diffraction and fluorescence analysis systems, industrial cabinet x-ray systems, industrial noncabinet x-ray systems, and electron microscopes

Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 December 2002

International Nuclear Information System (INIS)

2002-11-01

The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency, with the aim of minimizing their consequences. The International Atomic Energy Agency (IAEA) has specific functions assigned to it under these Conventions, to which, in addition to a large number of States (Section 1.7), the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. The arrangements between the IAEA, States that are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of these Conventions specifically concerning those articles that are operational in nature - are documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). In 2000, a complete revision of ENATOM, with all relevant sections updated, withdrawn or replaced with new material, was reissued as EPR-ENATOM (2000) to reflect new technological developments, operational concepts, views on standards in the area of emergency preparedness and response, and Member States' expectations. A separate publication, EPR-JPLAN (2000), the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan'), described a common understanding of how each of six co-sponsoring international organizations will act during a response and in making preparedness arrangements. It is intended that the ENATOM is reviewed and reissued biennially in line with the review cycle of the Joint Plan. Since the
Robotic-Assisted Versus Manual Prostatic Arterial Embolization for Benign Prostatic Hyperplasia: A Comparative Analysis

Energy Technology Data Exchange (ETDEWEB)

Bagla, Sandeep, E-mail: sandeep.bagla@gmail.com [Vascular Institute of Virginia, LLC (United States); Smirniotopoulos, John [New York Presbyterian Hospital/Weill Cornell Medical Center (United States); Orlando, Julie C.; Piechowiak, Rachel [Vascular Institute of Virginia, LLC (United States)

2017-03-15

PurposeProstatic artery embolization (PAE) is a safe and efficacious procedure for benign prostatic hyperplasia (BPH), though is technically challenging. We present our experience of technical and clinical outcomes of robotic and manual PAE in patients with BPH.Materials and MethodsIRB-approved retrospective study of 40 consecutive patients 49–81 years old with moderate or severe grade BPH from May 2014 to July 2015: 20 robotic-assisted PAE (group 1), 20 manual PAE (group 2). Robotic-assisted PAE was performed using the Magellan Robotic System. American Urological Association (AUA-SI) score, cost, technical and clinical success, radiation dose, fluoroscopy, and procedure time were reviewed. Statistical analysis was performed within and between each group using paired t test and one-way analysis of variance respectively, at 1 and 3 months.ResultsNo significant baseline differences in age and AUA-SI between groups. Technical success was 100% (group 1) and 95% (group 2). One unsuccessful subject from group 2 returned for a successful embolization using robotic assistance. Fluoroscopy and procedural times were similar between groups, with a non-significant lower patient radiation dose in group 1 (30,632.8 mGy/cm{sup 2} vs 35,890.9, p = 0.269). Disposable cost was significantly different between groups with the robotic-assisted PAE incurring a higher cost (group 1 $4530.2; group 2 $1588.5, p < 0.0001). Clinical improvement was significant in both arms at 3 months: group 1 mean change in AUA-SI of 8.3 (p = 0.006), group 2: 9.6 (p < 0.0001). No minor or major complications occurred.ConclusionsRobotic-assisted PAE offers technical success comparable to manual PAE, with similar clinical improvement with an increased cost.
Robotic-Assisted Versus Manual Prostatic Arterial Embolization for Benign Prostatic Hyperplasia: A Comparative Analysis

International Nuclear Information System (INIS)

Bagla, Sandeep; Smirniotopoulos, John; Orlando, Julie C.; Piechowiak, Rachel

2017-01-01

PurposeProstatic artery embolization (PAE) is a safe and efficacious procedure for benign prostatic hyperplasia (BPH), though is technically challenging. We present our experience of technical and clinical outcomes of robotic and manual PAE in patients with BPH.Materials and MethodsIRB-approved retrospective study of 40 consecutive patients 49–81 years old with moderate or severe grade BPH from May 2014 to July 2015: 20 robotic-assisted PAE (group 1), 20 manual PAE (group 2). Robotic-assisted PAE was performed using the Magellan Robotic System. American Urological Association (AUA-SI) score, cost, technical and clinical success, radiation dose, fluoroscopy, and procedure time were reviewed. Statistical analysis was performed within and between each group using paired t test and one-way analysis of variance respectively, at 1 and 3 months.ResultsNo significant baseline differences in age and AUA-SI between groups. Technical success was 100% (group 1) and 95% (group 2). One unsuccessful subject from group 2 returned for a successful embolization using robotic assistance. Fluoroscopy and procedural times were similar between groups, with a non-significant lower patient radiation dose in group 1 (30,632.8 mGy/cm"2 vs 35,890.9, p = 0.269). Disposable cost was significantly different between groups with the robotic-assisted PAE incurring a higher cost (group 1 $4530.2; group 2 $1588.5, p < 0.0001). Clinical improvement was significant in both arms at 3 months: group 1 mean change in AUA-SI of 8.3 (p = 0.006), group 2: 9.6 (p < 0.0001). No minor or major complications occurred.ConclusionsRobotic-assisted PAE offers technical success comparable to manual PAE, with similar clinical improvement with an increased cost.
Emergency procedures beyond design basis ''Feed and Bleed''

International Nuclear Information System (INIS)

Dominguez Bautista, M.T.; Campuzano Pena, F.

1994-01-01

The incorporation of Beyond-Design-Basis Emergency Procedures, also called the Emergency Manual or Severe Accident Manual, has been an important step forward in nuclear power plant safety. These procedures cover situations in which the deterministic criteria used in plant design have been contravened. In such situations new accident scenarios, unforeseen system actions or a combination of both, need to be considered. Establishing these procedures is actually the last in a sequence of activities the sequence includes definition of scenarios, study of their phenomena, analysis of optional system actions, verification of their effectiveness and finally, implementation of the procedure. The systematization of these new strategies is supported by the results of the probabilistic analyses which serve in this case to pinpoint the objectives of these strategies. This paper describes the application of this methodology in the definition of a procedure for heat sink recovery on the secondary side (feed and bleed) if this has been totally or partially lost in a beyond-design-basis event. (Author)
Manual of functions, assignments, and responsibilities for nuclear safety: Revision 2

Energy Technology Data Exchange (ETDEWEB)

1994-10-15

The FAR Manual is a convenient easy-to-use collection of the functions, assignments, and responsibilities (FARs) of DOE nuclear safety personnel. Current DOE directives, including Orders, Secretary of Energy Notices, and other assorted policy memoranda, are the source of this information and form the basis of the FAR Manual. Today, the majority of FARs for DOE personnel are contained in DOE`s nuclear safety Orders. As these Orders are converted to rules in the Code of Federal Regulations, the FAR Manual will become the sole source for information relating to the functions, assignments, responsibilities of DOE nuclear safety personnel. The FAR Manual identifies DOE directives that relate to nuclear safety and the specific DOE personnel who are responsible for implementing them. The manual includes only FARs that have been extracted from active directives that have been approved in accordance with the procedures contained in DOE Order 1321.1B.
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…
Determination of a Basis for Design of a Yam (Dioscorea Spp ...

African Journals Online (AJOL)

Manual separation is both tedious and expensive, so the work reported here was done to determine a suitable basis for the design of a mechanical minisett sorter. Results from this study showed that the minisetts cut from the regions of the parent tuber can be separated on the basis of characteristic dimensions of arc length ...
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...
Why most Brand Manuals fail when it comes to defining Brand Colors

DEFF Research Database (Denmark)

Abildgaard, Michael

2016-01-01

From top class Universities and governmental organizations to high-end global brands and well-known local brands, a surprising consistency of inattentiveness has been published in these compa-nies’ prestigious Brand Manuals and Brand Guides. When it comes to providing technical guidance, defining...
Long Term Operation R and D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

International Nuclear Information System (INIS)

Gaertner, John

2012-01-01

Establishing an improved technical basis for long term operation of existing plants is a nuclear industry priority. The Electric Power Research Institute (EPRI) has responded with a comprehensive Long Term Operation (LTO) Program addressing this need for existing nuclear power plants world-wide. The program supports both the business decisions necessary to achieve high performance operation and the licensing requirements for operation beyond 60 years. The program selects its R and D priorities in a structured and objective way with much industry input to provide useful results for decisions in the 2014 to 2019 time frame. The program is highly collaborative with U.S. Department of Energy (DOE) and with EPRI-member utilities. The R and D portfolio includes materials aging (metals, concrete, and cables), modernization of information and control technology, enhanced safety analysis, advanced fuel design, demonstration plant activities, life cycle management, and identification of aging management program need for subsequent license renewal. The program has focussed stakeholders world-wide on the technical issues of long term operation, and it is on-track to provide practical results for life extension and license renewal decisions. (author)
Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

Energy Technology Data Exchange (ETDEWEB)

OHara, J.M.; Higgins, J.C.

2010-01-31

Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.
Occupational safety manual. 4. rev. ed.

International Nuclear Information System (INIS)

Skiba, R.

1979-01-01

With the rapid technical development and increasing life expectancy, protection against occupational hazards has become a central economic and social problem. Consultants and others responsible for occupational safety should not only be interested in their work but also have sufficient basic knowledge. The complex subject is presented in a simplified and easily comprehensible manner, with particular regard to the practical side. The book is at the same time a textbook for basic training and a reference manual for the working practice. (orig./HP) [de
The research project on technical information basis for aging management in Fukui and Kinki area (2nd report)

International Nuclear Information System (INIS)

Fujimura, Kimiya; Watarumi, Chikae; Toudou, Tsugihiko

2009-01-01

The Research Project on Technical Information Basis for Aging Management was initiated in 2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI), to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging plants are regulated. Upon taking part in the R and D Roadmaps for Aging Management and Safe Long Term Operation, the experience and results of the participating organizations were considered and the following four topics were extracted. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants. 2) The development of inspection techniques to monitor the initiation and propagation of defects. 3) The development of a guideline for evaluating weld repair methods. 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as of coordinator to make a contracts, facilitate execution, and compile annual reports. In FY2008, 11 research subjects were proposed for this project and all were accepted. Of these, 4 subjects were related to the first topic (pipe thinning), 3 subjects were related to the second topic (inspection technique) and I subject was related to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)
The research project on technical information basis for aging management in Fukui and Kinki area. 3rd report

International Nuclear Information System (INIS)

Fujimura, Kimiya; Watarumi, Chikae; Toudou, Tsugihiko

2010-01-01

The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI), to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the R and D Roadmaps for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. (1) The improvement of pipe thinning management in nuclear power plants, (2) The development of inspection techniques to monitor the initiation and propagation of defects, (3) The development of a guideline for evaluating weld repair methods, (4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2009, 11 research subjects were proposed for this project and all were accepted. Of these, 4 subjects were related to the first topic (pipe thinning), 3 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)
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
Training and Development for Transitional Employment in Mature-Aged Manual Workers

Science.gov (United States)

Pillay, Hitendra; Kelly, Kathy; Tones, Megan

2010-01-01

Objectives: The purpose of the current article was to explore perceptions of transitional employment and training and development amongst blue collar workers employed in technical, trade, operations or physical and labour-intensive occupations within the local government system. Methods: The responses of manual workers to two national surveys…
Research in technical communication in the Netherlands

NARCIS (Netherlands)

Jansen, C.J.M.

1994-01-01

In the Netherlands, research in technical communication is a part of research in 'functional text,' which has concrete goals that must be achieved by lay readers. Three recent studies focus on the use of and failure to use software manuals, the minimalist approach and learning styles, and the effect
Tubular wells perforation manual for investigation and training of Guarani Aquifer System

International Nuclear Information System (INIS)

2007-01-01

The Environmental protection and sustainable development of the Aquifer Guarani System project is a initiative by Argentina, Brasil, Paraguay y Uruguay with the aim to raise the knowledge, legal and institutional sustainable management from 2003-2008 period. The Guarani consortium integrated by Tahal Engineers Ltda.(Israel), SEINCO SRL. (Uruguay), Hidrocontrol S:A:(Paraguay), Arcadis Hidroambiente S.A. (Argentina) have shown in Tubular wells perforation for investigation and training of Guarani Aquifer System manual their first product. This Manual includes technical especifications focused in Guarani Aquifer System harmessing building
Technical specifications: Tower Shielding Reactor II

International Nuclear Information System (INIS)

1979-02-01

The technical specifications define the key limitations that must be observed for safe operation of the Tower Shielding Reactor II (TSR-II) and an envelope of operation within which there is reasonable assurance that these limits cannot be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972
Technical specifications: Health Physics Research Reactor

International Nuclear Information System (INIS)

1979-02-01

The technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

Principles and technical aspects of PCR amplification

National Research Council Canada - National Science Library

Pelt-Verkuil, Elizabeth van; Belkum, Alex van; Hays, John P

2008-01-01

... to illustrate any particularly important concepts or comments. Indeed, all commercial PCR biotechnology companies offer information about their products on internet sites and in online technical manuals. These online resources will be invaluable for any readers requiring more detailed PCR protocols. The authors have provided references for many PCR co...
Regulatory manual for staging of cancer by CT

International Nuclear Information System (INIS)

Solorzano Marin, Jose Reinaldo

2008-01-01

The exact level for staging and making decisions about therapy that will be applied to cancer patients at the Servicio de Radiologia e Imagenes Medicas has been important for the Hospital Calderon Guardia. A template of report or manual has been suggested, with the information necessary for staging a particular type of cancer by analyzing the tomography of the patient. The TNM International System has been used to design the template of report, with a specific technical language and terminology unified theme for the oncologist and radiologist. This system is abstracted in the sixth edition of oncological staging manual of the American Joint Committee and its atlas; resources already acquired, and the helical CT scanner. The experience of the radiologist is critical, because he will be responsible to fill the document. [es
Operations and Maintenance Manual, Atmospheric Contaminant Sensor, Revision B.

Science.gov (United States)

National Aeronautics and Space Administration, Washington, DC.

The sensor is a mass spectrometer system which continuously monitors the atmospheric constituents of hydrogen, water vapor, nitrogen, oxygen, and carbon dioxide, and monitors the Freons on a demand sampling basis. The manual provides a system description, operational procedures, and maintenance and troubleshooting instructions. Circuit diagrams…
Improving artificial breeding of cattle and buffalo in Asia. Guidelines and recommendations. A manual prepared under the framework of an IAEA Technical Cooperation Regional RCA Project on 'Improving Animal Productivity and Reproductive Efficiency', with technical support of the Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture

International Nuclear Information System (INIS)

2005-11-01

Africa under the AFRA programme, to monitor and improve AI services. A recent Task Force meeting held under this project to 'Harmonize Procedures for Selection and Management of AI Bulls and Use of Semen Technology in African Countries' resulted in the compilation of a manual of guidelines similar to that envisaged for Asian countries. That manual was therefore used as a basic framework and necessary modifications and additions were done to meet the needs of RCA Member States and, in particular, to include aspects relevant to buffaloes. The main conclusions and recommendations from the RCA workshop were that the major challenges in the Asian region were: - Lack of a sound system for evaluation of breeding bulls; - Improper semen handling; - Inadequate and expensive supply of liquid nitrogen; - Inconsistent heat detection, incorrect timing of AI and poor hygiene; - Inadequate AI recording, follow-up and reporting; - Lack of clear breeding policies for cross-breeding; - Inadequate logistic support to field services; and - Lack of incentive schemes and accountability. It was clear that no universal remedy was possible for the identified problems, but there were common technical and procedural aspects that can be improved and standardized on the most appropriate techniques and procedures for obtaining optimum results under the prevailing conditions in Asia. The draft document prepared during the workshop was edited and the second draft was circulated to all national project coordinators for comments and suggestions for improvement. It was finally discussed at a Project Review and Planning Meeting held in Hangzhou, China in November 2002 and further material was incorporated as required. This manual therefore builds upon the experience gained in compiling a similar manual for use in African countries and is the result of collaboration between the national project coordinators of the RCA project, several experts in AI in the participating Member States, IAEA experts who
Rooftop Unit Comparison Calculator User Manual

Energy Technology Data Exchange (ETDEWEB)

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

2015-04-30

This document serves as a user manual for the Packaged rooftop air conditioners and heat pump units comparison calculator (RTUCC) and is an aggregation of the calculator’s website documentation. Content ranges from new-user guide material like the “Quick Start” to the more technical/algorithmic descriptions of the “Methods Pages.” There is also a section listing all the context-help topics that support the features on the “Controls” page. The appendix has a discussion of the EnergyPlus runs that supported the development of the building-response models.
Investigations on the quality of manual image segmentation in 3D radiotherapy planning

International Nuclear Information System (INIS)

Perelmouter, J.; Tuebingen Univ.; Bohsung, J.; Nuesslin, F.; Becker, G.; Kortmann, R.D.; Bamberg, M.

1998-01-01

In 3D radiotherapy planning image segmentation plays an important role in the definition process of target volume and organs at risk. Here, we present a method to quantify the technical precision of the manual image segmentation process. To validate our method we developed a virtual phantom consisting of several geometrical objects of changing form and contrast, which should be contoured by volunteers using the TOMAS tool for manual segmentation of the Heidelberg VOXELPLAN system. The results of this examination are presented. (orig.) [de
Aligning Theme and Information Structure to Improve the Readability of Technical Writing

Science.gov (United States)

Moore, N. A. J.

2006-01-01

The readability of technical writing, and technical manuals in particular, especially for second language readers, can be noticeably improved by pairing Theme with Given and Rheme with New. This allows for faster processing of text and easier access to the "method of development" of the text. Typical Theme-Rheme patterns are described, and the…
Tracer manual on crops and soils

International Nuclear Information System (INIS)

1976-01-01

The manual serves as a reference for agricultural scientists planning to use nuclear techniques. Training courses are held at various locations with different staff. The existence of a laboratory training manual is helpful to organizers, visiting lecturers, demonstrators and participants. It was primarily written for soil scientists from developing countries participating in training courses on the use of isotopes and radiation in soil-water-plant relations research. The training courses are designed to give soil scientists the basic terms and principles necessary for understanding ionizing radiation, its detection and measurement, its associated hazards and most of the more common applications. Due consideration is also given to the detection of stable isotopes and providing a clear understanding of their potential in research on crops and soils. Each experiment included this revised and updated manual (see IAEA Technical Reports Series No. 29: The Laboratory Training Manual on the Use of Isotopes and Radiation in Soil-Plant Relations Research, published in 1964) has been performed and tested for suitability in training courses. To facilitate the task of organizers in preparing for and planning the programmes of training courses, detailed information is provided on each experiment, indicating the time required for its performance and the necessary equipment, glassware, isotopes, chemicals, etc. A comprehensive glossary is included so that scientists may easily understand terms, units and expressions commonly used in this work. The glossary may also serve as an index since it includes the page number referring to the first mention of the term or expression
Incorporating travel time reliability into the Highway Capacity Manual. [supporting datasets

Science.gov (United States)

2013-11-30

The Highway Capacity Manual (HCM) historically has been among the most important reference guides used by transportation professionals seeking a systematic basis for evaluating the capacity, level of service, and performance measures for elements of ...
SRC-I demonstration plant analytical laboratory methods manual. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Klusaritz, M.L.; Tewari, K.C.; Tiedge, W.F.; Skinner, R.W.; Znaimer, S.

1983-03-01

This manual is a compilation of analytical procedures required for operation of a Solvent-Refined Coal (SRC-I) demonstration or commercial plant. Each method reproduced in full includes a detailed procedure, a list of equipment and reagents, safety precautions, and, where possible, a precision statement. Procedures for the laboratory's environmental and industrial hygiene modules are not included. Required American Society for Testing and Materials (ASTM) methods are cited, and ICRC's suggested modifications to these methods for handling coal-derived products are provided.
Basis of valve operator selection for SMART

International Nuclear Information System (INIS)

Kang, H. S.; Lee, D. J.; See, J. K.; Park, C. K.; Choi, B. S.

2000-05-01

SMART, an integral reactor with enhanced safety and operability, is under development for use of the nuclear energy. The valve operator of SMART system were selected through the data survey and technical review of potential valve fabrication vendors, and it will provide the establishment and optimization of the basic system design of SMART. In order to establish and optimize the basic system design of SMART, the basis of selection for the valve operator type were provided based on the basic design requirements. The basis of valve operator selection for SMART will be used as a basic technical data for the SMART basic and detail design and a fundamental material for the new reactor development in the future
Basis of valve operator selection for SMART

Energy Technology Data Exchange (ETDEWEB)

Kang, H. S.; Lee, D. J.; See, J. K.; Park, C. K.; Choi, B. S

2000-05-01

SMART, an integral reactor with enhanced safety and operability, is under development for use of the nuclear energy. The valve operator of SMART system were selected through the data survey and technical review of potential valve fabrication vendors, and it will provide the establishment and optimization of the basic system design of SMART. In order to establish and optimize the basic system design of SMART, the basis of selection for the valve operator type were provided based on the basic design requirements. The basis of valve operator selection for SMART will be used as a basic technical data for the SMART basic and detail design and a fundamental material for the new reactor development in the future.
Manual on environmental monitoring in normal operation

International Nuclear Information System (INIS)

1966-01-01

Many establishments handling radioactive materials produce, and to some extent also discharge, radioactive waste as part of their normal operation. The radiation doses to which members of the public may be exposed during such operation must remain below the stipulated level. The purpose of this manual is to provide technical guidance for setting up programmes of routine environmental monitoring in the vicinity of nuclear establishment. The annex gives five examples of routine environmental monitoring programmes currently in use: these have been indexed separately.
SAM Theory Manual

Energy Technology Data Exchange (ETDEWEB)

Hu, Rui [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

The System Analysis Module (SAM) is an advanced and modern system analysis tool being developed at Argonne National Laboratory under the U.S. DOE Office of Nuclear Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. SAM development aims for advances in physical modeling, numerical methods, and software engineering to enhance its user experience and usability for reactor transient analyses. To facilitate the code development, SAM utilizes an object-oriented application framework (MOOSE), and its underlying meshing and finite-element library (libMesh) and linear and non-linear solvers (PETSc), to leverage modern advanced software environments and numerical methods. SAM focuses on modeling advanced reactor concepts such as SFRs (sodium fast reactors), LFRs (lead-cooled fast reactors), and FHRs (fluoride-salt-cooled high temperature reactors) or MSRs (molten salt reactors). These advanced concepts are distinguished from light-water reactors in their use of single-phase, low-pressure, high-temperature, and low Prandtl number (sodium and lead) coolants. As a new code development, the initial effort has been focused on modeling and simulation capabilities of heat transfer and single-phase fluid dynamics responses in Sodium-cooled Fast Reactor (SFR) systems. The system-level simulation capabilities of fluid flow and heat transfer in general engineering systems and typical SFRs have been verified and validated. This document provides the theoretical and technical basis of the code to help users understand the underlying physical models (such as governing equations, closure models, and component models), system modeling approaches, numerical discretization and solution methods, and the overall capabilities in SAM. As the code is still under ongoing development, this SAM Theory Manual will be updated periodically to keep it consistent with the state of the development.
Technical basis for the CANDU steam generator tube fitness-for-service guidelines

International Nuclear Information System (INIS)

Kozluk, M.J.; Scarth, D.A.; Graham, D.B.

2002-01-01

Active degradation mechanisms in steam generators and preheaters in Canadian CANDU T M generating stations are managed through Steam Generator Programs that incorporate tube inspection, maintenance (cleaning), fitness-for-service assessment, and preventative plugging as part of the overall steam generator management strategy. Steam generator and preheater tubes are inspected in accordance with the CSA Standard CAN/CSA-N285.4-94[l]. When a detected flaw indication does not satisfy the criteria of acceptance by examination, CSA-N285.4-94 permits a fitness-for-service assessment to determine acceptability. In 1999 Ontario Power Generation issued, for trial use, fitness-for-service guidelines for steam generator and preheater tubes in CANDU nuclear power plants. The main objectives of the Fitness-for-Service Guidelines are to provide reasonable assurance that tube structural integrity is maintained, and to provide reasonable assurance that there are adequate margins between estimated accumulated dose and applicable site dose limits. The Fitness-for-Service Guidelines are intended to provide industry-standard acceptance criteria and evaluation procedures for assessing the condition of steam generator and preheater tubes in terms of tube structural integrity, operational leak rate, and consequential leakage during an upset or abnormal event. This paper describes the technical basis for the minimum required safety factors specified in Table IC-1 of the Fitness-for-Service Guidelines and for the flaw models used to develop the flaw stability requirements in the nonmandatory, Appendix C of the Fitness-for-Service Guidelines. (author)
Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

1997-01-01

This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program
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.
Tanning lamps ultraviolet emissions and compliance with technical standards

International Nuclear Information System (INIS)

Bonino, A.; Facta, S.; Saudino, S.; Anglesio, L.; D'Amore, G.

2009-01-01

In this work the compliance of tanning lamps with technical standards EN 60335-2-27 'Household and similar electrical appliances-Safety. Part 2: Particular requirements for appliances for skin exposure to ultraviolet and infrared radiation' was analysed. Results of this analysis showed that none of the examined technical documentation produced by the lamps manufacturers is fully compliant with the standard technique. Furthermore data reported in the same manuals, such as effective radiant exposure or irradiance, would indicate that these sources may be the cause of undue exposure to ultraviolet (UV) radiation. For this reason a measurement campaign on UV lamps used in tanning salons was organised. The first results of these measurements seem to confirm the doubts raised from the analysis of the lamp manuals: the use of a tanning lamp can lead to UV radiation exposure levels higher than reference maximum values recommended by EN 60335-2-27. (authors)
Load research manual. Volume 1. Load research procedures

Energy Technology Data Exchange (ETDEWEB)

Brandenburg, L.; Clarkson, G.; Grund, Jr., C.; Leo, J.; Asbury, J.; Brandon-Brown, F.; Derderian, H.; Mueller, R.; Swaroop, R.

1980-11-01

This three-volume manual presents technical guidelines for electric utility load research. Special attention is given to issues raised by the load data reporting requirements of the Public Utility Regulatory Policies Act of 1978 and to problems faced by smaller utilities that are initiating load research programs. In Volumes 1 and 2, procedures are suggested for determining data requirements for load research, establishing the size and customer composition of a load survey sample, selecting and using equipment to record customer electricity usage, processing data tapes from the recording equipment, and analyzing the data. Statistical techniques used in customer sampling are discussed in detail. The costs of load research also are estimated, and ongoing load research programs at three utilities are described. The manual includes guides to load research literature and glossaries of load research and statistical terms.
Technical Details on Beyond Design Basis Event Pilot Evaluations

Energy Technology Data Exchange (ETDEWEB)

None, None

2013-01-01

The primary focus of the BDBE pilot project was the review of BDBE analysis and mitigation features at four DOE nuclear facilities representing a range of DOE sites, nuclear facility types/activities, and responsible program offices. The pilots looked at (1) how beyond design basis accidents were evaluated and documented in the facility Documented Safety Analysis, (2) potential BDBE vulnerabilities and margins to failure of facility safety features as obtained from general area and specific system walkdowns and design documents reviews, and (3) preparations made in facility and site emergency management programs to respond to severe accidents. It also evaluated whether draft BDBE guidance on safety analysis and emergency management could be used to improve the analysis of and preparations for mitigating severe and beyond design basis accidents. The details of these activities are organized in this report as described below.

Flight dynamics analysis and simulation of heavy lift airships. Volume 2: Technical manual

Science.gov (United States)

Ringland, R. F.; Tischler, M. B.; Jex, H. R.; Emmen, R. D.; Ashkenas, I. L.

1982-01-01

The mathematical models embodied in the simulation are described in considerable detail and with supporting evidence for the model forms chosen. In addition the trimming and linearization algorithms used in the simulation are described. Appendices to the manual identify reference material for estimating the needed coefficients for the input data and provide example simulation results.
Energy Information Data Base: DECOL manual (Descriptive Cataloging On-Line)

International Nuclear Information System (INIS)

1980-01-01

The DOE Technical Information Center (TIC) is responsible for creating bibliographic data bases that are used in the announcement and retrieval of publications of all types dealing with all phases of energy. This manual tells how data are initially entered into the TIC interactive processing system, and describes in detail the data elements and types of items included in the data bases. 21 tables
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…
Development of iPad application "Postima" for quantitative analysis of the effects of manual therapy

Science.gov (United States)

Sugiyama, Naruhisa; Shirakawa, Tomohiro

2017-07-01

The technical difficulty of diagnosing joint misalignment and/or dysfunction by quantitative evaluation is commonly acknowledged among manual therapists. Usually, manual therapists make a diagnosis based on a combination of observing patient symptoms and performing physical examinations, both of which rely on subjective criteria and thus contain some uncertainty. We thus sought to investigate the correlations among posture, skeletal misalignment, and pain severity over the course of manual therapy treatment, and to explore the possibility of establishing objective criteria for diagnosis. For this purpose, we developed an iPad application that realizes the measurement of patients' postures and analyzes them quantitatively. We also discuss the results and effectiveness of the measurement and analysis.
Comprehensive Technical Report of the Inquiry into the Application of Living Systems Theory to 41 U. S. Army Battalions: Executive Summary. Volume 1

Science.gov (United States)

1984-11-01

information such as statutory and executive directives, regulations, and technical manuals is blended with matter/energy (people, equipment, and...which might be initiated in order to counteract these potential pathologies. An organizacion , like an organism, cannot survive when its basic processes...Normative Tables and Performance Indicator Scales presented in the study. The Tables and Scales, much like the specification in a technical ,. manual , permit
Technical Manual for the SAM Physical Trough Model

Energy Technology Data Exchange (ETDEWEB)

Wagner, M. J.; Gilman, P.

2011-06-01

NREL, in conjunction with Sandia National Lab and the U.S Department of Energy, developed the System Advisor Model (SAM) analysis tool for renewable energy system performance and economic analysis. This paper documents the technical background and engineering formulation for one of SAM's two parabolic trough system models in SAM. The Physical Trough model calculates performance relationships based on physical first principles where possible, allowing the modeler to predict electricity production for a wider range of component geometries than is possible in the Empirical Trough model. This document describes the major parabolic trough plant subsystems in detail including the solar field, power block, thermal storage, piping, auxiliary heating, and control systems. This model makes use of both existing subsystem performance modeling approaches, and new approaches developed specifically for SAM.
Oral Rehydration Therapy and the Control of Diarrheal Diseases. Training for Development. Peace Corps Information Collection & Exchange Training Manual No. T-34.

Science.gov (United States)

Clark, Mari; And Others

This manual was developed to train Peace Corps volunteers and other community health workers in oral rehydration therapy (ORT) and the control of diarrheal diseases. Using a competency-based format, the manual contains six training modules (organized in 22 sessions) that focus on interrelated health education and technical content areas. Each…
Fiscal Year 1986 Technical Objective Document (TOD).

Science.gov (United States)

1986-03-01

abilties superior to other IR and manual turrets. - START DATE: FY 88 END DATE: FY 90" PROJECT TITLE: COMPOSITE METAL FIRES EE 62:06 JON: 2673XXXX...TECHNOLOGY: FIRE ELEMENT: INTERACTION DESCRIPTION (TECHNICAL OBJECTIVE) Evaluate a new series of agents "BORALONS" capable of extinguishing metal fires and...PROJECT TITLE: COMPOSITE METAL FIRES PE: 63723 JON: 2104XXXX
Technical endoscopy

International Nuclear Information System (INIS)

Cavalar, K.O.

1988-01-01

A survey is provided on different versions of endoscopes, taking into account the new developments of video endoscopy. With a variety of practical examples it is shown that technical tests using endoscopy are a demanding task for nondestructive testing, whose requirements can only be met on a customized basis. (orig./HP) [de
Fifth technical meeting on quality

International Nuclear Information System (INIS)

Girard, A.

1998-01-01

This article reports on the 5th Technical Meeting on Quality which was held in San Diego on 20-22 October 1997 and which was attended by representatives of the Home and Joint Central Team and of manufacturers currently involved in the Large R and D projects. The meeting made progress towards the finalization of the ITER Quality Manual document for inclusion in the Final Design Report and the definition of the quality necessary for ITER procurement and construction
The National Energy Audit (NEAT) Engineering Manual (Version 6)

Energy Technology Data Exchange (ETDEWEB)

Gettings, M.B.

2001-04-20

Government-funded weatherization assistance programs resulted from increased oil prices caused by the 1973 oil embargo. These programs were instituted to reduce US consumption of oil and help low-income families afford the increasing cost of heating their homes. In the summer of 1988, Oak Ridge National Laboratory (ORNL) began providing technical support to the Department of Energy (DOE) Weatherization Assistance Program (WAP). A preliminary study found no suitable means of cost-effectively selecting energy efficiency improvements (measures) for single-family homes that incorporated all the factors seen as beneficial in improving cost-effectiveness and usability. In mid-1989, ORNL was authorized to begin development of a computer-based measure selection technique. In November of 1992 a draft version of the program was made available to all WAP state directors for testing. The first production release, Version 4.3, was made available in october of 1993. The Department of Energy's Weatherization Assistance Program has continued funding improvements to the program increasing its user-friendliness and applicability. initial publication of this engineering manual coincides with availability of Version 6.1, November 1997, though algorithms described generally apply to all prior versions. Periodic updates of specific sections in the manual will permit maintaining a relevant document. This Engineering Manual delineates the assumptions used by NEAT in arriving at the measure recommendations based on the user's input of the building characteristics. Details of the actual data entry are available in the NEAT User's Manual (ORNL/Sub/91-SK078/1) and will not be discussed in this manual.
Polymer Exemption Guidance Manual for premanufacture notices for new chemicals under the Toxic Substances Control Act (TSCA)

Science.gov (United States)

A technical manual to accompany, but not supersede the Premanufacture Notification Exemptions; Revisions of Exemptions for Polymers; Final Rule found at 40 CFR Part 723, (60) FR 16316-16336, published Wednesday, March 29, 1995.
National waste terminal storage repository in a bedded salt formation for spent unreprocessed fuel: construction accounting manual

International Nuclear Information System (INIS)

1978-12-01

The preparation of a cost estimate for a program to construct a new or add-on waste storage facility is one of the major objectives of the conceptual design effort. It is essential that a construction accounting manual be developed for use in estimating (conceptual, Title 1 and working estimates), cost accounting and cost control purposes on a consistent basis throughout life of the project. In order to meet this objective, itemized cost estimates and cost accounting data must be in sufficient detail to assure the reliability of such cost estimates and cost data. A cost accounting manual for contractors involved in the project is set forth in this document. For the conceptual design cost estimate, the estimate will be prepared in accordance with this construction accounting manual and all future estimates will be prepared on this basis. When work starts under the project, cost data will be accumulated and reported in accordance with this manual to provide consistency between estimates and actual cost data for cost control programs
The KAERI 10 MeV Electron Linac - Description and Operational Manual

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Cheol; Park, Seong Hee; Jung, Young Uk; Han, Young Hwan; Kang, Hee Young

2005-06-15

The objective of this technical report is to guide the right operation and maintenance of the KAERI electron linac system. The KAERI electron linac system consists of 2 MeV injector based on 176 MHz Normal conducting RF (Radio Frequency)cavity and 10 MeV main accelerator based on 352 MHz Superconducting RF cavity, electron beamlines (injection and extraction). Since a electron accelerator generates hazard radiation, this system is located at the shielded room in basement and we can operate the system using the remote control system. It includes the description and the operational manual as well as the detailed technical direction for trouble shooting.
The KAERI 10 MeV Electron Linac - Description and Operational Manual

International Nuclear Information System (INIS)

Lee, Byung Cheol; Park, Seong Hee; Jung, Young Uk; Han, Young Hwan; Kang, Hee Young

2005-06-01

The objective of this technical report is to guide the right operation and maintenance of the KAERI electron linac system. The KAERI electron linac system consists of 2 MeV injector based on 176 MHz Normal conducting RF (Radio Frequency)cavity and 10 MeV main accelerator based on 352 MHz Superconducting RF cavity, electron beamlines (injection and extraction). Since a electron accelerator generates hazard radiation, this system is located at the shielded room in basement and we can operate the system using the remote control system. It includes the description and the operational manual as well as the detailed technical direction for trouble shooting
Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Hickey, Eva E.; Strom, Daniel J.

2005-08-01

Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.
Technical Report and Data File User's Manual for the 1992 National Adult Literacy Survey.

Science.gov (United States)

Kirsch, Irwin; Yamamoto, Kentaro; Norris, Norma; Rock, Donald; Jungeblut, Ann; O'Reilly, Patricia; Berlin, Martha; Mohadjer, Leyla; Waksberg, Joseph; Goksel, Huseyin; Burke, John; Rieger, Susan; Green, James; Klein, Merle; Campbell, Anne; Jenkins, Lynn; Kolstad, Andrew; Mosenthal, Peter; Baldi, Stephane

Chapter 1 of this report and user's manual describes design and implementation of the 1992 National Adult Literacy Survey (NALS). Chapter 2 reviews stages of sampling for national and state survey components; presents weighted and unweighted response rates for the household component; and describes non-incentive and prison sample designs. Chapter…
[Manual lifting and manual transport: risk assessment and prevalence of work-related diseases in construction companies in Basilicata].

Science.gov (United States)

Nicoletti, S; Battevi, N; Colafemmina, G; Di Leone, G; Satriani, G; Ragone, P; Occhipinti, E

2013-01-01

The Basilicata Regional Headquarters of the Italian Institute for Insurance against Occupational Accidents and Disease (INAIL) and the Basilicata association of small building enterprises (Edilcassa di Basilicata) promoted a research project to assess the risk of manual lifting and manual transport in construction enterprises in the Basilicata Region and estimate the prevalence of related diseases. Manual lifting risk assessment was performed by calculating the VLI of 204 working days in as many building workers. Manual transport risk assessment was carried out comparing the weights transported (on the 204 days tested) with the reference values of the "Snoock and Ciriello" tables. Manual Ifting risk was present on 195 of the 204 days, with an average value of VLI equal to 2.1 (min 0.4, max 8.5), with higher values in the restructuring sector (VLI average of 2.3, min 0.4, max 8.5), and no significant differences between the different tasks. Manual transport risk was present on 129 of the 204 days, with average values of 1.2 (min 0.2, max 3.3), with no significant differences between the different tasks analyzed For both risks additional factors were present that were not analyzed by the methods of assessment used (for manual lifting: 8.8% of the geometries in the critical area; for manual transport: 39% of transport on shoulders, 42.5% on a route with uneven surface and 31.9% on a sloping route), so it is likely that the actual risk is greater than that indicated by the synthetic indices of exposure. The medical questionnaire showed from the case histories that 148 out of 546 subjects were positive for the threshold forpain or discomfort in the lumbosacral spine area and 99 out of 546 subjects reported suffering from an already diagnosed herniated spinal disk. Only 18% of osteoarticular diseases was reported to the Insurance Institute, al though there was widespread awareness that the diseases in question might be related to work. Diseases of the spine were
Emergency notification and assistance technical operations manual. Emergency preparedness and response. Date effective: 1 December 2000

International Nuclear Information System (INIS)

2000-11-01

The Convention on Early Notification of a Nuclear Accident (the 'Early Notification Convention') and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the 'Assistance Convention') are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency, with the aim of minimizing the consequences. The International Atomic Energy Agency (IAEA) has specific functions assigned to it under these Conventions, to which the World Health Organization (WHO), the World Meteorological Organization (WMO) and the Food and Agriculture Organization of the United Nations (FAO) are full parties. Since 1989, the arrangements between the IAEA, States which are IAEA Member States and/or Parties to one or both Conventions, all other relevant international intergovernmental organizations, and other States for facilitating the implementation of the Conventions - specifically of those of their articles which are operational in nature have been documented in the Emergency Notification and Assistance Technical Operations Manual (ENATOM). Recent events, for example, the launch of the Cassini satellite (USA, 1997), the Acerinox accident (Spain, 1998), the JCO criticality accident (Japan, 1999), the Istanbul accident (Turkey, 1999) and the Samut Prakarn accident (Thailand, 2000), have raised new issues and highlighted the expectation of States that the IAEA will use the framework of the Early Notification and Assistance Conventions to obtain and provide real-time emergency related information on such events. While the Early Notification Convention requires States Parties to report only accidents that may have significant transboundary radiological consequences, States may under the Assistance Convention legitimately request the assistance of the IAEA or an Accident State in obtaining information concerning a
Improving artificial breeding of cattle in Africa. Guidelines and recommendations. A manual prepared under the framework of an IAEA technical cooperation regional AFRA project on increasing and improving milk and meat production

International Nuclear Information System (INIS)

2005-04-01

cattle farmers and to arrive at a consensus on what can be considered 'best practice' in the countries represented. It was concluded that: (a) methods of keeping records, their analysis and use for evaluating genetic merit and fertility of AI bulls require improvement in most AFRA Member States; (b) the technical aspects of providing N-PD and related services to farmers based on progesterone assay have been clarified in many Member States; (c) the modalities and logistics of practical application under the different conditions in countries need to be further developed; and (d) there is a clear need for guidelines that can be used for improvement and harmonization of currently used technical procedures for AI in the Member States. Participants of the meeting developed a framework for the guidelines, formulated the first draft of the manual and identified the additional work necessary for its completion. The manual was subsequently compiled and the second draft was circulated to all AFRA national project coordinators for comments and suggestions for improvement. It was finally discussed at a Project Review, Coordination and Planning Meeting held in Addis Ababa in March 2002 and further material incorporated as required. This manual combines the outputs from the three meetings referred to above, and is the result of collaboration between the contributors listed at the end of the publication

FileMaker Pro 11 The Missing Manual

CERN Document Server

Prosser, Susan

2010-01-01

This hands-on, friendly guide shows you how to harness FileMaker's power to make your information work for you. With a few mouse clicks, the FileMaker Pro 11 database helps you create and print corporate reports, manage a mailing list, or run your entire business. FileMaker Pro 11: The Missing Manual helps you get started, build your database, and produce results, whether you're running a business, pursuing a hobby, or planning your retirement. It's a thorough, accessible guide for new, non-technical users, as well as those with more experience. Start up: Get your first database up and runnin
Creating a web site the missing manual

CERN Document Server

MacDonald, Matthew

2008-01-01

Think you have to be a technical wizard to build a great web site? Think again. If you want to create an engaging web site, this thoroughly revised, completely updated edition of Creating a Web Site: The Missing Manual demystifies the process and provides tools, techniques, and expert guidance for developing a professional and reliable web presence. Whether you want to build a personal web site, an e-commerce site, a blog, or a web site for a specific occasion or promotion, this book gives you detailed instructions and clear-headed advice for: Everything from planning to launching. From pi
Technical note: New applications for on-line automated solid phase extraction

OpenAIRE

MacFarlane, John D.

1997-01-01

This technical note explains the disadvantages of manual solid phase extraction (SPE) techniques and the benefits to be gained with automatic systems. The note reports on a number of general and highly specific applications using the Sample Preparation Unit OSP-2A.
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
H. W. Laboratory manual: 100 Area section

Energy Technology Data Exchange (ETDEWEB)

1950-07-01

The purpose of this manual is to present a Hazard Breakdown of all jobs normally encountered in the laboratory work of the three sections comprising the Analytic Section, Metallurgy and Control Division of the Technical Department. A Hazard Breakdown is a careful analysis of any job in which the source of possible dangers is clearly indicated for each particular step. The analysis is prepared by individuals who are thoroughly familiar with the specific job or procedure. It is felt that if the hazards herein outlined are recognized by the Laboratory personnel and the suggested safety cautions followed, the chance for injury will be minimized and the worker will become generally more safety conscious. The manual, which is prefaced by the general safety rules applying to all the laboratories, is divided into three main sections, one for each of the three sections into which the Laboratories Division is divided. These sections are as follows: Section 1 -- 200 Area Control; Section 2 -- 100 Area Control; Section 3 -- 300 Area Control, Essential Materials, and Methods Improvement.
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
Ageing management technical information investigations

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

In February 2013, there are 50 units of commercial nuclear power plants (NPPs) in Japan. We enter into a period that 20 units of them are operating for more than 30 years. Currently, regulation imposes utilities to conduct ageing technical evaluations of each unit before operation of 30 years from the commissioning, to develop the long term maintenance management policy for next 10 years and to submit to the regulatory authority the policy with the report on ageing management technical evaluation (AMTE) for each NPP. It is necessary for regulatory side to develop technical information bases incorporating latest technical knowledge as operating experiences in domestic and abroad on ageing of the plants necessary to conduct reviews of AMTE for each unit. Based on these standpoints, technical information bases investigations have been conducted from the viewpoints of material degradation of ageing NPPs. In order to develop scientific regulator judgment bases related to ageing management (AM) and long-term operation (LTO), investigations on latest information on ageing management in domestic and abroad are conducted and a set of documents including technical evaluation review manuals necessary to conduct AMTE are prepared. To utilize the results of the investigations for ageing technical evaluation, database including latest information related to AM and LTO are developed, ran and operated. In addition, investigations related to Fugen nuclear plant, under decommissioning plants, investigations on mechanism of stress corrosion cracking (SCC), thermal ageing and preventive technologies for SCC, detection and diagnosis technology for ageing degradation and condition monitoring technology are performed to validate and confirm effectiveness of the technologies. (author)
Risk management through dynamic technical specifications

International Nuclear Information System (INIS)

Klopp, George T.; Petersen, Thomas A.

2004-01-01

The wide deployment of plant specific probabilistic risk assessments for nuclear power plants has provided the means to effect a fresh risk management perspective and a fresh, risk based, regulatory outlook on nuclear power. There has been a great deal of conversation on risk based regulation within the U. S. nuclear power industry but, curiously, very little on effective risk management. This paper proposes a means to link the two subjects through the plant Technical Specifications. A revised concept for Technical Specifications is suggested which is based on deterministic analyses and probabilistic risk assessments for each plant. The revised Technical Specifications would consider, on a real-time basis, the exact state of the plant in terms of the status of key components and systems. It would depict current plant risk levels and compare those levels to the desired and limiting (alert/action) levels. It would advise the plant operator on the risk impact of proposed actions through a simple query system and illustrate the impact of such actions on plant status relative to designated risk values. The basis for the proposed approach lies in realistic deterministic plant analyses and probabilistic risk assessment (PRA) deployment tools being developed, in parallel, by a number of parties in the U.S. today. These PRAs are based primarily on the existing plant responses to Generic Letter 88-20, 'Individual Plant Examinations' (IPEs). Each of these tools allows the plant operator to input, on a real-time basis, the status of key equipment and systems. The tools then provide explicit illustrations of dependency effects; updated, 'real-time' risk status indications such as core damage frequency; and, in some cases, allow the operator to assess the risk impact of removing from service selected components for maintenance or testing. These systems generally operate on personal computers and provide nearly instantaneous responses to plant queries. Moving from these tools to
Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

International Nuclear Information System (INIS)

Korsah, K.

2001-01-01

This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in
How does the Augmented Reality Manual enhance cognitive activity while doing complex maintenance tasks?: Augmented Tutorial Overlaid Manual (ATOM)

International Nuclear Information System (INIS)

Yim, Ho Bin; Seong, Poong Hyun

2008-01-01

It has been more than a decade since the concept of Augmented Reality (AR) was introduced. Many related technologies, such as tracking and display, to animate this concept have improved to certain levels. AR is well suited for interaction with the cognitive vision system. In contrast to the virtual reality, AR applications enrich the perceived reality with additional visual information which ranges from text annotation and object highlighting to complex 3D objects. AR has been tested its potentiality in various forms of applications. For example, visitors wear Head Mount Display (HMD) to see virtual guides explaining artifacts in a museum or soldiers are informed geographical features about unfamiliar operation sites. Recently, researchers tried to use AR as a means of teaching or training apparatus; however, there are still some technical obstacles to put this fascinating technology into practice. In this study, we will use Cognitive Load Theory (CLT) to design a manual of pump maintenance and convert it to AR technology to propose a proto type of an on-line AR maintenance manual to prove its possibility as an interactive learning tool
How does the Augmented Reality Manual enhance cognitive activity while doing complex maintenance tasks?: Augmented Tutorial Overlaid Manual (ATOM)

Energy Technology Data Exchange (ETDEWEB)

Yim, Ho Bin; Seong, Poong Hyun [Korea Advanced Institute of Technology and Science, Daejeon (Korea, Republic of)

2008-10-15

It has been more than a decade since the concept of Augmented Reality (AR) was introduced. Many related technologies, such as tracking and display, to animate this concept have improved to certain levels. AR is well suited for interaction with the cognitive vision system. In contrast to the virtual reality, AR applications enrich the perceived reality with additional visual information which ranges from text annotation and object highlighting to complex 3D objects. AR has been tested its potentiality in various forms of applications. For example, visitors wear Head Mount Display (HMD) to see virtual guides explaining artifacts in a museum or soldiers are informed geographical features about unfamiliar operation sites. Recently, researchers tried to use AR as a means of teaching or training apparatus; however, there are still some technical obstacles to put this fascinating technology into practice. In this study, we will use Cognitive Load Theory (CLT) to design a manual of pump maintenance and convert it to AR technology to propose a proto type of an on-line AR maintenance manual to prove its possibility as an interactive learning tool.
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
Method of Characteristic (MOC) Nozzle Flowfield Solver - User’s Guide and Input Manual Version 2.0

Science.gov (United States)

2018-01-01

TECHNICAL REPORT RDMR-SS-17-13 METHOD OF CHARACTERISTIC (MOC) NOZZLE FLOWFIELD SOLVER—USER’S GUIDE AND INPUT MANUAL VERSION 2.0 Kevin D. Kennedy...1 II. PROGRAM READS AND WRITES ...2 B. Program Reads .................................................................................................. 4 C. Program Writes
Radiological survey activities: uranium mill tailings remedial action project procedures manual

International Nuclear Information System (INIS)

Little, C.A.; Berven, B.A.; Carter, T.E.

1986-07-01

The US Department of Energy (DOE) was assigned the responsibility for conducting remedial action at 24 sites, which are located in one eastern and nine western states. The DOE's responsibilities are being met through its Uranium Mill Tailings Remedial Action Project Office (UMTRA-PO) in Albuquerque, New Mexico. The purpose of this Procedures Manual is to provide a standardized set of procedures that document in an auditable manner the activities performed by the Radiological Survey Activities (RASA) group in the Dosimetry and Biophysical Transport Section (DABTS) of the Health and Safety Research Division (HASRD) at the Oak Ridge National Laboratory (ORNL), in its role as the Inclusion Survey Contractor (ISC). Members of the RASA group assigned to the UMTRA Project are headquartered in the ORNL/RASA office in Grand Junction, Colorado, and report to the ORNL/RASA Project Manager. The Procedures Manual ensures that the organizational, administrative, and technical activities of the RASA/UMTRA group conform properly to those of the ISC as described in the Vicinity Properties Management and Implementation Manual and the Summary Protocol. This manual also ensures that the techniques and procedures used by the RASA/UMTRA group and contractor personnel meet the requirements of applicable governmental, scientific, and industrial standards
Manual for the sampling of uranium mine tailings

International Nuclear Information System (INIS)

Feenstra, S.; Reades, D.W.; Cherry, J.A.; Chambers, D.B.; Case, G.G.; Ibbotson, B.G.

1983-04-01

The purpose of this manual is to describe the requisite sampling procedures to provide a basis for the application of uniform high-quality standards to detailed geotechnical, hydrogeological, geochemical and air quality measurements at Canadian uranium tailings disposal sites. The report describes the objective and scope of a sampling program, the preliminary data collection, and the procedures for sampling of tailings solids, surface water and seepage, tailings porewater, and wind-blown dust and radon
ITER technical advisory committee meeting

International Nuclear Information System (INIS)

Fujiwara, M.

1999-01-01

The ITER Technical Advisory Committee (TAC) meeting took place on December 20-22, 1999 at the Naka Joint Work Site. The objective of this meeting was to review the document 'Technical Basis for ITER-FEAT Outline Design (ODR)' issued by the Director on December 10. It was also aimed at providing the ITER Meeting scheduled for January 19-20, 2000 in Tokyo with a technical assessment of ODR and recommendations for the optimization of the anticipated plasma performance and engineering design, based on the guidelines approved by the Council in June 1998 and recommendations of the last TAC meeting
Nuclear forensics support. Technical guidance. Reference manual (Chinese Edition)

International Nuclear Information System (INIS)

2012-01-01

Illicit trafficking of nuclear and other radioactive material has been an issue of concern since the first seizures in the early 1990s. By the end of 2004 Member States had confirmed 540 cases, while about another 500 remain unconfirmed. Most of the confirmed cases have a criminal dimension, even if they were not for known terrorist purposes. The attacks of September 2001 in the USA dramatically emphasized the requirement for the enhanced control and security of nuclear and other radioactive material. In response to a resolution by the IAEA General Conference in September 2002 the IAEA has adopted an integrated approach to protection against nuclear terrorism. This brings together IAEA activities concerned with the physical protection of nuclear material and nuclear installations, nuclear material accountancy, detection and response to illicit nuclear trafficking, the security and safety of radioactive sources, emergency response measures - including pre-emergency measures in Member States and at the IAEA - and the promotion of State adherence to relevant international instruments. States have the responsibility for combating illicit trafficking and the inadvertent movements of radioactive material. The IAEA cooperates with Member States and other international organizations in joint efforts to prevent incidents of illicit trafficking and inadvertent movements and to harmonize policies and measures by providing relevant advice through a range of technical assistance and documents. In this context, the IAEA issued a group of three technical documents, co-sponsored by the World Customs Organization, Europol and Interpol, on the inadvertent movement and illicit trafficking of radioactive material. The first is Prevention of the Inadvertent Movement and Illicit Trafficking of Radioactive Material (IAEA-TECDOC-1311), the second is called Detection of Radioactive Material at Borders (IAEA-TECDOC-1312) and the third is Response to Events Involving the Inadvertent Movement
Final Assessment of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station

Energy Technology Data Exchange (ETDEWEB)

Anderson, Michael T.; Diaz, Aaron A.; Cinson, Anthony D.; Crawford, Susan L.; Prowant, Matthew S.; Doctor, Steven R.

2014-03-24

PNNL conducted a technical assessment of the NDE issues and protocols that led to missed detections of several axially oriented flaws in a steam generator primary inlet dissimilar metal weld at North Anna Power Station, Unit 1 (NAPS-1). This particular component design exhibits a significant outside-diameter (OD) taper that is not included as a blind performance demonstration mock-up within the industry’s Performance Demonstration Initiative, administered by EPRI. For this reason, the licensee engaged EPRI to assist in the development of a technical justification to support the basis for a site-specific qualification. The service-induced flaws at NAPS-1 were eventually detected as a result of OD surface machining in preparation for a full structural weld overlay. The machining operation uncovered the existence of two through-wall flaws, based on the observance of primary water leaking from the dissimilar metal weld. A total of five axially oriented flaws were detected in varied locations around the weld circumference. The field volumetric examination that was conducted at NAPS-1 was a non-encoded, real-time manual ultrasonic examination. PNNL conducted both an initial assessment, and subsequently, a more rigorous technical evaluation (reported here), which has identified an array of NDE issues that may have led to the subject missed detections. These evaluations were performed through technical reviews and discussions with NRC staff, EPRI NDE Center personnel, industry and ISI vendor personnel, and ultrasonic transducer manufacturers, and laboratory tests, to better understand the underlying issues at North Anna.
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.
Technical basis and programmatic requirements for large block testing of coupled thermal-mechanical-hydrological-chemical processes

International Nuclear Information System (INIS)

Lin, Wunan.

1993-09-01

This document contains the technical basis and programmatic requirements for a scientific investigation plan that governs tests on a large block of tuff for understanding the coupled thermal- mechanical-hydrological-chemical processes. This study is part of the field testing described in Section 8.3.4.2.4.4.1 of the Site Characterization Plan (SCP) for the Yucca Mountain Project. The first, and most important objective is to understand the coupled TMHC processes in order to develop models that will predict the performance of a nuclear waste repository. The block and fracture properties (including hydrology and geochemistry) can be well characterized from at least five exposed surfaces, and the block can be dismantled for post-test examinations. The second objective is to provide preliminary data for development of models that will predict the quality and quantity of water in the near-field environment of a repository over the current 10,000 year regulatory period of radioactive decay. The third objective is to develop and evaluate the various measurement systems and techniques that will later be employed in the Engineered Barrier System Field Tests (EBSFT)
INES - The International Nuclear Event Scale. User's manual

International Nuclear Information System (INIS)

2005-01-01

The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials. This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled 'Clarification of Issues Raised'. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request
Manual on public health action in radiation emergencies

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

Over the years, the World Health Organization (WHO) has issued a series of reports and publications providing guidance on the public health aspects of nuclear power production, in line with target 11 of the European policy for health for all, which calls for the reduction of injury, disability and death from accidents. Immediately after the nuclear accident at Chernobyl in April 1986, the WHO Regional Office for Europe established an emergency operation to provide technical cooperation and communication links with Member States. A special project on the public health dimensions of radiation emergencies was subsequently established, which included a series of activities related both directly to the Chernobyl accident and to emergency planning for future accidents. This manual brings together the experience gained in the special project to improve the planning for and response to emergencies. It has been prepared to meet public health needs arising from all types of major radiation emergency in the European Region. The manual describes the guiding principles and advises on the practical application of measures to protect and inform the public in a radiation emergency. It is hoped that the manual will promote close interaction between the WHO Member States in this field. The advice given in earlier WHO publications on radiation emergencies has been examined and revised in the light of recent experience 12 refs, 4 figs, 4 tabs
Manual on public health action in radiation emergencies

International Nuclear Information System (INIS)

1994-01-01

Over the years, the World Health Organization (WHO) has issued a series of reports and publications providing guidance on the public health aspects of nuclear power production, in line with target 11 of the European policy for health for all, which calls for the reduction of injury, disability and death from accidents. Immediately after the nuclear accident at Chernobyl in April 1986, the WHO Regional Office for Europe established an emergency operation to provide technical cooperation and communication links with Member States. A special project on the public health dimensions of radiation emergencies was subsequently established, which included a series of activities related both directly to the Chernobyl accident and to emergency planning for future accidents. This manual brings together the experience gained in the special project to improve the planning for and response to emergencies. It has been prepared to meet public health needs arising from all types of major radiation emergency in the European Region. The manual describes the guiding principles and advises on the practical application of measures to protect and inform the public in a radiation emergency. It is hoped that the manual will promote close interaction between the WHO Member States in this field. The advice given in earlier WHO publications on radiation emergencies has been examined and revised in the light of recent experience
Assessing the useability of technical manuals: a successful case history

International Nuclear Information System (INIS)

Robbins, J.C.; Johnson, L.M.

1979-01-01

The Software Documentation Group of the Computer Science and Services Division of Los Alamos Scientific Laboratory (LASL) conducted a computer documentation user study in 1978. The study was designed to assess the useability of LASL computer documentation. This paper describes the study, reviews the results, and discusses the study's implications for document development. The study itself provides a valuable model that is readily adaptable by anyone interested in assessing document useability. It was done in a short time, at reasonable cost, with substantial payoff in information and improved technical communication
Energy Research and Development Administration, Division of Safety, Standards, and Compliance respirator manual

International Nuclear Information System (INIS)

Douglas, D.D.; Hack, A.L.; Held, B.J.; Revoir, W.H.

1976-05-01

The manual has been prepared to provide technical information for contractors of the Energy Research and Development Administration (ERDA) on the application of respiratory protective devices for protection against airborne contaminants, both radioactive and nonradioactive. The various elements of a respirator program including selection and maintenance of equipment and training of personnel are described to assist in establishing adequate programs
Energy Research and Development Administration, Division of Safety, Standards, and Compliance respirator manual

Energy Technology Data Exchange (ETDEWEB)

Douglas, D.D.; Hack, A.L.; Held, B.J.; Revoir, W.H.

1976-05-01

The manual has been prepared to provide technical information for contractors of the Energy Research and Development Administration (ERDA) on the application of respiratory protective devices for protection against airborne contaminants, both radioactive and nonradioactive. The various elements of a respirator program including selection and maintenance of equipment and training of personnel are described to assist in establishing adequate programs.
Physical and technical basis of positron emission tomography (PET)

International Nuclear Information System (INIS)

Bauer, R.

1994-01-01

Positron emission tomography utilizes the annihilation of positrons, generating pairs of gamma quanta which are emitted in opposing directions. 'Electronic collimation' is performed by coincident detection of both quanta. Thus, there is no need for mechanical collimators and no limiting connection between sensitivity and spatial resolution. Transversal tomograms are reconstructed from the projection data by means of highly sophisticated data processing. The half life of the most positron emitters used in medical applications is short and of the order of some minutes. Therefore, many positron emitters have to be produced on-side by means of a cyclotron. PET is superior to SPECT with respect to physical and technical aspects, but the high costs of PET limit its wide-spread use up to now. (orig.) [de
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...
National Synchrotron Light Source user's manual: Guide to the VUV and x-ray beamlines

International Nuclear Information System (INIS)

Gmuer, N.F.

1993-04-01

The success of the National Synchrotron Light Source is based, in large part, on the size of the user community and the diversity of the scientific and technical disciplines represented by these users. As evidence of this success, the VUV Ring has just celebrated its 10th anniversary and the X-ray Ring will do the same in 1995. In order to enhance this success, the NSLS User's Manual: Guide to the VUV and X-Ray Beamlines - Fifth Edition, is being published. This Manual presents to the scientific community-at-large the current and projected architecture, capabilities and research programs of the various VUV and X-ray beamlines. Also detailed is the research and computer equipment a General User can expect to find and use at each beamline when working at the NSLS. The Manual is updated periodically in order to keep pace with the constant changes on these beamlines
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...
Technical manual: operation and equipment instructions for in situ impulse test

International Nuclear Information System (INIS)

1979-11-01

This manual describes the test equipment and procedures for a new field test which determines the shear modulus of a soil deposit at strain levels equivalent to those experienced during actual earthquakes. Results from this test are typically used as input parameters to response analyses for evaluating local soil effects during earthquake shaking. The test employs a cross-hole wave propagation procedure with velocity transducers located in closely spaced adjacent borings. Clear, consistent, and repeatable data in all types of soil and a method of data reduction different from conventional geophysical first arrival techniques are unique aspects of this new test. In addition to describing the principles of the test and data reduction procedures, major discussions of the field procedures are also included. Detailed drilling and testing information is provided both for planning and executing a test program
Groundwater technical procedures of the U.S. Geological Survey

Science.gov (United States)

Cunningham, William L.; Schalk, Charles W.

2011-01-01

A series of groundwater technical procedures documents (GWPDs) has been released by the U.S. Geological Survey, Water-Resources Discipline, for general use by the public. These technical procedures were written in response to the need for standardized technical procedures of many aspects of groundwater science, including site and measuring-point establishment, measurement of water levels, and measurement of well discharge. The techniques are described in the GWPDs in concise language and are accompanied by necessary figures and tables derived from cited manuals, reports, and other documents. Because a goal of this series of procedures is to remain current with the state of the science, and because procedures change over time, this report is released in an online format only. As new procedures are developed and released, they will be linked to this document.
Re-evaluation of the technical basis for the regulation of pressurized thermal shock in U.S. pressurized water reactor vessels

Energy Technology Data Exchange (ETDEWEB)

Malik, S.N.; Kirk, M.T.; Jackson, D.A.; Hackett, E.M.; Chokshi, N.C.; Siu, N.O.; Woods, H.W.; Bessette, D.E. [Office of Nuclear Regulatory Research, U.S. nuclear Regulatory Commission, Washington, D.C. (United States); Dickson, T.L. [Oak Ridge National Lab., Computational Physics and Engineering Div., Oak Ridge, TN (United States)

2001-07-01

The current federal regulation to insure that pressurized-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to potential pressurized thermal shock (PTS) events during the life of the plant were derived from computational models and technologies that were developed in the early-to-mid 1980's. Since that time, there have been several advancements and refinements to the relevant fracture technology, materials characterization methods, probabilistic risk assessment (PRA) and thermal-hydraulics (TH) computational methods. Preliminary studies performed in 1998 (that applied this new technology) indicated the potential that technical bases can be established to support a relaxation of the current federal regulation (10 CFR 50.61) for PTS. A revision of PTS regulation could have significant implications for plants reaching their end-of-license periods and future plant license-extension considerations. Based on the above, in 1999, the United States Nuclear Regulatory Commission initiated a comprehensive project, with the nuclear industry as a participant, to revisit the technical bases for the current regulations on PTS. This paper provides an overview and status of the methodology that has evolved over the last two years through interactions between experts in relevant disciplines (TH, PRA, materials and fracture mechanics, and non-destructive and destructive examination to predict distribution of fabrication induced flaws in the belt-line region of the PWR vessels) from the NRC staff, their contractors, and representatives from the nuclear industry. This updated methodology is currently being implemented into the FAVOR (Fracture Analysis of Vessels: Oak Ridge) computer code for application to re-examine the adequacy of the current regulations and to determine if technical basis can be established for relaxing the current regulation. It is anticipated that the effort will be completed in 2002. (authors)
Re-evaluation of the technical basis for the regulation of pressurized thermal shock in U.S. pressurized water reactor vessels

International Nuclear Information System (INIS)

Malik, S.N.; Kirk, M.T.; Jackson, D.A.; Hackett, E.M.; Chokshi, N.C.; Siu, N.O.; Woods, H.W.; Bessette, D.E.; Dickson, T.L.

2001-01-01

The current federal regulation to insure that pressurized-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to potential pressurized thermal shock (PTS) events during the life of the plant were derived from computational models and technologies that were developed in the early-to-mid 1980's. Since that time, there have been several advancements and refinements to the relevant fracture technology, materials characterization methods, probabilistic risk assessment (PRA) and thermal-hydraulics (TH) computational methods. Preliminary studies performed in 1998 (that applied this new technology) indicated the potential that technical bases can be established to support a relaxation of the current federal regulation (10 CFR 50.61) for PTS. A revision of PTS regulation could have significant implications for plants reaching their end-of-license periods and future plant license-extension considerations. Based on the above, in 1999, the United States Nuclear Regulatory Commission initiated a comprehensive project, with the nuclear industry as a participant, to revisit the technical bases for the current regulations on PTS. This paper provides an overview and status of the methodology that has evolved over the last two years through interactions between experts in relevant disciplines (TH, PRA, materials and fracture mechanics, and non-destructive and destructive examination to predict distribution of fabrication induced flaws in the belt-line region of the PWR vessels) from the NRC staff, their contractors, and representatives from the nuclear industry. This updated methodology is currently being implemented into the FAVOR (Fracture Analysis of Vessels: Oak Ridge) computer code for application to re-examine the adequacy of the current regulations and to determine if technical basis can be established for relaxing the current regulation. It is anticipated that the effort will be completed in 2002. (authors)
Sierra/SolidMechanics 4.48 Verification Tests Manual.

Energy Technology Data Exchange (ETDEWEB)

Plews, Julia A.; Crane, Nathan K; de Frias, Gabriel Jose; Le, San; Littlewood, David John; Merewether, Mark Thomas; Mosby, Matthew David; Pierson, Kendall H.; Porter, Vicki L.; Shelton, Timothy; Thomas, Jesse David; Tupek, Michael R.; Veilleux, Michael; Xavier, Patrick G.

2018-03-01

Presented in this document is a small portion of the tests that exist in the Sierra / SolidMechanics (Sierra / SM) verification test suite. Most of these tests are run nightly with the Sierra / SM code suite, and the results of the test are checked versus the correct analytical result. For each of the tests presented in this document, the test setup, a description of the analytic solution, and comparison of the Sierra / SM code results to the analytic solution is provided. Mesh convergence is also checked on a nightly basis for several of these tests. This document can be used to confirm that a given code capability is verified or referenced as a compilation of example problems. Additional example problems are provided in the Sierra / SM Example Problems Manual. Note, many other verification tests exist in the Sierra / SM test suite, but have not yet been included in this manual.
The use of EORTC measures in daily clinical practice—A synopsis of a newly developed manual

DEFF Research Database (Denmark)

Wintner, Lisa M; Sztankay, Monika; Aaronson, Neil

2016-01-01

possible and to encourage readers and end-users of EORTC measures to contribute to further needed high-quality research. The manual will be accessible on the EORTC Quality of Life Group website's homepage and will be periodically updated to take into account any new knowledge due to medical, technical...
Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

International Nuclear Information System (INIS)

TRAWINSKI, B.J.

2000-01-01

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

Outcome of manual hemorrhoidopexy in the management of hemorrhoids

Directory of Open Access Journals (Sweden)

Sujit Kumar

2014-01-01

Full Text Available Background: Manual hemorrhoidopexy is a new technique of treating second degree hemorrhoids. In contrast to the conventional resectional techniques (Milligan-Morgan, manual hemorrhoidopexy is a novel technique as described by T Carlo. It does not involve excision but plication with fixation of the prolapsing hemorrhoid. Objective: To study the outcome of manual hemorrhoidopexy and to compare manual hemorrhoidopexy with the traditional hemorrhoidectomy. Methods: This is a prospective study conducted over 16 months (January 2012 to April 2013 in the College of Medical Sciences Teaching Hospital (COMS-TH, Bharatpur, Chitwan, Department of Surgery. The patients who presented with third degree internal-hemorrhoids on a random basis, and underwent either conventional hemorrhoidectomy (Group A or Manual hemorrhoidopexy (Group B by senior consultant surgeons were included. The patients who had external hemorrhoids in addition to internal were excluded. Preoperative, intraoperative, and postoperative characteristics were evaluated. Results: Twenty five patients with median age group 42.5 years underwent conventional (Milligan-Morgan hemorrhoidectomy (Group A and 25 patients with mean age of 40.1 years underwent manual hemorrhoidopexy (Group B. Male patients were predominant in both groups. The patients in group A had more postoperative pain as compared to group B (as assessed by the visual analogue scale and requirement of post-operative analgesic and this was statistically significant (p<0.001. There was no significant difference among the other post-operative urinary retention. Twelve percent (n=3 patients in group A had post-operative bleeding and only 4% (n=1 in group B which was statistically significant (p<0.001. Mean duration of hospital stay in group A was 2.5 days as compared to 1.5 day in group B. Median follow up in both the study group was 3 (2-4 months. Conclusion: Manual hemorrhoidopexy has comparable outcomes in term of postoperative
A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities: User's manual for FIRIN

International Nuclear Information System (INIS)

Chan, M.K.; Ballinger, M.Y.; Owczarski, P.C.

1989-02-01

This manual describes the technical bases and use of the computer code FIRIN. This code was developed to estimate the source term release of smoke and radioactive particles from potential fires in nuclear fuel cycle facilities. FIRIN is a product of a broader study, Fuel Cycle Accident Analysis, which Pacific Northwest Laboratory conducted for the US Nuclear Regulatory Commission. The technical bases of FIRIN consist of a nonradioactive fire source term model, compartment effects modeling, and radioactive source term models. These three elements interact with each other in the code affecting the course of the fire. This report also serves as a complete FIRIN user's manual. Included are the FIRIN code description with methods/algorithms of calculation and subroutines, code operating instructions with input requirements, and output descriptions. 40 refs., 5 figs., 31 tabs
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
Manual therapy in osteoarthritis of the hip: outcome in specific subgroups of patients.

NARCIS (Netherlands)

Hoeksma, H.L.; Dekker, J.; Ronday, H.K.; Breedveld, F.C.; Ende, C.H.M. van den

2005-01-01

OBJECTIVE: To investigate whether manual therapy has particular benefit in subgroups of patients defined on the basis of hip function, range of joint motion, pain and radiological deterioration. METHODS: The study was performed in the out-patient clinic of physical therapy of a large hospital. Data
Load research manual. Volume 2. Fundamentals of implementing load research procedures

Energy Technology Data Exchange (ETDEWEB)

Brandenburg, L.; Clarkson, G.; Grund, Jr., C.; Leo, J.; Asbury, J.; Brandon-Brown, F.; Derderian, H.; Mueller, R.; Swaroop, R.

1980-11-01

This three-volume manual presents technical guidelines for electric utility load research. Special attention is given to issues raised by the load data reporting requirements of the Public Utility Regulatory Policies Act of 1978 and to problems faced by smaller utilities that are initiating load research programs. In Volumes 1 and 2, procedures are suggested for determining data requirements for load research, establishing the size and customer composition of a load survey sample, selecting and using equipment to record customer electricity usage, processing data tapes from the recording equipment, and analyzing the data. Statistical techniques used in customer sampling are discussed in detail. The costs of load research also are estimated, and ongoing load research programs at three utilities are described. The manual includes guides to load research literature and glossaries of load research and statistical terms.
Partial Red Blood Cell Exchange in Children and Young Patients with Sickle Cell Disease: Manual Versus Automated Procedure.

Science.gov (United States)

Escobar, Carlos; Moniz, Marta; Nunes, Pedro; Abadesso, Clara; Ferreira, Teresa; Barra, António; Lichtner, Anabela; Loureiro, Helena; Dias, Alexandra; Almeida, Helena

2017-10-31

The benefits of manual versus automated red blood cell exchange have rarely been documented and studies in young sickle cell disease patients are scarce. We aim to describe and compare our experience in these two procedures. Young patients (≤ 21 years old) who underwent manual- or automated-red blood cell exchange for prevention or treatment of sickle cell disease complications were included. Clinical, technical and hematological data were prospectively recorded and analyzed. Ninety-four red blood cell exchange sessions were performed over a period of 68 months, including 57 manual and 37 automated, 63 for chronic complications prevention, 30 for acute complications and one in the pre-operative setting. Mean decrease in sickle hemoglobin levels was higher in automated-red blood cell exchange (p exchange and access alarm on automated-red blood cell exchange. No major complication or alloimunization was recorded. Automated-red blood cell exchange decreased sickle hemoglobin levels more efficiently than manual procedure in the setting of acute and chronic complications of sickle cell disease, with minor technical concerns mainly due to vascular access. The threshold of sickle hemoglobin should be individualized for clinical and hematological goals. In our cohort of young patients, the need for an acceptable venous access was a limiting factor, but iron-overload was avoided. Automated red blood cell exchange is safe and well tolerated. It permits a higher sickle hemoglobin removal efficacy, better volume status control and iron-overload avoidance.
BWR NSSS design basis documentation

International Nuclear Information System (INIS)

Vij, R.S.; Bates, R.E.

2004-01-01

In 1985 an incident at Toledo Edison's Davis Besse plant caused the U.S. Nuclear Regulatory Commission (NRC) to re-evaluate the technical information that the utilities had readily available to support the design of their plants. The Design Basis programs, currently on going in most U.S. utilities, have been the nuclear industry's response to the needs identified by this re-evaluation. In order to understand the Design Basis programs which have been implemented by the U.S. nuclear utilities, it is necessary to understand the problem as it was perceived by the nuclear industry (the utilities, the original NSSS designers and the regulators) after the Davis-Besse incident, the subsequent programs undertaken by the industry under the leadership of INPO and NUMARC, the NRC's actions, and the overall evolution of the industry's vision in relation to this problem. This paper presents the history of the design basis efforts from the first recognition of the problem by the NRC after the Davis-Besse incident, describes the actions taken by the NRC, INPO, NUMARC, the U.S. utilities and the NSSS designers, and brings the problem statement up-to-date in relation to the vision presently held by the U.S. nuclear industry. It then presents a technical discussion to develop a detailed definition of design basis information to support the problem statement. The information originally supplied by the NSSS designers during the plant design and construction is discussed as well as its relationship to the previously defined design basis information. This section of the paper concludes by defining the additional information needed by nuclear utilities to satisfy the requirements developed from the problem statement. Having developed a definition of the additional information (i.e., information not originally supplied during design and construction) required to solve the design basis problem as it is presently perceived by the U.S. nuclear industry, the paper then discusses design basis
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.
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.
International Cooperative Programme for Assessment and Monitoring of Acidification of Rivers and Lakes. Programme Manual

Energy Technology Data Exchange (ETDEWEB)

Bowman, J.; Forsius, M.; Jeffries, D. [and others

1996-12-31

The International Cooperative Programme for Assessment of Acidification of Rivers and lakes (ICP Waters) was established in 1985 by the UN/ECE Executive Body for the Convention of Long-Range Transboundary Air Pollution. Achieving the programme objectives requires that both the temporally intensive and regionally extensive data are collected on a continuing basis. To guide the development and harmonization of the various national contributions, a manual was worked out. The present report is an expanded and consolidated revision of that manual. 33 refs., 3 tabs.
Human System Simulation in Support of Human Performance Technical Basis at NPPs

Energy Technology Data Exchange (ETDEWEB)

David Gertman; Katya Le Blanc; alan mecham; william phoenix; Magdy Tawfik; Jeffrey Joe

2010-06-01

This paper focuses on strategies and progress toward establishing the Idaho National Laboratory’s (INL’s) Human Systems Simulator Laboratory at the Center for Advanced Energy Studies (CAES), a consortium of Idaho State Universities. The INL is one of the National Laboratories of the US Department of Energy. One of the first planned applications for the Human Systems Simulator Laboratory is implementation of a dynamic nuclear power plant simulation (NPP) where studies of operator workload, situation awareness, performance and preference will be carried out in simulated control rooms including nuclear power plant control rooms. Simulation offers a means by which to review operational concepts, improve design practices and provide a technical basis for licensing decisions. In preparation for the next generation power plant and current government and industry efforts in support of light water reactor sustainability, human operators will be attached to a suite of physiological measurement instruments and, in combination with traditional Human Factors Measurement techniques, carry out control room tasks in simulated advanced digital and hybrid analog/digital control rooms. The current focus of the Human Systems Simulator Laboratory is building core competence in quantitative and qualitative measurements of situation awareness and workload. Of particular interest is whether introduction of digital systems including automated procedures has the potential to reduce workload and enhance safety while improving situation awareness or whether workload is merely shifted and situation awareness is modified in yet to be determined ways. Data analysis is carried out by engineers and scientists and includes measures of the physical and neurological correlates of human performance. The current approach supports a user-centered design philosophy (see ISO 13407 “Human Centered Design Process for Interactive Systems, 1999) wherein the context for task performance along with the
BOSS: Borehole Disposal of Disused Sealed Sources. A Technical Manual

International Nuclear Information System (INIS)

2011-01-01

The management of disused radioactive sources is the responsibility of individual Member States. Accordingly, interest in technologies to allow the safe, secure and sustainable management of disused sealed radioactive sources is growing. This publication is a technical summary on preparing and planning predisposal and disposal activities with regard to the BOSS (borehole disposal of disused sealed sources) system, a safe, simple and cost effective solution for the management of disused sealed radioactive sources. It advises potential implementers and decision makers on the implementation of BOSS, which is expected to provide Member States with a successful tool to contribute to the safety and security of current and future generations.
Risk assessment related to manual handling on choosen work possition in foundry Alstom Power Sp. z o. o.

Directory of Open Access Journals (Sweden)

G. Kowal

2010-04-01

Full Text Available Manual handling remains one of the different types of transport inside working place, although technological progress and modernorganization of work. Manual transport as a transport inside working place is related to foundry industry. According to polish lawregulations employer has to give consideration to manual handling in professional risk assessment and introduce actions for manualhandling reduction. In Foundry Elblag case there is found that in many processes manual handling are made by workers. For example wecan choose melting processes (additives manual feeding, mixing and pulling metallurgical slag, etc. or fettling processes like grinding.Objective of that analysis was to define level of risk related to manual handling in work stand chosen and define activities impacted onrisk assessment result with biggest range. For risk reduction, technical and organizational solutions were shown (better ergonomically work stand, method of work and worker’s awareness about good practices. In this study methods related to manual handling risk assessment were described, focus on KIM method used in Foundry Elblag. Key Item Method allow to estimate the risk by simple calculation based on key indicators (time rating points, rating points of mass, posture or work condition. Points were chosen based on timekeeping, information from workers and foreman.
Control and diagnostics of technical state of main electro technical and thermal equipment of NPP, TPS and HPS on the basis of thermovision technologies

International Nuclear Information System (INIS)

Banduryan, B.B.; Fedorenko, G.M.; Ostapchuk, L.B.; Saratov, V.O.

2006-01-01

The opportunity of using of thermovision technologies for detection of defects NPP, TPS and HPS electro technical and power equipment is shown. The results of thermovision monitoring of a turbine generator stator technical state are represented. The method for thermovision control of a technical state of a electrical machines and apparatus construction elements, for which the patent of Ukraine have been obtained, is described. he verification of the offered expedient thermovision control and diagnostics at 'Elektrovazhmash' factory was carried out
Quantitative radiology: automated CT liver volumetry compared with interactive volumetry and manual volumetry.

Science.gov (United States)

Suzuki, Kenji; Epstein, Mark L; Kohlbrenner, Ryan; Garg, Shailesh; Hori, Masatoshi; Oto, Aytekin; Baron, Richard L

2011-10-01

The purpose of this study was to evaluate automated CT volumetry in the assessment of living-donor livers for transplant and to compare this technique with software-aided interactive volumetry and manual volumetry. Hepatic CT scans of 18 consecutively registered prospective liver donors were obtained under a liver transplant protocol. Automated liver volumetry was developed on the basis of 3D active-contour segmentation. To establish reference standard liver volumes, a radiologist manually traced the contour of the liver on each CT slice. We compared the results obtained with automated and interactive volumetry with those obtained with the reference standard for this study, manual volumetry. The average interactive liver volume was 1553 ± 343 cm(3), and the average automated liver volume was 1520 ± 378 cm(3). The average manual volume was 1486 ± 343 cm(3). Both interactive and automated volumetric results had excellent agreement with manual volumetric results (intraclass correlation coefficients, 0.96 and 0.94). The average user time for automated volumetry was 0.57 ± 0.06 min/case, whereas those for interactive and manual volumetry were 27.3 ± 4.6 and 39.4 ± 5.5 min/case, the difference being statistically significant (p volumetry are accurate for measuring liver volume with CT, but automated volumetry is substantially more efficient.
FAIR - Baseline technical report. Executive summary

International Nuclear Information System (INIS)

Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

2006-09-01

This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)
Design manual for management of solid by-products from advanced coal technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-10-01

Developing coal conversion technologies face major obstacles in byproduct management. This project has developed several management strategies based on field trials of small-scale landfills in an earlier phase of the project, as well as on published/unpublished sources detailing regulatory issues, current industry practice, and reuse opportunities. Field testing, which forms the basis for several of the disposal alternatives presented in this design manual, was limited to byproducts from Ca-based dry SO{sub 2} control technologies, circulating fluidized bed combustion ash, and bubbling bed fluidized bed combustion ash. Data on byproducts from other advanced coal technologies and on reuse opportunities are drawn from other sources (citations following Chapter 3). Field results from the 5 test cases examined under this project, together with results from other ongoing research, provide a basis for predictive modeling of long-term performance of some advanced coal byproducts on exposure to ambient environment. This manual is intended to provide a reference database and development plan for designing, permitting, and operating facilities where advanced coal technology byproducts are managed.
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.
Non-technical skills for scrub practitioners.

Science.gov (United States)

McClelland, Guy

2012-12-01

The non-technical skills of situational awareness and the formation of effective interpersonal relationships are essential to enhance surgical outcomes. However, most scrub practitioners demonstrate only tacit awareness of these skills and develop such qualities on an informal basis. Application of non-technical skills may be assessed formally, using a structured framework, to transform normative behaviour and to strengthen barriers against the latent threats that may result from fallible humans working in inadequate organisational systems.
Technical skills requirement of Indonesian construction labors to work in Malaysia

Science.gov (United States)

Adi, Henny Pratiwi

2017-03-01

Labors skills is an important part of construction projects implementation. Suitability between the skills possessed by labors with the skills needed by user is required to increase employment opportunities. Malaysia is a country that using construction labors from Indonesia. This study aims to get the kind of technical skills required by users of Indonesian constructian labors in Malaysia and also the importance level of technical skills. Data collecting in this research was conducted through interviews and questionnaires on contractors in Malaysia. The next stage was determine the importance level of technical skills in work field of carpenter, bricklayer, plumber and painters. The importance level of technical skills analyzed using the Relative Importance Index (RII). The results showed that mastering the operation of both instruments either manually or electrically is the most importance in the technical skills. Therefore, an understanding of the types of equipment for work field and the manner of operation is need to had by Indonesian construction labors who will work in Malaysia.
Training Manual for Elements of Interface Definition and Control

Science.gov (United States)

Lalli, Vincent R. (Editor); Kastner, Robert E. (Editor); Hartt, Henry N. (Editor)

1997-01-01

The primary thrust of this manual is to ensure that the format and information needed to control interfaces between equipment are clear and understandable. The emphasis is on controlling the engineering design of the interface and not on the functional performance requirements of the system or the internal workings of the interfacing equipment. Interface control should take place, with rare exception, at the interfacing elements and no further. There are two essential sections of the manual. Chapter 2, Principles of Interface Control, discusses how interfaces are defined. It describes different types of interfaces to be considered and recommends a format for the documentation necessary for adequate interface control. Chapter 3, The Process: Through the Design Phases, provides tailored guidance for interface definition and control. This manual can be used to improve planned or existing interface control processes during system design and development. It can also be used to refresh and update the corporate knowledge base. The information presented herein will reduce the amount of paper and data required in interface definition and control processes by as much as 50 percent and will shorten the time required to prepare an interface control document. It also highlights the essential technical parameters that ensure that flight subsystems will indeed fit together and function as intended after assembly and checkout.
Pressure vessel design manual

CERN Document Server

Moss, Dennis R

2013-01-01

Pressure vessels are closed containers designed to hold gases or liquids at a pressure substantially different from the ambient pressure. They have a variety of applications in industry, including in oil refineries, nuclear reactors, vehicle airbrake reservoirs, and more. The pressure differential with such vessels is dangerous, and due to the risk of accident and fatality around their use, the design, manufacture, operation and inspection of pressure vessels is regulated by engineering authorities and guided by legal codes and standards. Pressure Vessel Design Manual is a solutions-focused guide to the many problems and technical challenges involved in the design of pressure vessels to match stringent standards and codes. It brings together otherwise scattered information and explanations into one easy-to-use resource to minimize research and take readers from problem to solution in the most direct manner possible. * Covers almost all problems that a working pressure vessel designer can expect to face, with ...
A technical basis to relax the dew point specification for the environment in the vapor space in DWPF canisters

International Nuclear Information System (INIS)

Louthan, M.R. Jr.

1995-05-01

This memorandum establishes the technical basis to conclude that relaxing, from 0 C to 20 C, the dew point specification for the atmosphere in the vapor space (free volume) of a DWPF canister will not provide an environment that will cause significant amounts of corrosion induced degradation of the canister wall. The conclusion is based on engineering analysis, experience and review of the corrosion literature. The basic assumptions underlying the conclusion are: (1) the canister was fabricated from Type 304L stainless steel; (2) the corrosion behavior of the canister material, including base metal, fusion zones and heat effected zones, is typified by literature data for, and industrial experience with, 300 series austenitic stainless steels; and (3) the glass-metal crevices created during the pouring operation will not alter the basic corrosion resistance of the steel although such crevices might serve as sites for the initiation of minor amounts of corrosion on the canister wall
ATR Technical Specification Upgrade Program

International Nuclear Information System (INIS)

McCracken, R.T.; Durney, J.L.; Freund, G.A.

1990-01-01

The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program
The International Nuclear Event Scale (INES) user's manual. 2001 edition; La escala internacional de sucesos nucleares (INES) manual del usuario. Edicion de 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-12-01

The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials.This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled 'Clarification of Issues Raised'. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request.
Technical review of WSRC-TR-93-614 criticality safety evaluation for disassembly basin sand filter

International Nuclear Information System (INIS)

Reed, R.L.

1994-01-01

The study documented in WSRC-TR-93-614 performed an evaluation of the criticality potential associated with the Disassembly Basin Sand Filter for K and L Areas. The document reviewed incorporated results of calculations documented in the engineering calculation N-CLC-K-00151. Analyses of the contents of disassembly basin sludge has indicated that the sludge contains fissile material in excess of subcritical mass limits as specified in ANSI/ANS standards. Previous studies had determined that the fissile material can not collect into a critical configuration in the basin. Since the sand filter is intended to remove suspended particles from the basin water and could serve as a mechanism to collect the fissile material into a critical configuration, the study examined conditions under which criticality could occur in the sand filter. The study shows that criticality is not considered possible in the sand filter. This review emphasized the technical accuracy and presentation of the evaluation. The evaluation was also examined for the elements required for NCSEs. The review was performed in accordance with the NRTSC technical review requirements and procedures and the E7 Manual technical review requirements. The technical review (per the E7 manual) of the engineering calculation (N-CLC-K-0 1 5 1) was previously performed by this reviewer
EPR-technical codes - a common basis for the EPR

International Nuclear Information System (INIS)

Zaiss, W.; Appell, B.

1997-01-01

The design and construction of Nuclear Power Plants implies a full set of codes and standards to define the construction rules of components and equipment. Rules are existing and are currently implemented, respectively in France and Germany (mainly RCCs and KTA safety standards). In the frame of the EPR-project, the common objective requires an essential industrial work programme between engineers from both countries to elaborate a common set of codes and regulations. These new industrial rules are called the ETCs (EPR Technical Codes). In the hierarchy the ETCs are - in case of France - on the common level of basic safety rules (RFS), design and construction rules (RCC) and - in Germany - belonging to RSK guidelines and KTA safety standards. A set of six ETCs will be elaborated to cover: safety and process, mechanical components, electrical equipment, instrumentation and control, civil works, fire protection. (orig.)
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
Methodology for assessing the safety of Hydrogen Systems: HyRAM 1.1 technical reference manual

Energy Technology Data Exchange (ETDEWEB)

Groth, Katrina; Hecht, Ethan; Reynolds, John Thomas; Blaylock, Myra L.; Erin E. Carrier

2017-03-01

The HyRAM software toolkit provides a basis for conducting quantitative risk assessment and consequence modeling for hydrogen infrastructure and transportation systems. HyRAM is designed to facilitate the use of state-of-the-art science and engineering models to conduct robust, repeatable assessments of hydrogen safety, hazards, and risk. HyRAM is envisioned as a unifying platform combining validated, analytical models of hydrogen behavior, a stan- dardized, transparent QRA approach, and engineering models and generic data for hydrogen installations. HyRAM is being developed at Sandia National Laboratories for the U. S. De- partment of Energy to increase access to technical data about hydrogen safety and to enable the use of that data to support development and revision of national and international codes and standards. This document provides a description of the methodology and models contained in the HyRAM version 1.1. HyRAM 1.1 includes generic probabilities for hydrogen equipment fail- ures, probabilistic models for the impact of heat flux on humans and structures, and computa- tionally and experimentally validated analytical and first order models of hydrogen release and flame physics. HyRAM 1.1 integrates deterministic and probabilistic models for quantifying accident scenarios, predicting physical effects, and characterizing hydrogen hazards (thermal effects from jet fires, overpressure effects from deflagrations), and assessing impact on people and structures. HyRAM is a prototype software in active development and thus the models and data may change. This report will be updated at appropriate developmental intervals.
Guidance Manual for preparing Nuclear and Radiological Emergency Preparedness and Response Plan

Energy Technology Data Exchange (ETDEWEB)

Muhammed, Kabiru [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Jeong, Seung-Young [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-10-15

The Nuclear and Radiological Emergency Preparedness and Response Plan(NREPRP) describes the capabilities, responsibilities and authorities of government agencies and a conceptual basis for integrating the activities of these agencies to protect public health and safety. The NREPRP addresses issues related to actual or perceived radiation hazard requiring a national response in order to: i. Provide co-ordination of a response involving multi-jurisdictions or significant national responsibilities; or ii. Provide national support to state and local governments. The objective of this research is to establish Guidance Manual for preparing a timely, organized and coordinated emergency response plan for Authorities/agencies to promptly and adequately determine and take actions to protect members of the public and emergency workers. The manual will not provide sufficient details for an adequate response. This level of details is contained in standard operating procedures that are being developed based on the plan developed. Base on the data obtain from integrated planning levels and responsibility sharing, the legal document of major government agencies participating in NREPRP form the legal basis for the response plan. Also the following documents should be some international legal binding documents. Base on the international safety requirement and some countries well developed NREPRP, we have drafted a guidance manual for new comer countries for easy development of their countries NREPRP. Also we have taken in to consideration lessons learn from most accident especially Fukushima accident.
Guidance Manual for preparing Nuclear and Radiological Emergency Preparedness and Response Plan

International Nuclear Information System (INIS)

Muhammed, Kabiru; Jeong, Seung-Young

2014-01-01

The Nuclear and Radiological Emergency Preparedness and Response Plan(NREPRP) describes the capabilities, responsibilities and authorities of government agencies and a conceptual basis for integrating the activities of these agencies to protect public health and safety. The NREPRP addresses issues related to actual or perceived radiation hazard requiring a national response in order to: i. Provide co-ordination of a response involving multi-jurisdictions or significant national responsibilities; or ii. Provide national support to state and local governments. The objective of this research is to establish Guidance Manual for preparing a timely, organized and coordinated emergency response plan for Authorities/agencies to promptly and adequately determine and take actions to protect members of the public and emergency workers. The manual will not provide sufficient details for an adequate response. This level of details is contained in standard operating procedures that are being developed based on the plan developed. Base on the data obtain from integrated planning levels and responsibility sharing, the legal document of major government agencies participating in NREPRP form the legal basis for the response plan. Also the following documents should be some international legal binding documents. Base on the international safety requirement and some countries well developed NREPRP, we have drafted a guidance manual for new comer countries for easy development of their countries NREPRP. Also we have taken in to consideration lessons learn from most accident especially Fukushima accident
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
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...
Irrigation Training Manual. Planning, Design, Operation, and Management of Small-Scale Irrigation Systems [and] Irrigation Reference Manual. A Technical Reference to Be Used with the Peace Corps Irrigation Training Manual T0076 in the Selection, Planning, Design, Operation, and Management of Small-Scale Irrigation Systems.

Science.gov (United States)

Salazar, LeRoy; And Others

This resource for trainers involved in irrigated agriculture training for Peace Corps volunteers consists of two parts: irrigation training manual and irrigation reference manual. The complete course should fully prepare volunteers serving as irrigation, specialists to plan, implement, evaluate and manage small-scale irrigation projects in arid,…

SRL process hazards review manual

International Nuclear Information System (INIS)

1980-08-01

The principal objective of the Process Hazards Management Program is to provide a regular, systematic review of each process at the Savannah River Laboratory (SRL) to eliminate injuries and to minimize property damage resulting from process hazards of catastrophic potential. Management effort is directed, through the Du Pont Safety Program, toward those controls and practices that ensure this objective. The Process Hazards Management Program provides an additional dimension to further ensure the health and safety of employees and the public. Du Pont has concluded that an organized approach is essential to obtain an effective and efficient process hazards review. The intent of this manual is to provide guidance in creating such an organized approach to performing process hazards reviews on a continuing basis
Standard technical specifications combustion engineering plants

International Nuclear Information System (INIS)

1992-09-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS
Authorization basis requirements comparison report

Energy Technology Data Exchange (ETDEWEB)

Brantley, W.M.

1997-08-18

The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation.
Authorization basis requirements comparison report

International Nuclear Information System (INIS)

Brantley, W.M.

1997-01-01

The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation
Design-Load Basis for LANL Structures, Systems, and Components

Energy Technology Data Exchange (ETDEWEB)

I. Cuesta

2004-09-01

This document supports the recommendations in the Los Alamos National Laboratory (LANL) Engineering Standard Manual (ESM), Chapter 5--Structural providing the basis for the loads, analysis procedures, and codes to be used in the ESM. It also provides the justification for eliminating the loads to be considered in design, and evidence that the design basis loads are appropriate and consistent with the graded approach required by the Department of Energy (DOE) Code of Federal Regulation Nuclear Safety Management, 10, Part 830. This document focuses on (1) the primary and secondary natural phenomena hazards listed in DOE-G-420.1-2, Appendix C, (2) additional loads not related to natural phenomena hazards, and (3) the design loads on structures during construction.
Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1976-01-01

The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation
Manual on brachytherapy. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to brachytherapy: its application and procedures guides
Do manual and voxel-based morphometry measure the same? – A proof of concept study

Directory of Open Access Journals (Sweden)

Niels K. Focke

2014-04-01

Full Text Available Voxel-based morphometry (VBM is a commonly used method to study volumetric variations on a whole brain basis. However it is often criticised for potential confounds, mainly based on imperfect spatial registration. We therefore aimed to evaluate if VBM and gold-standard manual volumetry are measuring the same effects with respect to subcortical grey matter volumes. Manual regions-of-interest (ROIs were drawn in the hippocampus, amygdala, nucleus accumbens, thalamus, putamen, pallidum and caudate nucleus bilaterally. Resulting volumes were used for a whole brain VBM correlation analysis with SPM8. The hippocampus, amygdala, putamen and caudate nucleus were correctly identified by SPM using the contemporary high-dimensional normalization (DARTEL toolbox. This strongly suggests that VBM and manual volumetry both are indeed measuring the same effects with regard to subcortical brain structures.
Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab
Main-coolant-pump shaft-seal guidelines. Volume 1. Maintenance-manual guidelines. Final report

International Nuclear Information System (INIS)

Fair, C.E.; Greer, A.O.

1983-03-01

This report presents a set of guidelines and a listing of information and data which should be included in maintenance manuals and procedures for Main Coolant Pump Shaft Seals. The noted guidelines and data listing are developed from EPRI sponsored nuclear plant seal operating experience studies. The maintenance oriented results of the most recent such study is summarized. The shaft seal and its auxiliary supporting systems are discussed from both technical and maintenance related viewpoints
A technical basis for meeting waste form stability requirements of 10 CFR 61

International Nuclear Information System (INIS)

Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

1988-01-01

To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper
Gastroenterology-Urology Devices; Manual Gastroenterology-Urology Surgical Instruments and Accessories. Final rule; technical amendment.

Science.gov (United States)

2017-03-01

The Food and Drug Administration (FDA) is amending the identification of manual gastroenterology-urology surgical instruments and accessories to reflect that the device does not include specialized surgical instrumentation for use with urogyencologic surgical mesh specifically intended for use as an aid in the insertion, placement, fixation, or anchoring of surgical mesh during urogynecologic procedures ("specialized surgical instrumentation for use with urogynecologic surgical mesh"). These amendments are being made to reflect changes made in the recently issued final reclassification order for specialized surgical instrumentation for use with urogynecologic surgical mesh.
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
Importance of the documentation of the manual of quality and procedures handbook in the nuclear technology center

International Nuclear Information System (INIS)

Domech More, J.; Bolanos Hernandez, R.; Quitero Rosello, R.; Fernandez Rondon, M.; Milian Lorenzo, D.; Rodriguez Gual, M.

1997-01-01

In the present work is presented the methodology used for the elaboration of manual of quality of the Nuclear Technology Center and the technical Procedures Handbook for the execution of Preliminary Safety report of the Juragua Nuclear Power Plant, as well as the importance that has this documentation for the work of the center
The International Nuclear Event Scale (INES) user's manual. 2001 edition

International Nuclear Information System (INIS)

2001-12-01

The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials.This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled 'Clarification of Issues Raised'. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request
The International Nuclear Event Scale (INES) user's manual. 2001 edition

International Nuclear Information System (INIS)

2001-02-01

The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials.This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled ''Clarification of Issues Raised''. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request
Improvements to Technical Specifications surveillance requirements

International Nuclear Information System (INIS)

Lobel, R.; Tjader, T.R.

1992-12-01

In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power
INTRA/Mod3.2. Manual and code description. Volume 2 - User`s manual

Energy Technology Data Exchange (ETDEWEB)

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
Development of technical information basis of aging management for nuclear power plants

International Nuclear Information System (INIS)

Kanno, M.

2007-01-01

In order to implement effective safety regulations on aging management for reactor facilities etc., the information on important technology issues, the latest technical knowledge including evaluation technology, test and research outcomes, related codes and standards, regulation information, operation experiences such as accidents and trouble, etc. with respect to aging-induced deterioration in and outside Japan and in other industries, were collected, organized and evaluated. (author)
Colonialism and Secondary Technical Education in Hong Kong: 1945-1997

Science.gov (United States)

Lau, Wai Wah; Kan, Flora

2011-01-01

This study examines the influence of the colonial experience (1945-1997) on the planning of secondary technical education in Hong Kong. Specifically, the origins of secondary technical institutions and their positioning in secondary education are examined. Primary source materials are used as the basis of investigation and analysis, supplemented…

Camp Health Aide Manual = Manual para trabajadores de salud.

Science.gov (United States)

Robinson, June Grube; And Others

This bilingual manual serves as a textbook for migrant Camp Health Aides. Camp Health Aides are members of migrant labor camps enlisted to provide information about health and social services to migrant workers and their families. The manual is divided into 12 tabbed sections representing lessons. Teaching notes printed on contrasting paper…
Technical and Technological Support of Agricultural Enterprises on the Basis of Association Interaction: a Methodical Approach

Directory of Open Access Journals (Sweden)

Pyvovar Petro V.

2017-12-01

Full Text Available The aim of the research is the development of a methodical approach to justifying directions of association interaction of agricultural enterprises for the most effective technical and technological support of their economic activities. It is substantiated that the decision-making regarding the directions of group interaction in the field of forming and using the machine and tractor fleet of agricultural enterprises should be based on results of a strategic analysis of the current level of and trends in the changes in indicators of their technical support. This includes several stages: 1 determining a scenario for the development of the technical base of the economic entity (matrix methods; 2 multifactor grouping taking into account the available equipment and resource potential; 3 identification of potential sources of financing and ways of attracting necessary funds, priority partners and types of equipment and technologies; 4 estimation of a current condition of the enterprise on financial, technical, economic and market criteria; 5 substantiation of directions of group interaction of the enterprise.
Federal Transit Administration's noise and vibration Guidance Manual: Updates after 10 years of experience

Science.gov (United States)

Hanson, Carl E.

2005-09-01

In April 1995, the Federal Transit Administration of the U.S. Department of Transportation issued its guidance manual, ``Transit Noise and Vibration Impact Assessment.'' The manual was written to provide direction for the preparation of noise and vibration sections of environmental documents for public transportation projects in the interest of promoting quality and uniformity in assessments. In the 10 years since its release, the guidance manual has been used as the basis of noise and vibration assessments in over 80 environmental documents and has been used worldwide as a standard method for performing transit noise analyses. An updated version has recently been prepared that takes account of improvements in tools, changes in the environmental assessment procedures, modifications of impact criteria, and experience with mitigation measures. These factors, and other background information, will be discussed to provide insight regarding the revisions in the new edition.
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
Technical and economic viability of electric power plants on the basis of renewable energy resources regarding hierarchical structure

Directory of Open Access Journals (Sweden)

Balzannikov Mikhail

2017-01-01

Full Text Available The article deals with power stations working on the basis of non-renewable energy resources and finite resources which will inevitably come to depletion in the future. These installations produce considerable negative impact on the environment, including air pollution. It is noted that considerable amounts of emissions of harmful substances accounts for the share of small thermal installations which aren’t always considered in calculations of pollution. The author specifies that emission reduction of harmful substances should be achieved due to wider use of environmentally friendly renewable energy resources. It is recommended to use hierarchical structure with the priority of ecological and social conditions of the region for technical and economic viability of consumers’ power supply systems and installations, based on renewable energy resources use. At the same time the author suggests considering federal, regional and object levels of viability. It is recommended to consider the main stages of lifecycle of an object for object level: designing, construction, operation, reconstruction of an object and its preservation. The author shows the example of calculation of power plant efficiency, based on renewable energy resources during its reconstruction, followed by power generation increase.
Configuration management after design basis reconstitution

International Nuclear Information System (INIS)

Purcell, J.J.; Livingston, B.R.

1991-01-01

Over the last few years, Fort Calhoun station (FCS) has implemented a number of programs to enhance plant operability and readiness. The design basis document (DBD) reconstitution project was the cornerstone of this effort. Vendor manual upgrade, operating procedures upgrade, plant equipment data-base verification, equipment labeling, and warehousing improvements were also implemented as part of this improvement program. With the completion of these programs, plant documentation was current to the baselines established by each program, and a configuration management program (CMP) was established to maintain this level of accuracy throughout the remaining life of FCS. Change control throughout the organization has been reviewed and upgraded to ensure that all changes are evaluated for impact to the design bases
Reader-Centered Technical Writing

Science.gov (United States)

Narayanan, M.

2012-12-01

Technical writing is an essential part of professional communication and in recent years it has shifted from a genre-based approach. Formerly, technical writing primarily focused on generating templates of documents and sometimes it was creating or reproducing traditional forms with minor modifications and updates. Now, technical writing looks at the situations surrounding the need to write. This involves deep thinking about the goals and objectives of the project on hand. Furthermore, one observes that it is very important for any participatory process to have the full support of management. This support needs to be well understood and believed by employees. Professional writing may be very persuasive in some cases. When presented in the appropriate context, technical writing can persuade a company to improve work conditions ensuring employee safety and timely production. However, one must recognize that lot of professional writing still continues to make use of reports and instruction manuals. Normally, technical and professional writing addresses four aspects. Objective: The need for generating a given professionally written technical document and the goals the document is expected to achieve and accomplish. Clientele: The clientele who will utilize the technical document. This may include the people in the organization. This may also include "unintended readers." Customers: The population that may be affected by the content of the technical document generated. This includes the stakeholders who will be influenced. Environment: The background in which the document is created. Also, the nature of the situation that warranted the generation of the document. Swiss Psychologist Jean Piaget's view of Learning focuses on three aspects. The author likes to extend Jean Piaget's ideas to students, who are asked to prepare and submit Reader-Centered Technical Writing reports and exercises. Assimilation: Writers may benefit specifically, by assimilating a new object into
A Manual of Style.

Science.gov (United States)

Nebraska State Dept. of Education, Lincoln.

This "Manual of Style" is offered as a guide to assist Nebraska State employees in producing quality written communications and in presenting a consistently professional image of government documents. The manual is not designed to be all-inclusive. Sections of the manual discuss formatting documents, memorandums, letters, mailing…
Scientific and technical basis of safety increase measures at NPPs with WWER

International Nuclear Information System (INIS)

Skalozubov, V.I.; Klyuchnikov, A.A.; Komarov, Yu.A.; Shavlakov, A.V.

2010-01-01

This monograph presents the original development of the authors on scientific and technical substantiation of foreground modern measures on safety increase at nuclear power plants with water-water reactors: development and implementation of operative diagnostic system for thermo acoustical instability of reactor core, substantituation of performance capacity and reliability of fast-acting reducing units systems and regulation systems of reactor emergency cooling at control of dominant for safety accidents.
MARS CODE MANUAL VOLUME III - Programmer's Manual

International Nuclear Information System (INIS)

Chung, Bub Dong; Hwang, Moon Kyu; Jeong, Jae Jun; Kim, Kyung Doo; Bae, Sung Won; Lee, Young Jin; Lee, Won Jae

2010-02-01

Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This programmer's manual provides a complete list of overall information of code structure and input/output function of MARS. In addition, brief descriptions for each subroutine and major variables used in MARS are also included in this report, so that this report would be very useful for the code maintenance. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible
Preventive maintenance basis: Volume 31 -- Relays -- timing. Final report

International Nuclear Information System (INIS)

Worledge, D.; Hinchcliffe, G.

1998-07-01

US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to timing relays. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program
Preventive maintenance basis: Volume 30 -- Relays -- control. Final report

International Nuclear Information System (INIS)

Worledge, D.; Hinchcliffe, G.

1998-07-01

US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to control relays. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program
Quality Manual

Science.gov (United States)

Koch, Michael

The quality manual is the “heart” of every management system related to quality. Quality assurance in analytical laboratories is most frequently linked with ISO/IEC 17025, which lists the standard requirements for a quality manual. In this chapter examples are used to demonstrate, how these requirements can be met. But, certainly, there are many other ways to do this.
The socio-technical system and nuclear safety

International Nuclear Information System (INIS)

Stefanescu, Petre; Mihailescu, Nicolae; Dragusin, Octavian

1999-01-01

In the field of nuclear safety there have been defined notions like 'technical factors' and 'human factors'. The technical factors depend on designing and manufacturing of components/equipment, actually depend on the people's work. The study of human factors consists in analyzing and recommending the terms that allow an individual to be a reliable and safety agent. Accordingly, he/she is placed in working conditions corresponding to human abilities, associating the means of three levels: - designing, i.e. the action upon the technical system and upon work organization; - correction, i.e. the action upon the evolution of the technical system and organizing; - formation/training, i.e. action upon operators. The paper presents a characterization of the socio-technical system and on this basis discusses the issue of individual adjustment to the socio-technical system and reciprocally, the issue of the socio-technical system adjustment to the individual. Concepts as: ergonomics, physical medium, man/machine interface and support of the operator, man/machine task sharing, the work organizing are put in relation with the central subject, the nuclear safety
Technical review of the dispersion and dose models used in the MILDOS computer program

International Nuclear Information System (INIS)

Horst, T.W.; Soldat, J.K.; Bander, T.J.

1982-05-01

The MILDOS computer code is used to estimate impacts of radioactive emissions from uranium milling facilities. This report reviews the technical basis of the models used in the MILDOS computer code. The models were compared with state-of-the-art predictions, taking into account the intended uses of the MILDOS code. Several suggested modifications are presented and the technical basis for those changes are given
Technical specification optimization program - engineered safety features

International Nuclear Information System (INIS)

Andre, G.R.; Jansen, R.L.

1986-01-01

The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS
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
Manual on gamma radiography. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to gamma radiography: its application and procedures guides
Manual on shielded enclosures. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to shielding enclosures: their application and procedures guides
Manual on nuclear gauges. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to nuclear gauges: their application and procedures guides

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

International Nuclear Information System (INIS)

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

1994-01-01

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-05-01

This Department of Energy (DOE) technical standards list (TSL) has been prepared by the Office of Nuclear Safety Policy and Standards (EH-31) on the basis of currently available technical information. Periodic updates of this TSL will be issued as additional information is received on standardization documents being issued, adopted, or canceled by DOE. This document was prepared for use by personnel involved in the selection and use of DOE technical standards and other Government and non-Government standards. This TSL provides listings of current DOE technical standards, non-Government standards that have been adopted by DOE, other standards-related documents in which DOE has a recorded interest, and canceled DOE technical standards. Information on new DOE technical standards projects, technical standards released for coordination, recently published DOE technical standards, and activities of non-Government standards bodies that may be of interest to DOE is published monthly in Standards Actions.
Wireless online position monitoring of manual valve types for plant configuration management in nuclear power plants

International Nuclear Information System (INIS)

Agarwal, Vivek; Buttles, John W.; Beaty, Lawrence H.; Naser, Joseph; Hallbert, Bruce P.

2016-01-01

In the current competitive energy market, the nuclear industry is committed to lower the operations and maintenance cost; increase productivity and efficiency while maintaining safe and reliable operation. The present operating model of nuclear power plants is dependent on large technical staffs that put the nuclear industry at long-term economic disadvantage. Technology can play a key role in nuclear power plant configuration management in offsetting labor costs by automating manually performed plant activities. The technology being developed, tested, and demonstrated in this paper will enable the continued safe operation of today’s fleet of light water reactors by providing the technical means to monitor components in plants today that are only routinely monitored through manual activities. The wireless enabled valve position indicators that are the subject of this paper are able to provide a valid position indication available continuously, rather than only periodically. As a result, a real-time (online) availability of valve positions using an affordable technologies are vital to plant configuration when compared with long-term labor rates, and provide information that can be used for a variety of plant engineering, maintenance, and management applications.
Basis for NGNP Reactor Design Down-Selection

Energy Technology Data Exchange (ETDEWEB)

L.E. Demick

2010-08-01

The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.
SHARP User Manual

Energy Technology Data Exchange (ETDEWEB)

Yu, Y. Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Shemon, E. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Thomas, J. W. [Argonne National Lab. (ANL), Argonne, IL (United States); Mahadevan, Vijay S. [Argonne National Lab. (ANL), Argonne, IL (United States); Rahaman, Ronald O. [Argonne National Lab. (ANL), Argonne, IL (United States); Solberg, Jerome [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-03-31

SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.
SHARP User Manual

International Nuclear Information System (INIS)

Yu, Y. Q.; Shemon, E. R.; Thomas, J. W.; Mahadevan, Vijay S.; Rahaman, Ronald O.; Solberg, Jerome

2016-01-01

SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.
User's Manual for FEMOM3DS. Version 1.0

Science.gov (United States)

Reddy, C.J.; Deshpande, M. D.

1997-01-01

FEMOM3DS is a computer code written in FORTRAN 77 to compute electromagnetic(EM) scattering characteristics of a three dimensional object with complex materials using combined Finite Element Method (FEM)/Method of Moments (MoM) technique. This code uses the tetrahedral elements, with vector edge basis functions for FEM in the volume of the cavity and the triangular elements with the basis functions similar to that described for MoM at the outer boundary. By virtue of FEM, this code can handle any arbitrarily shaped three-dimensional cavities filled with inhomogeneous lossy materials. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computers on which the code is intended to run.
Manual of radioisotope production

International Nuclear Information System (INIS)

1966-01-01

The Manual of Radioisotope Production has been compiled primarily to help small reactor establishments which need a modest programme of radioisotope production for local requirements. It is not comprehensive, but gives guidance on essential preliminary considerations and problems that may be met in the early stages of production. References are included as an aid to the reader who wishes to seek further in the extensive literature on the subject. In preparing the Manual, which is in two parts, the Agency consulted several Member States which already have long experience in radioisotope production. An attempt has been made to condense this experience, firstly, by setting out the technical and economic considerations which govern the planning and execution of an isotope programme and, secondly, by providing experimental details of isotope production processes. Part I covers topics common to all radioisotope processing, namely, laboratory design, handling and dispensing of radioactive solutions, quality control, measurement and radiological safety. Part II contains information on the fifteen radioisotopes in most common use. These are bromine-82, cobalt-58, chromium-51, copper-64, fluorine-18, gold-198, iodine-131, iron-59, magnesium-28, potassium-42, sodium-24, phosphorus-32, sulphur-35, yttrium-90 and zinc-65. Their nuclear properties are described, references to typical applications are given and published methods of production are reviewed; also included are descriptions in detail of the production processes used at several national atomic energy organizations. No attempt has been made to distinguish the best values for nuclear data or to comment on the relative merits of production processes. Each process is presented essentially as it was described by the contributor on the understanding that critical comparisons are not necessary for processes which have been well tried in practical production for many years. The information is presented as a guide to enable
Dry-run of site investigation planning using the manual for preliminary investigation in Japan

International Nuclear Information System (INIS)

Akamura, Shigeki; Miwa, Tadashi; Tanaka, Tatsuya; Shiratsuchi, Hiroshi; Horio, Atsushi

2011-01-01

A stepwise site selection process has been adopted for geological disposal of HLW in Japan. Literature surveys, followed by preliminary investigations (PI) and, finally, detailed investigations in underground facilities will be carried out in the successive selection stages. In the PI stage, surface-based investigations such as borehole surveys and geophysical prospecting will be implemented. In order to conduct the PI appropriately and efficiently within a restricted timeframe and budget, planning and management of PI are very important. NUMO therefore compiled existing knowledge and experience in the planning and managing of investigations in the form of manuals to be used to improve and maintain internal expertise. The first editions of the two manuals were prepared on the basis of experience overseas, and then they were revised by taking technological environment, laws and regulation in Japan into consideration. This paper introduces the procedure of PI planning using manual as well as the results of the dry-run, with the Yokosuka area as a hypothetical PI area, where the monstraction study is under way. Based on the dry-run, applicability of the manual is checked and, at the same time, further revisions are made to improve the content. (author)
Evaluation of manual and automatic manually triggered ventilation performance and ergonomics using a simulation model.

Science.gov (United States)

Marjanovic, Nicolas; Le Floch, Soizig; Jaffrelot, Morgan; L'Her, Erwan

2014-05-01

In the absence of endotracheal intubation, the manual bag-valve-mask (BVM) is the most frequently used ventilation technique during resuscitation. The efficiency of other devices has been poorly studied. The bench-test study described here was designed to evaluate the effectiveness of an automatic, manually triggered system, and to compare it with manual BVM ventilation. A respiratory system bench model was assembled using a lung simulator connected to a manikin to simulate a patient with unprotected airways. Fifty health-care providers from different professional groups (emergency physicians, residents, advanced paramedics, nurses, and paramedics; n = 10 per group) evaluated manual BVM ventilation, and compared it with an automatic manually triggered device (EasyCPR). Three pathological situations were simulated (restrictive, obstructive, normal). Standard ventilation parameters were recorded; the ergonomics of the system were assessed by the health-care professionals using a standard numerical scale once the recordings were completed. The tidal volume fell within the standard range (400-600 mL) for 25.6% of breaths (0.6-45 breaths) using manual BVM ventilation, and for 28.6% of breaths (0.3-80 breaths) using the automatic manually triggered device (EasyCPR) (P < .0002). Peak inspiratory airway pressure was lower using the automatic manually triggered device (EasyCPR) (10.6 ± 5 vs 15.9 ± 10 cm H2O, P < .001). The ventilation rate fell consistently within the guidelines, in the case of the automatic manually triggered device (EasyCPR) only (10.3 ± 2 vs 17.6 ± 6, P < .001). Significant pulmonary overdistention was observed when using the manual BVM device during the normal and obstructive sequences. The nurses and paramedics considered the ergonomics of the automatic manually triggered device (EasyCPR) to be better than those of the manual device. The use of an automatic manually triggered device may improve ventilation efficiency and decrease the risk of
Spent nuclear fuel project technical databook

Energy Technology Data Exchange (ETDEWEB)

Reilly, M.A.

1998-07-22

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.
Spent nuclear fuel project technical databook

International Nuclear Information System (INIS)

Reilly, M.A.

1998-01-01

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values
Technical note: CT-guided biopsy of lung masses using an automated guiding apparatus

International Nuclear Information System (INIS)

Chellathurai, Amarnath; Kanhirat, Saneej; Chokkappan, Kabilan; Swaminathan, Thiruchendur S; Kulasekaran, Nadhamuni

2009-01-01

Automated guiding apparatuses for CT-guided biopsies are now available. We report our experience with an indigenous system to guide lung biopsies. This system gave results similar to those with the manual technique. Automated planning also appears to be technically easier, it requires fewer number of needle passes, consumes less time, and requires fewer number of check scans
Writing the Trenches: What Students of Technical Writing and Literature Can Learn Together

Science.gov (United States)

Baake, Ken; Shelton, Jen

2017-01-01

We argue for a course in which students analyze writing about a common topic--in this case World War I--from multiple genres (e.g., poetry and technical manuals). We address the divide between instruction in pragmatic and literary writing and calls to bridge that gap. Students working in disparate areas of English learn the strengths and the…
Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The present Manual on Quality Assurance (QA) for Installation and Commissioning of Instrumentation, Control and Electrical (ICE) Equipment of Nuclear Power Plants contains supporting material and illustrative examples for implementing basic requirements of the quality assurance programme in procurement, receiving, installation and commissioning of this equipment. The Manual on Quality Assurance for Installation and Commissioning of ICE Equipment is designed to supplement and be consistent with the Guidebook as well as with the IAEA Code and Safety Guides on Quality Assurance. It is intended for the use of managerial staff and QA personnel of nuclear power plant owners or the organizations respectively responsible for the legal, technical, administrative and financial aspects of a nuclear power plant. The information provided in the Manual will also be useful to the inspection staff of the regulatory organization in the planning and performance of regulatory inspections at nuclear power plants
Working Memory for Linguistic and Non-linguistic Manual Gestures: Evidence, Theory, and Application.

Science.gov (United States)

Rudner, Mary

2018-01-01

Linguistic manual gestures are the basis of sign languages used by deaf individuals. Working memory and language processing are intimately connected and thus when language is gesture-based, it is important to understand related working memory mechanisms. This article reviews work on working memory for linguistic and non-linguistic manual gestures and discusses theoretical and applied implications. Empirical evidence shows that there are effects of load and stimulus degradation on working memory for manual gestures. These effects are similar to those found for working memory for speech-based language. Further, there are effects of pre-existing linguistic representation that are partially similar across language modalities. But above all, deaf signers score higher than hearing non-signers on an n-back task with sign-based stimuli, irrespective of their semantic and phonological content, but not with non-linguistic manual actions. This pattern may be partially explained by recent findings relating to cross-modal plasticity in deaf individuals. It suggests that in linguistic gesture-based working memory, semantic aspects may outweigh phonological aspects when processing takes place under challenging conditions. The close association between working memory and language development should be taken into account in understanding and alleviating the challenges faced by deaf children growing up with cochlear implants as well as other clinical populations.
Technical Meeting on Grading of the Application of Management System Requirements. Presentations

International Nuclear Information System (INIS)

2012-01-01

The objectives of this Technical Meeting are threefold: - to share international experiences and lessons learned, as well as exchange views on best practices and strategies to overcome the difficulties encountered; - to review and discuss the draft technical report on 'Grading the Application of Management System Requirements, to allow the participants to contribute to the improvement of the document and to enrich it with practical examples; and - to strengthen the international networking of specialists in the field. The topics covered during the meeting will include: - Examples and case studies presented by participants from countries with nuclear facilities (mainly focused on NPPs, and, where appropriate, from research reactors, fuel cycle and waste management facilities) on grading the application of management system requirements and lessons learned. - Reviewing and improving the final draft of a technical report on 'Grading the Application of Management System Requirements', which will supersede the previous guidance: Grading of Quality Assurance Requirement: A Manual (Technical Reports Series No. 328)
Technical diagnostics of steam turbines

International Nuclear Information System (INIS)

Vlckova, B.; Drahy, J.

1987-01-01

This paper deals with practical experience in application of technical diagnostics methods to steam turbines, in particular using pedestal and shaft vibration measurements as well as estimation of bearing metal temperature and ultrasound emission signals. An estimation of effectiveness of the diagnostics methods used is given on the basis of experimental investigations made on a 30-MW turbine. (author)
Discussion on enterprise technical standard management work

International Nuclear Information System (INIS)

Li Xinyou

2010-01-01

The technical standard management is an important part of enterprise information work, also the basis of enterprise standardization work. Only by rational and orderly management, can it exert maximum effectiveness, provide reliable support for the production and business of enterprise. (author)
Quantitative X ray analysis system. User's manual and guide to X ray fluorescence technique

International Nuclear Information System (INIS)

2009-01-01

This guide covers trimmed and re-arranged version 3.6 of the Quantitative X ray Analysis System (QXAS) software package that includes the most frequently used methods of quantitative analysis. QXAS is a comprehensive quantitative analysis package that has been developed by the IAEA through research and technical contracts. Additional development has also been carried out in the IAEA Laboratories in Seibersdorf where QXAS was extensively tested. New in this version of the manual are the descriptions of the Voigt-profile peak fitting, the backscatter fundamental parameters' and emission-transmission methods of chemical composition analysis, an expanded chapter on the X ray fluorescence physics, and completely revised and increased number of practical examples of utilization of the QXAS software package. The analytical data accompanying this manual were collected in the IAEA Seibersdorf Laboratories in the years 2006/2007

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS
Standard Technical Specifications, Westinghouse Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation
Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS
CRISP instrument manual

International Nuclear Information System (INIS)

Bucknall, D.G.; Langridge, Sean

1997-05-01

This document is a user manual for CRISP, one of the two neutron reflectomers at ISIS. CRISP is highly automated allowing precision reproducible measurements. The manual provides detailed instructions for the setting-up and running of the instrument and advice on data analysis. (UK)
Salinas : theory manual.

Energy Technology Data Exchange (ETDEWEB)

Walsh, Timothy Francis; Reese, Garth M.; Bhardwaj, Manoj Kumar

2004-08-01

This manual describes the theory behind many of the constructs in Salinas. For a more detailed description of how to use Salinas , we refer the reader to Salinas, User's Notes. Many of the constructs in Salinas are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Salinas are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programer-notes manual, the user's notes and of course the material in the open literature.
PCs The Missing Manual

CERN Document Server

Karp, David

2005-01-01

Your vacuum comes with one. Even your blender comes with one. But your PC--something that costs a whole lot more and is likely to be used daily and for tasks of far greater importance and complexity--doesn't come with a printed manual. Thankfully, that's not a problem any longer: PCs: The Missing Manual explains everything you need to know about PCs, both inside and out, and how to keep them running smoothly and working the way you want them to work. A complete PC manual for both beginners and power users, PCs: The Missing Manual has something for everyone. PC novices will appreciate the una
The development of technical database of advanced spent fuel management process

Energy Technology Data Exchange (ETDEWEB)

Ro, Seung Gy; Byeon, Kee Hoh; Song, Dae Yong; Park, Seong Won; Shin, Young Jun

1999-03-01

The purpose of this study is to develop the technical database system to provide useful information to researchers who study on the back end nuclear fuel cycle. Technical database of advanced spent fuel management process was developed for a prototype system in 1997. In 1998, this database system is improved into multi-user systems and appended special database which is composed of thermochemical formation data and reaction data. In this report, the detailed specification of our system design is described and the operating methods are illustrated as a user's manual. Also, expanding current system, or interfacing between this system and other system, this report is very useful as a reference. (Author). 10 refs., 18 tabs., 46 fig.
The development of technical database of advanced spent fuel management process

International Nuclear Information System (INIS)

Ro, Seung Gy; Byeon, Kee Hoh; Song, Dae Yong; Park, Seong Won; Shin, Young Jun

1999-03-01

The purpose of this study is to develop the technical database system to provide useful information to researchers who study on the back end nuclear fuel cycle. Technical database of advanced spent fuel management process was developed for a prototype system in 1997. In 1998, this database system is improved into multi-user systems and appended special database which is composed of thermochemical formation data and reaction data. In this report, the detailed specification of our system design is described and the operating methods are illustrated as a user's manual. Also, expanding current system, or interfacing between this system and other system, this report is very useful as a reference. (Author). 10 refs., 18 tabs., 46 fig
Management of Chronic Lateral Epicondylitis With Manual Therapy and Local Cryostimulation: A Pilot Study.

Science.gov (United States)

Richer, Nadia; Marchand, Andrée-Anne; Descarreaux, Martin

2017-12-01

The purpose of this pilot study was to evaluate the feasibility and efficacy of adding cryostimulation to manual therapy in patients with chronic lateral epicondylitis. The control group (n = 19) was treated with manual therapy consisting of soft-tissue therapy and radial head mobilizations. The experimental group (n = 18) received cryostimulation in addition to manual therapy care similar to that for the control group. Both protocols consisted of 8 treatments over a 4-week period. Outcome measures included pain intensity (visual analog scale), pain-free grip strength (handheld dynamometer), and functional index (Patient-Rated Tennis Elbow Evaluation questionnaire). Assessments were performed at baseline, postintervention, and 3-month follow-up. Adherence and dropout rates were also considered. Both groups exhibited significant improvements in pain intensity and functional index at postintervention assessments, which were maintained at follow-up. All participants attended the prescribed number of treatments, but 27% were lost at follow-up. Minor adverse events were reported after cryostimulation in 4 cases. This study indicated that it is feasible to complete a clinical trial evaluating the efficacy of adding cryostimulation to manual therapy in patients with chronic lateral epicondylitis. On the basis of these preliminary data, the combination of cryostimulation and manual therapy care did not provide any additional benefits in both the short term and the long term. Manual myofascial point treatment and mobilization techniques yielded positive outcomes in chronic lateral epicondylitis. Further studies should focus on the sole therapeutic effect of cryostimulation in both patients with acute and those with chronic conditions.
Savannah River Plant 200 Area technical manual. Part SP. Processing of Np/sup 237/ and Pu/sup 238/

Energy Technology Data Exchange (ETDEWEB)

Hill, A.J. (comp.)

1963-01-03

This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and purification of Np/sup 237/ and Pu/sup 238/, the finishing of Np, the preparation of NpO/sub 2/, the disposal of spent resin, and the safety aspects of the handling of hydrazine. The section on the fabrication of NpO/sub 2/-Al slugs will be added later. 76 refs., 22 figs.
Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS
The technical need for food irradiation as a basis for approval

International Nuclear Information System (INIS)

Boegl, K.W.; Dehne, L.I.; Helle, N.; Schreiber, G.A.; Schuettler, C.; Zagon, J.

1992-01-01

The contribution deals with the development of legal regulations concerning irradiated food and the discussions during the last 35 years about the technical need, the different points of view about health consequences, and the behaviour and expectations of consumers. The attitudes of the German Research Society, the Federal Health Office, of Federal Parliament and Federal Council, of the Federal Government and of the governments of the states, and of international organizations are discussed in the light of three factors: - is there any need for action, - political determination, and - change of implementation. Legal restrictions and consumer behaviour may influence developments in the field of alternative techniques. To what extent is, exemplified by spices and dried vegetables. (orig.) [de
Proceedings: EPRI Workshop 2 -- Technical basis for EPA HLW disposal criteria

International Nuclear Information System (INIS)

Rogers, V.

1993-03-01

The Electric Power Research Institute (EPRI) sponsored this workshop to address the scientific and technical issues underlying the regulatory criteria, or standard, for the disposal of spent nuclear fuel, high-level radioactive waste, and transuranic waste, commonly referred to collectively as high-level waste (HLW). These regulatory criteria were originally promulgated by the US Environmental Protection Agency (EPA) in 40 CFR Part 191 in 1985. However, significant portions of the regulation were remanded by the Ninth Circuit Court of Appeals in 1987. This is the second of two workshops. Topics discussed include: gas pathway; individual and groundwater protection; human intrusion; population protection; performance; TRU conversion factors and discussions. Individual projects re processed separately for the databases
Manual on restoration strategies for radioactive-contaminated sites. RESTRAT-TD 14

International Nuclear Information System (INIS)

Zeevaert, T.; Brendler, V.; Nordlinder, S.; Hedemann Jensen, P.; Bousher, A.

1999-06-01

This report is submitted as Technical Deliverable No. 14 against the requirements of the RESTRAT (Restoration Strategies for radioactively contaminated Sites and their Close Surroundings) Project. In this manual the methodology for ranking restoration options is explained and applied to example sites that are representative for major categories of contaminated sites. Potentially relevant techniques for restoration of contaminated sites are identified and characterised and the data collected included on a CD-ROM. For the ranking of the restoration options, a multi-attribute utility (MAU) type of analysis has been chosen with a view to the various categories of attributes that are being taken into account: radiological health detriment; economic costs; social factors. The methods of assessing the attributes and converting the attribute values into utility values for the scoring of the options are explained. The models applied for assessing the collective dose to the population and for the ranking of the remediation options (MAU analysis) are explained and the software included on two CD-ROMs added to the manual
Manual on restoration strategies for radioactive-contaminated sites. RESTRAT-TD 14

Energy Technology Data Exchange (ETDEWEB)

Zeevaert, T.; Brendler, V.; Nordlinder, S.; Hedemann Jensen, P.; Bousher, A

1999-06-01

This report is submitted as Technical Deliverable No. 14 against the requirements of the RESTRAT (Restoration Strategies for radioactively contaminated Sites and their Close Surroundings) Project. In this manual the methodology for ranking restoration options is explained and applied to example sites that are representative for major categories of contaminated sites. Potentially relevant techniques for restoration of contaminated sites are identified and characterised and the data collected included on a CD-ROM. For the ranking of the restoration options, a multi-attribute utility (MAU) type of analysis has been chosen with a view to the various categories of attributes that are being taken into account: radiological health detriment; economic costs; social factors. The methods of assessing the attributes and converting the attribute values into utility values for the scoring of the options are explained. The models applied for assessing the collective dose to the population and for the ranking of the remediation options (MAU analysis) are explained and the software included on two CD-ROMs added to the manual.
User's Manual for FEMOM3DR. Version 1.0

Science.gov (United States)

Reddy, C. J.

1998-01-01

FEMoM3DR is a computer code written in FORTRAN 77 to compute radiation characteristics of antennas on 3D body using combined Finite Element Method (FEM)/Method of Moments (MoM) technique. The code is written to handle different feeding structures like coaxial line, rectangular waveguide, and circular waveguide. This code uses the tetrahedral elements, with vector edge basis functions for FEM and triangular elements with roof-top basis functions for MoM. By virtue of FEM, this code can handle any arbitrary shaped three dimensional bodies with inhomogeneous lossy materials; and due to MoM the computational domain can be terminated in any arbitrary shape. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computers on which the code is intended to run.
Support for Astronaut's View of Mexican/ Central American Fires and on-Line Earth Observations Training Manual

Science.gov (United States)

Kaminski, Charles F., Jr.

1999-01-01

A small project to compile remote sensing and in-site data to review the processes leading to the May 1998 Mexican/Central American fires was undertaken. A web page based on this project was assembled. The second project initiated involved an interactive and on-line program that will replace the paper version of the Earth Observations Preflight Training Manual. Technical support was provided to Prof. Marvin Glasser as needed.
Eco-Innovation Manual

DEFF Research Database (Denmark)

O'Hare, Jamie Alexander; McAloone, Tim C.; Pigosso, Daniela Cristina Antelmi

Aim of this manual is to introduce a methodology for the implementation of eco‐innovation within small and medium sized companies in developing and emerging economies. The intended audience of this manual is organizations that provide professional services to guide and support manufacturing compa...... companies to improve their sustainability performance....
PERANCANGAN DAN PEMBUATAN APLIKASI ERD GENERATOR NOTASI ORM DARI SKRIP BASIS DATA ORACLE BERBASIS J2EE

Directory of Open Access Journals (Sweden)

Leo Willyanto Santoso

2004-01-01

Full Text Available The existing of database processing is needed by many institutions and companies. Database is not only to get information faster, it is also enlarging their service to customer. For companies, this advantage can increase competency. Because of this reason, many companies using manual processing turn to database. As mentioned above, database reverse engineering process has became a necessity for database developers to understand the structure of any databases. Commonly, this structure is modeled in some notations of Entity Relationships Diagram (ERD. The graphical visualization of database structure in an ERD can use many notations, so it is easy to understand. One of the approaches, which are easy to understand, is Object Role Modeling (ORM diagram. By reverse engineering the mapping process to relation schema of a database, ERD generation from a data definition language script of Oracle can be done. For more flexibility, this application is constructed web based with Servlets technology that is propertied by JavaTM 2 SDK. Abstract in Bahasa Indonesia : Kehadiran pemrosesan basis data diperlukan oleh berbagai institusi dan perusahaan. Basis data tidak hanya mempercepat pemerolehan informasi, tetapi juga dapat meningkatkan pelayanan kepada pelanggan. Bagi perusahaan, keuntungan seperti ini dapat meningkatkan daya saingnya terhadap perusahaan lain. Hal ini pulalah yang mendorong banyak perusahaan yang menggunakan pemrosesan manual mulai beralih memanfaatkan basis data. Sejalan dengan hal di atas, proses reverse engineering terhadap suatu basis data menjadi suatu kebutuhan bagi perancang basis data untuk mengetahui struktur dari sebuah basis data. Struktur tersebut biasanya dimodelkan dalam bentuk Entity Relationships Diagram (ERD. Penggambaran struktur basis data dalam sebuah ERD dapat menggunakan berbagai notasi agar menjadi lebih mudah dimengerti. Salah satu notasi yang pendekatannya mudah dipahami adalah notasi Object Role Modeling (ORM diagram
Using communication norms in socio-technical systems

NARCIS (Netherlands)

Weigand, H.; Whitworth, B.; de Moor, A.

2009-01-01

Often socio-technical systems are designed simply on the basis of what the user asks, and without considering explicitly whether the required process structure is right and wrong. However, poor communication may cause many problems. Therefore, a design cycle should always include diagnosis, and in

Chinese biogas manual: popularising technology in the countryside

Energy Technology Data Exchange (ETDEWEB)

van Buren, A [ed.

1979-01-01

The production of biogas from agricultural, human, and animal wastes in rural areas of China is described. This manual is one of the Science in the Countryside Editions, which are specially designed to popularise technology. It pre-supposes as little technical education as possible, relying instead on the appendix to provide basic principles; it contains minute and graphic textual explanations of how to go about drawing a plan, laying foundations, or applying mortar in paper-thin coats. As far as possible, the book is intended to short-cut the trial and errors that people in Sichuan had to go through while experimenting. it also tries to give the reader an idea of what is going on out of sight in the working digester, so that the technology becomes intelligible and so that it can be used to its full potential. Biogas tanks are financed and built by the brigade, the team, or individual families, depending on size. The details of how this is done depends on local circumstances. The allocation of responsibility of maintenance, repair and operation is essential to the success of a biogas programme. Every pit has a pressure gauge and each family has been carefully instructed when to let out gas. Feeding material into the pit is a continuous process with guidelines for the proportion of liquids to solids. The key to their success lies in the core of experts in the Biogas Group, whose job it is to go from team to team helping with repair and reminding people to maintain the safety standards. Perhaps the most interesting and startling lessons-which are relevant not only to biogas but also to other areas of technical innovation in rural areas-can be learnt from the success recorded here that local communities have had in assimilating and adapting the technology to their own needs and conditions. This manual is the single, standard textbook used by the Chinese when embarking on biogas projects.
Chinese biogas manual: popularising technology in the countryside

Energy Technology Data Exchange (ETDEWEB)

Van Buren, A [ed.

1979-01-01

The production of biogas from agricultural, human, and animal wastes in rural areas of China is described. This manual is one of the Science in the Countryside Editions, which are specially designed to popularise technology. It pre-supposes as little technical education as possible, relying instead on the appendix to provide basic principles; it contains minute and graphic textual explantations of how to go about drawing a plan, laying foundations, or applying mortar in paper-thin coats. As far as possible, the book is intended to short-cut the trial and errors that people in Sichuan had to go through while experimenting. It also tries to give the reader an idea of what is going on out of sight in the working digester, so that the technology becomes intelligible and so that it can be used to its full potential. Biogas tanks are financed and built by the brigade, the team, or individual families, depending on size. The details of how this is done depends on local circumstances. The allocation of responsibility of maintenance, repair and operation is essential to the success of a biogas programme. Every pit has a pressure gauge and each family has been carefully instructed when to let out gas. Feeding material into the pit is a continuous process with guidelines for the proportion of liquids to solids. The key to their success lies in the core of experts in the Biogas Group, whose job it is to go from team to team helping with repair and reminding people to maintain the safety standards. Perhaps the most interesting and startling lessons-which are relevant not only to biogas but also to other areas of technical innovation in rural areas-can be learned from the success recorded here that local communities have had in assimilating and adapting the technology to their own needs and conditions. This manual is the single, standard textbook used by the Chinese when embarking on biogas projects.
Customisation of an instrument to assess anaesthesiologists' non-technical skills.

Science.gov (United States)

Jepsen, Rikke M H G; Spanager, Lene; Lyk-Jensen, Helle T; Dieckmann, Peter; Østergaard, Doris

2015-02-22

The objectives of the study were to identify Danish anaesthesiologists' non-technical skills and to customise the Scottish-developed Anaesthetists' Non-Technical Skills instrument for Danish anaesthesiologists. Six semi-structured group interviews were conducted with 31 operating room team members: anaes-thesiologists, nurse anaesthetists, surgeons, and scrub nurses. Interviews were transcribed verbatim and analysed using directed content analysis. Anaesthesiologists' non-technical skills were identified, coded, and sorted using the original instrument as a basis. The resulting prototype instrument was discussed with anaesthesiologists from 17 centres to ensure face validity. Interviews lasted 46-67 minutes. Identified examples of anaesthesiologists' good or poor non-technical skills fit the four categories in the original instrument: situation awareness; decision making; team working; and task management. Anaesthesiologists' leadership role in the operating room was emphasised: the original 'Task Management' category was named 'Leadership'. One new element, 'Demonstrating self-awareness' was added under the category 'Situation Awareness'. Compared with the original instrument, half of the behavioural markers were new, which reflected that being aware of and communicating one's own abilities to the team; working systematically; and speaking up to avoid adverse events were important skills. The Anaesthetists' Non-Technical Skills instrument was customised to a Danish setting using the identified non-technical skills for anaesthesiologists and the original instrument as basis. The customised instrument comprises four categories and 16 underpinning elements supported by multiple behavioural markers. Identifying non-technical skills through semi-structured group interviews and analysing them using direct content analysis proved a useful method for customising an assessment instrument to another setting.
Technical issues for WIPP

International Nuclear Information System (INIS)

Hunter, T.O.

1979-01-01

Emplacement of wastes in the WIPP will include experiments on various waste types which will provide essential data on waste-rock interaction and repository response. These experiments will include evolution of the synergistic effects of both heat production, radiation, and actual waste forms. While these studies will provide essential data on the validity of waste isolation in bedded salt, they will be preceded by a broad-based experimental program which will resolve many of the current technical issues providing not only an assessment of the safety of performing such experiments but also the technical basis for assurance that the appropriate experiments are performed. Data and predictive modeling techniques, which are currently available, can bound the consequences associated with these technical issues. Predictions of the impact on public safety based on these analyses indicate that safe waste disposal in WIPP salt beds is achievable; however, a major use of WIPP will be to conduct realistic experiments with HLW forms to address some of the unresolved details of these waste/salt interactions
Facilitating awareness of philosophy of science, ethics and communication through manual skills training in undergraduate education.

Science.gov (United States)

Kordahl, Hilde Lund; Fougner, Marit

2017-03-01

Professional health science education includes a common theoretical basis concerning the theory of science, ethics and communication. Former evaluations by first-year students of the bachelor physiotherapy program at Oslo and Akershus University College of Applied Sciences (HiOA) show that they find it hard to understand the relation between these particular topics and future professional practice. This challenge is the starting point for a pedagogical development project that aims to develop learning contexts that highlight the relevance of these theoretical concepts. The aim of the study is to explore and present findings on the value of using Sykegrep manual skills classes as an arena in which students can be encouraged to think about, reflect on and appreciate the role and value of the philosophical perspectives that inform their practice and contributes to practise knowledge. A qualitative study with data collection through focus groups was performed and analyzed using thematic content analysis. Eighteen first-year undergraduate students, who had completed the manual skills course, participated in the study. Analysis of the data yielded three categories of findings that can be associated with aspects of philosophy of science, ethics and communication. These are as follows: 1) preconceived understanding of physiotherapy; 2) body knowledge perspectives; and 3) relational aspects of interactions. Undergraduate students' understanding and experience of philosophy of science, ethics and communication may be facilitated by peer collaboration, reflection on intimacy and touch and the ethical aspects of interaction during manual skills training. Practical classes in Sykegrep provide a basis for students' discussions about the body as well as their experiences with the body in the collaborative learning context. The students' reflections on their expectations of manual skills in physiotherapy and experiences of touch and being touched can facilitate an awareness of
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)
Survey of a technology to introduce the waste-fueled power generation. Basic manual for introduction of the waste-fueled power generation; Haikibutsu hatsuden donyu gijutsu chosa. Haikibutsu hatsuden donyu kihon manual

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

Local government offices, etc., which are expected to shoulder responsibility for introducing the waste-fueled power generation, want to need exact information on technical information concerning the waste-fueled power generation and the method to materialize the introduction plan, etc. Therefore, Electric Power Development Co. surveyed and studied it under the contract with NEDO. The results were collected together as a basic manual for introduction of the waste-fueled power generation. As an outline of the waste-fueled power generation, the manual explains the significance, the present situation and potentials, the waste-fueled power system, an outline of working out the waste-fueled power generation plan, an outline of construction and operation/maintenance of the waste-fueled power generation, an outline of various systems relating to the waste-fueled power generation, etc. As the items for the study of making a concrete plan for power generation equipment, the manual explains the amount of refuse to be incinerated, the present status of generation capacity as viewed from the quality of refuse, the quality of refuse and the design of power generation equipment, boiler efficiency, power generation efficiency, construction cost and operation cost, etc. In addition, the paper describes a case study of the waste-fueled power generation plan. 118 figs., 39 tabs.
Program management system manual

International Nuclear Information System (INIS)

1989-08-01

OCRWM has developed a program management system (PMS) to assist in organizing, planning, directing and controlling the Civilian Radioactive Waste Management Program. A well defined management system is necessary because: (1) the Program is a complex technical undertaking with a large number of participants, (2) the disposal and storage facilities to be developed by the Program must be licensed by the Nuclear Regulatory Commission (NRC) and hence are subject to rigorous quality assurance (QA) requirements, (3) the legislation mandating the Program creates a dichotomy between demanding schedules of performance and a requirement for close and continuous consultation and cooperation with external entities, (4) the various elements of the Program must be managed as parts of an integrated waste management system, (5) the Program has an estimated total system life cycle cost of over $30 billion, and (6) the Program has a unique fiduciary responsibility to the owners and generators of the nuclear waste for controlling costs and minimizing the user fees paid into the Nuclear Waste Fund. This PMS Manual is designed and structured to facilitate strong, effective Program management by providing policies and requirements for organizing, planning, directing and controlling the major Program functions
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.
Technical Basis for Evaluating Software-Related Common-Cause Failures

Energy Technology Data Exchange (ETDEWEB)

Muhlheim, Michael David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard [Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-04-01

The instrumentation and control (I&C) system architecture at a nuclear power plant (NPP) incorporates protections against common-cause failures (CCFs) through the use of diversity and defense-in-depth. Even for well-established analog-based I&C system designs, the potential for CCFs of multiple systems (or redundancies within a system) constitutes a credible threat to defeating the defense-in-depth provisions within the I&C system architectures. The integration of digital technologies into the I&C systems provides many advantages compared to the aging analog systems with respect to reliability, maintenance, operability, and cost effectiveness. However, maintaining the diversity and defense-in-depth for both the hardware and software within the digital system is challenging. In fact, the introduction of digital technologies may actually increase the potential for CCF vulnerabilities because of the introduction of undetected systematic faults. These systematic faults are defined as a “design fault located in a software component” and at a high level, are predominately the result of (1) errors in the requirement specification, (2) inadequate provisions to account for design limits (e.g., environmental stress), or (3) technical faults incorporated in the internal system (or architectural) design or implementation. Other technology-neutral CCF concerns include hardware design errors, equipment qualification deficiencies, installation or maintenance errors, instrument loop scaling and setpoint mistakes.
Preventive maintenance basis: Volume 1 -- Air-operated valves. Final report

International Nuclear Information System (INIS)

Worledge, D.; Hinchcliffe, G.

1997-07-01

US nuclear plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This report provides an overview of the PM Basis project and describes use of the PM Basis database. This document provides a program of PM tasks suitable for application to Air Operated Valves (AOV's) in nuclear power plants. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used, in conjunction with material from other sources, to develop a complete PM program or to improve an existing program. Users of this information will be utility managers, supervisors, craft technicians, and training instructors responsible for developing, optimizing, or fine-tuning PM programs
Standard Technical Specifications, Babcock and Wilcox Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations
Technical modifications and management innovations in exporting nuclear reactor projects

International Nuclear Information System (INIS)

Mao Xiaoming; Qin Xijiu; Ding Hu; Xue Zhaoqun; Wen Shengjun

2009-01-01

As a main channel for the foreign economic cooperation of China nuclear industry, China Zhongyuan Engineering Corporation (CZEC) has been constantly engaged in technical modifications and management innovations in its exporting nuclear reactor projects. In the implementation of heavy water research reactor contract in Algeria, CZEC had established a complete and adequate design standards system in compliance with the international standards, and made significant modifications to the reference reactor in the aspects of reactor power and reactor safety, solved quite some technical issues which-affected the reactor technical performance. The modifications and improvements enabled the technical parameters, safety features, reactor multipurpose application to attain to the advanced level in the world. In the 300 MWe PWR NPPs in Pakistan, safety features had been updated in line with upgrading regulatory requisites. The design philosophy and technology application demonstrated CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC in promoting China made equipment items and components exportation. (authors)
Multi-Cultural Competency-Based Vocational Curricula. Automotive Mechanics. Multi-Cultural Competency-Based Vocational/Technical Curricula Series.

Science.gov (United States)

Hepburn, Larry; Shin, Masako

This document, one of eight in a multi-cultural competency-based vocational/technical curricula series, is on automotive mechanics. This program is designed to run 36 weeks and cover 10 instructional areas: the engine; drive trains--rear ends/drive shafts/manual transmission; carburetor; emission; ignition/tune-up; charging and starting;…
Working Memory for Linguistic and Non-linguistic Manual Gestures: Evidence, Theory, and Application

Directory of Open Access Journals (Sweden)

Mary Rudner

2018-05-01

Full Text Available Linguistic manual gestures are the basis of sign languages used by deaf individuals. Working memory and language processing are intimately connected and thus when language is gesture-based, it is important to understand related working memory mechanisms. This article reviews work on working memory for linguistic and non-linguistic manual gestures and discusses theoretical and applied implications. Empirical evidence shows that there are effects of load and stimulus degradation on working memory for manual gestures. These effects are similar to those found for working memory for speech-based language. Further, there are effects of pre-existing linguistic representation that are partially similar across language modalities. But above all, deaf signers score higher than hearing non-signers on an n-back task with sign-based stimuli, irrespective of their semantic and phonological content, but not with non-linguistic manual actions. This pattern may be partially explained by recent findings relating to cross-modal plasticity in deaf individuals. It suggests that in linguistic gesture-based working memory, semantic aspects may outweigh phonological aspects when processing takes place under challenging conditions. The close association between working memory and language development should be taken into account in understanding and alleviating the challenges faced by deaf children growing up with cochlear implants as well as other clinical populations.
Significance of technical rules for environmental pollution control

International Nuclear Information System (INIS)

Grefen, K.

1989-01-01

Technical rules for environmental pollution control are very important in times of intensified technical progress and especially in view of the alterations of the legislative basis of the European Market in 1992. In the fields of jurisprudence, science and technology they serve as a decision-making aid for authorities, specialists in plant development and operation and the preparatory stages of international legislation. The topic is explained by the development of guidelines with the VDI-Commission on Air Pollution Prevention. (orig.) [de
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
Estimation of regulated term of technical systems further operation

International Nuclear Information System (INIS)

Strel'nikov, V.P.

2008-01-01

The technique of estimating the regulated term of technical systems further operation on the basis of data on failures during operation and use of probabilistic-physical model of failures (DN-distribution) is proposed
Manual of plant producers and services in environmental protection. Database in the field of environmental protection

International Nuclear Information System (INIS)

Serve, C.

1992-01-01

On the basis of an enquiry, the Stuttgart Chamber of Industry and Commerce produced a database of the services offered by regional and supraregional companies in the field of environmental protection. The data are presented in this manual, classified as follows: noise protection systems; sanitation systems and services; other systems and services. (orig.) [de
The technical bases for government emergency plans

International Nuclear Information System (INIS)

Champion, D.; Herviou, K.

2006-01-01

Despite technical and organisational existing arrangements to prevent human and equipment failures, the occurrence of a severe accident inducing an important release of radioactive or toxic products could not be totally excluded. Public authorities are responsible for the development of emergency plans which main objective is the protection of the population in case of accident. The efficiency of emergency plans assumes they have been established before the occurrence of any accident, taking into account specificities of the installation and its environment. On the basis of the list of possible events likely to induce releases into the environment, some 'envelope' scenarios are selected and their consequences are assessed- The comparison of the consequences to reference levels for which protective actions are recommended gives the area where actions may be required. This approach is applied for the different nuclear facilities in France. Examples are given in the article on the definition of emergency plans technical basis for nuclear power plants, other nuclear facilities and transportation of radioactive materials. (authors)

Manual on high energy teletherapy. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to high energy radiotherapy: its application and procedures guides
[Personal emergency call system based on human vital and system technical parameters in a Smart Home environment].

Science.gov (United States)

Hampicke, M; Schadow, B; Rossdeutscher, W; Fellbaum, K; Boenick, U

2002-11-01

Progress in microtechnology and radio transmission technology has enabled the development of highly reliable emergency-call systems. The present article describes systems that have been specially designed to improve the safety and independence of handicapped and elderly persons living at home. For such persons immediate help in an emergency situation is of crucial importance. The technical state of the art of emergency-call systems specially developed for use by the elderly, is briefly discussed, in particular the well-known radio emergency-call button, with the aid of which an alarm can be activated manually. This system, however, does not offer adequate safety in all emergency situations. Alternative or complementary systems designed to automatically trigger an alarm on the basis of the recording and evaluation of so-called vital parameters, are therefore proposed. In addition, in a smart-home environment with networked devices, further parameters--so-called environment parameters can be used. It is found that the identification of an emergency situation becomes more reliable as the number of parameters employed increases.
User Manuals for a Primary Care Electronic Medical Record System: A Mixed Methods Study of User- and Vendor-Generated Documents.

Science.gov (United States)

Shachak, Aviv; Dow, Rustam; Barnsley, Jan; Tu, Karen; Domb, Sharon; Jadad, Alejandro R; Lemieux-Charles, Louise

2013-06-04

Tutorials and user manuals are important forms of impersonal support for using software applications including electronic medical records (EMRs). Differences between user- and vendor documentation may indicate support needs, which are not sufficiently addressed by the official documentation, and reveal new elements that may inform the design of tutorials and user manuals. What are the differences between user-generated tutorials and manuals for an EMR and the official user manual from the software vendor? Effective design of tutorials and user manuals requires careful packaging of information, balance between declarative and procedural texts, an action and task-oriented approach, support for error recognition and recovery, and effective use of visual elements. No previous research compared these elements between formal and informal documents. We conducted an mixed methods study. Seven tutorials and two manuals for an EMR were collected from three family health teams and compared with the official user manual from the software vendor. Documents were qualitatively analyzed using a framework analysis approach in relation to the principles of technical documentation described above. Subsets of the data were quantitatively analyzed using cross-tabulation to compare the types of error information and visual cues in screen captures between user- and vendor-generated manuals. The user-developed tutorials and manuals differed from the vendor-developed manual in that they contained mostly procedural and not declarative information; were customized to the specific workflow, user roles, and patient characteristics; contained more error information related to work processes than to software usage; and used explicit visual cues on screen captures to help users identify window elements. These findings imply that to support EMR implementation, tutorials and manuals need to be customized and adapted to specific organizational contexts and workflows. The main limitation of the study
User Manuals for a Primary Care Electronic Medical Record System: A Mixed Methods Study of User- and Vendor-Generated Documents

Science.gov (United States)

Dow, Rustam; Barnsley, Jan; Tu, Karen; Domb, Sharon; Jadad, Alejandro R.; Lemieux-Charles, Louise

2015-01-01

Research problem Tutorials and user manuals are important forms of impersonal support for using software applications including electronic medical records (EMRs). Differences between user- and vendor documentation may indicate support needs, which are not sufficiently addressed by the official documentation, and reveal new elements that may inform the design of tutorials and user manuals. Research question What are the differences between user-generated tutorials and manuals for an EMR and the official user manual from the software vendor? Literature review Effective design of tutorials and user manuals requires careful packaging of information, balance between declarative and procedural texts, an action and task-oriented approach, support for error recognition and recovery, and effective use of visual elements. No previous research compared these elements between formal and informal documents. Methodology We conducted an mixed methods study. Seven tutorials and two manuals for an EMR were collected from three family health teams and compared with the official user manual from the software vendor. Documents were qualitatively analyzed using a framework analysis approach in relation to the principles of technical documentation described above. Subsets of the data were quantitatively analyzed using cross-tabulation to compare the types of error information and visual cues in screen captures between user- and vendor-generated manuals. Results and discussion The user-developed tutorials and manuals differed from the vendor-developed manual in that they contained mostly procedural and not declarative information; were customized to the specific workflow, user roles, and patient characteristics; contained more error information related to work processes than to software usage; and used explicit visual cues on screen captures to help users identify window elements. These findings imply that to support EMR implementation, tutorials and manuals need to be customized and
Electric utility engineer`s FGD manual -- Volume 1: FGD process design. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-04

Part 1 of the Electric Utility Engineer`s Flue Gas Desulfurization (FGD) Manual emphasizes the chemical and physical processes that form the basis for design and operation of lime- and limestone-based FGD systems applied to coal- or oil-fired steam electric generating stations. The objectives of Part 1 are: to provide a description of the chemical and physical design basis for lime- and limestone-based wet FGD systems; to identify and discuss the various process design parameters and process options that must be considered in developing a specification for a new FGD system; and to provide utility engineers with process knowledge useful for operating and optimizing a lime- or limestone-based wet FGD system.
User's manual for CBS3DS, version 1.0

Science.gov (United States)

Reddy, C. J.; Deshpande, M. D.

1995-10-01

CBS3DS is a computer code written in FORTRAN 77 to compute the backscattering radar cross section of cavity backed apertures in infinite ground plane and slots in thick infinite ground plane. CBS3DS implements the hybrid Finite Element Method (FEM) and Method of Moments (MoM) techniques. This code uses the tetrahedral elements, with vector edge basis functions for FEM in the volume of the cavity/slot and the triangular elements with the basis functions for MoM at the apertures. By virtue of FEM, this code can handle any arbitrarily shaped three-dimensional cavities filled with inhomogeneous lossy materials; due to MoM, the apertures can be of any arbitrary shape. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computer the code is intended to run.
Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

International Nuclear Information System (INIS)

Lee, D.W.; Shingleton, K.L.

1996-01-01

Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated
IS MANUAL THERAPY A RATIONAL APPROACH TO IMPROVING HEALTH-RELATED QUALITY OF LIFE IN PEOPLE WITH ARTHRITIS?

Science.gov (United States)

Cameron, Melainie

2002-01-01

Background: People with arthritic disease are advised to participate in gentle exercise on a regular basis, and pursue long-term medication regimes. Alternative therapies are also used by people with arthritis, and may sometimes be recommended by rheumatologists and other medical personnel. Alternative therapies may be divided into two types: active therapies, in which the patient takes a driving role, and passive therapies, in which the therapy cannot proceed unless driven by a therapist. Objective: To review the effectiveness of manual therapy in improving the health-related quality of life (HRQOL) of people with two common arthritis conditions: Osteoarthritis and rheumatoid arthritis. Discussion: Massage, and other passive (practitioner-driven) manual therapies, have been anecdotally reported to improve health-related quality of life (HRQOL) in people with arthritis. Many manual therapists consult with patients who have arthritic diseases, receive referrals from rheumatologists, and consider the arthritic diseases to be within their field of practise. Although there is empirical evidence that manual therapy with some types of arthritis is beneficial, the level of effectiveness however is under-researched. Medical authorities are reluctant to endorse manual therapies for arthritis due to a lack of scientific evidence demonstrating efficacy, safety, and cost effectiveness. PMID:17987169
EML procedures manual

International Nuclear Information System (INIS)

Volchok, H.L.; de Planque, G.

1982-01-01

This manual contains the procedures that are used currently by the Environmental Measurements Laboratory of the US Department of Energy. In addition a number of analytical methods from other laboratories have been included. These were tested for reliability at the Battelle, Pacific Northwest Laboratory under contract with the Division of Biomedical and Environmental Research of the AEC. These methods are clearly distinguished. The manual is prepared in loose leaf form to facilitate revision of the procedures and inclusion of additional procedures or data sheets. Anyone receiving the manual through EML should receive this additional material automatically. The contents are as follows: (1) general; (2) sampling; (3) field measurements; (4) general analytical chemistry; (5) chemical procedures; (6) data section; (7) specifications
Partners Plus: Families and Caregivers in Partnerships. A Family-Centered Guide to Respite Care. Trainer's Workshop Manual [and] Community Planning Manual [and] A Family Manual [and] Caregiver Manual.

Science.gov (United States)

Ownby, Lisa L.; Hooke, Amanda C.; Moore, Dee Wylie; Garland, Corinne W.; Frank, Adrienne

Four manuals on implementing the Partners Respite Model, which provides respite care for children with disabilities or chronic illnesses, comprise this document. The Community Planning Manual offers a step-by-step guide to replication of the Partners Respite Model and is divided into sections on developing the Partners program, implementing the…
LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User's manual

International Nuclear Information System (INIS)

McFadden, J.G.

1998-01-01

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user's manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document
Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS
Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M
Demand of authorization to create the 'Flamanville 3' Basis Nuclear Installation. Synthesis report of the technical examination

International Nuclear Information System (INIS)

2007-02-01

The present report has for objective to present to the College of Asn a synthesis of the technical instruction piloted by the services of Asn and realized by their technical supports (I.R.S.N., G.P.R., S.P.N.) during the period 2001-2006. After a reminder of the conditions of the examination of the safety options of the project EPR made between 1993 and 2000, this report explains the progress and the modalities of the instruction realized from 2001 till 2006. It draws up then, besides a notice of the Asn services at request of creation authorization, a synthesis of the technical examination realized according to axes presented on the fig 1. Finally, it presents the main lines of the examination that it would stay to realize if the creation authorization was delivered. (N.C.)
Technical bid evaluation

International Nuclear Information System (INIS)

Bruchhausen, E. v.

1975-01-01

It is shown which kind of problems arise for the owners of the project and what is the recommendable method of approach. A detailed description of the necessary working team, information in delegation of work and tasks of procedure, criteria of valuation and classification method. Examples of schemes are shown which are the basis of the technical bid evaluation: tables 'data of system/component' and 'scope of supply'. The procedure of normalization of the bids and of specifying the owners supplies are explained. The content of the final report is described. (HP) [de
The ISIS Open GENIE user manual

International Nuclear Information System (INIS)

Akeroyd, F.A.; Ashworth, R.L.; Campbell, S.I.; Johnston, S.D.; Martin, J.M.; Moreton-Smith, C.M.; Sivia, D.S.

2000-01-01

This manual should enable you to become familiar with Open GENIE quickly and easily. It therefore complements the Open GENIE Reference Manual which should be used to understand the full meaning of Open GENIE commands. The reference manual is accessible on the ISIS web server at: http://www.isis.rl.ac.uk/GENIEReferenceManual/ and the user manual is planned to be accessible by January '98 at http://www.isis.rl.ac.ukIGENIEUserManual/. The Open GENIE User Manual is separated into two parts: Part A. The User Manual. An introduction to the use of Open GENIE. Part B. The Installation Guide. General information on how to install and run Open GENIE. Assuming that you are new to Open GENIE and have just downloaded a copy you will need to consult the Installation Guide to get Open GENIE installed on your machine. After this we recommend you experiment with some of the example files to get an idea of the capabilities of Open GENIE. For further information, comments, additions of routines that you feel should be included, please contact us at genie at isise.rl.ac.uk
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.
Frontoparietal Tracts Linked to Lateralized Hand Preference and Manual Specialization.

Science.gov (United States)

Howells, Henrietta; Thiebaut de Schotten, Michel; Dell'Acqua, Flavio; Beyh, Ahmad; Zappalà, Giuseppe; Leslie, Anoushka; Simmons, Andrew; Murphy, Declan G; Catani, Marco

2018-04-21

Humans show a preference for using the right hand over the left for tasks and activities of everyday life. While experimental work in non-human primates has identified the neural systems responsible for reaching and grasping, the neural basis of lateralized motor behavior in humans remains elusive. The advent of diffusion imaging tractography for studying connectional anatomy in the living human brain provides the possibility of understanding the relationship between hemispheric asymmetry, hand preference, and manual specialization. In this study, diffusion tractography was used to demonstrate an interaction between hand preference and the asymmetry of frontoparietal tracts, specifically the dorsal branch of the superior longitudinal fasciculus, responsible for visuospatial integration and motor planning. This is in contrast to the corticospinal tract and the superior cerebellar peduncle, for which asymmetry was not related to hand preference. Asymmetry of the dorsal frontoparietal tract was also highly correlated with the degree of lateralization in tasks requiring visuospatial integration and fine motor control. These results suggest a common anatomical substrate for hand preference and lateralized manual specialization in frontoparietal tracts important for visuomotor processing.
Preventive maintenance basis: Volume 19 -- HVAC -- chillers and compressors. Final report

International Nuclear Information System (INIS)

Worledge, D.; Hinchcliffe, G.

1997-12-01

US nuclear power plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This document provides a program of preventive maintenance tasks suitable for application to HVAC -- Chillers and Compressors. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used in conjunction with material from other sources, to develop a complete PM program or to improve an existing program
The development of practice manual for LSC based on job analysis in radiation measurement and analysis

International Nuclear Information System (INIS)

Shin, W H; Park, T J

2017-01-01

Radiation technology is closely related to the industrial growth and the creation of employment in Korea. The techniques as radiation or/and radioactivity measurement, and the practical skills achieving a higher level analysis are required. In this study, practice manual for liquid scintillation counter were developed by job analysis. Raw data applied in job analysis are collected by on/off line survey by 420 workers employed in KOREA. Importance-priority analysis was performed to make duties and competency unit that consists of knowledge, skills as each task. Refined data was reviewed by expert who experienced actual duties on site. Classification was conducted by focus group interview to deduct duties and competency unit. From the radiation devices in measurement and analysis, liquid scintillation counter was preferentially selected because of the high demands for training. Investigation of build-up status to liquid scintillation counter in KOREA was conducted. Then technical specification and operating procedure of 2 main devices were analyzed and integrated by practice manual. Duties and competency unit were applied to integrated materials respectively. To validate effectiveness, test curriculum was designed by the advanced course to workers who engaged in radiation measurement and analysis. The developed manual is structured to take advantage of test training. This manual will be a practical handbook that can improve the knowledge, skills of radiation workers in Korea. (paper)

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