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Sample records for technical basis manual

  1. 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.

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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…

  13. 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...

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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

  20. 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.

  1. 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

  2. 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…

  3. 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

  4. 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

  5. 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…

  6. 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.

  7. 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...

  8. 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…

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. 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

  14. 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.

  15. 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

  16. 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…

  17. 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.

  18. 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

  19. 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…

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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.

  8. 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.

  9. 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

  10. 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.

  11. 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

  12. 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...

  13. 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...

  14. 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...

  15. 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)

  16. 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

  17. 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

  18. 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.

  19. 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.

  20. 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…

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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)

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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

  17. 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

  18. 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…

  19. 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.

  20. 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)

  1. 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

  2. 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…

  3. 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.

  4. 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.

  5. 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.

  6. 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

  7. 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...

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. 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

  15. 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.

  16. 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.

  17. 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.)

  18. 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

  19. 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.

  20. 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

  1. 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

  2. Technical basis of radiation therapy. Practical clinical applications. 5. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Levitt, Seymour H. [Karolinska Institutet Stockholm (Sweden). Dept. of Oncol-Pathol; Perez, Carlos A. [Washington Univ. Medical Center, St. Louis, MO (United States). Dept. of Radiation Oncology; Purdy, James A. [California Univ., Sacramento, CA (United States). Dept. of Radiation Oncology; Poortmans, Philip [Institute Verbeeten, Tilburg (Netherlands). Dept. of Radiation Oncology

    2012-07-01

    This well-received book, now in its fifth edition, is unique in providing a detailed description of the technological basis of radiation therapy. Another novel feature is the collaborative writing of the chapters by North American and European authors. This considerably broadens the book's perspective and increases its applicability in daily practice throughout the world. The book is divided into two sections. The first covers basic concepts in treatment planning, including essential physics and biological principles related to time-dose-fractionation, and explains the various technological approaches to radiation therapy, such as intensity-modulated radiation therapy, tomotherapy, stereotactic radiotherapy, and high and low dose rate brachytherapy. Issues relating to quality assurance, technology assessment, and cost-benefit analysis are also reviewed. The second part of the book discusses in depth the practical clinical applications of the different radiation therapy techniques in a wide range of cancer sites. All of the chapters have been written by leaders in the field. This book will serve to instruct and acquaint teachers, students, and practitioners in the various fields of oncology with the basic technological factors and approaches in radiation therapy. (orig.)

  3. 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

  4. 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

  5. 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

  6. 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, ...

  7. 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

  8. 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

  9. 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)

  10. 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)

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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...

  20. 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.

  1. 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

  2. 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.

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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)

  17. 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.

  18. 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

  19. 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.

  20. 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…

  1. Analysis and evaluation of the ASTEC model basis on plant simulations. 2. Technical report

    International Nuclear Information System (INIS)

    Koppers, Vera; Braehler, Thimo; Koch, Marco K.

    2015-06-01

    The present report is the 2 nd Technical Report of the research project ''Analysis and Evaluation of the ASTEC model basis'' funded by the Federal Ministry for Economic Affairs and Energy (BMWi 1501433) and conducted at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at Ruhr-Universitaet Bochum. Within this report, the quality of a nuclear power plant simulation with ASTEC is investigated. Different parameters are varied to analyze the simulation stability within the dataset, which describes a generic German Konvoi power plant and is deposit in the program set of ASTEC. Firstly, plant specifications in the data set are checked for plausibility. In addition, the compliance of the data set with the nodalization rules is verified. After that, the stationary phase, in which no accident is calculated, is analyzed and parametric studies are performed in the transient phase, focusing on the primary and secondary circuit as well as on the containment behavior. The performed calculations focusing the primary and secondary circuit indicate a high dependency of the simulation results on the user's input in the data set. There are significant deviations between each simulations results, for example in the different calculated point of time of the reactor pressure vessel failure. Already changes in the stationary phase cause a significantly earlier reactor pressure vessel failure compared to the simulation with the original data. Beyond that, the location of the leakage of the reactor pressure vessel lower head varied and therefore cannot be clearly determined, although there have been no changes by the user on the accident course. A reliable indication of the plant behavior under severe accident conditions is therefore difficult using ASTEC. The results of the parametric studies within the Containment show the same significant influence of certain parameter changes on the simulation results. By using the

  2. 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

  3. 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.

  4. 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.

  5. 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

  6. 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.

  7. 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.

  8. 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

  9. 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.

  10. 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

  11. 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)

  12. Development of non-destructive testing and technical diagnostics is a basis of safety

    International Nuclear Information System (INIS)

    Klyuev, V.V.

    1996-01-01

    It is evident that in the 21st century the diagnostics and inspection of quality will occupy a more significant area in solving safety problems. The corresponding inspection systems will become an inseparable part of the majority of installations in power engineering, engineering, metallurgy and other branches. On the other hand, the methods and means of nondestructive inspection and technical diagnostics are being converted together with modernization of the technological base, micro miniaturization, and will become more intellectualized and complex

  13. 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.

  14. 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

  15. A Technical Basis for Employing Facility Ventilation Air Exchange Rates in the Decision to Downpost

    CERN Document Server

    Mantooth, D S

    2001-01-01

    Utilizing the ventilation exchange rate as a basis for the decision to downpost a location within a facility from an airborne radiation area (ARA) based on initial air count(DAC). Not used in the case of a confirmed or suspected contamination release.

  16. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement. Refs, figs, tabs

  17. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    International Nuclear Information System (INIS)

    1998-01-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement

  18. 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

  19. 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

  20. Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual

    International Nuclear Information System (INIS)

    Jenkins, J.B.

    1996-01-01

    The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce maintenance costs. Ten prototype units have been built and tested. This report describes the design of the new NIM and the testing that took place to verify its acceptability

  1. 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

  2. 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

  3. Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations

    Energy Technology Data Exchange (ETDEWEB)

    Hugo, Jacques [Idaho National Lab. (INL), Idaho Falls, ID (United States); Forester, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gertman, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Medema, Heather [Idaho National Lab. (INL), Idaho Falls, ID (United States); Persensky, Julius [Idaho National Lab. (INL), Idaho Falls, ID (United States); Whaley, April [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-08-01

    This report presents preliminary research results from the investigation into the development of new models and guidance for Concepts of Operations in advanced small modular reactor (AdvSMR) designs. AdvSMRs are nuclear power plants (NPPs), but unlike conventional large NPPs that are constructed on site, AdvSMRs systems and components will be fabricated in a factory and then assembled on site. AdvSMRs will also use advanced digital instrumentation and control systems, and make greater use of automation. Some AdvSMR designs also propose to be operated in a multi-unit configuration with a single central control room as a way to be more cost-competitive with existing NPPs. These differences from conventional NPPs not only pose technical and operational challenges, but they will undoubtedly also have regulatory compliance implications, especially with respect to staffing requirements and safety standards.

  4. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  5. Reentry planning: The technical basis for offsite recovery following warfare agent contamination

    Energy Technology Data Exchange (ETDEWEB)

    Watson, A.P.; Munro, N.B.

    1990-04-01

    In the event on an unplanned release of chemical agent during any stage of Chemical Stockpile Disposal Program (CSDP), the potential exists for contamination of drinking water, forage crops, grains, garden produce and livestock. Persistent agents, such as VX or sulfur mustard, pose the greatest human health concern for reentry. The purpose of this technical support study is to provide information and analyses that can be used by federal, state and local emergency planners in determining the safety or reentry to, as well as the potential for recovery of, contaminated or suspect areas beyond the installation boundary. Guidelines for disposition of livestock, agricultural crops and personal/real property are summarized. Advisories for ingestion of food crops, water, meat and milk from the affected zones are proposed. This document does not address potential adverse effects to, or agent contamination of, wild species of plants or animals. 80 refs., 4 figs., 29 tabs.

  6. A technical basis for the flux corrected local conditions critical heat flux correlation

    International Nuclear Information System (INIS)

    Luxat, J.C.

    2008-01-01

    The so-called 'flux-corrected' local conditions CHF correlation was developed at Ontario Hydro in the 1980's and was demonstrated to successfully correlate the Onset of Intermittent Dryout (OID) CHF data for 37-element fuel with a downstream-skewed axial heat flux distribution. However, because the heat flux correction factor appeared to be an ad-hoc, albeit a successful modifying factor in the correlation, there was reluctance to accept the correlation more generally. This paper presents a thermalhydraulic basis, derived from two-phase flow considerations, that supports the appropriateness of the heat flux correction as a local effects modifying factor. (author)

  7. 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)

  8. The WIPP research and development program: providing the technical basis for defense waste disposal

    International Nuclear Information System (INIS)

    Hunter, Th.O.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

  9. 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.

  10. Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012

    Energy Technology Data Exchange (ETDEWEB)

    Nancy J. Lybeck; Vivek Agarwal; Binh T. Pham; Heather D. Medema; Kirk Fitzgerald

    2012-09-01

    The Light Water Reactor Sustainability program at Idaho National Laboratory (INL) is actively conducting research to develop and demonstrate online monitoring (OLM) capabilities for active components in existing Nuclear Power Plants. A pilot project is currently underway to apply OLM to Generator Step-Up Transformers (GSUs) and Emergency Diesel Generators (EDGs). INL and the Electric Power Research Institute (EPRI) are working jointly to implement the pilot project. The EPRI Fleet-Wide Prognostic and Health Management (FW-PHM) Software Suite will be used to implement monitoring in conjunction with utility partners: the Shearon Harris Nuclear Generating Station (owned by Duke Energy for GSUs, and Braidwood Generating Station (owned by Exelon Corporation) for EDGs. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for GSUs. GSUs are main transformers that are directly connected to generators, stepping up the voltage from the generator output voltage to the highest transmission voltages for supplying electricity to the transmission grid. Technical experts from Shearon Harris are assisting INL and EPRI in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the FW-PHM Software Suite and tested using data from Shearon-Harris. Parallel research on EDGs is being conducted, and will be reported in an interim report during the first quarter of fiscal year 2013.

  11. Technical basis for storage of Zircaloy-clad spent fuel in inert gases

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Gilbert, E.R.

    1983-09-01

    The technical bases to establish safe conditions for dry storage of Zircaloy-clad fuel are summarized. Dry storage of fuel with zirconium alloy cladding has been licensed in Canada, the Federal Republic of Germany, and Switzerland. Dry storage demonstrations, hot cell tests, and modeling have been conducted using Zircaloy-clad fuel. The demonstrations have included irradiated boiling water reactor, pressurized heavy-water reactor, and pressurized water reactor fuel assemblies. Irradiated fuel has been emplaced in and retrieved from metal casks, dry wells, silos, and a vault. Dry storage tests and demonstrations have involved about 15,000 fuel rods, and about 5600 rods have been monitored during dry storage in inert gases with maximum cladding temperatures ranging from 50 to 570 0 C. Although some tests and demonstrations are still in progress, there is currently no evidence that any rods exposed to inert gases have failed (one PWR rod exposed to an air cover gas failed at about 270 0 C). Based on this favorable experience, it is concluded that there is sufficient information on fuel rod behavior, storage conditions, and potential cladding failure mechanisms to support licensing of dry storage in the US. This licensing position includes a requirement for inert cover gases and a maximum cladding temperature guideline of 380 0 C for Zircaloy-clad fuel. Using an inert cover gas assures that even if fuel with cladding defects were placed in dry storage, or if defects develop during storage, the defects would not propagate. Tests and demonstrations involving Zircaloy-clad rods and assemblies with maximum cladding temperatures above 400 0 C are in progress. When the results from these tests have been evaluated, the viability of higher temperature limits should be examined. Acceptable conditions for storage in air and dry storage of consolidated fuel are issues yet to be resolved

  12. Technical Basis For Radiological Acceptance Criteria For Uranium At The Y-12 National Security Complex

    Energy Technology Data Exchange (ETDEWEB)

    Veinot, K. G.

    2009-07-22

    The purpose of this report is to establish radiological acceptance criteria for uranium. Other factors for acceptance not considered include criticality safety concerns, contaminants to the process stream, and impacts to the Safety Basis for the affected facilities. Three types of criteria were developed in this report. They include limits on external penetrating and non-penetrating radiation and on the internal hazard associated with inhalation of the material. These criteria are intended to alleviate the need for any special controls beyond what are normally utilized for worker protection from uranium hazards. Any proposed exceptions would require case-by-case evaluations to determine cost impacts and feasibility. Since Y-12 has set rigorous ALARA goals for worker doses, the external limits are based on assumptions of work time involved in the movement of accepted material plus the desire that external doses normally received are not exceeded, and set so that no special personnel monitoring would be required. Internal hazard controls were established so that dose contributions from non-uranium nuclides would not exceed 10% of that expected from the uranium component. This was performed using a Hazard Index (HI) previously established for work in areas contaminated with non-uranium nuclides. The radiological acceptance criteria for uranium are summarized in Table 1. Note that these limits are based on the assumption that radioactive daughter products have reached equilibrium.

  13. Analysis of waste treatment requirements for DOE mixed wastes: Technical basis

    International Nuclear Information System (INIS)

    1995-02-01

    The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation's allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered

  14. Research and experience report 2016 - Developments in the technical and legal basis for nuclear oversight

    International Nuclear Information System (INIS)

    2017-04-01

    Projects in the research programme of the Swiss Federal Nuclear Safety Inspectorate (ENSI) contribute to the clarification of outstanding issues, establish fundamentals and develop the tools required for its regulatory activities. International projects deliver results that Switzerland could not achieve on its own and encourage cross-border networking. The research on fuels and materials covers the reactor core and the multiple barriers for the retainment of radioactive materials especially concerning high burn-up rates and safety criteria. In 2016, the Studsvik Cladding Integrity Project in Sweden commissioned a new test facility to investigate the behaviour of fuel rods in loss of coolant accidents (LOCA). Research into structural materials focuses on ageing processes. In the NORA project at the Paul Scherrer Institute (PSI), platinum is injected into the cooling system with a view to reducing corrosion. Projects conducted under the auspices of the OECD's Nuclear Energy Agency (NEA) and relating to internal events and damage encourage the international exchange of information on incidents, accidents and component damage. Subject-specific databases are created on incidents involving fires or damage to passive metal components. In 2016 the OECD CODAP project prepared a report on reliability and integrity management in pressurised components. ENSI supports research projects on external events such as earthquakes, flooding, aircraft crashes and explosions. Within the OECD MECOS project, the behaviour of pipes subjected to powerful earthquakes was modelled; it showed improvements in the calculation of cyclic loading and on the limits for simulating elastic-plastic material behaviour under high loads. The impact of operator actions on incidents and accidents is the most important human factor in view of reducing uncertainty in probabilistic safety analyses, as well as the interfaces between humans and technical systems. System behaviour and accident sequences in

  15. TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION

    International Nuclear Information System (INIS)

    Fayer, J.M.; Freedman, V.L.; Ward, A.L.; Chronister, G.B.

    2010-01-01

    tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive

  16. 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

  17. Research and experience report 2012. Developments in the technical and legal basis of nuclear oversight

    International Nuclear Information System (INIS)

    2013-04-01

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) acts upon the basis of the latest developments in science and technology. ENSI supports and coordinates safety research, the results of which influence directly its Guidelines, individual decisions and resources. Research projects also serve training purposes and maintain competence within ENSI and its experts. The research in fuels and materials covers the reactor core and the graded approach to barriers used for the confinement of radioactive materials. Based on test results from accidents involving a loss of coolant ENSI instructed the operators of Swiss nuclear power plants to review whether they were relevant to their own facilities. Ageing mechanisms affecting structural materials are crucial to the long-term operation of nuclear power plants. Specialised thematic databases are being created in order to facilitate a systematic analysis of relevant operating experience from numerous countries. In addition to damage that may result from events within nuclear power plants, the safety analyses also reflect external events. ENSI supports international projects conducting complex experiments and simulations of aircraft accidents and earthquakes. It is involved in some projects relating to flood risks. The effect of operator behaviour on accidents in nuclear power plants is the focus point of research into human factors which identifies and analyses certain operator errors influencing negatively the course of an accident. Proposals to improve accident procedures were developed. This research area also focuses on the influence of the control room layout on the performance of operating staff. System behaviour and accident sequences in nuclear power plants are analysed in conditions ranging from normal operations through to accidents resulting in core melt-down. The results are used for the quantitative evaluation of the plant risk in probabilistic safety analyses. Applied research in radiological protection ranges

  18. 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

  19. 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)

  20. 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)

  1. 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

  2. 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)

  3. Technical manual for COMET

    International Nuclear Information System (INIS)

    Song, Jin Ho; Kwon, Young Min; Kim, Taek Mo; Lee, Sang Jong; Jeong, Hae Yong

    1996-07-01

    The purpose of this report is to provide a description for a COMET computer code which is to be used in the analysis of mass and energy releases during post-blowdown phase of LOCA. The mass and energy data re to be used as input data for the containment functional design. This report contains a brief description of analytical models and guidelines for the usage of the computer code. This computer code is to be used for both cold leg and hot leg break analyses. A verification analyses are performed for Ulchin 3 and 4 cold and hot leg break. 11 figs (Author)

  4. 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.

  5. 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)

  6. 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

  7. 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.

  8. 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.)

  9. 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.

  10. Pre-shipment preparations at the Savannah River Site - WSRC's technical basis to support DOE's approval to ship

    International Nuclear Information System (INIS)

    Thomas, Jay E.; Bickley, Donald W.; Conatser, E. Ray

    2000-01-01

    Store', to provide a disciplined method for ensuring that all of the pre-shipment receipt preparations have been completed. This paper will provide a detailed description of each of the pre-shipment process steps WSRC performs to produce the technical basis for approving the receipt and storage of spent nuclear fuel at the Savannah River Site. It is intended to be a guide to reactor operators who plan on returning 'U.S. origin' SNF and to emphasize the need for accurate and timely completion of pre-shipment activities. (author)

  11. 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.

  12. 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

  13. 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

  14. 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.

  15. 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.

  16. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

    International Nuclear Information System (INIS)

    Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B.

    1996-03-01

    A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

  17. 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.)

  18. 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.

  19. Mammography manual for the daily routine. A technical, practical and quality guide for radiologists, gynaecologists and radiographers

    International Nuclear Information System (INIS)

    Roth-Ganter, G.; Fischer, U.

    2002-01-01

    Gudrun Roth-Ganther presents in this book a wealth of professional experience that she has been accumulating over many years as a radiographer tutor at home and abroad. Step by step the reader will learn how to make high-quality mammographs. Important aspects: the normal radiographic anatomy of the mamma, factors influencing the image quality, technical parameters, exposure techniques, approaches for quality assessment and quality assurance, detecting and avoiding mistakes. (orig./CB) [de

  20. An interrelation of physical and technical readiness as a basis in sport result achievement of 400 m hurdlers

    Directory of Open Access Journals (Sweden)

    Oleg Grebeniuk

    2017-04-01

    Full Text Available Purpose: to establish the relationship of physical and technical preparedness to achieve sports results of 400 m hurdlers at the stage of preliminary base preparation. Material & Methods: study involved the first grade athletes in the amount of 18 people. Methods of research: pedagogical observation, pedagogical experiment, pedagogical testing of physical and technical readiness, telepodometry, methods of mathematical statistics. Results: it found that the major indicators of special physical readiness in the step of preliminary base preparation are: run at 100 m. result which was 96.4% from the model; run at 200 m – 96,0% from the model; run at 400 m – 98,7% from the model; hopping run 100 m – 93,4% and jumps 20 m on one leg – 91,1% % from the model. Conclusion: study of individual elements technique allows us to characterize not only the technique of movements, but also the level of physical qualities.

  1. Security during the Construction of New Nuclear Power Plants: Technical Basis for Access Authorization and Fitness-For-Duty Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Branch, Kristi M.; Baker, Kathryn A.

    2009-09-01

    A technical letter report to the NRC summarizing the findings of a benchmarking study, literature review, and workshop with experts on current industry standards and expert judgments about needs for security during the construction phase of critical infrastructure facilities in the post-September 11 U.S. context, with a special focus on the construction phase of nuclear power plants and personnel security measures.

  2. Technical basis for implementing the use of the PCM-1B for personnel releases at tank farms

    International Nuclear Information System (INIS)

    Brown, R.L.

    1996-01-01

    Currently, Tanks Farms Transition Projects require personnel to perform a whole body survey with portable survey instrumentation prior to entering an automated counting system capable of performing a whole body survey. This practice is redundant since automated whole body survey devices are, in most cases, more sensitive and are less likely to be used incorrectly than portable instrumentation. Additionally, Article 221.2 of the Hanford Site Radiological Control Manual (HSRCM-1) states ''Monitoring for contamination should be performed using frisking equipment that under laboratory conditions can detect total contamination of at least the values specified in Table 2-2.'' Based on this criteria implementing the use of an automated whole body survey device would save significant time, money and reduce the current crowding and potential loss of contamination control that now occurs during peak times at step off pads. This document describes implementation process for applying PCM-1B instruments to perform personnel release surveys

  3. Dump the pump: manual aspiration thrombectomy (MAT) with a syringe is technically effective, expeditious, and cost-efficient.

    Science.gov (United States)

    Gross, Bradley A; Jadhav, Ashutosh P; Jovin, Tudor G; Jankowitz, Brian Thomas

    2018-04-01

    Syringe aspiration for manual aspiration thrombectomy (MAT) is a cost- and time-efficient alternative to an aspiration pump with likely similar efficacy. It is counterintuitive to expect the pump to perform better than direct vacuum with a syringe, as the pump must deliver vacuum additionally through a canister and meters of tubing. To present in vitro and clinical results of MAT with a syringe. An in vitro analysis was performed comparing vacuum pressures generated by syringe aspiration and with pump aspiration. This was then complemented with prospective clinical data providing details of angiographic and clinical outcomes for syringe MAT. The in vitro analysis demonstrated that equal to slightly greater vacuum pressures were generated by a 60 cc syringe as compared with the pump in both static and partial flow conditions. In our clinical series, 106/113 acute stroke thrombectomies over a 6-month period were performed with syringe MAT on the first pass. Syringe usage instead of pump tubing and a canister led to a total savings of $58 300. The rate of Thrombolysis in Cerebral Infarction 2b/3 recanalization was 93%. Adjunctive stentriever usage was performed in 23% of cases. Median puncture to reperfusion time was 25 min; mean change in National Institute of Health Stroke Scale score at 24 hours was an improvement of 5.1 (median 6). The in-hospital mortality rate was 10%. Seventy percent of patients were discharged to home (modified Rankin Scale (mRS) score 0-2) or a rehabilitation facility (mRS score 2-4). MAT using a syringe is a safe, fast, and more cost-effective approach than using an aspiration pump. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  4. Projected configuration of a coal-fired district heating source on the basis of comparative technical-economical optimization analysis

    Directory of Open Access Journals (Sweden)

    Tańczuk Mariusz

    2017-01-01

    Full Text Available District heating technologies should be efficient, effective and environmentally friendly. The majority of the communal heating systems in Poland produce district hot water in coal-fired boilers. A large number of them are considerably worn out, low-efficient in the summer time and will not comply with forthcoming regulations. One of the possible solution for such plants is repowering with new CHP systems or new boilers fuelled with fuels alternative to coal. Optimisation analysis of the target configuration of municipal heat generating plant is analysed in the paper. The work concerns repowering the existing conventional heat generating plant according to eight different scenarios of the plant configuration meeting technical and environmental requirements forecasted for the year of 2035. The maximum demand for heat of the system supplied by the plant is 185 MW. Taking into account different technical configurations on one side, and different energy and fuel prices on the other side, the comparative cost-benefits analysis of the assumed scenarios has been made. The basic economical index NPV (net present value has been derived for each analysed scenario and the results have been compared and discussed. It was also claimed that the scenario with CHP based on ICE engines is optimal.

  5. Projected configuration of a coal-fired district heating source on the basis of comparative technical-economical optimization analysis

    Science.gov (United States)

    Tańczuk, Mariusz; Radziewicz, Wojciech; Olszewski, Eligiusz; Skorek, Janusz

    2017-10-01

    District heating technologies should be efficient, effective and environmentally friendly. The majority of the communal heating systems in Poland produce district hot water in coal-fired boilers. A large number of them are considerably worn out, low-efficient in the summer time and will not comply with forthcoming regulations. One of the possible solution for such plants is repowering with new CHP systems or new boilers fuelled with fuels alternative to coal. Optimisation analysis of the target configuration of municipal heat generating plant is analysed in the paper. The work concerns repowering the existing conventional heat generating plant according to eight different scenarios of the plant configuration meeting technical and environmental requirements forecasted for the year of 2035. The maximum demand for heat of the system supplied by the plant is 185 MW. Taking into account different technical configurations on one side, and different energy and fuel prices on the other side, the comparative cost-benefits analysis of the assumed scenarios has been made. The basic economical index NPV (net present value) has been derived for each analysed scenario and the results have been compared and discussed. It was also claimed that the scenario with CHP based on ICE engines is optimal.

  6. Technical note: A simple rumen collection device for calves: An adaptation of a manual rumen drenching system.

    Science.gov (United States)

    Klopp, R N; Oconitrillo, M J; Sackett, A; Hill, T M; Schlotterbeck, R L; Lascano, G J

    2018-07-01

    A limited amount of research is available related to the rumen microbiota of calves, yet there has been a recent spike of interest in determining the diversity and development of calf rumen microbial populations. To study the microbial populations of a calf's rumen, a sample of the rumen fluid is needed. One way to take a rumen fluid sample from a calf is by fistulating the animal. This method requires surgery and can be very stressful on a young animal that is trying to adapt to a new environment and has a depressed immune system. Another method that can be used instead of fistulation surgery is a rumen pump. This method requires a tube to be inserted into the rumen through the calf's esophagus. Once inside the rumen, fluid can be pumped out and collected in a few minutes. This method is quick, inexpensive, and does not cause significant stress on the animal. This technical note presents the materials and methodology used to convert a drenching system into a rumen pump and its respective utilization in 2 experiments using dairy bull calves. Copyright © 2018 American Dairy Science Association. Published by Elsevier Inc. All rights reserved.

  7. Technical basis and radiological release plan for trackhoe number-sign H0-17-5669 at 100 BC-1

    International Nuclear Information System (INIS)

    Wesselman, M.A.

    1996-03-01

    This report documents the development of a method for the radiological release of a tracked heavy equipment vehicle used in the excavation of the 116 C-1 crib at Hanford Reservation, including the technical bases for selection of release criteria and the instrumentation to be used for the surveys. The vehicle is a backhoe with an articulated arm extending from a tracked vehicle body and for ease is called a ''trackhoe''. The trackhoe was used at the 1301N crib to install the initial string of temporary casing. The trackhoe dug into the crib overburden to a depth of about 10 feet and in the process the bucket became contaminated with mixed fission/activation products and plutonium. An attempt was made to decontaminate the bucket, but was only partially successful as the facilities at the work site were not adequate to achieve a complete release. Surveys of the bucket indicated that direct readings for beta-gamma contamination were over 100 times higher than those for alpha contamination

  8. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.

    2009-11-30

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  9. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    2009-01-01

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  10. 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.

  11. 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

  12. Analysis and evaluation of the ASTEC model basis on fission product and aerosol release phenomena from melts. 3. Technical report

    International Nuclear Information System (INIS)

    Agethen, K.; Koch, M.K.

    2016-04-01

    The present report is the 3 rd Technical Report within the research project ''ASMO'' founded by the German Federal Ministry for Economic Affairs and Energy (BMWi 1501433) and projected at the Chair of Energy Systems and Energy Economics (LEE) within the workgroup Reactor Simulation and Safety at the Ruhr-Universitaet Bochum (RUB). The focus in this report is set on the release of fission products and the contribution to the source term, which is formed in the late phase after failure of the reactor pressure vessel during MCCI. By comparing the RUB simulation results including the fission product release rates with further simulations of GRS and VEIKI it can be indicated that the simulations have a high sensitivity in respect to the melting point temperature. It can be noted that the release rates are underestimated for most fission product species with the current model. Especially semi-volatile fission products and the lanthanum release is underestimated by several orders of magnitude. Based on the ACE experiment L2, advanced considerations are presented concerning the melt temperature, the gas temperature, the segregation and a varied melt configuration. Furthermore, the influence of the gas velocity is investigated. This variation of the gas velocity causes an underestimation of the release rates compared to the RUB base calculation. A model extension to oxidic species for lanthanum and ruthenium shows a significant improvement of the simulation results. In addition, the MEDICIS module has been enhanced to document the currently existing species, are displayed in a *.ist-file. This expansion shows inconsistencies between the melt composition and the fission product composition. Based on these results, there are still some difficulties regarding the release of fission products in the MEDICIS module and the interaction with the material data base (MOB) which needs further investigation.

  13. Evaluation of economic and technical efficiency of diesel engines operation on the basis of volume combustion rate

    Directory of Open Access Journals (Sweden)

    І. О. Берестовой

    2016-11-01

    Full Text Available The article deals with a new approach to evaluation of complex efficiency of diesel engines. Traditionally, cylinder’s capacity, rotation frequency, average efficient pressure inside cylinder, piston’s stroke, average piston’s velocity, fuel specific consumption and other indices are used as generalizing criteria, characterizing diesel engine’s efficiency, but they do not reflect interrelation between engine’s complex efficiency and a set of economic, mass-dimensional, operational and ecological efficiency. The approach applied in the article makes it possible to reveal the existing and modify the existing methods of solving the problem of improving diesel engine’s efficiency with due regard to interrelation of the parameters, characterizing efficiency of their operation. Statistic analyses were carried out, on the basis of which an assumption regarding the existence of interrelation between specific fuel consumption and the analyzed engine’s parameters was made. Processing of statistical data for various analyzed functions of diesel engines helped offer a function, illustrating the link between volume combustion rate, piston’s area and nominal theoretical specific fuel consumption. Interrelation between volume combustion rate, nominal parameters of diesel operation and efficiency indices, obtained by processing statistical data of more than 500 models of diesels of different series was evaluated, the main feature of it being a mathematical trend. The analysis of the obtained function makes it possible to establish an interrelation between economic efficiency of a diesel, its main index being specific fuel consumption and volume combustion rate and design peculiarities

  14. 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)

  15. 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)

  16. The empirical basis of substance use disorders diagnosis: research recommendations for the Diagnostic and Statistical Manual of Mental Disorders, fifth edition (DSM-V).

    Science.gov (United States)

    Schuckit, Marc A; Saunders, John B

    2006-09-01

    This paper presents the recommendations, developed from a 3-year consultation process, for a program of research to underpin the development of diagnostic concepts and criteria in the Substance Use Disorders section of the Diagnostic and Statistical Manual of Mental Disorders (DSM) and potentially the relevant section of the next revision of the International Classification of Diseases (ICD). A preliminary list of research topics was developed at the DSM-V Launch Conference in 2004. This led to the presentation of articles on these topics at a specific Substance Use Disorders Conference in February 2005, at the end of which a preliminary list of research questions was developed. This was further refined through an iterative process involving conference participants over the following year. Research questions have been placed into four categories: (1) questions that could be addressed immediately through secondary analyses of existing data sets; (2) items likely to require position papers to propose criteria or more focused questions with a view to subsequent analyses of existing data sets; (3) issues that could be proposed for literature reviews, but with a lower probability that these might progress to a data analytic phase; and (4) suggestions or comments that might not require immediate action, but that could be considered by the DSM-V and ICD 11 revision committees as part of their deliberations. A broadly based research agenda for the development of diagnostic concepts and criteria for substance use disorders is presented.

  17. 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.

  18. 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

  19. 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.

  20. Establishment of Technical Collaboration basis between Korea and France for the development of severe accident assessment computer code under high burnup condition

    International Nuclear Information System (INIS)

    Kim, H. D.; Kim, D. H.; Park, S. Y.; Park, J. H.

    2005-10-01

    This project was performed by KAERI in the frame of construction of the international cooperative basis on the nuclear energy. This was supported from MOST under the title of 'Establishment of Technical Collaboration basis between Korea and France for the development of severe accident assessment computer code under high burn up condition'. The current operating NPP are converting the burned fuel to the wasted fuel after burn up of 40 GWD/MTU. But in Korea, burn up of more than 60 GWD/MTU will be expected because of the high fuel efficiency but also cost saving for storing the wasted fuel safely. The domestic research for the purpose of developing the fuel and the cladding that can be used under the high burn up condition up to 100 GWD/MTU is in progress now. But the current computer code adopts the model and the data that are valid only up to the 40 GWD/MTU at most. Therefore the current model could not take into account the phenomena that may cause differences in the fission product release behavior or in the core damage process due to the high burn up operation (more than 40 GWD/MTU). To evaluate the safety of the NPP with the high burn up fuel, the improvement of current severe accident code against the high burn up condition is an important research item. Also it should start without any delay. Therefore, in this study, an expert group was constructed to establish the research basis for the severe accident under high burn up conditions. From this expert group, the research items regarding the high burn up condition were selected and identified through discussion and technical seminars. Based on these selected items, the meeting between IRSN and KAERI to find out the cooperative research items on the severe accident under the high burn up condition was held in the IRSN headquater in Paris. After the meeting, KAERI and IRSN agreed to cooperate with each other on the selected items, and to co-host the international seminar, and to develop the model and to

  1. Use of knowledge and experience gained from the Fukushima Daiichi Nuclear Power Station accident to establish the technical basis for strategic off-site response

    International Nuclear Information System (INIS)

    Miyahara, Kaname; Saito, Kimiaki; Iijima, Kazuki; McKinley, Ian; Hardie, Susan

    2015-03-01

    This report provides a concise overview of knowledge and experience gained from the activities for environmental remediation after the Fukushima Daiichi (1F) accident. It is specifically tailored for international use, to establish or refine the technical basis for strategic, off-site response to nuclear incidents. It reflects JAEA's key role in the research associated with both remediation of contaminated areas and also the natural contamination migration processes in non-remediated areas, in collaboration with other Japanese and international organisations and research institutes. Environmental monitoring and mapping to define boundary conditions in terms of the distribution of radioactivity and resultant doses, guides the resultant response. Radiation protection considerations set constraints, with approaches developed to estimate doses to different critical groups and set appropriate dose reduction targets. Decontamination activities, with special emphasis on associated waste management, provide experience in evaluation of the effectiveness of decontamination and the pros and cons of different approaches / technologies. The assessment of the natural behaviour of contaminant radionuclides and their mobility in the environment is now focused almost entirely on radiocaesium. Here, the impact of natural mobility in terms of self-cleaning / re-concentration in cleaned areas is discussed, along with possible actions to modify such transport or manage potential areas of radiocaesium accumulation. Many of the conditions in Fukushima are similar to those following past contamination events in other countries, where natural self-cleaning alone has allowed recovery to such an extent that the original incident is now largely forgotten. Decontamination efforts in Japan will certainly accelerate this process. On-going remediation work is based on a good technical understanding of the movement of radiocaesium in the environment and this understanding is being translated into

  2. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Gunther, W.; Martinez-Guridi, G.

    2010-01-01

    New and advanced reactors will use integrated digital instrumentation and control (I and C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I and C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I and C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I and C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I and C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I and C conditions as part of the design process and the HSI features and functions that support operators to monitor I and C performance and manage I and C degradations when they occur. In addition, we identified topics for future research.

  3. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.; W. Gunther, G. Martinez-Guridi

    2010-02-26

    New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I&C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I&C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I&C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I&C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I&C conditions as part of the design process and the HSI features and functions that support operators to monitor I&C performance and manage I&C degradations when they occur. In addition, we identified topics for future research.

  4. 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...

  5. 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,…

  6. 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...

  7. 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.

  8. 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.

  9. TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM OXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Duffey, J.; Livingston, R.; Berg, J.; Veirs, D.

    2012-07-02

    The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO{sub 2}) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO{sub 2} feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO{sub 2} (i.e., 950 C for 2 hours) preclude use of the HBL PuO{sub 2} in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO{sub 2} that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO{sub 2} from oxalate precipitation processes from 950 C to 640 C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 {micro}g/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 {micro}g/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013

  10. 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

  11. 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

  12. 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.

  13. Decision Support System for Aquifer Recharge (AR) and Aquifer Storage and Recovery (ASR) Planning, Design, and Evaluation - Principles and Technical Basis

    Science.gov (United States)

    Aquifer recharge (AR) is a technical method being utilized to enhance groundwater resources through man-made replenishment means, such as infiltration basins and injections wells. Aquifer storage and recovery (ASR) furthers the AR techniques by withdrawal of stored groundwater at...

  14. 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)

  15. 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

  16. 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

  17. 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…

  18. 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.

  19. 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.

  20. 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

  1. 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.

  2. 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

  3. THE PROBLEMS OF MODELING THE RELIABILITY STRUCTURE OF THE COMPLEX TECHNICAL SYSTEM ON THE BASIS OF A STEAM‐WATER SYSTEM OF THE ENGINE ROOM

    Directory of Open Access Journals (Sweden)

    Leszek CHYBOWSKI

    2012-04-01

    Full Text Available In the paper the concept of a system structure with particular emphasis on the reliability structure has been presented. Advantages and disadvantages of modeling the reliability structure of a system using reliability block diagrams (RBD have been shown. RBD models of a marine steam‐water system constructed according to the concept of ‘multi‐component’, ‘one component’ and mixed models have been discussed. Critical remarks on the practical application of models which recognize only the structural surplus have been dealt with. The significant value of the model by professors Smalko and Jaźwiński called by them ‘default reliability structure’ has been pointed out. The necessity of building a new type of models: quality‐quantity, useful in the methodology developed by the author's multi-criteria analysis of importance of elements in the reliability structure of complex technical systems.

  4. South Africa's greenhouse gas emissions under business-as-usual: The technical basis of 'Growth without Constraints' in the Long-Term Mitigation Scenarios

    International Nuclear Information System (INIS)

    Winkler, Harald; Hughes, Alison; Marquard, Andrew; Haw, Mary; Merven, Bruno

    2011-01-01

    This article describes the methodology for projecting business-as-usual GHG trajectory developed in technical work for South Africa's Long-Term Mitigation Scenarios (LTMSs), in particular the 'Growth without Constraints' (GWCs) scenario. Technically rigorous projections are important as developing countries define their commitment to act on mitigation relative to business-as-usual (BAU). The key drivers for the GWC scenario include GDP (both growth rate and composition), population, discount rate and technological change. GDP emerged as an important driver in the research for LTMS and further analysis. If South Africa's economy grows without constraints over the next few decades, GHG emissions will continue to escalate, multiplying more than four-fold by mid-century. There is little gain in energy efficiency, and emissions continue to be dominated by energy use and supply, the latter remaining coal-based in GWC. We analyse the projections (not predictions) in relation to various measures. The LTMS GWC scenario is compared to other projections, nationally and internationally. A broadly comparable projection is being used at national level, for electricity planning. When compared to projections from international models, we find that the assumptions about GDP growth rates are a key factor, and suggest that comparisons of global data-sets against national analyses is important. - Highlights: → Specifies business-as-usual GHG trajectory for South Africa's Long-Term Mitigation Scenarios. → Provides details on methodology, drivers of emissions and key parameters. → In a scenario of Growth without Constraints, emissions would quadruple by 2050. → Analysis of resulting emission projection, not a prediction. → Compares projections from other national and international models.

  5. 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.

  6. 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

  7. Concept for creating program-technical complex of safety monitoring with system of safety parameters presentation functions on the basis of routine WWER-1000 systems

    International Nuclear Information System (INIS)

    Dunaev, V.G.; Tarasov, M. V.; Povarov, P.V.

    2005-01-01

    Prerequisites of creating the software-hardware complex for reactor safety monitoring on the Volgodonsk NPP are analyzed and generalized. The concept of this complex is based on functions of the safety parameters presentation system. It will serve as an interface between operator and technological process and give to operator a possibility to estimate quickly the state of the safety of the nuclear power unit. The complex will be created on the basis of routine reactor monitoring and control systems intended for the WWER-1000 reactor. In addition to existing soft- and hard-wares for reactor monitoring and for analysis of technological archive, it is proposed to create and connect in parallel the new software-hardware complex which ensures calculation and presentation of generalized factors of reactor safety [ru

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

    International Nuclear Information System (INIS)

    DeGrassi, G.

    1992-10-01

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

  9. Experiments performed on a man-made crack in the flat low-permeability basement as a basis for large-scale technical extraction of terrestrial heat

    Energy Technology Data Exchange (ETDEWEB)

    Kappelmeyer, O.; Jung, R.; Rummel, F.

    1984-01-01

    Research work is performed on an in-situ experimental field in the crystalline subsoil near Falkenberg in East Bavaria which are to help develop new technologies for exploiting geothermal energy. The aim is to make terrestrial heat available for technical utilization even with a relatively normal geologic structure of the subsoil - i.e. far away from volcanos and outside of layers carrying water or steam. To achieve this objective, artificial heat exchange systems were produced by hydraulic fracturing of crystalline rocks at a depth of 250 m. Geometric positions of these cracks were located by means of seismic and geo-electric methods. Seismic observations allowed deriving a crack model which helped with penetrating the man-made crack by sectional drilling. The circulation system consisting in production drill-hole, crack system and sectional drill-hole was studied for hydraulic parameter (e.g. flow resistance) and thermal efficiency at various pressure levels in the crack. Crack width was measured at different pressure stages for the first time. Thermal model calculations allow transferral of the results gained from the flat relatively cool basement to basement areas of an elevated temperature. A number of rock parameters which are relevant for an assessment whether or not the subsoil is suitable for creating artificial heat exchange systems, were examined on-site and bench-scale.

  10. 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

  11. Metrication manual

    International Nuclear Information System (INIS)

    Harper, A.F.A.; Digby, R.B.; Thong, S.P.; Lacey, F.

    1978-04-01

    In April 1978 a meeting of senior metrication officers convened by the Commonwealth Science Council of the Commonwealth Secretariat, was held in London. The participants were drawn from Australia, Bangladesh, Britain, Canada, Ghana, Guyana, India, Jamaica, Papua New Guinea, Solomon Islands and Trinidad and Tobago. Among other things, the meeting resolved to develop a set of guidelines to assist countries to change to SI and to compile such guidelines in the form of a working manual

  12. 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...

  13. 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.

  14. Technical basis for the reduction of the maximum temperature TGA-MS analysis of oxide samples from the 3013 destructive examination program

    International Nuclear Information System (INIS)

    Scogin, J. H.

    2016-01-01

    Thermogravimetric analysis with mass spectroscopy of the evolved gas (TGA-MS) is used to quantify the moisture content of materials in the 3013 destructive examination (3013 DE) surveillance program. Salts frequently present in the 3013 DE materials volatilize in the TGA and condense in the gas lines just outside the TGA furnace. The buildup of condensate can restrict the flow of purge gas and affect both the TGA operations and the mass spectrometer calibration. Removal of the condensed salts requires frequent maintenance and subsequent calibration runs to keep the moisture measurements by mass spectroscopy within acceptable limits, creating delays in processing samples. In this report, the feasibility of determining the total moisture from TGA-MS measurements at a lower temperature is investigated. A temperature of the TGA-MS analysis which reduces the complications caused by the condensation of volatile materials is determined. Analysis shows that an excellent prediction of the presently measured total moisture value can be made using only the data generated up to 700 °C and there is a sound physical basis for this estimate. It is recommended that the maximum temperature of the TGA-MS determination of total moisture for the 3013 DE program be reduced from 1000 °C to 700 °C. It is also suggested that cumulative moisture measurements at 550 °C and 700°C be substituted for the measured value of total moisture in the 3013 DE database. Using these raw values, any of predictions of the total moisture discussed in this report can be made.

  15. Technical basis for the reduction of the maximum temperature TGA-MS analysis of oxide samples from the 3013 destructive examination program

    Energy Technology Data Exchange (ETDEWEB)

    Scogin, J. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-03-24

    Thermogravimetric analysis with mass spectroscopy of the evolved gas (TGA-MS) is used to quantify the moisture content of materials in the 3013 destructive examination (3013 DE) surveillance program. Salts frequently present in the 3013 DE materials volatilize in the TGA and condense in the gas lines just outside the TGA furnace. The buildup of condensate can restrict the flow of purge gas and affect both the TGA operations and the mass spectrometer calibration. Removal of the condensed salts requires frequent maintenance and subsequent calibration runs to keep the moisture measurements by mass spectroscopy within acceptable limits, creating delays in processing samples. In this report, the feasibility of determining the total moisture from TGA-MS measurements at a lower temperature is investigated. A temperature of the TGA-MS analysis which reduces the complications caused by the condensation of volatile materials is determined. Analysis shows that an excellent prediction of the presently measured total moisture value can be made using only the data generated up to 700 °C and there is a sound physical basis for this estimate. It is recommended that the maximum temperature of the TGA-MS determination of total moisture for the 3013 DE program be reduced from 1000 °C to 700 °C. It is also suggested that cumulative moisture measurements at 550 °C and 700°C be substituted for the measured value of total moisture in the 3013 DE database. Using these raw values, any of predictions of the total moisture discussed in this report can be made.

  16. Research and experience report 2016 - Developments in the technical and legal basis for nuclear oversight; Erfahrungs- und Forschungsbericht 2016 - Entwicklungen im Bereich der Grundlagen der nuklearen Aufsicht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-04-15

    Projects in the research programme of the Swiss Federal Nuclear Safety Inspectorate (ENSI) contribute to the clarification of outstanding issues, establish fundamentals and develop the tools required for its regulatory activities. International projects deliver results that Switzerland could not achieve on its own and encourage cross-border networking. The research on fuels and materials covers the reactor core and the multiple barriers for the retainment of radioactive materials especially concerning high burn-up rates and safety criteria. In 2016, the Studsvik Cladding Integrity Project in Sweden commissioned a new test facility to investigate the behaviour of fuel rods in loss of coolant accidents (LOCA). Research into structural materials focuses on ageing processes. In the NORA project at the Paul Scherrer Institute (PSI), platinum is injected into the cooling system with a view to reducing corrosion. Projects conducted under the auspices of the OECD's Nuclear Energy Agency (NEA) and relating to internal events and damage encourage the international exchange of information on incidents, accidents and component damage. Subject-specific databases are created on incidents involving fires or damage to passive metal components. In 2016 the OECD CODAP project prepared a report on reliability and integrity management in pressurised components. ENSI supports research projects on external events such as earthquakes, flooding, aircraft crashes and explosions. Within the OECD MECOS project, the behaviour of pipes subjected to powerful earthquakes was modelled; it showed improvements in the calculation of cyclic loading and on the limits for simulating elastic-plastic material behaviour under high loads. The impact of operator actions on incidents and accidents is the most important human factor in view of reducing uncertainty in probabilistic safety analyses, as well as the interfaces between humans and technical systems. System behaviour and accident sequences in

  17. 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

  18. Technologies for improving current and future light water reactor operation and maintenance: Development on the basis of experience. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-09-01

    experienced in nuclear power plant operation and maintenance. Worldwide, the average energy availability factor has increased from approximately 70 percent in 1989 to 79 percent' in 1998, with some utilities achieving significantly higher values. This is being achieved through integrated programmes, including personnel training and quality assurance, from improvements implemented in plant systems and components, and from improvements in outage duration for maintenance, refuelling, and other scheduled shutdowns, as well as forced outages. International co-operation is a key role in this success. The various programmes of the World Association of Nuclear Operators (WANO) to exchange information and encourage communication of experience, and the activities of the IAEA including projects in nuclear power plant performance assessment and feedback, effective quality management, and information exchange meetings on technology advances, are important examples of international co-operation to improve the performance of nuclear power plants. This IAEA Technical Committee meeting (TCM) was convened to provide a forum for information exchange on technologies for improving plant operation and maintenance which can contribute to enhanced economic competitiveness of LWRs, and on on-going or planned technology development expected to achieve further improvements. Information exchange of recent positive experience on development and/or implementation of technologies that have resulted in reduced operation and maintenance costs of LWRs, and information on on-going or planned activities, was strongly encouraged

  19. Technologies for improving current and future light water reactor operation and maintenance: Development on the basis of experience. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    experienced in nuclear power plant operation and maintenance. Worldwide, the average energy availability factor has increased from approximately 70 percent in 1989 to 79 percent' in 1998, with some utilities achieving significantly higher values. This is being achieved through integrated programmes, including personnel training and quality assurance, from improvements implemented in plant systems and components, and from improvements in outage duration for maintenance, refuelling, and other scheduled shutdowns, as well as forced outages. International co-operation is a key role in this success. The various programmes of the World Association of Nuclear Operators (WANO) to exchange information and encourage communication of experience, and the activities of the IAEA including projects in nuclear power plant performance assessment and feedback, effective quality management, and information exchange meetings on technology advances, are important examples of international co-operation to improve the performance of nuclear power plants. This IAEA Technical Committee meeting (TCM) was convened to provide a forum for information exchange on technologies for improving plant operation and maintenance which can contribute to enhanced economic competitiveness of LWRs, and on on-going or planned technology development expected to achieve further improvements. Information exchange of recent positive experience on development and/or implementation of technologies that have resulted in reduced operation and maintenance costs of LWRs, and information on on-going or planned activities, was strongly encouraged.

  20. Research and experience report 2012. Developments in the technical and legal basis of nuclear oversight; Erfahrungs- und Forschungsbericht 2012. Entwicklungen im Bereich der Grundlagen der nuklearen Aufsicht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) acts upon the basis of the latest developments in science and technology. ENSI supports and coordinates safety research, the results of which influence directly its Guidelines, individual decisions and resources. Research projects also serve training purposes and maintain competence within ENSI and its experts. The research in fuels and materials covers the reactor core and the graded approach to barriers used for the confinement of radioactive materials. Based on test results from accidents involving a loss of coolant ENSI instructed the operators of Swiss nuclear power plants to review whether they were relevant to their own facilities. Ageing mechanisms affecting structural materials are crucial to the long-term operation of nuclear power plants. Specialised thematic databases are being created in order to facilitate a systematic analysis of relevant operating experience from numerous countries. In addition to damage that may result from events within nuclear power plants, the safety analyses also reflect external events. ENSI supports international projects conducting complex experiments and simulations of aircraft accidents and earthquakes. It is involved in some projects relating to flood risks. The effect of operator behaviour on accidents in nuclear power plants is the focus point of research into human factors which identifies and analyses certain operator errors influencing negatively the course of an accident. Proposals to improve accident procedures were developed. This research area also focuses on the influence of the control room layout on the performance of operating staff. System behaviour and accident sequences in nuclear power plants are analysed in conditions ranging from normal operations through to accidents resulting in core melt-down. The results are used for the quantitative evaluation of the plant risk in probabilistic safety analyses. Applied research in radiological protection ranges

  1. Research and experience report 2012. Developments in the technical and legal basis of nuclear oversight; Erfahrungs- und Forschungsbericht 2012. Entwicklungen im Bereich der Grundlagen der nuklearen Aufsicht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) acts upon the basis of the latest developments in science and technology. ENSI supports and coordinates safety research, the results of which influence directly its Guidelines, individual decisions and resources. Research projects also serve training purposes and maintain competence within ENSI and its experts. The research in fuels and materials covers the reactor core and the graded approach to barriers used for the confinement of radioactive materials. Based on test results from accidents involving a loss of coolant ENSI instructed the operators of Swiss nuclear power plants to review whether they were relevant to their own facilities. Ageing mechanisms affecting structural materials are crucial to the long-term operation of nuclear power plants. Specialised thematic databases are being created in order to facilitate a systematic analysis of relevant operating experience from numerous countries. In addition to damage that may result from events within nuclear power plants, the safety analyses also reflect external events. ENSI supports international projects conducting complex experiments and simulations of aircraft accidents and earthquakes. It is involved in some projects relating to flood risks. The effect of operator behaviour on accidents in nuclear power plants is the focus point of research into human factors which identifies and analyses certain operator errors influencing negatively the course of an accident. Proposals to improve accident procedures were developed. This research area also focuses on the influence of the control room layout on the performance of operating staff. System behaviour and accident sequences in nuclear power plants are analysed in conditions ranging from normal operations through to accidents resulting in core melt-down. The results are used for the quantitative evaluation of the plant risk in probabilistic safety analyses. Applied research in radiological protection ranges

  2. Pdap Manual

    DEFF Research Database (Denmark)

    Pedersen, Mads Mølgaard; Larsen, Torben J.

    Pdap, Python Data Analysis Program, is a program for post processing, analysis, visualization and presentation of data e.g. simulation results and measurements. It is intended but not limited to the domain of wind turbines. It combines an intuitive graphical user interface with python scripting...... that allows automation and implementation of custom functions. This manual gives a short introduction to the graphical user interface, describes the mathematical background for some of the functions, describes the scripting API and finally a few examples on how automate analysis via scripting is presented....... The newest version, and more documentation and help on how to used, extend and automate Pdap can be found at the webpage www.hawc2.dk...

  3. 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

  4. 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.

  5. Acquisition Guide for Interactive Electronic Technical Manuals

    Science.gov (United States)

    2000-04-01

    6.1 ASCII Editors A𔄂 A.6.2 ADEPT*Editor.... Aŝ A.6.3 FrameMaker +SGML (FM+SGML) A൒ A.6.4 IADS A_n A.7 Developing and Editing...Interface A-9 Figure A-6. FrameMaker +SGML Authoring Environment A-l 1 Figure A-7. IADS Reader Aൔ Figure A-8. TechSight Viewer A_13 Figure A-9...errors should be corrected before importing an SGML-tagged file into ADEPT. A.6.3 FrameMaker +SGML (FM+SGML) FM+SGML is an Adobe System product and

  6. 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…

  7. Technical Basis for Assessing Uranium Bioremediation Performance

    International Nuclear Information System (INIS)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N'Guessan

    2008-01-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation

  8. Technical Basis for Assessing Uranium Bioremediation Performance

    Energy Technology Data Exchange (ETDEWEB)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N’Guessan

    2008-04-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

  9. 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...

  10. 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 ...

  11. 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

  12. 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

  13. 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

  14. Technical basis for instrumentation and control design improvements in WWER-440/230 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-01-01

    Instrumentation and control (I and C) has been recognized as an area which requires substantial improvements in WWER NNPs, particularly for model 230 plants. Under contract with the IAEA the Spanish company Empresarios Agrupados (EA) developed a basic document proposing a technical basis for improvements related to the following most significant aspects of I and C: criteria for safety classification; remote shutdown panel; I and C support to operation and control room design; instrumentation set point margins; accident monitoring instrumentation. This publication is derived from the original report of EA which was circulated by the IAEA for review by staff members and experts from various Member States. It was finally agreed upon at a Consultants' meeting convened by the IAEA in Vienna in May 1994 with the participation of experts from France, Germany and Spain. The guidance expressed in this report is based on the IAEA/NUSS standards, safety guides and practices, and on regulations in use in various Member States. It is proposed as a way of carrying out the necessary studies to improve safety by upgrading the vital part of instrumentation an control in WWER-440 model 230 nuclear power plants. 28 refs, 3 figs

  15. 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.

  16. 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.)

  17. 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

  18. 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.

  19. 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.

  20. 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

  1. 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…

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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…

  8. 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.

  9. 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…

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. HASL procedures manual

    International Nuclear Information System (INIS)

    Harley, J.H.

    1977-08-01

    Additions and corrections to the following sections of the HASL Procedures Manual are provided: General, Sampling, Field Measurements; General Analytical Chemistry, Chemical Procedures, Data Section, and Specifications

  15. 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

  16. 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

  17. 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)

  18. Oil Spill Response Manual

    NARCIS (Netherlands)

    Marieke Zeinstra; Sandra Heins; Wierd Koops

    2014-01-01

    A two year programme has been carried out by the NHL University of Applied Sciences together with private companies in the field of oil and chemical spill response to finalize these manuals on oil and chemical spill response. These manuals give a good overview of all aspects of oil and chemical

  19. 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....

  20. Marketing Research. Instructor's Manual.

    Science.gov (United States)

    Small Business Administration, Washington, DC.

    Prepared for the Administrative Management Course Program, this instructor's manual was developed to serve small-business management needs. The sections of the manual are as follows: (1) Lesson Plan--an outline of material covered, which may be used as a teaching guide, presented in two columns: the presentation, and a step-by-step indication of…

  1. Indoor Air Quality Manual.

    Science.gov (United States)

    Baldwin Union Free School District, NY.

    This manual identifies ways to improve a school's indoor air quality (IAQ) and discusses practical actions that can be carried out by school staff in managing air quality. The manual includes discussions of the many sources contributing to school indoor air pollution and the preventive planning for each including renovation and repair work,…

  2. GERTS GQ User's Manual.

    Science.gov (United States)

    Akiba, Y.; And Others

    This user's manual for the simulation program Graphical Evaluation and Review Technique (GERT) GQ contains sections on nodes, branches, program input description and format, and program output, as well as examples. Also included is a programmer's manual which contains information on scheduling, subroutine descriptions, COMMON Variables, and…

  3. 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)

  4. 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

  5. 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...

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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…

  11. (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 ...

  12. Handling, conditioning and storage of spent sealed radioactive sources. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    2000-05-01

    This report is intended to provide reference material, guidance and know-how on handling, conditioning and storage of spent sealed radioactive sources (SRS) to both users of SRS and operators of waste management facilities. The scope of this report covers all types of SRS except those exempted from regulatory control. The report contains in some detail technical procedures for the conditioning of spent SRS, describes the means required to assure the quality of the resulting package and discusses the measures to prepare waste packages with a certain flexibility to accommodate possible future disposal requirements

  13. 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

  14. 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.

  15. 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.

  16. 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.

  17. Technical writing versus technical writing

    Science.gov (United States)

    Dillingham, J. W.

    1981-01-01

    Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

  18. 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)

  19. HASL procedures manual

    International Nuclear Information System (INIS)

    1980-08-01

    Addition and corrections to the following sections of the HASL Procedures Manual are provided: Table of Contents; Bibliography; Fallout Collection Methods; Wet/Dry Fallout Collection; Fluoride in Soil and Sediment; Strontium-90; Natural Series; Alpha Emitters; and Gamma Emitters

  20. SEVERO code - user's manual

    International Nuclear Information System (INIS)

    Sacramento, A.M. do.

    1989-01-01

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

  1. The organizational measurement manual

    National Research Council Canada - National Science Library

    Wealleans, David

    2001-01-01

    ... Relationship of process to strategic measurements Summary 37 36Contents 19/10/2000 1:23 pm Page vi vi THE ORGANIZATIONAL MEASUREMENT MANUAL 4 PART 2 ESTABLISHING A PROCESS MEASUREMENT PROGRAMME...

  2. Geochemical engineering reference manual

    Energy Technology Data Exchange (ETDEWEB)

    Owen, L.B.; Michels, D.E.

    1984-01-01

    The following topics are included in this manual: physical and chemical properties of geothermal brine and steam, scale and solids control, processing spent brine for reinjection, control of noncondensable gas emissions, and goethermal mineral recovery. (MHR)

  3. NCDC Archive Documentation Manuals

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Climatic Data Center Tape Deck Documentation library is a collection of over 400 manuals describing NCDC's digital holdings (both historic and current)....

  4. EMAP Users Manual.

    Science.gov (United States)

    Kotz, Arnold; Redondo, Rory

    Presented is the user's manual for the Educational Manpower Information Sources Project (EMAP), an information file containing approximately 325 document abstracts related to the field of educational planning. (The EMAP file is described in document SP 006 747.) (JB)

  5. 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)

  6. 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…

  7. Reference design for a centralized spent sealed sources facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1995-07-01

    To assist Member States in establishing facilities in which the most frequently occurring spent sealed sources can be safely conditioned, the IAEA has financed the development of a generic design for a Spent Sealed Sources Facility (SSS Facility). The purpose of this TECDOC is to provide enough general information about the functions and capabilities of the SSS Facility to enable the reader to understand what the facility can do to contribute towards the management of spent sealed sources without providing all the technical and/or design information available. Sufficient information is provided to enable the reader to judge how and to what extent such a facility can contribute to national radioactive waste management infrastructure. 2 refs, 5 figs, 1 tab

  8. Reference design for a centralized spent sealed sources facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    To assist Member States in establishing facilities in which the most frequently occurring spent sealed sources can be safely conditioned, the IAEA has financed the development of a generic design for a Spent Sealed Sources Facility (SSS Facility). The purpose of this TECDOC is to provide enough general information about the functions and capabilities of the SSS Facility to enable the reader to understand what the facility can do to contribute towards the management of spent sealed sources without providing all the technical and/or design information available. Sufficient information is provided to enable the reader to judge how and to what extent such a facility can contribute to national radioactive waste management infrastructure. 2 refs, 5 figs, 1 tab.

  9. 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

  10. 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.

  11. 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

  12. 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...

  13. 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

  14. 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.

  15. 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.

  16. 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

  17. South Africa's greenhouse gas emissions under business-as-usual: The technical basis of 'Growth without Constraints' in the Long-Term Mitigation Scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Winkler, Harald, E-mail: Harald.WInkler@uct.ac.za [University of Cape Town, Energy Research Centre, Upper Campus, Rondebosch, W Cape 7701 (South Africa); Hughes, Alison; Marquard, Andrew [University of Cape Town, Energy Research Centre, Upper Campus, Rondebosch, W Cape 7701 (South Africa); Haw, Mary [PJCarew Consulting, 103 Hout Street, Cape Town 8001 (South Africa); Merven, Bruno [University of Cape Town, Energy Research Centre, Upper Campus, Rondebosch, W Cape 7701 (South Africa)

    2011-10-15

    This article describes the methodology for projecting business-as-usual GHG trajectory developed in technical work for South Africa's Long-Term Mitigation Scenarios (LTMSs), in particular the 'Growth without Constraints' (GWCs) scenario. Technically rigorous projections are important as developing countries define their commitment to act on mitigation relative to business-as-usual (BAU). The key drivers for the GWC scenario include GDP (both growth rate and composition), population, discount rate and technological change. GDP emerged as an important driver in the research for LTMS and further analysis. If South Africa's economy grows without constraints over the next few decades, GHG emissions will continue to escalate, multiplying more than four-fold by mid-century. There is little gain in energy efficiency, and emissions continue to be dominated by energy use and supply, the latter remaining coal-based in GWC. We analyse the projections (not predictions) in relation to various measures. The LTMS GWC scenario is compared to other projections, nationally and internationally. A broadly comparable projection is being used at national level, for electricity planning. When compared to projections from international models, we find that the assumptions about GDP growth rates are a key factor, and suggest that comparisons of global data-sets against national analyses is important. - Highlights: > Specifies business-as-usual GHG trajectory for South Africa's Long-Term Mitigation Scenarios. > Provides details on methodology, drivers of emissions and key parameters. > In a scenario of Growth without Constraints, emissions would quadruple by 2050. > Analysis of resulting emission projection, not a prediction. > Compares projections from other national and international models.

  18. Public illumination manual; Manual de iluminacao publica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    This work aims to guide in the correct choice and usage of the adequate public illumination equipment. It also aims to help the public authorities in terms of the best economical and technical choice, as well as the adequate maintenance of the equipment in order to obtain the most efficiency and safety with minimum costs 22 figs., 11 tabs.

  19. Public illumination manual; Manual de iluminacao publica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    This work aims to guide in the correct choice and usage of the adequate public illumination equipment. It also aims to help the public authorities in terms of the best economical and technical choice, as well as the adequate maintenance of the equipment in order to obtain the most efficiency and safety with minimum costs 22 figs., 11 tabs.

  20. 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.

  1. 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

  2. Aircraft operations management manual

    Science.gov (United States)

    1992-01-01

    The NASA aircraft operations program is a multifaceted, highly diverse entity that directly supports the agency mission in aeronautical research and development, space science and applications, space flight, astronaut readiness training, and related activities through research and development, program support, and mission management aircraft operations flights. Users of the program are interagency, inter-government, international, and the business community. This manual provides guidelines to establish policy for the management of NASA aircraft resources, aircraft operations, and related matters. This policy is an integral part of and must be followed when establishing field installation policy and procedures covering the management of NASA aircraft operations. Each operating location will develop appropriate local procedures that conform with the requirements of this handbook. This manual should be used in conjunction with other governing instructions, handbooks, and manuals.

  3. 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

  4. Nuclear material operations manual

    International Nuclear Information System (INIS)

    Tyler, R.P.

    1981-02-01

    This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  5. Salinas : theory manual.

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-11-01

    Salinas provides a massively parallel implementation of structural dynamics finite element analysis, required for high fidelity, validated models used in modal, vibration, static and shock analysis of structural systems. 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 programmer notes manual, the user's notes and of course the material in the open literature.

  6. Nuclear material operations manuals

    International Nuclear Information System (INIS)

    Tyler, R.P.

    1979-06-01

    This manual is intended to provide a concise and comprehensive documentation of the operating procedures currently practiced at Sandia Laboratories with regard to the management, control, and accountability of radioactive and nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  7. Nuclear material operations manual

    International Nuclear Information System (INIS)

    Tyler, R.P.; Gassman, L.D.

    1978-04-01

    This manual is intended to provide a concise and comprehensive documentation of the operating procedures currently practiced at Sandia Laboratories with regard to the management, control, and accountability of radioactive and nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations--management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of ''play-scripts'' in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion

  8. 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

  9. 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

  10. Assessment of technical-scale dewatering results in decanters on the basis of measurements of water types in sewage sludge; Bestimmung grosstechnischer Entwaesserungsergebnisse in Dekantern basierend auf der Messung der Wasserarten von Klaerschlaemmen

    Energy Technology Data Exchange (ETDEWEB)

    Kopp, J.; Dichtl, N. [Technische Univ. Braunschweig (Germany). Inst. fuer Siedlungswasserwirtschaft

    1999-07-01

    In a sewage sludge suspension, three water portions can be measured and distinguished from each other. The free water portion is not bound to sludge particles and can be separated by mechanical dewatering. The interstitial water portion bound by capillary forces and bound water (on surfaces and in cells) remain in the sludge cake after dewatering. The described measuring system for thermo-gravimetric determination of the water portions of sewage sludge was adjusted and calibrated at Braunschweig Technical University and permits prognosticating the maximum attainable content of solids through mechanical dewatering in high-performance decanters. (orig.) [German] In einer Klaerschlammsuspension koennen drei Wasseranteile messtechnisch unterschieden werden. Der freie Wasseranteil ist nicht an die Schlammpartikel gebunden und ist bei einer maschinellen Entwaesserung abtrennbar. Der kapillar gehaltene Zwischenraumwasseranteil und das gebundene Wasser (auf Oberflaechen und in Zellen) verbleibt nach der Entwaesserung im Schlammkuchen. Die an der TU Braunschweig angepasste und kalibrierte Messanlage zur thermo-gravimetrischen Bestimmung der Wasseranteile eines Klaerschlammes ermoeglicht es, den maximal bei der maschinellen Entwaesserung in Hochleistungsdekantern erreichbaren Feststoffgehalt zu prognostizieren. (orig.)

  11. MANUAL LOGIC CONTROLLER (MLC)

    OpenAIRE

    Claude Ziad Bayeh

    2015-01-01

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

  12. Beyond the Manual Channel

    DEFF Research Database (Denmark)

    , the main focus there is on spoken languages in their written and spoken forms. This series of workshops, however, offers a forum for researchers focussing on sign languages. For the fourth time, the workshop had sign language corpora as its main topic. This time, the focus was on any aspect beyond...... the manual channel. Not surprisingly, most papers deal with non-manuals on the face. Once again, the papers at this workshop clearly identify the potentials of even closer cooperation between sign linguists and sign language engineers, and we think it is events like this that contribute a lot to a better...

  13. Radar and ARPA manual

    CERN Document Server

    Bole, A G

    2013-01-01

    Radar and ARPA Manual focuses on the theoretical and practical aspects of electronic navigation. The manual first discusses basic radar principles, including principles of range and bearing measurements and picture orientation and presentation. The text then looks at the operational principles of radar systems. Function of units; aerial, receiver, and display principles; transmitter principles; and sitting of units on board ships are discussed. The book also describes target detection, Automatic Radar Plotting Aids (ARPA), and operational controls of radar systems, and then discusses radar plo

  14. TRUBA User Manual

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-04-25

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

  15. TRUBA User Manual

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  16. Netbooks The Missing Manual

    CERN Document Server

    Biersdorfer, J

    2009-01-01

    Netbooks are the hot new thing in PCs -- small, inexpensive laptops designed for web browsing, email, and working with web-based programs. But chances are you don't know how to choose a netbook, let alone use one. Not to worry: with this Missing Manual, you'll learn which netbook is right for you and how to set it up and use it for everything from spreadsheets for work to hobbies like gaming and photo sharing. Netbooks: The Missing Manual provides easy-to-follow instructions and lots of advice to help you: Learn the basics for using a Windows- or Linux-based netbookConnect speakers, printe

  17. Security electronics circuits manual

    CERN Document Server

    MARSTON, R M

    1998-01-01

    Security Electronics Circuits Manual is an invaluable guide for engineers and technicians in the security industry. It will also prove to be a useful guide for students and experimenters, as well as providing experienced amateurs and DIY enthusiasts with numerous ideas to protect their homes, businesses and properties.As with all Ray Marston's Circuits Manuals, the style is easy-to-read and non-mathematical, with the emphasis firmly on practical applications, circuits and design ideas. The ICs and other devices used in the practical circuits are modestly priced and readily available ty

  18. RELAP-7 Theory Manual

    Energy Technology Data Exchange (ETDEWEB)

    Berry, Ray Alden [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zou, Ling [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhao, Haihua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhang, Hongbin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Peterson, John William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Martineau, Richard Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kadioglu, Samet Yucel [Idaho National Lab. (INL), Idaho Falls, ID (United States); Andrs, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-03-01

    This document summarizes the physical models and mathematical formulations used in the RELAP-7 code. In summary, the MOOSE based RELAP-7 code development is an ongoing effort. The MOOSE framework enables rapid development of the RELAP-7 code. The developmental efforts and results demonstrate that the RELAP-7 project is on a path to success. This theory manual documents the main features implemented into the RELAP-7 code. Because the code is an ongoing development effort, this RELAP-7 Theory Manual will evolve with periodic updates to keep it current with the state of the development, implementation, and model additions/revisions.

  19. 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.

  20. 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

  1. Functional description of PreSRM v1.3. Technical manual for use of PreSRM (Preprocessor Standard Calculation Methods); Functionele omschrijving PreSRM v1.3. Technische handleiding voor gebruik van PreSRM (Preprocessor Standaard RekenMethoden)

    Energy Technology Data Exchange (ETDEWEB)

    Vermeulen, A.T. [ECN Environment and Energy Engineering, Petten (Netherlands)

    2013-07-15

    The PreSRM software library is prescribed in The Netherlands by the government to be used in the dispersion modeling of air pollution when evaluating air quality guidelines in outside air. The code is maintained by ECN and needs to be updated annually. This technical manual describes the use of PreSRM by programmers and documents the update for the current year 2013, including all updated meteorological and air quality background information for the year 2012 [Dutch] PreSRM is een software bibliotheek voor rekenmodellen gebruikt bij de beoordeling van luchtkwaliteit. In Nederland schrijft de Regeling Beoordeling Luchtkwaliteit (RBL) voor onder welke condities welke rekenmethodes gebruikt moeten worden om aan de luchtkwaliteitsnormen te toetsen. In de RBL worden drie Standaard RekenMethodes (SRM's) beschreven. Tevens wordt daarin vastgesteld welke invoergegevens gebruikt moeten worden voor emissies, achtergrondconcentraties, meteorologie en terreinruwheid. Deze gegevens worden jaarlijks geactualiseerd. Dit rapport is een technische handleiding voor de programmeurs en ontwikkelaars van de implementaties van standaard rekenmethoden en systeembeheerders van gebruikers en beschrijft aanpassingen in de huidige versie van de bibliotheek.

  2. 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.

  3. 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...

  4. 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...

  5. Nuclear electronics laboratory manual

    International Nuclear Information System (INIS)

    1984-05-01

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

  6. Manual for subject analysis

    International Nuclear Information System (INIS)

    2002-01-01

    This document is one in a series of publications known as the ETDE/INIS Joint Reference Series and also constitutes a part of the ETDE Procedures Manual. It presents the rules, guidelines and procedures to be adopted by centers submitting input to the International Nuclear Information System (INIS) or the Energy Technology Data Exchange (ETDE). It is a manual for the subject analysis part of input preparation, meaning the selection, subject classification, abstracting and subject indexing of relevant publications, and is to be used in conjunction with the Thesauruses, Subject Categories documents and the documents providing guidelines for the preparation of abstracts. The concept and structure of the new manual are intended to describe in a logical and efficient sequence all the steps comprising the subject analysis of documents to be reported to INIS or ETDE. The manual includes new chapters on preparatory analysis, subject classification, abstracting and subject indexing, as well as rules, guidelines, procedures, examples and a special chapter on guidelines and examples for subject analysis in particular subject fields. (g.t.; a.n.)

  7. Aquatic Microbiology Laboratory Manual.

    Science.gov (United States)

    Cooper, Robert C.; And Others

    This laboratory manual presents information and techniques dealing with aquatic microbiology as it relates to environmental health science, sanitary engineering, and environmental microbiology. The contents are divided into three categories: (1) ecological and physiological considerations; (2) public health aspects; and (3)microbiology of water…

  8. Tokai densitometer manual

    International Nuclear Information System (INIS)

    Sprinkle, J.K. Jr.; Hsue, S.T.; Junck, K.

    1987-01-01

    In 1979, the Tokai densitometer was installed at the Tokai Reprocessing Plant in Tokai, Japan. It uses a nondestructive active technique (K-edge absorption densitometry) to assay solutions for plutonium content. The original hardware was upgraded in 1984 and 1985. This manual describes the instrument's operation after the upgrade. 2 refs

  9. Political Education Manual.

    Science.gov (United States)

    League of United Latin American Citizens, Washington, DC.

    Written to help Hispanics understand the electoral process more thoroughly and to encourage them to participate more actively in the political arena, this manual begins by describing the present status of the Hispanic electorate and then explains how laws are made, how Hispanics can influence legislation, and how to organize a voter registration…

  10. Coulometer operator's manual

    International Nuclear Information System (INIS)

    Criscuolo, A.L.

    1977-07-01

    The coulometer control system automates the titration of uranium and plutonium as performed by the CMB-1 group. The system consists of a printer, microcontroller, and coulometer, all of which are controlled by an algorithm stored in the microcontroller read-only memory. This manual describes the titration procedure using the coulometer control system, its theory and maintenance

  11. Regulations and Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Lydia J. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2011-07-25

    The purpose of the Regulations and Procedures Manual (RPM) is to provide LBNL personnel with a reference to University and Lawrence Berkeley National Laboratory (LBNL or Laboratory) policies and regulations by outlining normal practices and answering most policy questions that arise in the day-to-day operations of Laboratory organizations. Much of the information in this manual has been condensed from detail provided in LBNL procedure manuals, Department of Energy (DOE) directives, and Contract DE-AC02-05CH11231. This manual is not intended, however, to replace any of those documents. RPM sections on personnel apply only to employees who are not represented by unions. Personnel policies pertaining to employees represented by unions may be found in their labor agreements. Questions concerning policy interpretation should be directed to the LBNL organization responsible for the particular policy. A link to the Managers Responsible for RPM Sections is available on the RPM home page. If it is not clear which organization is responsible for a policy, please contact Requirements Manager Lydia Young or the RPM Editor.

  12. Regulations and Procedures Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Lydia [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2010-09-30

    The purpose of the Regulations and Procedures Manual (RPM) is to provide Laboratory personnel with a reference to University and Lawrence Berkeley National Laboratory policies and regulations by outlining the normal practices and answering most policy questions that arise in the day-to-day operations of Laboratory departments. Much of the information in this manual has been condensed from detail provided in Laboratory procedure manuals, Department of Energy (DOE) directives, and Contract DE-AC02-05CH11231. This manual is not intended, however, to replace any of those documents. The sections on personnel apply only to employees who are not represented by unions. Personnel policies pertaining to employees represented by unions may be found in their labor agreements. Questions concerning policy interpretation should be directed to the department responsible for the particular policy. A link to the Managers Responsible for RPM Sections is available on the RPM home page. If it is not clear which department should be called, please contact the Associate Laboratory Director of Operations.

  13. ABCC publication manual

    Energy Technology Data Exchange (ETDEWEB)

    1959-01-01

    The reporting policy of the Atomic Bomb Casualty Commission is described in detail in this manual. Specific topics covered are: research project register; research publication policy; USA publication procedures; Japan publication procedures, report preparation instructions; and a glossary of institutions terms, phrases, and symbols. 15 figures. (DMC)

  14. Matematica 3. Manual.

    Science.gov (United States)

    D'Alu, Maria Jose Miranda de Sousa

    This teachers manual accompanies a mathematics textbook, written in Portuguese, for third graders. It closely follows the objectives and methodology of the major curricula used throughout the schools in the United States. The 11 chapters deal with: numeration (0-999,999); addition with and without regrouping; subtraction with and without…

  15. Manual on industrial radiography

    International Nuclear Information System (INIS)

    1981-08-01

    This manual is intended as a source of educational material to personnel seeking certification as industrial radiographers, and as a guide and reference text for educational organizations that are providng courses in industrial radiography. It covers the basic principles of x-ray and gamma radiation, radiation safety, films and film processing, welding, casting and forging, aircraft structures and components, radiographic techniques, and records

  16. Idaho Safety Manual.

    Science.gov (United States)

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This manual is intended to help teachers, administrators, and local school boards develop and institute effective safety education as a part of all vocational instruction in the public schools of Idaho. This guide is organized in 13 sections that cover the following topics: introduction to safety education, legislation, levels of responsibility,…

  17. Functional Assessment Inventory Manual.

    Science.gov (United States)

    Crewe, Nancy M.; Athelstan, Gary T.

    This manual, which provides extensive new instructions for administering the Functional Assessment Inventory (FAI), is intended to enable counselors to begin using the inventory without undergoing any special training. The first two sections deal with the need for functional assessment and issues in the development and use of the inventory. The…

  18. Manual Hydraulic Structures

    NARCIS (Netherlands)

    Molenaar, W.F.; Voorendt, M.Z.

    This manual is the result of group work and origins in Dutch lecture notes that have been used since long time. Amongst the employees of the Hydraulic Engineering Department that contributed to this work are dr.ir. S. van Baars, ir.K.G.Bezuijen, ir.G.P.Bourguignon, prof.ir.A.Glerum,

  19. SNL Abuse Testing Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Orendorff, Christopher [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lamb, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Steele, Leigh Anna Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    This report describes recommended abuse testing procedures for rechargeable energy storage systems (RESSs) for electric vehicles. This report serves as a revision to the FreedomCAR Electrical Energy Storage System Abuse Test Manual for Electric and Hybrid Electric Vehicle Applications (SAND2005-3123).

  20. Sexism in Parenting Manuals

    Science.gov (United States)

    DeFrain, John D.

    1977-01-01

    Parental roles, as delineated in many of the popular parenting manuals on the market, are reviewed and assessed. It is concluded that the vast majority of authors of child-rearing guides implicity or explicitly endorse the traditional roles of father as the dominant breadwinner and mother as the nurturant caretaker. (Author)

  1. Rescue Manual. Module 6.

    Science.gov (United States)

    Ohio State Univ., Columbus. Instructional Materials Lab.

    This learner manual for rescuers covers the current techniques or practices required in the rescue service. The sixth of 10 modules contains 4 chapters: (1) industrial rescue; (2) rescue from a confined space; (3) extrication from heavy equipment; and (4) rescue operations involving elevators. Key points, an introduction, and conclusion accompany…

  2. Manually operated coded switch

    International Nuclear Information System (INIS)

    Barnette, J.H.

    1978-01-01

    The disclosure related to a manually operated recodable coded switch in which a code may be inserted, tried and used to actuate a lever controlling an external device. After attempting a code, the switch's code wheels must be returned to their zero positions before another try is made

  3. Southern Ductile Training Manual.

    Science.gov (United States)

    Alabama State Dept. of Education, Montgomery.

    This instructor's manual contains the materials required to conduct the competency-based workplace literacy program that was developed to help employees at a foundry that has evolved from a small, family-owned business into a major foundry group with several automated production systems. The workplace literacy program consists of 24 lessons in…

  4. NDS EXFOR Manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1979-06-01

    This manual contains the coding rules and formats and NDS internal compilation rules for the exchange format (EXFOR) for the transmission of nuclear reaction data between national and international nuclear data centres, and for the data storage and retrieval system of the IAEA Nuclear Data Section

  5. Consumer Decisions. Student Manual.

    Science.gov (United States)

    Florida State Dept. of Education, Tallahassee. Div. of Vocational Education.

    This student manual covers five areas relating to consumer decisions. Titles of the five sections are Consumer Law, Consumer Decision Making, Buying a Car, Convenience Foods, and Books for Preschool Children. Each section may contain some or all of these materials: list of objectives, informative sections, questions on the information and answers,…

  6. NACS Store Planning Manual.

    Science.gov (United States)

    College Store Journal, 1979

    1979-01-01

    Topics discussed by the NACS Store Planning/Renovation Committees in this updated version of the college store renovation manual include: short- and long-range planning, financial considerations, professional planning assistance, the store's image and business character, location considerations, building requirements, space requirements, fixtures,…

  7. Default Management Manual.

    Science.gov (United States)

    Dent, Richard A.

    This manual is designed to instruct administrators of the Guaranteed Student Loan (GSL) Program in how to take every step possible to administer the program effectively and to minimize the program costs of serving the high risk student. It shows schools how to work with students throughout their time in school, create ownership of the loan(s) by…

  8. RRFC hardware operation manual

    International Nuclear Information System (INIS)

    Abhold, M.E.; Hsue, S.T.; Menlove, H.O.; Walton, G.

    1996-05-01

    The Research Reactor Fuel Counter (RRFC) system was developed to assay the 235 U content in spent Material Test Reactor (MTR) type fuel elements underwater in a spent fuel pool. RRFC assays the 235 U content using active neutron coincidence counting and also incorporates an ion chamber for gross gamma-ray measurements. This manual describes RRFC hardware, including detectors, electronics, and performance characteristics

  9. CANAL user's manual

    International Nuclear Information System (INIS)

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

    1979-11-01

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

  10. AELIB user's manual

    International Nuclear Information System (INIS)

    Evans, L.E.; Klawitter, G.L.

    1981-05-01

    This report is an updatable manual for users of AELIB, the AECL Library of FORTRAN-callable routines for the CRNL CDC 6600/CYBER 170 system. It provides general advice on the use of this library and detailed information on the selection and usage of particular library routines

  11. Water Quality Monitoring Manual.

    Science.gov (United States)

    Mason, Fred J.; Houdart, Joseph F.

    This manual is designed for students involved in environmental education programs dealing with water pollution problems. By establishing a network of Environmental Monitoring Stations within the educational system, four steps toward the prevention, control, and abatement of water pollution are proposed. (1) Train students to recognize, monitor,…

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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)

  19. Imagining Technicities

    DEFF Research Database (Denmark)

    Liboriussen, Bjarke; Plesner, Ursula

    2011-01-01

    to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

  20. 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

  1. 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

  2. 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…

  3. 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

  4. 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

  5. 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…

  6. 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

  7. Missouri Highway Safety Manual Recalibration

    Science.gov (United States)

    2018-05-01

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

  8. Developing a Pupil Transportation Manual.

    Science.gov (United States)

    Douglas, Dave

    1987-01-01

    District-level pupil transportation manuals that contain clear, concise information about objectives, policies, and regulations are a must. These manuals should also specify procedures concerning evaluation processes, personnel recruitment and selection, and the driver training program. (MLH)

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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

  14. INTERNATIONAL ENGLISH MANUAL

    Energy Technology Data Exchange (ETDEWEB)

    AMADOR, MABLE; KELLER, YVONNE KELLER

    2002-02-22

    This document presents a set of guidelines for authors who wish to express themselves more clearly to foreign readers, or readers whose first language is not American English. Topics include idioms, technical terms, jargon, word meaning, acronyms, and international conventions of measurement. The guidelines will help writers of technical documents present their ideas more effectively to audiences that may include individuals whose first language is not American English, including audiences with individuals from other English-speaking countries.

  15. Large Hadron Collider manual

    CERN Document Server

    Lavender, Gemma

    2018-01-01

    What is the universe made of? How did it start? This Manual tells the story of how physicists are seeking answers to these questions using the world’s largest particle smasher – the Large Hadron Collider – at the CERN laboratory on the Franco-Swiss border. Beginning with the first tentative steps taken to build the machine, the digestible text, supported by color photographs of the hardware involved, along with annotated schematic diagrams of the physics experiments, covers the particle accelerator’s greatest discoveries – from both the perspective of the writer and the scientists who work there. The Large Hadron Collider Manual is a full, comprehensive guide to the most famous, record-breaking physics experiment in the world, which continues to capture the public imagination as it provides new insight into the fundamental laws of nature.

  16. NDS EXFOR manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1996-01-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The IAEA Nuclear Data Section uses the EXFOR system not only for the center-to-center data exchange but also as its data storage and retrieval system. This NDS EXFOR MANUAL therefore contains the agreed EXFOR coding rules and format, supplemented by NDS internal compilation rules. The EXFOR system and the EXFOR nuclear data library with several million data records originate from the cooperation of an increasing number of data centers whose names and addresses can be found inside the Manual. Their contributions and cooperative efforts are gratefully acknowledged. (author)

  17. Radiation protection manual

    International Nuclear Information System (INIS)

    Spang, A.

    1983-01-01

    According to the Radiation Protection Ordinance, radiation protection experts directing or supervising the handling of radioactive materials must have expert knowledge. The concept of expert knowledge has been clearly defined by the Fachverband e.V. in a catalogue of instruction goals. The manual follows the principles of this catalogue; it presents the expert knowledge required in a total of 15 subject groups. There is an index which helps the reader to find his specific subject group and the knowledge required of him in this subject group. However, the manual gives only an outline of the subject matter in many instances and should therefore not be regarded as a textbook in the proper sense. (orig./HP) [de

  18. REBA experimenters' manual

    International Nuclear Information System (INIS)

    Schuch, R.L.

    1977-04-01

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

  19. NDS EXFOR manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1985-08-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The IAEA Nuclear Data Section uses the EXFOR system not only for the center-to-center data exchange but also as its data storage and retrieval system. This NDS EXFOR MANUAL therefore contains the agreed EXFOR coding rules and format, supplemented by NDS internal compilation rules. The EXFOR system and the EXFOR nuclear data library with several million data records originate from the cooperation of an increasing number of data centers whose names and addresses can be found inside the Manual. Their contributions and cooperative efforts are gratefully acknowledged. (author)

  20. MINTEQ user's manual

    International Nuclear Information System (INIS)

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

    1987-02-01

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

  1. Auxiliary mine ventilation manual

    International Nuclear Information System (INIS)

    Workplace Safety North

    2010-01-01

    An adequate ventilation system is needed for air quality and handling in a mine and is comprised of many different pieces of equipment for removing contaminated air and supplying fresh air and thereby provide a satisfactory working environment. This manual highlights auxiliary ventilation systems made up of small fans, ducts, tubes, air movers, deflectors and additional air flow controls which distribute fresh air delivered by the primary system to all areas. A review of auxiliary ventilation is provided. Design, operation and management issues are discussed and guidelines are furnished. This manual is limited to underground hard rock operations and does not address directly other, specific auxiliary systems, either in underground coal mines or uranium mines.

  2. Auxiliary mine ventilation manual

    Energy Technology Data Exchange (ETDEWEB)

    Workplace Safety North

    2010-07-01

    An adequate ventilation system is needed for air quality and handling in a mine and is comprised of many different pieces of equipment for removing contaminated air and supplying fresh air and thereby provide a satisfactory working environment. This manual highlights auxiliary ventilation systems made up of small fans, ducts, tubes, air movers, deflectors and additional air flow controls which distribute fresh air delivered by the primary system to all areas. A review of auxiliary ventilation is provided. Design, operation and management issues are discussed and guidelines are furnished. This manual is limited to underground hard rock operations and does not address directly other, specific auxiliary systems, either in underground coal mines or uranium mines.

  3. Oil trading manual

    International Nuclear Information System (INIS)

    Long, D.

    1995-01-01

    This manual provides basic information on all aspects of oil trading. Topics reviewed in Part 1 include physical characteristics and refining and oil pricing arrangements. Part 2 on instruments and markets contains chapters on crude oil markets, product markets, forward and futures contracts, forward paper markets, oil future exchanges, options, swaps and long term oil markets. Part 3 deals with administration and has chapters on operations and logistics, credit control, accounting, taxation of oil trading, contracts and legal and regulatory issues. (UK)

  4. Manual of Radiation Protection

    International Nuclear Information System (INIS)

    Gambini, D.J.; Granier, R.; Boisserie, G.

    1992-01-01

    This manual explains the principles and practice of radiation protection for those whose work in research, in the field of medicine or in the industry requires the use of radiation sources. It provides the information radiation users need to protect themselves and others and to understand and comply with international recommendations, regulations and legislation regarding the use of radionuclides and radiation machines. It is designed to teach a wide audience of doctors, biologists, research scientists, technicians, engineers, students and others

  5. IAC user manual

    Science.gov (United States)

    Vos, R. G.; Beste, D. L.; Gregg, J.

    1984-01-01

    The User Manual for the Integrated Analysis Capability (IAC) Level 1 system is presented. The IAC system currently supports the thermal, structures, controls and system dynamics technologies, and its development is influenced by the requirements for design/analysis of large space systems. The system has many features which make it applicable to general problems in engineering, and to management of data and software. Information includes basic IAC operation, executive commands, modules, solution paths, data organization and storage, IAC utilities, and module implementation.

  6. ETAP user's manual

    International Nuclear Information System (INIS)

    Watanabe, Norio; Higuchi, Suminori.

    1990-11-01

    The event tree analysis technique has been used in Probabilistic Safety Assessment for LWRs to delineate various accident scenarios leading to core melt or containment failure and to evaluate their frequencies. This technique often requires manual preparation of event trees with iterative process and time-consuming work in data handling. For the purpose of reducing manual efforts in event tree analysis, we developed a new software package named ETAP (Event Tree Analysis Supporting Program) for event tree analysis. ETAP is an interactive PC-based program which has the ability to construct, update, document, and quantify event trees. Because of its fast running capability to quantify event trees, use of the EATP program can make it easy to perform the sensitivity studies on a variety of system/containment performance issues. This report provides a user's manual for ETAP, which describes the structure, installation, and use of EATP. This software runs on NEC/PC-9800 or compatible PCs that have a 640 KB memory and MS-DOS 2.11 or higher. (author)

  7. Sodium safety manual

    International Nuclear Information System (INIS)

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

    1980-09-01

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

  8. Sustainability analysis. Development of various indicators of sustainability for technical environmental analysis and evaluation of local heat supply networks on the basis of regenerative energies in comparison to fossil energy sources

    International Nuclear Information System (INIS)

    Hehenberger-Risse, Diana

    2013-06-01

    The aim of this thesis is to define indicators to evaluate local heat supply systems based on renewable energy compared to fossil energy reference scenarios. With these indicators a assessment matrix was developed as a planning instrument for the realization of sustainable and energy-efficient local heat supply systems. Further inferences from single projects on regions can be done. In these thesis a method was developed to assess the sustainability of local heat supply systems with the focus on ecology under consideration of economically and social aspects. This method uses a set of indicators composed of Input-, Output-, Efficiency- and Balance indicators. To realize advancement in comparison to present situations, an environmental quality target to advance the environmental impacts of minimum 75% was defined. For the developing and application of the indicators different examples from projects and scenarios of combined heat production from Biomass, Biogas, Solar heat combined with near-surface geothermal storage; geothermal energy and fossil peakload supply were calculated. These scenarios were related to a basis fossil energy scenario. Overall, the two district heating projects Speichersdorf and Mitterteich were compared. In this case, the project Speichersdorf with different coverage areas and decrease heat densities was investigated. The lengths of electrical grid of two areas are 10,828 m and 6,027 m. Those were opposed to the biomass district-heating project Mitterteich with a grid length of 360 m and a higher heat density decrease. Furthermore, a scenario for heat supply was designed and calculated using geothermal plant operating in duplicate to provide heat to the large coverage area for the storage project village. The calculation of the various processes and scenarios was performed with the program GEMIS 4.8 based on the total heat generated (final energy) by the respective supply type. The study examined the main system components; boilers, solar heat

  9. 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

  10. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimize the management of the Technical Network (TN), to ease the understanding and purpose of devices connected to the TN, and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive email notifications from IT/CS asking them to add the corresponding information in the network database. Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  11. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimise the management of the Technical Network (TN), to facilitate understanding of the purpose of devices connected to the TN and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive e-mails from IT/CS asking them to add the corresponding information in the network database at "network-cern-ch". Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  12. 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

  13. Forest pests in central America: Field guide. Technical manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    In Central America, plant health problems have grown to an unprecedented level during the past few years along with the establishment of extensive homogeneous forest plantations, at times leading to the such drastic solutions as widespread felling of trees or massive use of pesticides. This field guide on forest pests was commissioned by the Multipurpose Tree Crop Dissemination (MADELENA) project and focuses on pests found in Costa Rica, home of PIROF (Programa Interinstitucional de Proteccion Forestal), a pioneer in forest pest research. The guide offers fast identification of forest pests and some general information on their biology and epidemiology. It consists of two sections: (1) lists of the specific pests (insects, vertebrates, pathogens, and parasites) of 18 priority forest tree species, and lists of the specific tree part or developmental stage they afflict.

  14. Manual of best practices of technical requirements for forestry laboratories

    Science.gov (United States)

    José Ugarte Oliva; José Camero Jiménez; Jessica Moscoso Guerrero

    2015-01-01

    Actualmente el comercio mundial se realiza a gran escala, estableciéndose requisitos cada día más exigentes, donde los productores y consumidores requieren realizar transacciones comerciales con unamayor de confiabilidad, y donde la calidad de los productos y servicioses un aspecto crítico en las actividades comerciales.

  15. Technical Manuals for the Elderly - Can Controlled Language Principles Help?

    DEFF Research Database (Denmark)

    Møller, Margrethe H.

    It is a challenge to the elderly to manoeuvre in today’s ICT society, where the command of technology plays an increasing role at all levels. On the one hand, age-related impairments may infl uence the ability of the elderly to familiarize with new technology. On the other hand, technological...

  16. 100-N technical manual. Volume 2A: Systems descriptions

    Energy Technology Data Exchange (ETDEWEB)

    1963-12-31

    This report contains engineering drawings for the control room, reactor monitoring systems, and reactor control systems for the N reactor. Each console in the control room is detailed. Other systems discussed are: stack air monitoring system, charging machine control systems, and heating and ventilation control systems. A N reactor plant glossary is included.

  17. Advanced Acoustic Model Technical Reference and User Manual

    Science.gov (United States)

    2010-09-01

    loss (point source). Aatm = ANSI/ ISO atmospheric absorption standard.28 Agrd = Ground reflection and attenuation losses, caused by the ground and the...433.2 1,021.8 25000 788 429.6 1,017.6 26000 754 426.1 1,013.4 27000 722 422.5 1,009.2 28000 691 418.9 1,004.9 29000 660 415.4 1,000.6 30000 631...ANSI/ ISO standard.28 Examples of the weather effects are described here. Consider a situation with winds approximately blowing from NW to SE. Figure 2

  18. AEL Continuous School Improvement Questionnaire. User Manual and Technical Report.

    Science.gov (United States)

    Meehan, Merrill L.; Cowley, Kimberly S.; Craig, James R.; Balow, Nancy; Childers, Robert D.

    The Continuous School Improvement Questionnaire (CSIQ) developed by the AEL helps a school staff gauge its performance on six dimensions related to continuous school improvement. Each member of the staff responds to the CSIQ individually. Although results might be used at the district or regional level, the most widely intended unit for applying…

  19. The Foreign Disclosure and Technical Information System (FORDTIS) User Manual

    Science.gov (United States)

    1985-07-01

    INDIA 10 BRITISH INDIAN OCEAN TERRITORY IP CLIPPERTON ISLAND IQ UNITED STATES MISCELLANEOUS PACIFIC ISLANDS (obsolete) IR , IRAN IS ISRAEL IT...CARTIER ISLANDS AU AUSTRIA AV ANGUILLA AY ANTARCTICA BA BAHRAIN BB BARBADOS ’ - ’ BC BOTSWANA BD BERMUDA BE BELGIUM BP...BAHAMAS, THE BG BANGLADESH BH BELIZE BL BOLIVIA BM BURMA BN BENIN (formerly DM) BP SOLOMON ISLANDS BQ NAVASSA ISLAND BR BRAZIL BS BASSAS DA INDIA

  20. Energy Statistics Manual; Manual de Estadisticas Energeticas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    Detailed, complete, timely and reliable statistics are essential to monitor the energy situation at a country level as well as at an international level. Energy statistics on supply, trade, stocks, transformation and demand are indeed the basis for any sound energy policy decision. For instance, the market of oil -- which is the largest traded commodity worldwide -- needs to be closely monitored in order for all market players to know at any time what is produced, traded, stocked and consumed and by whom. In view of the role and importance of energy in world development, one would expect that basic energy information to be readily available and reliable. This is not always the case and one can even observe a decline in the quality, coverage and timeliness of energy statistics over the last few years.

  1. Energy Statistics Manual; Manual Statistik Energi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Detailed, complete, timely and reliable statistics are essential to monitor the energy situation at a country level as well as at an international level. Energy statistics on supply, trade, stocks, transformation and demand are indeed the basis for any sound energy policy decision. For instance, the market of oil -- which is the largest traded commodity worldwide -- needs to be closely monitored in order for all market players to know at any time what is produced, traded, stocked and consumed and by whom. In view of the role and importance of energy in world development, one would expect that basic energy information to be readily available and reliable. This is not always the case and one can even observe a decline in the quality, coverage and timeliness of energy statistics over the last few years.

  2. 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...

  3. INIS: Database manual

    International Nuclear Information System (INIS)

    2003-01-01

    This document is one in a series of publications known as the INIS Reference Series. It is intended for users of INIS (International Nuclear Information System) output data on various media (FTP file, CD-ROM, e-mail file, earlier magnetic tape, cartridge, etc.). This manual provides a description of each data element including information on contents, structure and usage as well as historical overview of additions, deletions and changes of data elements and their contents that have taken place over the years. Each record contains certain control data fields (001-009), one, two or three bibliographic levels, a set of descriptors, and zero, one or more abstracts, one in English and optionally one or more in another language. In order to facilitate the description of the system, the sequence of data elements is based on the input or, as it is internally called, worksheet format which differs from the exchange format described in the manual IAEA-INIS-7. A separate section is devoted to each data element and deviations from the exchange format are indicated whenever present. As the Record Leader and the Directory are sufficiently explained in Chapter 3.1 of IAEA-INIS-7, the contents of this manual are limited to control fields and data fields; the detailed explanations are intended to supplement the basic information given in Chapter 3.2 of IAEA-INIS-7. Bibliographic levels are used to identify component parts of a publication, i.e. chapters in a book, articles in a journal issue, conference papers in a proceedings volume. All bibliographic levels contained in a record are given in a control data field. Each bibliographic level identifier appears in the subdirectory with a pointer to its position in the record

  4. MAP user's manual copyright

    International Nuclear Information System (INIS)

    Pillsbury, R.D. Jr.

    1991-12-01

    The program MITMAP represents a set of general purpose, two- dimensional, finite element programs for the calculation of magnetic fields. It consists of the program MAP and MAP2DJ. The two programs are used to solve different electromagnetic problems, but they have a common set of subrountines for pre- and postprocessing. Originally separate programs, they have been combined to make modification easier. The manuals, however, will remain separate. The program MAP is described in this manual. MAP is applicable to the class of problems with two-dimensional-planar or axisymmetric - geometries, in which the current density and the magnetic vector potential have only a single nonvanishing component. The single component is associated with the direction that is perpendicular to the plane of the problem and is invariant with respect to that direction. Maxwell's equations can be reduced to a solver diffusion equation in terms of the single, nonvanishing component of the magnetic vector potential for planar problems and to a single component of a vector potential for planar problems and to a single component of a vector diffusion equation for axisymmetric problems. The magnetic permeability appears in the governing equation. The permeability may be a function of the magnetic flux density. In addition, any electrically conducting material present will have eddy currents induced by a time varying magnetic field. These eddy currents must be included in the solution process. This manual provides a description of the structure of the input data and output for the program. There are several example problems presented that illustrate the major program features. Appendices are included that contain a derivation of the governing equations and the application of the finite element method to the solution of the equations

  5. 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.

  6. Modern TTL circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Modern TTL Circuits Manual provides an introduction to the basic principles of Transistor-Transistor Logic (TTL). This book outlines the major features of the 74 series of integrated circuits (ICs) and introduces the various sub-groups of the TTL family.Organized into seven chapters, this book begins with an overview of the basics of digital ICs. This text then examines the symbology and mathematics of digital logic. Other chapters consider a variety of topics, including waveform generator circuitry, clocked flip-flop and counter circuits, special counter/dividers, registers, data latches, com

  7. Manual of Decolonization

    DEFF Research Database (Denmark)

    Gigone, Fabio

    2010-01-01

    During a residency in Bethlehem, Venice-based design and research studio Salottobuono formulated a 'strategy of subversion' for Israeli settlements in the West Bank. From this comes the elegant Manual of Decolonization; a generic but detailed resource for all post-occupation scenarios. Assessing...... how evacuated and imposed structures can be transformed in collaboration with local stakeholders, the book's plans, models and projections are divided into themes like 'De-parcelling', 'Re-combining' and 'Un-roofing'; landscape, nature and materials are considered at length. The outcome is an open...

  8. CMOS circuits manual

    CERN Document Server

    Marston, R M

    1995-01-01

    CMOS Circuits Manual is a user's guide for CMOS. The book emphasizes the practical aspects of CMOS and provides circuits, tables, and graphs to further relate the fundamentals with the applications. The text first discusses the basic principles and characteristics of the CMOS devices. The succeeding chapters detail the types of CMOS IC, including simple inverter, gate and logic ICs and circuits, and complex counters and decoders. The last chapter presents a miscellaneous collection of two dozen useful CMOS circuits. The book will be useful to researchers and professionals who employ CMOS circu

  9. Coal marketing manual 1987

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    This manual provides information on the international coal market in tabulated format. Statistics are presented for the Australian coal industry, exports, currency movements, world coal production, coal and coke imports and exports. Detailed information is provided on the Australian coal industry including mine specific summaries. Pricing summaries for thermal and coking coal in 1987, coal quality standards and specifications, trends in coal prices and stocks. Imports and exports for World coal and coke, details of shipping, international ports and iron and steel production. An exporters index of Australian and overseas companies with industry and government contacts is included. 15 figs., 67 tabs.

  10. Optoelectronics circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Optoelectronics Circuits Manual covers the basic principles and characteristics of the best known types of optoelectronic devices, as well as the practical applications of many of these optoelectronic devices. The book describes LED display circuits and LED dot- and bar-graph circuits and discusses the applications of seven-segment displays, light-sensitive devices, optocouplers, and a variety of brightness control techniques. The text also tackles infrared light-beam alarms and multichannel remote control systems. The book provides practical user information and circuitry and illustrations.

  11. Timergenerator circuits manual

    CERN Document Server

    Marston, R M

    2013-01-01

    Timer/Generator Circuits Manual is an 11-chapter text that deals mainly with waveform generator techniques and circuits. Each chapter starts with an explanation of the basic principles of its subject followed by a wide range of practical circuit designs. This work presents a total of over 300 practical circuits, diagrams, and tables.Chapter 1 outlines the basic principles and the different types of generator. Chapters 2 to 9 deal with a specific type of waveform generator, including sine, square, triangular, sawtooth, and special waveform generators pulse. These chapters also include pulse gen

  12. Health physics instrument manual

    International Nuclear Information System (INIS)

    Gupton, E.D.

    1978-08-01

    The purpose of this manual is to provide apprentice health physics surveyors and other operating groups not directly concerned with radiation detection instruments a working knowledge of the radiation detection and measuring instruments in use at the Laboratory. The characteristics and applications of the instruments are given. Portable instruments, stationary instruments, personnel monitoring instruments, sample counters, and miscellaneous instruments are described. Also, information sheets on calibration sources, procedures, and devices are included. Gamma sources, beta sources, alpha sources, neutron sources, special sources, a gamma calibration device for badge dosimeters, and a calibration device for ionization chambers are described

  13. IMAGE User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Stehfest, E; De Waal, L; Oostenrijk, R.

    2010-09-15

    This user manual contains the basic information for running the simulation model IMAGE ('Integrated Model to Assess the Global Environment') of PBL. The motivation for this report was a substantial restructuring of the source code for IMAGE version 2.5. The document gives concise content information about the submodels, tells the user how to install the program, describes the directory structure of the run environment, shows how scenarios have to be prepared and run, and gives insight in the restart functionality.

  14. Radioanalytical methods manual

    International Nuclear Information System (INIS)

    Chiu, N.W.; Dean, J.R.

    1986-01-01

    This Radioanalytical Methods manual is comprised of 12 chapters. It includes a review of the pertinent literature up to the end of 1982 pertaining to the measurement of the radioactive species listed under the terms of the contract. Included is methodology recommended for the decompositions of soils, tailings, ores, biological samples and air filters. Detailed analytical methodology for the measurement of gross alpha, gross beta, gross gamma, uranium, radium-226, radium-228, lead-210, thorium-232, thorium-230, thorium-228, total thorium, radon-222, radon-220 and radon-219 is presented

  15. ASSERT-4 user's manual

    International Nuclear Information System (INIS)

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

    1984-09-01

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

  16. Health and safety manual

    International Nuclear Information System (INIS)

    1980-02-01

    The manual consists of the following chapters: general policies and administration; the Environmental Health and Safety Department; the Medical Services Department: biological hazards; chemical safety; confined space entry; cryogenic safety; electrical safety; emergency plans; engineering and construction; evacuations, trenching, and shoring; fire safety; gases, flammable and compressed; guarding, mechanical; ladders and scaffolds, work surfaces; laser safety; materials handling and storage; noise; personal protective equipment; pressure safety; radiation safety, ionizing and non-ionizing; sanitation; seismic safety; training, environmental health and safety; tools, power and hand-operated; traffic and transportation; and warning signs and devices

  17. Astronaut training manual

    Science.gov (United States)

    Coleman, E. A.

    1980-01-01

    Scientific information from previous space flights, space medicine, exercise physiology, and sports medicine was used to prepare a physical fitness manual suitable for use by members of the NASA astronaut population. A variety of scientifically valid exercise programs and activities suitable for the development of physical fitness are provided. Programs, activities, and supportive scientific data are presented in a concise, easy to read format so as to permit the user to select his or her mode of training with confidence and devote time previously spent experimenting with training routines to preparation for space flight. The programs and activities included were tested and shown to be effective and enjoyable.

  18. FISPACT 97: user manual

    International Nuclear Information System (INIS)

    Forrest, R.A.; Sublet, J.-Ch.

    1997-05-01

    FISPACT is the inventory code included in the European Activation System (EASY). A new version of FISPACT: FISPACT-97 has been developed and this report is the User manual for the code. It explains the use of all the code words used in the input file to specify a FISPACT run and describes how all the data files are connected. A series of appendices cover the working of the code and the physical and mathematical details. Background information on the data files and extensive examples of input files suitable for various applications are included. (Author)

  19. Timber designers' manual

    CERN Document Server

    Ozelton, E C

    2008-01-01

    This major reference manual covers both overall and detail design of structural timber, including aspects such as shear deflection, creep, dynamic and lateral stability considerations for flexural members.Available for the first time in paperback, the Third Edition was substantially revised to take account of the many changes since the previous edition was published in 1984. It is based on British Standard BS 5268-2: 2002, which brought design concepts closer to European practice and Eurocode 5.Features of the Third Edition include:* information on bolt values including

  20. NASCAP programmer's reference manual

    Science.gov (United States)

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

    1993-05-01

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

  1. Percept User Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Carnes, Brian [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kennon, Stephen Ray [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This document is the main user guide for the Sierra/Percept capabilities including the mesh_adapt and mesh_transfer tools. Basic capabilities for uniform mesh refinement (UMR) and mesh transfers are discussed. Examples are used to provide illustration. Future versions of this manual will include more advanced features such as geometry and mesh smoothing. Additionally, all the options for the mesh_adapt code will be described in detail. Capabilities for local adaptivity in the context of offline adaptivity will also be included. This page intentionally left blank.

  2. Optoelectronics circuits manual

    CERN Document Server

    Marston, R M

    1999-01-01

    This manual is a useful single-volume guide specifically aimed at the practical design engineer, technician, and experimenter, as well as the electronics student and amateur. It deals with the subject in an easy to read, down to earth, and non-mathematical yet comprehensive manner, explaining the basic principles and characteristics of the best known devices, and presenting the reader with many practical applications and over 200 circuits. Most of the ICs and other devices used are inexpensive and readily available types, with universally recognised type numbers.The second edition

  3. 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

  4. 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

  5. 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...

  6. 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

  7. 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

  8. Sustainability analysis. Development of various indicators of sustainability for technical environmental analysis and evaluation of local heat supply networks on the basis of regenerative energies in comparison to fossil energy sources; Nachhaltigkeitsanalyse. Entwicklung verschiedener Nachhaltigkeitsindikatoren zur umwelttechnischen Analyse und Bewertung von Nahwaermeversorgungsnetzen auf Basis regenerativer Energien im Vergleich zu fossilen Energietraegern

    Energy Technology Data Exchange (ETDEWEB)

    Hehenberger-Risse, Diana

    2013-06-15

    The aim of this thesis is to define indicators to evaluate local heat supply systems based on renewable energy compared to fossil energy reference scenarios. With these indicators a assessment matrix was developed as a planning instrument for the realization of sustainable and energy-efficient local heat supply systems. Further inferences from single projects on regions can be done. In these thesis a method was developed to assess the sustainability of local heat supply systems with the focus on ecology under consideration of economically and social aspects. This method uses a set of indicators composed of Input-, Output-, Efficiency- and Balance indicators. To realize advancement in comparison to present situations, an environmental quality target to advance the environmental impacts of minimum 75% was defined. For the developing and application of the indicators different examples from projects and scenarios of combined heat production from Biomass, Biogas, Solar heat combined with near-surface geothermal storage; geothermal energy and fossil peakload supply were calculated. These scenarios were related to a basis fossil energy scenario. Overall, the two district heating projects Speichersdorf and Mitterteich were compared. In this case, the project Speichersdorf with different coverage areas and decrease heat densities was investigated. The lengths of electrical grid of two areas are 10,828 m and 6,027 m. Those were opposed to the biomass district-heating project Mitterteich with a grid length of 360 m and a higher heat density decrease. Furthermore, a scenario for heat supply was designed and calculated using geothermal plant operating in duplicate to provide heat to the large coverage area for the storage project village. The calculation of the various processes and scenarios was performed with the program GEMIS 4.8 based on the total heat generated (final energy) by the respective supply type. The study examined the main system components; boilers, solar heat

  9. 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)

  10. 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

  11. 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

  12. 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…

  13. Technical Basis of Scaling Relationships for the Pretreatment Engineering Platform

    Energy Technology Data Exchange (ETDEWEB)

    Kuhn, William L.; Arm, Stuart T.; Huckaby, James L.; Kurath, Dean E.; Rassat, Scot D.

    2008-07-15

    Pacific Northwest National Laboratory has been tasked by Bechtel National Inc. (BNI) on the River Protection Project-Waste Treatment Plant (RPP-WTP) project to perform research and development activities. The Pretreatment Engineering Platform (PEP) is being designed and constructed as part of a plan to respond to an issue raised by the WTP External Flowsheet Review Team (EFRT) entitled “Undemonstrated Leaching Processes” and numbered M12. The PEP replicates the WTP leaching process using prototypic equipment and control strategies. The approach for scaling PEP performance data to predict WTP performance is critical to the successful resolution of the EFRT issue. This report describes the recommended PEP scaling approach, PEP data interpretation and provides recommendations on test conduct and data requirements.

  14. Mesorad dose assessment model. Volume 1. Technical basis

    International Nuclear Information System (INIS)

    Scherpelz, R.I.; Bander, T.J.; Athey, G.F.; Ramsdell, J.V.

    1986-03-01

    MESORAD is a dose assessment model for emergency response applications. Using release data for as many as 50 radionuclides, the model calculates: (1) external doses resulting from exposure to radiation emitted by radionuclides contained in elevated or deposited material; (2) internal dose commitment resulting from inhalation; and (3) total whole-body doses. External doses from airborne material are calculated using semi-infinite and finite cloud approximations. At each stage in model execution, the appropriate approximation is selected after considering the cloud dimensions. Atmospheric processes are represented in MESORAD by a combination of Lagrangian puff and Gaussian plume dispersion models, a source depletion (deposition velocity) dry deposition model, and a wet deposition model using washout coefficients based on precipitation rates

  15. SENTINEL trademark technical basis report for Limerick. Final report

    International Nuclear Information System (INIS)

    Burns, E.T.; Lee, L.K.; Mitman, J.T.; Vanover, D.E.; Wilson, D.K.

    1997-12-01

    PECO Energy in cooperation with the Electric Power Research Institute (EPRI) installed the SENTINEL trademark software at its Limerick Generating Station. This software incorporates models of the safety and support systems which are used to display the defense in depth present in the plant and a quantitative assessment of the plant risks during proposed on-line maintenance. During the past year, PECO Energy personnel have used this display to evaluate the safety of proposed on-line maintenance schedules. The report describes the motivation for and the development of the SENTINEL software. It describes the generation of Safety Function Assessment Trees and Plant Transient Assessment Trees and their use in evaluating the level of defense-in-depth of key plant safety functions and the susceptibility of the plant to critical transient events. Their results are displayed by color indicators ranging from green, through yellow and orange to red to show increasingly hazardous conditions. The report describes the use of the Limerick Probabilistic Safety Assessment within the SENTINEL code to calculate an instantaneous core damage frequency and the criteria by which this frequency is translated to a color indicator. Finally, the report describes the Performance Criteria Assessment which tracks and trends system/train unavailability to document conformance to the requirements of the Maintenance Rule

  16. Technical Basis of Scaling Relationships for the Pretreatment Engineering Platform

    International Nuclear Information System (INIS)

    Kuhn, William L.; Arm, Stuart T.; Huckaby, James L.; Kurath, Dean E.; Rassat, Scot D.

    2008-01-01

    Pacific Northwest National Laboratory has been tasked by Bechtel National Inc. (BNI) on the River Protection Project-Waste Treatment Plant (RPP-WTP) project to perform research and development activities. The Pretreatment Engineering Platform (PEP) is being designed and constructed as part of a plan to respond to an issue raised by the WTP External Flowsheet Review Team (EFRT) entitled 'Undemonstrated Leaching Processes' and numbered M12. The PEP replicates the WTP leaching process using prototypic equipment and control strategies. The approach for scaling PEP performance data to predict WTP performance is critical to the successful resolution of the EFRT issue. This report describes the recommended PEP scaling approach, PEP data interpretation and provides recommendations on test conduct and data requirements

  17. MIXING OF INCOMPATIBLE MATERIALS IN WASTE TANKS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    SANDGREN, K.R.

    2006-01-01

    This document presents onsite radiological, onsite toxicological, and offsite toxicological consequences, risk binning, and control decision results for the mixing of incompatible materials in waste tanks representative accident. Revision 4 updates the analysis to consider bulk chemical additions to single shell tanks (SSTs)

  18. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    KOZLOWSKI, D.S.

    2005-01-01

    The body of this document analyzes scenarios involving releases of dried tank waste from the DBVS dried waste transfer system and OGTS HEPA filters. Analyses of dried waste release scenarios from the CH-TRUM WPU are included as Appendix D

  19. SENTINEL trademark technical basis report for Peach Bottom. Final report

    International Nuclear Information System (INIS)

    1998-04-01

    PECO Energy in cooperation with the Electric Power Research Institute (EPRI) installed the SENTINEL trademark software at its Peach Bottom Atomic Power Station (PBAPS). This software incorporates models of the safety and support systems which are used to display the defense in depth present in the plant and a quantitative assessment of the plant risks during proposed on-line maintenance. During the past nine months, PECO Energy personnel have used this display to evaluate the safety of proposed on-line maintenance schedules. The report describes the motivation for and the development of the SENTINEL software. It describes the generation of Safety Function Assessment Trees and Plant Transient Assessment Trees and their use in evaluating the level of defense-in-depth of key plant safety functions and the susceptibility of the plant to critical transient events. Their results are displayed by color indicators ranging from green, through yellow and orange, to red to show increasingly hazardous conditions. The report describes the use of the PBAPS Probabilistic Safety Assessment within the SENTINEL code to calculate an instantaneous core damage frequency and the criteria by which this frequency is translated to a color indicator

  20. Technical Basis for Flood Protection at Nuclear Power Plants

    Science.gov (United States)

    2015-07-01

    CHL SR-15-3 36 forces (FEMA 1993). The building’s utilities and sanitary facilities, including heating, air conditioning, electrical, water supply...and sanitary sewage services must be located above the DBFL, completely enclosed within the building’s watertight walls or made watertight and...to a height of approximately 1.5 ft. In areas where cohesive materials (such as clay ) are available, greater heights can be achieved, depending on