Procedures manual for the Evaluated Nuclear Structure Data File

International Nuclear Information System (INIS)

Bhat, M.R.

1987-10-01

This manual is a collection of various notes, memoranda and instructions on procedures for the evaluation of data in the Evaluated Nuclear Structure Data File (ENSDF). They were distributed at different times over the past few years to the evaluators of nuclear structure data and some of them were not readily avaialble. Hence, they have been collected in this manual for ease of reference by the evaluators of the international Nuclear Structure and Decay Data (NSDD) network contribute mass-chains to the ENSDF. Some new articles were written specifically for this manual and others are reivsions of earlier versions

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1999-07-02

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Extract from IAEA's Resources Manual in Nuclear Medicine - Part 2. - Human Resources Development

International Nuclear Information System (INIS)

2003-01-01

The Nuclear Medicine Section of the International Atomic Energy Agency is now engaged in finalizing a reference manual in nuclear medicine, entitled, 'Resources Manual in Nuclear Medicine'. Several renowned professionals from all over the world, from virtually all fields of nuclear medicine have contributed to this manual. The World Journal of Nuclear Medicine will publish a series of extracts from this manual as previews. This is the second extract from the Resources Manual, Part-2 of the chapter on Human Resources Development. (author)

Quality management for nuclear power plant operation: A manual

International Nuclear Information System (INIS)

1990-01-01

The experience from well operated nuclear power plants shows that achievement of safe, reliable and economic performance is closely related to a strong commitment and involvement by the management personnel. A system of controls is necessary to ensure that satisfactory quality in operation is achieved and maintained over the long term. The key to achieving and assuring quality lies in the ability of management to define performance objectives and to ensure that significant safety and reliability problems are prevented or detected early and resolved. This Manual has been developed by the IAEA to assist plant managers in fulfilling their responsibility with regard to the control and direction of quality and of quality assurance activities in nuclear power plant operation. It emphasizes quality objectives for nuclear power plant operation and indicates the way in which a quality system based on quality assurance principles as established in the IAEA NUSS documents can be used by managers to accomplish these objectives. Since the Manual is mainly directed at management personnel, it is presented in the form of short highlighted practices complemented by typical examples of forms and procedures. Since not all the activities under the heading of quality in operation could be covered in a single document, the activities selected for this Manual comprise those where it was felt that practical advice is generally needed. A pragmatic document useful for direct application by plant managers was the envisaged objective

Nuclear power plant control room crew task analysis database: SEEK system. Users manual

International Nuclear Information System (INIS)

Burgy, D.; Schroeder, L.

1984-05-01

The Crew Task Analysis SEEK Users Manual was prepared for the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission. It is designed for use with the existing computerized Control Room Crew Task Analysis Database. The SEEK system consists of a PR1ME computer with its associated peripherals and software augmented by General Physics Corporation SEEK database management software. The SEEK software programs provide the Crew Task Database user with rapid access to any number of records desired. The software uses English-like sentences to allow the user to construct logical sorts and outputs of the task data. Given the multiple-associative nature of the database, users can directly access the data at the plant, operating sequence, task or element level - or any combination of these levels. A complete description of the crew task data contained in the database is presented in NUREG/CR-3371, Task Analysis of Nuclear Power Plant Control Room Crews (Volumes 1 and 2)

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Manual of functions, assignments, and responsibilities for nuclear safety: Revision 2

Energy Technology Data Exchange (ETDEWEB)

1994-10-15

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

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

International Nuclear Information System (INIS)

1988-01-01

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

The design of operating procedures manuals for nuclear power plants

International Nuclear Information System (INIS)

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

1977-03-01

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

Development of an in vitro laboratory manual for nuclear medicine technology students

International Nuclear Information System (INIS)

Meyers, A.

1989-01-01

This study evaluated existing in vitro education materials in qualitative and quantitative parameters that currently exist to educate potential clinicians of nationally accredited nuclear medicine programs. A review of over 300 articles, texts, and manuals pertaining to in vitro nuclear medicine procedures clearly demonstrated that no in vitro laboratory manual for undergraduate students presently exited. Every nuclear medicine program director in the United States was surveyed. They were asked for their overall philosophy in terms of developing an in vitro manual and requested to evaluate the significant of 22 general principles/concepts and 34 specific laboratory testing procedures. From the response to the survey, an in vitro nuclear medicine manual was created and appended to the study. The manual consists of lecture and study material, chapter reviews, and laboratory assignments and exercises

Electronic manual of the nuclear characteristics analysis code-set for FBR

International Nuclear Information System (INIS)

Makino, Tohru

2001-03-01

Reactor Physics Gr., System Engineering Technology Division, O-arai Engineering Center has consolidated the nuclear design database to improve analytical methods and prediction accuracy for large fast breeder cores such as demonstration or commercial FBRs from the previous research. The up-to-date information about usage of the nuclear characteristics analysis code-set was compiled as a part of the improvement of basic design data base for FBR core. The outlines of the electronic manual are as follows; (1) The electronic manual includes explanations of following codes: JOINT : Code Interface Program. SLAROM, CASUP : Effective Cross Section Calculation Code. CITATION-FBR : Diffusion Analysis Code. PERKY : Perturbative Diffusion Analysis Code. SNPERT, SNPERT-3D : Perturbative Transport Analysis Code. SAGEP, SAGEP-3D : Sensitivity Coefficient Calculation Code. NSHEX : Transport Analysis Code using Nodal Method. ABLE : Cross Section Adjustment Calculation Code. ACCEPT : Predicting Accuracy Evaluation Code. (2) The electronic manual is described using HTML file format and PDF file for easy maintenance, updating and for easy referring through JNC Intranet. User can refer manual pages by usual Web browser software without any special setup. (3) Many of manual pages include link-tags to jump to related pages. String search is available in both HTML and PDF documents. (4) User can download source code, sample input data and shell script files to carry out each analysis from download page of each code (JNC inside only). (5) Usage of the electronic manual and maintenance/updating process are described in this report and it makes possible to enroll new code or new information in the electronic manual. Since the information has been taken into account about modifications and error fixings, added to each code after the last consolidation in 1994, the electronic manual would cover most recent status of the nuclear characteristics analysis code-set. One of other advantages of use

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

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

2000-02-03

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-05-15

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

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)

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)

SNAP operating system reference manual

International Nuclear Information System (INIS)

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

1982-03-01

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

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

Feedwater control system in nuclear power plants

International Nuclear Information System (INIS)

Masuyama, Hideo.

1981-01-01

Purpose: To enable switching operation for feedwater systems in a short time and with no fluctuations in the reactor water level by increasing or decreasing the flow rate in the feedwater systems during automatic operation by the amount of the fluctuations in the flow rate in the feedwater system during manual operation. Constitution: In a BWR type nuclear power plant having a plurality of feedwater systems to a nuclear reactor, a feedwater control system is constituted with a reactor water level controller, a M/A switcher for switching either of automatic flow rate demand signals or manual flow rate set signals from the reactor level controller to apply flow rate demand signals for each of the feedwater systems, a calculation device for calculating the flow rate set signals in the feedwater systems during manual operation and an adder for subtracting the flow rate set signals in the manual feedwater system calculated in the calculating device from the automatic flow rate demand signals for the feedwater systems during automatic operation. This enables rapid switching for the feedwater systems with no fluctuations in the reactor water level by increasing or decreasing the flow rate in the feedwater systems during automatic operation by the amount of fluctuations in the flow rate in the feedwater systems during manual operation and compensating the effects in upon manual and automatic switching by the M/A switcher. (Seki, T.)

Quality assurance manual for the development of digital systems

International Nuclear Information System (INIS)

Lee, Cheol Kwon; Kwon, Kee Choon; You, Young Eun; Kim, Kwan Hyun; Park, Jung Woo; Park, Chan Seok

2001-12-01

A digital safety system is being developed by three companies under the Korea Nuclear I and C System R and D Program. This Quality Assurance Manual (QAM) is written to ensure the safety and reliability of the system and to meet the regulatory requirements associated with quality assurance. This QAM describes eighteen elements of quality assurance criteria required for the development of the system, which are coincident with the criteria specified in Nuclear Energy Laws and Enforcement Regulations of Nuclear Energy Laws and 10CFR50 Appendix B. This QAM is submitted to the regulatory body with other documents related to the quality assurance activities performed during the system development. And its safety, validity and fulfillment are reviewed and audited in the review process of topical report of the digital safety system

HVAC system operation manual of IMEF

International Nuclear Information System (INIS)

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

1997-06-01

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

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

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

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1975-01-01

Policies and procedures are presented which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumers Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary

Nuclear structure references coding manual

International Nuclear Information System (INIS)

Ramavataram, S.; Dunford, C.L.

1984-02-01

This manual is intended as a guide to Nuclear Structure References (NSR) compilers. The basic conventions followed at the National Nuclear Data Center (NNDC), which are compatible with the maintenance and updating of and retrieval from the Nuclear Structure References (NSR) file, are outlined. The structure of the NSR file such as the valid record identifiers, record contents, text fields as well as the major topics for which [KEYWORDS] are prepared are ennumerated. Relevant comments regarding a new entry into the NSR file, assignment of [KEYNO ], generation of [SELECTRS] and linkage characteristics are also given. A brief definition of the Keyword abstract is given followed by specific examples; for each TOPIC, the criteria for inclusion of an article as an entry into the NSR file as well as coding procedures are described. Authors submitting articles to Journals which require Keyword abstracts should follow the illustrations. The scope of the literature covered at NNDC, the categorization into Primary and Secondary sources, etc. is discussed. Useful information regarding permitted character sets, recommended abbreviations, etc. is given

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

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)

Intelligent Automated Nuclear Fuel Pellet Inspection System

International Nuclear Information System (INIS)

Keyvan, S.

1999-01-01

At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques

Manual on quality assurance for the survey, evaluation and confirmation of nuclear power plant sites

International Nuclear Information System (INIS)

1987-04-01

The present Manual on Quality Assurance for the Survey, Evaluation and Confirmation of Nuclear Power Plant Sites contains supporting material and illustrates examples for implementing the requirements contained in the Code of Practice on Quality Assurance for Safety in Nuclear Power Plants to the activities of survey, evaluation and confirmation of nuclear power plant sites. At the same time the Code of Practice for Safety in Nuclear Power Plant Siting, and Safety Guides in the siting series contain requirements and recommendations to implement a quality assurance programme in selected activities of the siting process. This manual is intended to provide guidance and illustrate examples on this implementation. During preparation and reviews of this Manual it was found out that the methodology of implementation of the quality assurance programme in siting activities is still under development. For these reasons it was considered appropriate to publish this Manual as a temporary publication for trial use

Manual for IRS Coding. Joint IAEA/NEA International Reporting System for Operating Experience

International Nuclear Information System (INIS)

2011-01-01

The International Reporting System for Operating Experience (IRS) is jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). In early 2010, the IAEA and OECD/NEA jointly issued the IRS Guidelines, which described the reporting system and process and gave users the necessary elements to enable them to produce IRS reports to a high standard of quality while retaining the effectiveness of the system expected by all Member States operating nuclear power plants. The purpose of the present Manual for IRS Coding is to provide supplementary guidance specifically on the coding element of IRS reports to ensure uniform coding of events that are reported through IRS. This Coding Manual does not supersede the IRS Guidelines, but rather, supports users and preparers in achieving a consistent and high level of quality in their IRS reports. Consistency and high quality in the IRS reports allow stakeholders to search and retrieve specific event information with ease. In addition, well-structured reports also enhance the efficient management of the IRS database. This Coding Manual will give specific guidance on the application of each section of the IRS codes, with examples where necessary, of when and how these codes are to be applied. As this reporting system is owned by the Member States, this manual has been developed and approved by the IRS National Coordinators with the assistance of the IAEA and NEA secretariats

Manual fire fighting tactics at Nuclear Power Plant

International Nuclear Information System (INIS)

Jee, Moon Hak; Moon, Chan Kook

2012-01-01

The general requirements of fire protection at nuclear power plant (NPP) are fire protection program, fire hazard analysis, and fire prevention features. In addition, specific fire protection requirements such as water supplies, fire detection, fire protection of safe related equipment, and safe shutdown capabilities must be provided. Particularly, manual fire fighting is required as specific requirements with the provisions to secure manual fire suppression, fire brigade and its training, and administrative controls for manual fire fighting. If a fire is alarmed and confirmed to be a real fire, the fire brigade must take manual fire fighting activities as requested at fire protection program. According to the present requirements in itself, there is not any specific manual fire fighting ways or practical strategies. In general, fire zones or compartments at NPPs are built in a confined condition. In theory, the fire condition will change from a combustible-controlled fire to a ventilation-governing fire with the time duration. In case of pool fire with the abundant oxygen and flammable liquid, it can take just a few minutes for the flash-over to occur. For the well-confined fire zone, it will change from a flame fire to a smoldering state before the entrance door is opened by the fire brigade. In this context, the manual fire fighting activities must be based on a quantitative analysis and a fire risk evaluation. At this paper, it was suggested that the fire zones at NPPs should be grouped on the inherent functions and fire characteristics. Based on the fire risk characteristics and the fire zone grouping, the manual fire fighting tactics are suggested as an advanced fire fighting solution

Nuclear science references coding manual

International Nuclear Information System (INIS)

Ramavataram, S.; Dunford, C.L.

1996-08-01

This manual is intended as a guide to Nuclear Science References (NSR) compilers. The basic conventions followed at the National Nuclear Data Center (NNDC), which are compatible with the maintenance and updating of and retrieval from the Nuclear Science References (NSR) file, are outlined. In Section H, the structure of the NSR file such as the valid record identifiers, record contents, text fields as well as the major TOPICS for which are prepared are enumerated. Relevant comments regarding a new entry into the NSR file, assignment of , generation of and linkage characteristics are also given in Section II. In Section III, a brief definition of the Keyword abstract is given followed by specific examples; for each TOPIC, the criteria for inclusion of an article as an entry into the NSR file as well as coding procedures are described. Authors preparing Keyword abstracts either to be published in a Journal (e.g., Nucl. Phys. A) or to be sent directly to NNDC (e.g., Phys. Rev. C) should follow the illustrations in Section III. The scope of the literature covered at the NNDC, the categorization into Primary and Secondary sources, etc., is discussed in Section IV. Useful information regarding permitted character sets, recommended abbreviations, etc., is given under Section V as Appendices

PRIS-STATISTICS: Power Reactor Information System Statistical Reports. User's Manual

International Nuclear Information System (INIS)

2013-01-01

The IAEA developed the Power Reactor Information System (PRIS)-Statistics application to assist PRIS end users with generating statistical reports from PRIS data. Statistical reports provide an overview of the status, specification and performance results of every nuclear power reactor in the world. This user's manual was prepared to facilitate the use of the PRIS-Statistics application and to provide guidelines and detailed information for each report in the application. Statistical reports support analyses of nuclear power development and strategies, and the evaluation of nuclear power plant performance. The PRIS database can be used for comprehensive trend analyses and benchmarking against best performers and industrial standards.

INES: The International Nuclear Event Scale user's manual

International Nuclear Information System (INIS)

1992-09-01

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

Safety manual for civil engineering and building works of nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

This manual lays down the various important considerations that go into safe design of civil structures for nuclear power plants. This manual identifies the design approach, quality assurance requirements and acceptance criteria that need to be observed to assure safety. Considerations on civil design having bearing on safety, during decommissioning are also indicated. (original). 37 refs., tabs

Manually controlled neutron-activation system

International Nuclear Information System (INIS)

Johns, R.A.; Carothers, G.A.

1982-01-01

A manually controlled neutron activation system, the Manual Reactor Activation System, was designed and built and has been operating at one of the Savannah River Plant's production reactors. With this system, samples can be irradiated for up to 24 hours and pneumatically transferred to a shielded repository for decay until their activity is low enough for them to be handled at a radiobench. The Manual Reactor Activation System was built to provide neutron activation of solid waste forms for the Alternative Waste Forms Leach Testing Program. Neutron activation of the bulk sample prior to leaching permits sensitive multielement radiometric analyses of the leachates

Reliable control system for nuclear power plant

International Nuclear Information System (INIS)

Okamoto, Tetsuo; Miyazaki, Shiro

1980-01-01

The System 1100 for nuclear power plants is the measuring and control system which utilizes the features of the System 1100 for electric power market in addition to the results of nuclear instrumentation with EBS-ZN series, and it has the following features. The maintenance and inspection in operation are easy. The construction of control loops is made flexibly by the combination of modules. The construction of multi-variable control system using mainly feed forward control is easy. Such functions as the automatic switching of control modes can be included. The switching of manual and automatic operations is easy, and if some trouble occurred in a module, the manual operation can be made. The aseismatic ability is improved by rigid structure cubicles. Nonflammable materials are used for wires, multi-core cables, paints and printed boards. The anti-noise characteristics are improved, and the reliability is high. The policy of developing the System 1100 for nuclear power plants, the type approval tests on modules and units and the type approval test on the system are described. The items of the system type approval test were standard performance test, earthquake test, noise isolation test, temperature and humidity test, and drift test. The aseismatic cubicle showed good endurance in its vibration test. (Kako, I.)

WAM-E user's manual

International Nuclear Information System (INIS)

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

1986-07-01

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

Knowledge-based full-automatic control system for a nuclear ship reactor

International Nuclear Information System (INIS)

Shimazaki, J.; Nakazawa, T.; Yabuuchi, N.

2000-01-01

Plant operations aboard nuclear ships require quick judgements and actions due to changing marine conditions such as wind, waves and currents. Furthermore, additional human support is not available for nuclear ship operation at sea, so advanced automatic operations are necessary to reduce the number of operators required finally. Therefore, an advanced automatic operating system has been developed based on operational knowledge of nuclear ship 'Mutsu' plant. The advanced automatic operating system includes both the automatic operation system and the operator-support system which assists operators in completing actions during plant accidents, anomaly diagnosis and plant supervision. These system are largely being developed using artificial intelligent techniques such as neural network, fuzzy logic and knowledge-based expert. The automatic operation system is fundamentally based upon application of an operator's knowledge of both normal (start-up to rated power level) and abnormal (after scram) operations. Comparing plant behaviors from start-up to power level by the automatic operation with by 'Mutsu' manual operation, stable automatic operation was obtained almost same as manual operation within all operating limits. The abnormal automatic system was for hard work of manual operations after scram or LOCA accidents. An integrating system with the normal and the abnormal automatic systems are being developed for interacting smoothly both systems. (author)

Nuclear criticality safety. Chapter 0530 of AEC manual

International Nuclear Information System (INIS)

2006-01-01

The programme objectives of this chapter of the U.S. Atomic Energy Commission manual on nuclear criticality safety are to protect the health and safety of the public and of the government and contractor personnel working in plants that handle fissionable material and to protect public and private property from the consequences of a criticality accident occurring in AEC-owned plants and other AEC-contracted activities involving fissionable materials

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual

International Nuclear Information System (INIS)

Gilbert, B.G.; Reece, W.J.; Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.

1990-12-01

The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal computer. NUCLARR can furnish the end user with data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented is a five-volume series of reports. Volume V: Data Manual provides a hard-copy representation of all data and related information available within the NUCLARR system software. This document is organized in three sections. Part 1 is the summary description, which presents an overview of the NUCLARR system and data processing procedures. Part 2 contains all data and information relevant to the human error probability (HEP) data side of NUCLARR. Data and information for the hardware component failure data (HCFD) side are presented in Part 3. 7 refs

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual

International Nuclear Information System (INIS)

Gilbert, B.G.; Reece, W.J.; Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.

1990-12-01

The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal computer. NUCLARR can furnish the end user with data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume V: Data Manual provides a hard-copy representation of all data and related information available within the NUCLARR system software. This document is organized in three sections. Part 1 is the summary description, which presents an overview of the NUCLARR system and data processing procedures. Part 2 contains all data and information relevant to the human error probability (HEP) side of NUCLARR. Data and information for the hardware component failure data (HCFD) side are presented in Part 3. 7 refs., 1 fig

Nuclear structure data file. A manual for preparation of data sets

International Nuclear Information System (INIS)

Ewbank, W.B.; Schmorak, M.R.; Bertrand, F.E.; Feliciano, M.; Horen, D.J.

1975-06-01

The Nuclear Data Project at ORNL is building a computer-based file of nuclear structure data, which is intended for use by both basic and applied users. For every nucleus, the Nuclear Structure Data File contains evaluated nuclear structure information. This manual describes a standard input format for nuclear structure data. The format is sufficiently structured that bulk data can be entered efficiently. At the same time, the structure is open-ended and can accommodate most measured or deduced quantities that yield nuclear structure information. Computer programs have been developed at the Data Project to perform consistency checking and routine calculations. Programs are also used for preparing level scheme drawings. (U.S.)

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-09-01

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

Retrofitting Trojan Nuclear Plant's spent resin transfer system

International Nuclear Information System (INIS)

Pierce, R.E.

1979-01-01

The spent resin slurry transport system at the Trojan Nuclear Plant operated by Portland General Electric Company is one of the most advanced systems of its type in the nuclear industry today. The new system affords the plant's operators safe remote sonic indication for spent resin and cover water levels, manual remote dewatering and watering capability to establish desirable resin-to-water volumetric ratios, reliable non-mechanical resin agitation utilizing fixed spargers, and controllable process flow utilizing a variable speed recessed impeller pump

EVALUATED NUCLEAR STRUCTURE DATA FILE. A MANUAL FOR PREPARATION OF DATA SETS

International Nuclear Information System (INIS)

TULI, J.K.

2001-01-01

This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A ≤ 293), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses A ≥ 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information

21 CFR 892.5650 - Manual radionuclide applicator system.

Science.gov (United States)

2010-04-01

... system. (a) Identification. A manual radionuclide applicator system is a manually operated device... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Manual radionuclide applicator system. 892.5650.... This generic type of device may include patient and equipment supports, component parts, treatment...

Modernizing computerized nuclear material accounting systems

International Nuclear Information System (INIS)

Erkkila, B.H.; Claborn, J.

1995-01-01

DOE Orders and draft orders for nuclear material control and accountability address a complete material control and accountability (MC and A) program for all DOE contractors processing, using, or storing nuclear materials. A critical element of an MC and A program is the accounting system used to track and record all inventories of nuclear material and movements of materials in those inventories. Most DOE facilities use computerized accounting systems to facilitate the task of accounting for all their inventory of nuclear materials. Many facilities still use a mixture of a manual paper system with a computerized system. Also, facilities may use multiple systems to support information needed for MC and A. For real-time accounting it is desirable to implement a single integrated data base management system for a variety of users. In addition to accountability needs, waste management, material management, and production operations must be supported. Information in these systems can also support criticality safety and other safety issues. Modern networked microcomputers provide extensive processing and reporting capabilities that single mainframe computer systems struggle with. This paper describes an approach being developed at Los Alamos to address these problems

WASTES: Wastes system transportation and economic simulation: Version 2, Programmer's reference manual

International Nuclear Information System (INIS)

Buxbaum, M.E.; Shay, M.R.

1986-11-01

The WASTES Version II (WASTES II) Programmer's Reference Manual was written to document code development activities performed under the Monitored Retrievable Storage (MRS) Program at Pacific Northwest Laboratory (PNL). The manual will also serve as a valuable tool for programmers involved in maintenance of and updates to the WASTES II code. The intended audience for this manual are experienced FORTRAN programmers who have only a limited knowledge of nuclear reactor operation, the nuclear fuel cycle, or nuclear waste management practices. It is assumed that the readers of this manual have previously reviewed the WASTES II Users Guide published as PNL Report 5714. The WASTES II code is written in FORTRAN 77 as an extension to the SLAM commercial simulation package. The model is predominately a FORTRAN based model that makes extensive use of the SLAM file maintenance and time management routines. This manual documents the general manner in which the code is constructed and the interactions between SLAM and the WASTES subroutines. The functionality of each of the major WASTES subroutines is illustrated with ''block flow'' diagrams. The basic function of each of these subroutines, the algorithms used in them, and a discussion of items of particular note in the subroutine are reviewed in this manual. The items of note may include an assumption, a coding practice that particularly applies to a subroutine, or sections of the code that are particularly intricate or whose mastery may be difficult. The appendices to the manual provide extensive detail on the use of arrays, subroutines, included common blocks, parameters, variables, and files

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

Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

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

Information retrieval system of nuclear power plant database (PPD) user's guide

International Nuclear Information System (INIS)

Izumi, Fumio; Horikami, Kunihiko; Kobayashi, Kensuke.

1990-12-01

A nuclear power plant database (PPD) and its retrieval system have been developed. The database involves a large number of safety design data of nuclear power plants, operating and planned in Japan. The information stored in the database can be retrieved at high speed, whenever they are needed, by use of the retrieval system. The report is a user's manual of the system to access the database utilizing a display unit of the JAERI computer network system. (author)

A manual of nuclear medicine procedures

International Nuclear Information System (INIS)

Das, B.K.; Noreen Norfaraheen Lee Abdullah

2012-01-01

Nuclear medicine is a fast growing specialty. The procedures provide quantitative parameters of organ functions required for modern practice of medicine. With the development of new machines and increased application of computer software, the procedures are under continuous change. Some procedures have become outdated or redundant while new methods have been introduced to enhance the quality of information obtained from a particular application. Although there are a few books published abroad to inform doctors and technical staff about the procedures, a comprehensive source to give quick information about how different test are performed, particularly the new developments and the expected outcome both in normal and abnormal cases has been a long felt need. The physician ordering a Nuclear Medicine test also needs to know what patient preparations are required for optimal results, how to satisfy the queries of the patient particularly in respect of radiation exposure which sometimes can be a major concern of the patient. This manual has been prepared not only to describe technical details of various procedures that are currently practiced in Nuclear Medicine, but also to provide quick information for the doctors and health care personnel on how to inform the patients about the investigation for which they are being referred and how to interpret the results. Since there is no such comprehensive book published yet in Asia including South-East Asia, it is likely to be in great demand in the region. All students of Master Degree, M.D., DRM, DMRIT, M.Sc. (Nuclear Medicine) and technologists already working in various diagnostic centers will likely buy this book. General practitioners and specialists who refer patients for different radioisotope investigations may find this book useful for quick reference. (author)

Remote inspection system for nuclear power plants

International Nuclear Information System (INIS)

Inagaki, K.; Fujii, M.; Doi, A.; Harima, T.

1977-01-01

A remote inspection system for nuclear power plants was constructed based on an analysis of inspections performed by an operator on patrol. This system consists of an operator's console and a remote station. The remote station, equipped with five kinds of sensors, is steered along the inspection route by a photoelectric guiding system or may be manually controlled from an operator's console in a main control room. Signals for control and inspection data are multiplexed and transmitted through a coaxial cable

Manual for a Volunteer Services System.

Science.gov (United States)

Helgerson, Linda; And Others

This manual presents guidelines for planning, monitoring, and controlling the development and operation of volunteer assistance programs. The materials included address questions related to both the process of establishing a volunteer program and the administration of a volunteer management system. The manual is not intended to provide a blueprint…

Spent nuclear fuel project cold vacuum drying facility operations manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Physical protection. Vol. 6 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This document follows the guidelines of the INPRO report M ethodology for the assessment of innovative nuclear reactors and fuel cycles, Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) , IAEA-TECDOC-1434 (2004), together with its previous report G uidance for the evaluation for innovative nuclear reactors and fuel cycles, Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), IAEATECDOC-1362 (2003). This INPRO manual is comprised of an overview volume and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). The INPRO Manual for the area of physical protection (Volume 6) provides guidance to the assessor of an INS (innovative nuclear energy system) under a physical protection regime in a country that is planning to install a nuclear power program (or maintaining or enlarging an existing one), and describes the application of the

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 3: Hardware component failure data; Volume 5, Revision 4

International Nuclear Information System (INIS)

Reece, W.J.; Gilbert, B.G.; Richards, R.E.

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data

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

Airport Information Retrieval System (AIRS) System Support Manual

Science.gov (United States)

1973-01-01

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

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

International Nuclear Information System (INIS)

2007-01-01

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

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 2: Human error probability (HEP) data; Volume 5, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Reece, W.J.; Gilbert, B.G.; Richards, R.E. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data.

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 2: Human error probability (HEP) data; Volume 5, Revision 4

International Nuclear Information System (INIS)

Reece, W.J.; Gilbert, B.G.; Richards, R.E.

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual, Part 2: Human Error Probability (HEP) Data. Volume 5, Revision 4

International Nuclear Information System (INIS)

Reece, W.J.; Gilbert, B.G.; Richards, R.E.

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data

Manual of use and accounting of radioactive material and procedures of radiological protection for nuclear medicine

International Nuclear Information System (INIS)

Chavez, Miguel

1997-03-01

This manual of use and accounting of material radioactive and procedures of radiological safety tries to facilitate workings of protection of material radioactive in services of medicine nuclear, during diagnosis (examinations with x-rays, or those that are made in nuclear medicine), or during the processing of diseases, mainly of the carcinomas (x-ray)

Empire-3.2 Malta. Modular System for Nuclear Reaction Calculations and Nuclear Data Evaluation. User's Manual

International Nuclear Information System (INIS)

Herman, M.; Capote, R.; Sin, M.

2013-08-01

EMPIRE is a modular system of nuclear reaction codes, comprising various nuclear models, and designed for calculations over a broad range of energies and incident particles. The system can be used for theoretical investigations of nuclear reactions as well as for nuclear data evaluation work. Photons, nucleons, deuterons, tritons, helions ( 3 He), α's, and light or heavy ions can be selected as projectiles. The energy range starts just above the resonance region in the case of a neutron projectile, and extends up to few hundred MeV for heavy ion induced reactions. The code accounts for the major nuclear reaction models, such as optical model, Coupled Channels and DWBA (ECIS06 and OPTMAN), Multi-step Direct (ORION + TRISTAN), NVWY Multi-step Compound, exciton model (PCROSS), hybrid Monte Carlo simulation (DDHMS), and the full featured Hauser-Feshbach model including width fluctuations and the optical model for fission. Heavy ion fusion cross section can be calculated within the simplified coupled channels approach (CCFUS). A comprehensive library of input parameters based on the RIPL-3 library covers nuclear masses, optical model parameters, ground state deformations, discrete levels and decay schemes, level densities, fission barriers, and γ-ray strength functions. Effects of the dynamic deformation of a fast rotating nucleus can be taken into account in the calculations (BARFIT, MOMFIT). The results can be converted into the ENDF-6 format using the accompanying EMPEND code. Modules of the ENDF Utility Codes and the ENDF Pre-Processing codes are applied for ENDF file verification. The package contains the full EXFOR library of experimental data in computational format C4 that are automatically retrieved during the calculations. EMPIRE contains the resonance module that retrieves data from the electronic version of the Atlas of Neutron Resonances by Mughabghab (not provided with the EMPIRE distribution), to produce resonance section and related covariances for the

EXFOR Systems Manual Nuclear reaction Data Exchange Format

International Nuclear Information System (INIS)

McLane, V.

2000-01-01

EXFOR is an exchange format designed to allow transmission of nuclear reaction data between the members of the Nuclear Data Centers Network. This document has been written for use by the members of the Network and includes matters of procedure and protocol, as well as detailed rules for the compilation of data. Users may prefer to consult EXFOR Basics' for a brief description of the format

EXFOR SYSTEMS MANUAL NUCLEAR REACTION DATA EXCHANGE FORMAT.

Energy Technology Data Exchange (ETDEWEB)

MCLANE,V.; NUCLEAR DATA CENTER NETWORK

2000-05-19

EXFOR is an exchange format designed to allow transmission of nuclear reaction data between the members of the Nuclear Data Centers Network. This document has been written for use by the members of the Network and includes matters of procedure and protocol, as well as detailed rules for the compilation of data. Users may prefer to consult EXFOR Basics' for a brief description of the format.

Manual on nuclear gauges. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

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

Advanced display concepts in nuclear control rooms

International Nuclear Information System (INIS)

Clark, M.T.; Banks, W.W.; Blackman, H.S.; Gertman, D.I.

1982-01-01

Precursors necessary for the development of a full-scale predictor display/control system have been under development since the mid 1940's. The predictor display itself has been available for use in manual control systems since 1958. However, the nuclear industry has not yet explored the uses and benefits of predictor systems. The purpose of this paper is to provide information on the application of this technology to the nuclear industry. The possibility of employing a simulation-based control system for nuclear plant systems that currently use conventional auto/manual schemes is discussed. By employing simulation-based systems, a predictor display could be made available to the operator during manual operations, thus facilitating control without outwardly affecting the overall control scheme

Workshop on nuclear structure and decay data: Theory and evaluation manual - Pt. 2

International Nuclear Information System (INIS)

Nichols, A.L.; McLaughlin, P.K.; p.mclaughlin@iaea.org

2004-11-01

A two-week Workshop on Nuclear Structure and Decay Data: Theory and Evaluation was organized and administrated by the IAEA Nuclear Data Section, and hosted at the Abdus Salam International Centre for Theoretical Physics (ICTP) in Trieste, Italy from 17 to 28 November 2003. The aims and contents of this workshop are summarized, along with the agenda, list of participants, comments and recommendations. Workshop materials are also included that are freely available on CD-ROM (all relevant PowerPoint presentations and manuals along with appropriate computer codes). (author)

Workshop on nuclear structure and decay data: Theory and evaluation manual - Pt. 1

International Nuclear Information System (INIS)

Nichols, A.L.; McLaughlin, P.K.; p.mclaughlin@iaea.org

2004-11-01

A two-week Workshop on Nuclear Structure and Decay Data: Theory and Evaluation was organized and administrated by the IAEA Nuclear Data Section, and hosted at the Abdus Salam International Centre for Theoretical Physics (ICTP) in Trieste, Italy from 17 to 28 November 2003. The aims and contents of this workshop are summarized, along with the agenda, list of participants, comments and recommendations. Workshop materials are also included that are freely available on CD-ROM (all relevant PowerPoint presentations and manuals along with appropriate computer codes). (author)

Study of nuclear computer code maintenance and management system

International Nuclear Information System (INIS)

Ryu, Chang Mo; Kim, Yeon Seung; Eom, Heung Seop; Lee, Jong Bok; Kim, Ho Joon; Choi, Young Gil; Kim, Ko Ryeo

1989-01-01

Software maintenance is one of the most important problems since late 1970's.We wish to develop a nuclear computer code system to maintenance and manage KAERI's nuclear software. As a part of this system, we have developed three code management programs for use on CYBER and PC systems. They are used in systematic management of computer code in KAERI. The first program is embodied on the CYBER system to rapidly provide information on nuclear codes to the users. The second and the third programs were embodied on the PC system for the code manager and for the management of data in korean language, respectively. In the requirement analysis, we defined each code, magnetic tape, manual and abstract information data. In the conceptual design, we designed retrieval, update, and output functions. In the implementation design, we described the technical considerations of database programs, utilities, and directions for the use of databases. As a result of this research, we compiled the status of nuclear computer codes which belonged KAERI until September, 1988. Thus, by using these three database programs, we could provide the nuclear computer code information to the users more rapidly. (Author)

46 CFR 112.01-5 - Manual emergency lighting and power system.

Science.gov (United States)

2010-10-01

... EMERGENCY LIGHTING AND POWER SYSTEMS Definitions of Emergency Lighting and Power Systems § 112.01-5 Manual emergency lighting and power system. A manual emergency lighting and power system is one in which a single... 46 Shipping 4 2010-10-01 2010-10-01 false Manual emergency lighting and power system. 112.01-5...

Wireless online position monitoring of manual valve types for plant configuration management in nuclear power plants

International Nuclear Information System (INIS)

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

2016-01-01

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

Importance of the documentation of the manual of quality and procedures handbook in the nuclear technology center

International Nuclear Information System (INIS)

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

1997-01-01

In the present work is presented the methodology used for the elaboration of manual of quality of the Nuclear Technology Center and the technical Procedures Handbook for the execution of Preliminary Safety report of the Juragua Nuclear Power Plant, as well as the importance that has this documentation for the work of the center

22 CFR 308.10 - Security of records systems-manual and automated.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Security of records systems-manual and automated... Security of records systems—manual and automated. The head of the agency has the responsibility of... destruction of manual and automatic record systems. These security safeguards shall apply to all systems in...

BEACON/MOD: a computer program for thermal-hydraulic analysis of nuclear reactor containments - user's manual

International Nuclear Information System (INIS)

Broadus, C.R.; Doyle, R.J.; James, S.W.; Lime, J.F.; Mings, W.J.

1980-04-01

The BEACON code is a best-estimate, advanced containment code designed to perform a best-estimate analysis of the flow of a mixture of air, water, and steam in a nuclear reactor containment system under loss-of-coolant accident conditions. The code can simulate two-component, two-phase fluid flow in complex geometries using a combination of two-dimensional, one-dimensional, and lumped-parameter representations for the various parts of the system. The current version of BEACON, which is designated BEACON/MOD3, contains mass and heat transfer models for wall film and wall conduction. It is suitable for the evaluation of short-term transients in dry-containment systems. This manual describes the models employed in BEACON/MOD3 and specifies code implementation requirements. It provides application information for input data preparation and for output data interpretation

Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

International Nuclear Information System (INIS)

Sakenas, C.A.; McKenna, T.J.; Perkins, K.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. US Nuclear Regulatory Commission Response is the fifth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

Nuclear computerized library for assessing reactor reliability (NUCLARR): Data manual: Part 1, Summary description

International Nuclear Information System (INIS)

Gertman, D.I.; Gilbert, B.G.; Gilmore, W.E.; Galyean, W.J.

1988-06-01

This volume of a five-volume series summarizes those data currently resident in the first release of the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) data base. The raw human error probability (HEP) and hardware component failure data (HCFD) contained herein are accompanied by a glossary of terms and the HEP and hardware taxonomies used to structure the data. Instructions are presented on how the user may navigate through the NUCLARR data management system to find anchor values to assist in solving risk-related problems. Volume V: Data Manual will be updated on a periodic basis so that risk analysis without access to a computer may have access to the largest NUCLARR data. This document Part 1 of Volume 5 introduces aspects of the NUCLARR data base management system and prepares the reader for reviewing data in other Parts of Volume 5

Site security personnel training manual

International Nuclear Information System (INIS)

1978-10-01

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

The International Nuclear Event Scale (INES) user's manual. 2001 edition; La escala internacional de sucesos nucleares (INES) manual del usuario. Edicion de 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-12-01

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

ISE System Development Methodology Manual

Energy Technology Data Exchange (ETDEWEB)

Hayhoe, G.F.

1992-02-17

The Information Systems Engineering (ISE) System Development Methodology Manual (SDM) is a framework of life cycle management guidelines that provide ISE personnel with direction, organization, consistency, and improved communication when developing and maintaining systems. These guide-lines were designed to allow ISE to build and deliver Total Quality products, and to meet the goals and requirements of the US Department of Energy (DOE), Westinghouse Savannah River Company, and Westinghouse Electric Corporation.

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.)

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

Assessment of Deafblind Access to Manual Language Systems (ADAMLS)

Science.gov (United States)

Blaha, Robbie; Carlson, Brad

2007-01-01

This document presents the Assessment of Deafblind Access to Manual Language Systems (ADAMLS), a resource for educational teams who are responsible for developing appropriate adaptations and strategies for children who are deafblind who are candidates for learning manual language systems. The assessment tool should be used for all children with a…

Supervision and atuomatic control of robotics systems in nuclear environments

International Nuclear Information System (INIS)

Benner, J.; Leinemann, K.

1992-01-01

The paper describes new developments in controlling remote handling systems for nuclear applications. The main emphasis is to use robotic equipment and methods for reaching a high degree of system autonomy. A remote handling workstation concept is described, supporting various stages of mission planning and supervision by means of suited geometrical, procedural and functional models. The presented control system enables easy switching between semi-autonomous and manual task execution and sensor data integration. Some experimental results of a prototypic implementation are also described

Supervision and automatic control of robotic systems in nuclear environments

International Nuclear Information System (INIS)

Benner, J.; Leinemann, K.

1992-01-01

This paper describes new developments in controlling remote handling systems for nuclear applications. The main emphasis is to use robotic equipment and methods for reaching a high degree of system autonomy. A remote handling workstation concept is described, supporting various stages of mission planning and supervision by means of suited geometrical, procedural and functional models. The presented control system enables easy switching between semi-autonomous and manual task execution and sensor data integration. Some experimental results of a prototypic implementation are also described

Radiation protection technician job task analysis manual

International Nuclear Information System (INIS)

1990-03-01

This manual was developed to assist all DOE contractors in the design and conduct of job task analysis (JTA) for the radiation protection technician. Experience throughout the nuclear industry and the DOE system has indicated that the quality and efficiency in conducting a JTA at most sites is greatly enhanced by using a generic task list for the position, and clearly written guidelines on the JTA process. This manual is designed to provide this information for personnel to use in developing and conducting site-specific JTAs. (VC)

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

International Nuclear Information System (INIS)

Chino, Masamichi

1992-06-01

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

Safety assessment of a robotic system handling nuclear material

International Nuclear Information System (INIS)

Atcitty, C.B.; Robinson, D.G.

1996-01-01

This paper outlines the use of a Failure Modes and Effects Analysis for the safety assessment of a robotic system being developed at Sandia National Laboratories. The robotic system, The Weigh and Leak Check System, is to replace a manual process at the Department of Energy facility at Pantex by which nuclear material is inspected for weight and leakage. Failure Modes and Effects Analyses were completed for the robotics process to ensure that safety goals for the system had been meet. These analyses showed that the risks to people and the internal and external environment were acceptable

An overview of review guidelines for HDL programmable devices in nuclear safety systems

International Nuclear Information System (INIS)

Komanduri, Raghavan; Srivani, L.; Thirugnana Murthy, D.

2013-01-01

HDL programmable devices viz. CPLDs and FPGAs are increasingly being used to implement digital designs in the I and C systems performing safety functions of nuclear power plants. Synthesizable RTL descriptions manually written in HDLs are the first step in developing industry standard large scale digital designs. The reliability of the implementation is determined by the methodologies followed by the designer during development. Very few guidelines on HPD design practices, specific to nuclear industry are available. This paper presents an overview of the existing guidelines such as IEC 62566 and U.S. NRC's 'Review guidelines for FPGAs in nuclear power plant safety systems'. (author)

EXFOR systems manual: Nuclear reaction data exchange format

International Nuclear Information System (INIS)

McLane, V.

1996-07-01

This document describes EXFOR, the exchange format designed to allow transmission of nuclear reaction data between the members of the Nuclear Data Centers Network. In addition to storing the data and its bibliographic information, experimental information, including source of uncertainties, is also compiled. The status and history of the data set is also included, e.g., the source of the data, any updates which have been made, and correlations to other data sets. The exchange format, as outlined, is designed to allow a large variety of numerical data tables with explanatory and bibliographic information to be transmitted in an easily machine-readable format (for checking and indicating possible errors) and a format that can be read by personnel (for passing judgment on and correcting any errors indicated by the machine)

A system design for the nuclear material accounting reports control based on the intra-net

International Nuclear Information System (INIS)

Jeon, I.; Park, S. J.; Min, K. S.

2003-01-01

The 34 nuclear facilities, including the nuclear power plants, were on operating in Korea and the Technology Center for Nuclear Control(TCNC) has been submit the nuclear material accounting reports to the government and IAEA. At the start point of this work, all reports were controlled via manually and at now, they were controlled based on the client/server system. The fast progress of the computer and internet communication changes the environment of computing from disk operating system to web based system using internet. So, a new system to access the safeguards information and nuclear material accounting system more convenient was needed. In this thesis, a safeguards information control system including the nuclear material accounting reports at the state level based on the web was designed. The oracle RDBMS (Relational Data Base Management System) was adopted for data base management. And all users can access this program via inter-net using their own computer

Laboratory training manual on the use of nuclear techniques in pesticide research

International Nuclear Information System (INIS)

1983-01-01

This is a laboratory training manual on the use of nuclear techniques, and in particular radioisotopes in pesticide research. It is designed to give the scientists involved in pesticide research the basic terms and principles for understanding ionizing radiation: detection and measurement its hazards and safety measures, and some of the more common applications. Laboratory exercises representing the types of experiments that are valuable in pesticide research programmes and field tests which demonstrate the use of radiolabelled pesticides are included

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

Requirements to be met by the operation manual

International Nuclear Information System (INIS)

1981-03-01

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

The International Nuclear Event Scale (INES) user's manual. 2001 edition

International Nuclear Information System (INIS)

2001-12-01

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

The International Nuclear Event Scale (INES) user's manual. 2001 edition

International Nuclear Information System (INIS)

2001-02-01

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

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

International Nuclear Information System (INIS)

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

1979-11-01

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

SAFEPAQ-II. User manual[Nuclear data

Energy Technology Data Exchange (ETDEWEB)

Forrest, R.A

2001-03-01

SAFEPAQ-II is the new software tool that has been developed to enable efficient production of the EAF nuclear data libraries that are required as input to the FISPACT activation code. It forms part of the European Activation System (EASY), and replaces SAFEPAQ and SYMPAL that were used previously. It enables all the nuclear data to be stored in relational databases (Access) and by using an interactive user interface allows the data to be viewed, modified, validated and then produced in the required EAF format as text files. It is written in Visual Basic and runs under the Windows NT4 and 98 operating systems. The Windows operating system has the great advantage of portability and SAFEPAQ-II has been successfully installed at two external sites for use by UKAEA's international collaborators. It has been used in the production of the EAF-2001 data libraries. (author)

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

International Nuclear Information System (INIS)

Weber, Andreas; Erfle, Robert; Feinkohl, Dirk

2012-01-01

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

An accountancy system for nuclear materials control in research centres

International Nuclear Information System (INIS)

Buttler, R.; Bueker, H.; Vallee, J.

1979-01-01

The Nuclear Accountancy and Control System (NACS) was developed at KFA Juelich in accordance with the requirements of the Non-Proliferation Treaty. The main features are (1) recording of nuclear material in inventory items. These are combined to form batches wherever suitable; (2) extrapolation of accounting data as a replacement for detailed measurement of inventory items data. Recording and control of nuclear material are carried out on two levels with access to a common data bank. The lower level deals with nuclear materials handling plus internal management while on the upper level there is a central control point which is responsible for nuclear safeguarding within the entire research centre. By keeping the organizational and technical infrastructure it was possible to develop a system which is both economical and operator-oriented. In this system the emphasis of nuclear safeguarding is placed on the acquisition of the nuclear material inventory. As much consideration has been given to the interests of the various operational levels and organizational units as to internal and national regulations. Since it is part of the safeguarding and control system, access to the NACS must be restricted to a limited number of users only. Furthermore, it must include facilities for manual control in the form of records. Authorization for access must correspond with the various tasks of different user groups. All necessary data are acquired decentrally in the organizational units and entered via a terminal. It is available to the user groups on both levels through a central data bank. To meet all requirements, the NACS has been designed as an integrated, computer-assisted information system for the automated processing of extensive and multi-level nuclear materials data. As part of the preventive measures entailed with nuclear safeguarding, the accountancy system enables the operator of a nuclear plant to furnish proof of non-diversion of nuclear material. (author)

Manual for THOR-AirPAS - air pollution assessment system

DEFF Research Database (Denmark)

Jensen, Steen Solvang; Ketzel, Matthias; Brandt, Jørgen

The report provides an outline of the THOR-AirPAS - air pollution assessment system and a brief manual for getting started with the air quality models and input data included in THOR-AirPAS.......The report provides an outline of the THOR-AirPAS - air pollution assessment system and a brief manual for getting started with the air quality models and input data included in THOR-AirPAS....

The JOSHUA (J80) system programmer`s manual

Energy Technology Data Exchange (ETDEWEB)

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

1993-08-01

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

Laboratory training manual on the use of nuclear techniques in animal parasitology

International Nuclear Information System (INIS)

1982-01-01

The Manual is designed for specialist training in the use of nuclear techniques in animal parasitology. The theoretical part contains a general introduction to experimental work in this field. Laboratory exercises are divided into Basic Exercises (17) and Applied Exercises (25) oriented to research in the immunology and pathogenesis of host-parasite interactions using radioisotopic methods and to disease management through the use of radiation-attenuated vaccines. The closing part contains a number of practical guidelines and data for work with radioisotopes in general and for the use of radioisotopic methods in animal parasitology

Clean Lead Facility Inventory System user's manual

International Nuclear Information System (INIS)

Garcia, J.F.

1994-12-01

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

System specifications for the NDS EXFOR System

International Nuclear Information System (INIS)

Attree, P.M.; Smith, P.M.

1979-07-01

EXFOR is the agreed exchange format for the magnetic-tape exchange of nuclear reaction data between national and international nuclear data centres for the benefit of nuclear data users in all countries. The NDS EXFOR System is a computerized system for the storage and retrieval of EXFOR information compiled or received by the IAEA. This document is an internal manual for the system specifications of the NDS EXFOR System. It includes flow charts, system and program summaries, input and output specifications and file and record descriptions. The manual is updated from time to time when system modifications are made

Total system for manufacture of nuclear vessels by computer: VECTRON

International Nuclear Information System (INIS)

Inagawa, Jin; Ueno, Osamu; Hanai, Yoshiharu; Ohkawa, Isao; Washizu, Hideyuki

1980-01-01

VECTRON (Vessel Engineering by Computer Tool and Rapid Operating for the N/C System) is a CAM (Computer Aided Manufacturing) system that has been developed to produce high quality and highly accurate vessels for nuclear power plants and other industrial plants. Outputs of this system are design drawings, manufacturing information and magnetic tapes of the N/C marking machine for vessel shell plates including their attachments. And it can also output information at each stage of designing, marking, cutting, forming and assembling by treating the vessels in three dimensions and by using data filing systems and plotting program for general use. The data filing systems consist of functional and manufacturing data of each part of vessels. This system not only realizes a change from manual work to computer work, but also leads us to improve production engineering and production jigs for safety and high quality. At present, VECTRON is being applied to the manufacture of the shell plates of primary containment vessels in the Kashiwazaki-Kariwa Nuclear Power Station Unit 1 (K-1) and the Fukushima Daini Nuclear Power Station Unit 3 (2F-3), to realize increased productivity. (author)

Transportation security personnel training manual

International Nuclear Information System (INIS)

1978-11-01

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

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Infrastructure. Vol. 3 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3, outlined here), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). Within INPRO, the term infrastructure can be defined as the collection of capabilities of institutions involved in a nuclear power program in a given country that are necessary for the successful deployment (or enlargement) and operation of an INS, including legal and institutional, industrial and economic, and socio-political features. Within INPRO, the definition of an INS includes activities and facilities (i.e. components) at both the front end of the fuel cycle (e.g., mining, enrichment, fuel fabrication) and the back end (e.g., reprocessing, storage, and repository) (Section 4.2.1 of Volume 1 of the INPRO manual. Consequently, within INPRO, such facilities are not considered to be a part of the INPRO area of infrastructure, albeit that they influence the size of the necessary infrastructure required in a given

Manual for environmental radiological surveillance

International Nuclear Information System (INIS)

Sumiya, Shuichi; Matsuura, Kenichi; Nakano, Masanao; Takeyasu, Masanori; Morisawa, Masato; Onuma, Toshimitsu; Fujita, Hiroki; Mizutani, Tomoko; Watanabe, Hajime; Sugai, Masamitsu

2010-03-01

Environmental radiation monitoring around the Tokai Reprocessing Plant has been conducted by the Nuclear Fuel Cycle Engineering Laboratories, based on 'Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV - Environmental monitoring' and Environmental Radiation Monitoring Program decided by the Ibaraki prefectural government. The radiation monitoring installations and equipments were also prepared for emergency. This manual describes; (1) the installations of radiological measurement, (2) the installations of meteorological observation, and (3) environmental data processing system for executing the terrestrial environmental monitoring by Environmental Protection Section, Radiation Protection Department. The environmental monitoring has been operated through the manual published in 1993 (PNC TN8520 93-001). Then the whole articles were revised because the partially of installations and equipments having been updated in recent years. (author)

Electrical and electronic subsystems of a nuclear waste tank annulus inspection system

International Nuclear Information System (INIS)

Evenson, R.J.

1981-06-01

The nuclear waste tank annulus inspection system is designed specifically for use at the Nuclear Regulatory Commission's Nuclear Fuel Services Facility at West Valley, New York. This system sends a television and photographic camera into the space between the walls of a double-shell nuclear waste tank to obtain images of the inner and outer walls at precisely known locations. The system is capable of inspecting a wall section 14 ft wide by 27 ft high. Due to the high temperature and radiation of the annulus environment, the operating life for the inspection device is uncertain, but is expected to be at least 100 h, with 1000 R/h at 82 0 C. The film camera is shielded with 1/2 in. of lead to minimize radiation fogging of the film during a 25-min picture taking excursion. The operation of the inspection system is semiautomated with remote manual prepositioning of the camera, followed by a computer controlled wall scan. This apparatus is currently set up to take an array of contiguous pictures, but is adaptable to other modes of operation

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

Science.gov (United States)

Foley, Walter; Harr, Gordon

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

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

New Nuclear Emergency Prognosis system in Korea

Science.gov (United States)

Lee, Hyun-Ha; Jeong, Seung-Young; Park, Sang-Hyun; Lee, Kwan-Hee

2016-04-01

This paper reviews the status of assessment and prognosis system for nuclear emergency response in Korea, especially atmospheric dispersion model. The Korea Institute of Nuclear Safety (KINS) performs the regulation and radiological emergency preparedness of the nuclear facilities and radiation utilizations. Also, KINS has set up the "Radiological Emergency Technical Advisory Plan" and the associated procedures such as an emergency response manual in consideration of the IAEA Safety Standards GS-R-2, GS-G-2.0, and GS-G-2.1. The Radiological Emergency Technical Advisory Center (RETAC) organized in an emergency situation provides the technical advice on radiological emergency response. The "Atomic Computerized Technical Advisory System for nuclear emergency" (AtomCARE) has been developed to implement assessment and prognosis by RETAC. KINS developed Accident Dose Assessment and Monitoring (ADAMO) system in 2015 to reflect the lessons learned from Fukushima accident. It incorporates (1) the dose assessment on the entire Korean peninsula, Asia region, and global region, (2) multi-units accident assessment (3) applying new methodology of dose rate assessment and the source term estimation with inverse modeling, (4) dose assessment and monitoring with the environmental measurements result. The ADAMO is the renovated version of current FADAS of AtomCARE. The ADAMO increases the accuracy of the radioactive material dispersion with applying the LDAPS(Local Data Assimilation Prediction System, Spatial resolution: 1.5 km) and RDAPS(Regional Data Assimilation Prediction System, Spatial resolution: 12km) of weather prediction data, and performing the data assimilation of automatic weather system (AWS) data from Korea Meteorological Administration (KMA) and data from the weather observation tower at NPP site. The prediction model of the radiological material dispersion is based on the set of the Lagrangian Particle model and Lagrangian Puff model. The dose estimation methodology

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Safety of nuclear fuel cycle facilities. Vol. 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (laid out in this report) (Volume 9).This report elaborates on the guidance given in the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1434, and the previous INPRO report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1362 (2003), in the area of safety of nuclear reactors. The present version of this manual deals with safety issues related to design and operation of mining, milling, refining, conversion, enrichment, fuel fabrication, fuel storage and fuel reprocessing facilities. The INPRO Manual starts with an introduction in Chapter 1. Chapter 2 sets out the necessary input for an INPRO assessment of the safety of an innovative nuclear fuel cycle facility. This includes information on the design for the plant and the safety

Quality assurance in nuclear medicine

International Nuclear Information System (INIS)

Kaul, A.

1986-01-01

'Quality Assurance in Nuclear Medicine' is the title of the English language original that has been translated into German. The manual very extensively deals with quality control of nuclear medical equipment. Tests are explained for checking radioactivity measuring devices, manual and automatic in-vitro sample measuring systems, in-vivo measuring systems with single or multiple detectors, rectlinear scanners, and gamma cameras, including the phantoms required for the methods. Other chapters discuss the quality control of radiopharmaceuticals, or the quality assurance in data recording and evaluation of results. Helpful comments on the organisation of quality assurance programms are given. The book is intended as a practical guide for introducing quality assurance principles in nuclear medicine in the Federal Republic of Germany. With 13 figs., 22 tabs [de

Guidance Manual for preparing Nuclear and Radiological Emergency Preparedness and Response Plan

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

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

Guidance Manual for preparing Nuclear and Radiological Emergency Preparedness and Response Plan

International Nuclear Information System (INIS)

Muhammed, Kabiru; Jeong, Seung-Young

2014-01-01

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

Root Cause Analysis Following an Event at a Nuclear Installation: Reference Manual

International Nuclear Information System (INIS)

2015-01-01

Following an event at a nuclear installation, it is important to determine accurately its root causes so that effective corrective actions can be implemented. As stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles: “Processes must be put in place for the feedback and analysis of operating experience”. If this process is completed effectively, the probability of a similar event occurring is significantly reduced. Guidance on how to establish and implement such a process is given in IAEA Safety Standards Series No. NS-G-2.11, A System for the Feedback of Experience from Events in Nuclear Installations. To cater for the diverse nature of operating experience events, several different root cause analysis (RCA) methodologies and techniques have been developed for effective investigation and analysis. An event here is understood as any unanticipated sequence of occurrences that results in, or potentially results in, consequences to plant operation and safety. RCA is not a topic uniquely relevant to event investigators: knowledge of the concepts enhances the learning characteristics of the whole organization. This knowledge also makes a positive contribution to nuclear safety and helps to foster a culture of preventing event occurrence. This publication allows organizations to deepen their knowledge of these methodologies and techniques and also provides new organizations with a broad overview of the RCA process. It is the outcome of a coordinated effort involving the participation of experts from nuclear organizations, the energy industry and research centres in several Member States. This publication also complements IAEA Services Series No. 10, PROSPER Guidelines: Guidelines for Peer Review and for Plant Self- Assessment of Operational Experience Feedback Process, and is intended to form part of a suite of publications developing the principles set forth in these guidelines. In addition to the information and description of RCA

RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Supplement 1, RELAP4/MOD5, Update 2

International Nuclear Information System (INIS)

Bruch, C.G.

1976-08-01

RELAP4/MOD5, Update 1 was released to the Nuclear Regulatory Commission in January 1976. Six months of extensive use of Update 1 has led to the identification and correction of a number of errors in the code, as well as some logic changes, additional Evaluation Model (EM) checks, and one model revision. These changes have culminated in the release of an improved code identified as RELAP4/MOD5, Update 2. The RELAP4/MOD5 interim User's Manual (Interim Report SRD-113-76) reflected the Update 1 version of the code. The purpose of the supplement presented is to update the Interim User's Manual for use with RELAP4/MOD5, Update 2. Major differences between Updates 1 and 2 and the checkout of Update 2 are discussed. The final version of the User's Manual will be written in accordance with Update 2 and will be published as ANCR-NUREG 1335 during September 1976. Annotation of the existing three volumes of the User's Manual to cross-reference this Supplement is recommended

SNL/CA Environmental Management System Program Manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2005-09-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program was developed in accordance with Department of Energy (DOE) Order 450.1 and incorporates the elements of the International Standard on Environmental Management Systems, ISO 14001.

System specifications for the NDS EXFOR System

Energy Technology Data Exchange (ETDEWEB)

Attree, P M; Smith, P M

1982-06-01

EXFOR is the agreed exchange format for the magnetic-tape exchange of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. The NDS EXFOR System is a computerized system for the storage and retrieval of EXFOR information compiled or received of the IAEA. This document is an internal manual for the system specifications of the NDS EXFOR System. It includes flow charts, system and program summaries, input and output specifications and file and record descriptions. The manual is updated from time to time when system modifications are made; the first version was issued in July 1979. (author)

Hanford Environmental Information System (HEIS) user's manual

International Nuclear Information System (INIS)

1991-10-01

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

Nuclear Plant Analyzer: Installation manual. Volume 1

International Nuclear Information System (INIS)

Snider, D.M.; Wagner, K.L.; Grush, W.H.; Jones, K.R.

1995-01-01

This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenient means of interactively controlling the host program through user-defined pop-up menus. The NPA was designed to serve primarily as an analysis tool. After a brief introduction to the Computer Visual System and the NPA, an analyst can quickly create a simple picture or set of pictures to aide in the study of a particular phenomenon. These pictures can range from simple collections of square boxes and straight lines to complex representations of emergency response information displays

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.

quality assurance systems in nuclear fuel procurement and manufacturing

International Nuclear Information System (INIS)

Can, S.

1997-01-01

Quality is the totality of features and characteristics of a product or service that bear on its ability to satisfy stated or implied needs. Quality control is activities and techniques used to fulfill the requirements of quality. Quality assurance is a system and its main components are requirements. QA program, organization and responsibilities, design and verification, material and its control, manufacturing and process control, inspections, audits and documents: manuals, specifications, instructions. Quality assurance systems are largely based on ISO 9000 series of the International Standards Organization. ISO 9000 series has been adopted and published by Turkish Standards Institute as TS-ISO 9000. International Atomic Energy Agency also published a guide (50-SG-QA11) ''Quality Assurance in the Procurement, Design and Manufacture of Nuclear Fuel Assemblies'' in the safety guide series. In this study the role of quality control in quality assurance systems, inspection and test plans and acceptance and nonconformance quality levels will be explained in relation to nuclear fuel production. Examples of applications in quality assurance systems based on ISO 9000 will be given

BEACON/MOD2A: a computer program for subcompartment analysis of nuclear reactor containment. A user's manual

International Nuclear Information System (INIS)

Wells, R.A.

1979-03-01

The BEACON code is a Best Estimate Advanced Containment code which being developed by EG and G, Idaho, Inc., at the Idaho National Engineering Laboratory. The program is designed to perform a best estimate analysis of the flow of a mixture of air, water, and steam in a nuclear reactor containment system under loss-of-coolant accident conditions. The code can simulate two-component, two-phase fluid flow in complex geometries using a combination of two-dimensional, one-dimensional, and lumped-parameter representations for the various parts of the system. The current version of BEACON, which is designated BEACON/MOD2A, contains mass and heat transfer models for wall film and for wall conduction. It is suitable for the evaluation of short term transients in PWR dry containment systems. This manual describes the models employed in BEACON/MOD2A and specifies code implementation requirements. It provides application information for input data preparation and for output data interpretation

A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities: User's manual for FIRIN

International Nuclear Information System (INIS)

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

1989-02-01

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

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)

INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Environmental Impact of Stressors. INPRO Manual

International Nuclear Information System (INIS)

2016-01-01

This publication provides guidance on assessing of sustainability of a nuclear energy system (NES) in the area of environmental impact of stressors. The INPRO methodology is a comprehensive tool for the assessment of sustainability of an NES. Basic principles, user requirements and criteria have been defined in different areas of INPRO methodology. These include economics, infrastructure, waste management, proliferation resistance, environmental impact of stressors, environmental impact from depletion of resources, and safety of nuclear reactors and fuel cycle facilities. The ultimate goal of the application of the INPRO methodology is to check whether the assessed NES fulfils all the criteria, and hence the user requirements and basic principles, and therefore presents a system for a Member State that is sustainable in the long term

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

Energy Technology Data Exchange (ETDEWEB)

Schreck, R.I.

1991-10-01

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

Design of make-up water system for Tehran research reactor spent nuclear fuels storage pool

Energy Technology Data Exchange (ETDEWEB)

Aghoyeh, Reza Gholizadeh [Reactor Research Group, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), North Amirabad, P.O. Box 14155-1339, Tehran (Iran, Islamic Republic of); Khalafi, Hosein, E-mail: hkhalafi@aeoi.org.i [Reactor Research Group, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), North Amirabad, P.O. Box 14155-1339, Tehran (Iran, Islamic Republic of)

2010-10-15

Spent nuclear fuels storage (SNFS) is an essential auxiliary system in nuclear facility. Following discharge from a nuclear reactor, spent nuclear fuels have to be stored in water pool of SNFS away from reactor to allow for radioactive to decay and removal of generated heat. To prevent corrosion damage of fuels and other equipments, the storage pool is filled with de-ionized water which serves as moderator, coolant and shielding. The de-ionized water will be provided from make-up water system. In this paper, design of a make-up water system for optimal water supply and its chemical properties in SNFS pool is presented. The main concern of design is to provide proper make-up water throughout the storage time. For design of make-up water system, characteristics of activated carbon purifier, anionic, cationic and mixed-bed ion-exchangers have been determined. Inlet water to make-up system provide from Tehran municipal water system. Regulatory Guide 1.13 of the and graver company manual that manufactured the Tehran research reactor (TRR) make-up water system have been used for make-up water system of TRR spent nuclear fuels storage pool design.

Design of make-up water system for Tehran research reactor spent nuclear fuels storage pool

International Nuclear Information System (INIS)

Aghoyeh, Reza Gholizadeh; Khalafi, Hosein

2010-01-01

Spent nuclear fuels storage (SNFS) is an essential auxiliary system in nuclear facility. Following discharge from a nuclear reactor, spent nuclear fuels have to be stored in water pool of SNFS away from reactor to allow for radioactive to decay and removal of generated heat. To prevent corrosion damage of fuels and other equipments, the storage pool is filled with de-ionized water which serves as moderator, coolant and shielding. The de-ionized water will be provided from make-up water system. In this paper, design of a make-up water system for optimal water supply and its chemical properties in SNFS pool is presented. The main concern of design is to provide proper make-up water throughout the storage time. For design of make-up water system, characteristics of activated carbon purifier, anionic, cationic and mixed-bed ion-exchangers have been determined. Inlet water to make-up system provide from Tehran municipal water system. Regulatory Guide 1.13 of the and graver company manual that manufactured the Tehran research reactor (TRR) make-up water system have been used for make-up water system of TRR spent nuclear fuels storage pool design.

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Development of advanced automatic operation system for nuclear ship. 1. Perfect automatic normal operation

International Nuclear Information System (INIS)

Nakazawa, Toshio; Yabuuti, Noriaki; Takahashi, Hiroki; Shimazaki, Junya

1999-02-01

Development of operation support system such as automatic operating system and anomaly diagnosis systems of nuclear reactor is very important in practical nuclear ship because of a limited number of operators and severe conditions in which receiving support from others in a case of accident is very difficult. The goal of development of the operation support systems is to realize the perfect automatic control system in a series of normal operation from the reactor start-up to the shutdown. The automatic control system for the normal operation has been developed based on operating experiences of the first Japanese nuclear ship 'Mutsu'. Automation technique was verified by 'Mutsu' plant data at manual operation. Fully automatic control of start-up and shutdown operations was achieved by setting the desired value of operation and the limiting value of parameter fluctuation, and by making the operation program of the principal equipment such as the main coolant pump and the heaters. This report presents the automatic operation system developed for the start-up and the shutdown of reactor and the verification of the system using the Nuclear Ship Engineering Simulator System. (author)

INES: The International Nuclear and Radiological Event Scale User's Manual. 2008 Edition (Spanish Edition)

International Nuclear Information System (INIS)

2010-11-01

INES, the International Nuclear and Radiological Event Scale, was developed in 1990 by experts convened by the IAEA and the OECD Nuclear Energy Agency with the aim of communicating the safety significance of events. This edition of the INES User?s Manual is designed to facilitate the task of those who are required to rate the safety significance of events using the scale. It includes additional guidance and clarifications, and provides examples and comments on the continued use of INES. With this new edition, it is anticipated that INES will be widely used by Member States and become the worldwide scale for putting into proper perspective the safety significance of any event associated with the transport, storage and use of radioactive material and radiation sources, whether or not the event occurs at a facility.

INES: The International Nuclear and Radiological Event Scale User's Manual. 2008 Edition (Chinese Edition)

International Nuclear Information System (INIS)

2012-01-01

INES, the International Nuclear and Radiological Event Scale, was developed in 1990 by experts convened by the IAEA and the OECD Nuclear Energy Agency with the aim of communicating the safety significance of events. This edition of the INES User's Manual is designed to facilitate the task of those who are required to rate the safety significance of events using the scale. It includes additional guidance and clarifications, and provides examples and comments on the continued use of INES. With this new edition, it is anticipated that INES will be widely used by Member States and become the worldwide scale for putting into proper perspective the safety significance of any event associated with the transport, storage and use of radioactive material and radiation sources, whether or not the event occurs at a facility.

Nuclear reactor insulation and preheat system

International Nuclear Information System (INIS)

Wampole, N.C.

1978-01-01

An insulation and preheat system is disclosed for preselected components of a fluid cooled nuclear reactor. A gas tight barrier or compartment of thermal insulation surrounds the selected components and includes devices to heat the internal atmosphere of the ocmpartment. An external surface of the compartment of enclosure is cooled, such as by a circulating fluid. The heating devices provide for preheating of the components, as well as maintenance of a temperature sufficient to ensure that the reactor coolant fluid will not solidify during shutdown. The external cooling limits the heat transferred to other plant structures, such as supporting concrete and steel. The barrier is spaced far enough from the surrounded components so as to allow access for remote or manual inspection, maintenance, and repair

Orientation manual for INIS and AGRIS (OMINAS)

International Nuclear Information System (INIS)

Binggeli, M.H.

1979-01-01

The manual is intended as a basic introduction to the computerized information systems, INIS (International Nuclear Information System) and AGRIS (International Information System for the Agricultural Sciences and Technology). Both systems contain information on already published literature, and include non-conventional literature (i.e. literature not available through normal commercial channels). Full bibliographic details and a subject classification are given. INIS, in addition, supplies descriptors, data-flagged where appropriate, and abstracts with every item of literature reported. The guiding principle followed by INIS and AGRIS is one of shared responsibility in development and operation. Both input is decentralized. The collection and preparation of documents relevant to the defined subject scopes are the responsibility of the country of publication. This decentralized input is transmitted to Vienna where centralized processing, merging and dispatching take place. The main output products are two printed journals, INIS Atomindex and AGRINDEX, and magnetic tape services. The manual is divided into four parts. The first is intended as a general introduction, and gives a bird's-eye view of the principles involved in the operation of the two systems. The second and third deal with INIS and AGRIS, respectively, and offer orientation in greater depth. The last part deals with the computer aspects of the system. The manual contains several appendices, a subject index and a list of basic references

Cuerpo de Paz Manual de Sistema de Programacion y Capacitacion (Peace Corps Programming and Training System Manual): T0063.

Science.gov (United States)

Peace Corps, Washington, DC.

This Spanish version of the Peace Corps Programming and Training System Manual is designed to help field staff members of the Peace Corps train volunteers. Its task descriptions, guidelines, examples, and definitions are intended to be practical and informative rather than restrictive. The manual is divided into six major sections: (1)…

SNL/CA Environmental Management System Program Manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2007-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004. Elements of the ISO standard overlap with those of Department of Energy (DOE) Order 450.1, thus SNL/CA's EMS program also meets the DOE requirements.

Automated ultrasonic inspection of nuclear plant components

International Nuclear Information System (INIS)

Baron, J.A.; Dolbey, M.P.

1982-01-01

For reasons of safety and efficiency, automated systems are used in performing ultrasonic inspection of nuclear components. An automated system designed specifically for the inspection of headers in a nuclear plant is described. In-service inspection results obtained with this system are shown to correlate with pre-service inspection results obtained by manual methods

Integrated Reliability and Risk Analysis System (IRRAS), Version 2.5: Reference manual

International Nuclear Information System (INIS)

Russell, K.D.; McKay, M.K.; Sattison, M.B.; Skinner, N.L.; Wood, S.T.; Rasmuson, D.M.

1991-03-01

The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the user the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification. Version 1.0 of the IRRAS program was released in February of 1987. Since that time, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 2.5 and is the subject of this Reference Manual. Version 2.5 of IRRAS provides the same capabilities as Version 1.0 and adds a relational data base facility for managing the data, improved functionality, and improved algorithm performance. 7 refs., 348 figs

Performance evaluation recommendations and manuals of nuclear power plants outdoor significant civil structures earthquake resistance

International Nuclear Information System (INIS)

2005-06-01

Performance evaluation recommendations and manuals of nuclear power plants outdoor significant civil structures earthquake resistance have been updated in June 2005 by the Japan Society of Civil Engineers. Based on experimental and analytical considerations on the recommendations of May 2002, analytical seismic models of soils for underground structures, effects of vertical motions on time-history dynamic analysis and shear fracture of reinforced concretes by cyclic loadings have been evaluated and incorporated in new recommendations. (T. Tanaka)

Surface Moisture Measurement System Operation and Maintenance Manual

International Nuclear Information System (INIS)

Ritter, G.A.; Pearce, K.L.; Stokes, T.L.

1995-12-01

This operations and maintenance manual addresses deployment, equipment and field hazards, operating instructions, calibration verification, removal, maintenance, and other pertinent information necessary to safely operate and store the Surface Moisture Measurement System (SMMS) and Liquid Observation Well Moisture Measurement System (LOWMMS). These systems were developed primarily in support of Tank Waste Remediation System (TWRS) Safety Programs for moisture measurement in organic and ferrocyanide watch list tanks

Development of Process Automation in the Neutron Activation Analysis Facility in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Yussup, N.; Azman, A.; Ibrahim, M.M.; Rahman, N.A.A.; Che Sohashaari, S.; Atan, M.N.; Hamzah, M.A.; Mokhtar, M.; Khalid, M.A.; Salim, N.A.A.; Hamzah, M.S.

2018-01-01

Neutron Activation Analysis (NAA) has been established in Malaysian Nuclear Agency (Nuclear Malaysia) since 1980s. Most of the procedures established from sample registration to analysis are performed manually. These manual procedures carried out by the NAA laboratory personnel are time consuming and inefficient. Hence, system automation is developed in order to provide an effective method to replace redundant manual data entries and produce faster sample analysis and calculation process. This report explains NAA process in Nuclear Malaysia and describes the automation development in detail which includes sample registration software, automatic sample changer system which consists of hardware and software; and sample analysis software. (author)

Development of an environmental safety case guidance manual

International Nuclear Information System (INIS)

Wellstead, Matthew John

2014-01-01

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

Time warp operating system version 2.7 internals manual

Science.gov (United States)

1992-01-01

The Time Warp Operating System (TWOS) is an implementation of the Time Warp synchronization method proposed by David Jefferson. In addition, it serves as an actual platform for running discrete event simulations. The code comprising TWOS can be divided into several different sections. TWOS typically relies on an existing operating system to furnish some very basic services. This existing operating system is referred to as the Base OS. The existing operating system varies depending on the hardware TWOS is running on. It is Unix on the Sun workstations, Chrysalis or Mach on the Butterfly, and Mercury on the Mark 3 Hypercube. The base OS could be an entirely new operating system, written to meet the special needs of TWOS, but, to this point, existing systems have been used instead. The base OS's used for TWOS on various platforms are not discussed in detail in this manual, as they are well covered in their own manuals. Appendix G discusses the interface between one such OS, Mach, and TWOS.

MELCOR computer code manuals

Energy Technology Data Exchange (ETDEWEB)

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

1995-03-01

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

MELCOR computer code manuals

International Nuclear Information System (INIS)

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

1995-03-01

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

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

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

A manual of recommended practices for hydrogen energy systems

Energy Technology Data Exchange (ETDEWEB)

Hoagland, W.; Leach, S. [W. Hoagland and Associates, Boulder, CO (United States)

1997-12-31

Technologies for the production, distribution, and use of hydrogen are rapidly maturing and the number and size of demonstration programs designed to showcase emerging hydrogen energy systems is expanding. The success of these programs is key to hydrogen commercialization. Currently there is no comprehensive set of widely-accepted codes or standards covering the installation and operation of hydrogen energy systems. This lack of codes or standards is a major obstacle to future hydrogen demonstrations in obtaining the requisite licenses, permits, insurance, and public acceptance. In a project begun in late 1996 to address this problem, W. Hoagland and Associates has been developing a Manual of Recommended Practices for Hydrogen Systems intended to serve as an interim document for the design and operation of hydrogen demonstration projects. It will also serve as a starting point for some of the needed standard-setting processes. The Manual will include design guidelines for hydrogen procedures, case studies of experience at existing hydrogen demonstration projects, a bibliography of information sources, and a compilation of suppliers of hydrogen equipment and hardware. Following extensive professional review, final publication will occur later in 1997. The primary goal is to develop a draft document in the shortest possible time frame. To accomplish this, the input and guidance of technology developers, industrial organizations, government R and D and regulatory organizations and others will be sought to define the organization and content of the draft Manual, gather and evaluate available information, develop a draft document, coordinate reviews and revisions, and develop recommendations for publication, distribution, and update of the final document. The workshop, Development of a Manual of Recommended Practices for Hydrogen Energy Systems, conducted on March 11, 1997 in Alexandria, Virginia, was a first step.

Nuclear forensics support. Reference manual

International Nuclear Information System (INIS)

2006-01-01

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

Manual for WSPEEDI international data communication network

Energy Technology Data Exchange (ETDEWEB)

Takahashi, Masatoshi; Nagai, Haruyasu; Chino, Masamichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2000-09-01

Japan Atomic Energy Research Institute has developed a computer-based dose prediction system WSPEEDI (System for Prediction of Environmental Emergency Dose Information) for predicting the radiological impacts on the Japanese people of a nuclear accident abroad to meet the requirement caused by the Chernobyl accident. Because WSPEEDI reached on the practical stage through several verification studies, the development of international data communication network is started to exchange modeling products and environmental data quickly. This manual describes registration, search and management of modeling products and environmental data and handling of tele-conference tool. (author)

Utilization technique of 'radiation management manual in medical field (2012).' What should be learnt from the Fukushima nuclear accident

International Nuclear Information System (INIS)

Kikuchi, Toru

2014-01-01

From the abstract of contents of the 'Radiation management manual in medical field (2012),' the utilization technique of the manual is introduced. Introduced items are as follows: (1) Exposure management; exposure management for radiation medical workers, patients, and citizens in the medical field, and exposure management for radiation workers and citizens involved in the emergency work related to the Fukushima nuclear accident, (2) Health management; health management for radiation medical workers, (3) Radiation education: Education/training for radiation medical workers, and radiation education for health care workers, (4) Accident and emergency measures; emergency actions involved in the radiation accidents and radiation medicine at medical facilities

Can pulsed xenon ultraviolet light systems disinfect aerobic bacteria in the absence of manual disinfection?

Science.gov (United States)

Jinadatha, Chetan; Villamaria, Frank C; Ganachari-Mallappa, Nagaraja; Brown, Donna S; Liao, I-Chia; Stock, Eileen M; Copeland, Laurel A; Zeber, John E

2015-04-01

Whereas pulsed xenon-based ultraviolet light no-touch disinfection systems are being increasingly used for room disinfection after patient discharge with manual cleaning, their effectiveness in the absence of manual disinfection has not been previously evaluated. Our study indicates that pulsed xenon-based ultraviolet light systems effectively reduce aerobic bacteria in the absence of manual disinfection. These data are important for hospitals planning to adopt this technology as adjunct to routine manual disinfection. Published by Elsevier Inc.

Composting of tobacco plant waste by manual turning and forced aeration system

Directory of Open Access Journals (Sweden)

Nonglak Saithep

2009-05-01

Full Text Available The efficiency of tobacco plant waste composting, by the manual turning and the forced aeration system, was compared. Tobacco plant waste, cow manure, urea fertiliser, and a compost inoculum mixture at a 100:10:0.2:0.01 ratio respectively, with 60% (w/v moisture content, were set up in piling forms. The piles of the manual turning system were provided with turning aeration by hand at intervals of 7 days during the composting process. For the forced aeration system, each pile was aerated by a 3-HP air pump with a flow rate of 19 litres min-1 for 15 minutes every morning and evening. The completely randomised design of turned and force-aerated piles was performed in triplicate. The composting activity of both systems during the composting period was measured by several parameters: temperature, pH, moisture content, C/N ratio, growth of microorganisms, cellulase activity, and nicotine degradation in the set-up piles. Both systems had similar temperature, pH, and moisture content conditions in the piles during the composting process. However, the forced aeration system was more advantageous for the growth of mesophilic and thermophilic microorganisms, for cellulase activity from cellulase-producing microorganisms, and for nicotine degradation, when compared to the manual turning system. In conclusion, the forced aeration system was more efficient than the manual turning system in composting and is a viable alternative method for the composting process.

Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0. Volume 5, Systems Analysis and Risk Assessment (SARA) tutorial manual

International Nuclear Information System (INIS)

Sattison, M.B.; Russell, K.D.; Skinner, N.L.

1994-07-01

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs) primarily for nuclear power plants. This volume is the tutorial manual for the Systems Analysis and Risk Assessment (SARA) System Version 5.0, a microcomputer-based system used to analyze the safety issues of a open-quotes familyclose quotes [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. A series of lessons is provided that guides the user through some basic steps common to most analyses performed with SARA. The example problems presented in the lessons build on one another, and in combination, lead the user through all aspects of SARA sensitivity analysis capabilities

Manual control of unstable systems

Science.gov (United States)

Allen, R. W.; Hogue, J. R.; Parseghian, Z.

1986-01-01

Under certain operational regimes and failure modes, air and ground vehicles can present the human operator with a dynamically unstable or divergent control task. Research conducted over the last two decades has explored the ability of the human operator to control unstable systems under a variety of circumstances. Past research is reviewed and human operator control capabilities are summarized. A current example of automobile directional control under rear brake lockup conditions is also reviewed. A control system model analysis of the driver's steering control task is summarized, based on a generic driver/vehicle model presented at last year's Annual Manual. Results from closed course braking tests are presented that confirm the difficulty the average driver has in controlling the unstable directional dynamics arising from rear wheel lockup.

Sandia National Laboratories, California Environmental Management System program manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2013-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 436.1.

Sandia National Laboratories, California Environmental Management System program manual

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2014-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 436.1.

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

Science.gov (United States)

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

Techniques for controlling air pollution from the operation of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

1966-03-01

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

Root Cause Analysis Following an Event at a Nuclear Installation: Reference Manual. Companion CD

International Nuclear Information System (INIS)

2015-01-01

Following an event at a nuclear installation, it is important to determine accurately its root causes so that effective corrective actions can be implemented. As stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles: “Processes must be put in place for the feedback and analysis of operating experience”. If this process is completed effectively, the probability of a similar event occurring is significantly reduced. Guidance on how to establish and implement such a process is given in IAEA Safety Standards Series No. NS-G-2.11, A System for the Feedback of Experience from Events in Nuclear Installations. To cater for the diverse nature of operating experience events, several different root cause analysis (RCA) methodologies and techniques have been developed for effective investigation and analysis. An event here is understood as any unanticipated sequence of occurrences that results in, or potentially results in, consequences to plant operation and safety. RCA is not a topic uniquely relevant to event investigators: knowledge of the concepts enhances the learning characteristics of the whole organization. This knowledge also makes a positive contribution to nuclear safety and helps to foster a culture of preventing event occurrence. This publication allows organizations to deepen their knowledge of these methodologies and techniques and also provides new organizations with a broad overview of the RCA process. It is the outcome of a coordinated effort involving the participation of experts from nuclear organizations, the energy industry and research centres in several Member States. This publication also complements IAEA Services Series No. 10, PROSPER Guidelines: Guidelines for Peer Review and for Plant Self- Assessment of Operational Experience Feedback Process, and is intended to form part of a suite of publications developing the principles set forth in these guidelines. In addition to the information and description of RCA

Programmer's manual for CAMCON: Compliance Assessment Methodology CONtroller

International Nuclear Information System (INIS)

Rechard, R.P.; Gilkey, A.P.; Rudeen, D.K.; Byle, K.A.; Iuzzolino, H.J.

1993-05-01

CAMCON, the Compliance Assessment Methodology CONtroller, is an analysis system that assists in assessing the compliance of the Waste Isolation Pilot Plant (WIPP) with applicable long-term regulations of the US Environmental Protection Agency, including Subpart B of the Environmental Standards for the Management and Disposal of spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191 and 40CFR268.6, which is the portion of the Land Disposal Restrictions implementing the Resource, Conservative, and Recovery Act of 1976, as amended that states the conditions for disposal of hazardous chemical wastes. This manual provides an architectural overview of the CAMCON system. Furthermore this manual presents guidelines and presents suggestions for programmers developing the many different types of software necessary to investigate various events and physical processes of the WIPP. These guidelines include user interface requirements, minimum quality assurance requirements, coding style suggestions, and the use of numerous software libraries developed specifically for or adapted for the CAMCON system

ENDF/B-5 formats manual 1984

Energy Technology Data Exchange (ETDEWEB)

Kinsey, R; Magurno, B A

1986-09-01

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

Instrumentation and control upgrade evaluation methodology. Volume 1: Manual. Final report

International Nuclear Information System (INIS)

Bliss, M.; Brown, E.; Florio, F.; Stofko, M.

1996-07-01

This methodology manual describes how to develop an Upgrade Evaluation Report (UER) for an I and C system that has been identified as an upgrade candidate in the I and C Life Cycle Management Plan (LCMP). A UER can be developed by a nuclear power plant to determine the cost-effectiveness and feasibility of upgrading an aging or obsolete Instrumentation and Control (I and C) System. A separate UER is developed for each upgrade candidate system. A UER will determine if a given system requires an upgrade or if it is more cost-effective to maintain the present system. If an upgrade is unnecessary, the system will be reclassified as a retained system and a system maintenance plan will be developed for it. This manual is accompanied by a workbook (EPRI TR-104963-V2) which contains various worksheets, outlines, and generic interview questions that aid in the UER development process

Data acquisition for X ray microprobe. User's manual

International Nuclear Information System (INIS)

2002-01-01

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

Hazardous Solvent Substitution Data System reference manual

International Nuclear Information System (INIS)

Branham-Haar, K.A.; Twitchell, K.E.

1993-07-01

Concern for the environment, in addition to Federal regulation, mandate the replacement of hazardous solvents with safer cleaning agents. Manufacturers are working to produce these replacement solvents. As these products are developed, potential users need to be informed of their availability. To promote the use of these new products instead of traditional solvents, the Idaho National Engineering Laboratory (INEL) has developed the Hazardous Solvent Substitution Data System (HSSDS). The HSSDS provides a comprehensive system of information on alternatives to hazardous solvents and related subjects, and it makes that information available to solvent users, industrial hygienists, and process engineers. The HSSDS uses TOPIC reg-sign, a text retrieval system produced by Verity, Inc., to allow a user to search for information on a particular subject. TOPIC reg-sign produces a listing of the retrieved documents and allows the use to examine the documents individually and to use the information contained in them. This reference manual does not replace the comprehensive TOPIC reg-sign user documentation (available from Verity, Inc.), or the HSSDS Tutorial (available from the INEL). The purpose of this reference manual is to provide enough instruction on TOPIC reg-sign so the user may begin accessing the data contained in the HSSDS

Operations Manual for Incident and Emergency Communication. Date Effective: 1 June 2012

International Nuclear Information System (INIS)

2012-01-01

years, the Unified System for Information Exchange in Incidents and Emergencies (USIE) for Contact Points and for INES national officers, revision of the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan), and changes to better reflect that emergency situations can arise from both accidents and criminal and other unauthorized acts. The General Conference of the IAEA in resolution GC(49)/RES/9 requested the Secretariat to continue to review and, as necessary, streamline its mechanisms for reporting and for sharing information and encouraged Member States to do the same. In 2007 the General Conference of the IAEA, in resolution GC(51)/RES/11, welcomed the decision to develop a global, unified incident and emergency reporting system which combines the Emergency Notification and Assistance Technical Operations Manual (ENATOM) arrangements and the Nuclear Events Web-based System (NEWS) mechanism. In resolution GC(54)/RES/7 the General Conference of the IAEA requested the Secretariat to continue its efforts to finalize and implement a global and unified system for reporting and sharing information on nuclear and radiological accidents and incidents, and to act upon the feedback provided by Member States. The General Conference of the IAEA, in resolution GC(54)/RES/7, also encouraged all Member States to enhance, where necessary, their own preparedness and response capabilities for nuclear and radiological incidents and emergencies, by improving capabilities to prevent accidents, to respond to emergencies and to mitigate any harmful consequences and, where necessary, to request support from the Secretariat or from other Member States in developing national capabilities consistent with international standards, and urges all Member States to take part in these exercises. The General Conference in resolution GC(55)/RES/9 urges Member States to reinforce emergency notification, reporting and information sharing arrangements and capabilities

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

Accountability methods for plutonium and uranium: the NRC manuals

Energy Technology Data Exchange (ETDEWEB)

Gutmacher, R.G.; Stephens, F.B.

1977-09-28

Four manuals containing methods for the accountability of plutonium nitrate solutions, plutonium dioxide, uranium dioxide and mixed uranium-plutonium oxide have been prepared by us and issued by the U.S. Nuclear Regulatory Commission. A similar manual on methods for the accountability of uranium and plutonium in reprocessing plant dissolver solutions is now in preparation. In the present paper, we discuss the contents of the previously issued manuals and give a preview of the manual now being prepared.

Accountability methods for plutonium and uranium: the NRC manuals

International Nuclear Information System (INIS)

Gutmacher, R.G.; Stephens, F.B.

1977-01-01

Four manuals containing methods for the accountability of plutonium nitrate solutions, plutonium dioxide, uranium dioxide and mixed uranium-plutonium oxide have been prepared by us and issued by the U.S. Nuclear Regulatory Commission. A similar manual on methods for the accountability of uranium and plutonium in reprocessing plant dissolver solutions is now in preparation. In the present paper, we discuss the contents of the previously issued manuals and give a preview of the manual now being prepared

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

Composting of tobacco plant waste by manual turning and forced aeration system

OpenAIRE

Nonglak Saithep

2009-01-01

The efficiency of tobacco plant waste composting, by the manual turning and the forced aeration system, was compared. Tobacco plant waste, cow manure, urea fertiliser, and a compost inoculum mixture at a 100:10:0.2:0.01 ratio respectively, with 60% (w/v) moisture content, were set up in piling forms. The piles of the manual turning system were provided with turning aeration by hand at intervals of 7 days during the composting process. For the forced aeration system, each pile was aerated by a...

Integration of computerized operation support systems on a nuclear power plant environment

Energy Technology Data Exchange (ETDEWEB)

Jaime, Guilherme D.G.; Almeida, Jose C.S.; Oliveira, Mauro V., E-mail: gdjaime@ien.gov.br, E-mail: jcsa@ien.gov.br, E-mail: mvitor@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Servico de Sistemas Complexos. Divisao de Engenharia Nuclear

2015-07-01

Automation of certain tasks in a Nuclear Power Plant (NPP) control room is expected to result in reduced operators' mental workload, which may induce other benefits such as enhanced situation awareness and improved system performance. The final goal should be higher level of operational safety. Thus, recent works are increasingly assessing automation. The LABIHS compact NPP simulator, though, still operates under strictly manual printed hard-copy procedures, despite of the fact that the simulator incorporates several advancements in design of digitalized Human-Interfaces (HSIs). This work presents the development, implementation and integration of selected components to achieve increased level of computerized/automated operation of the LABIHS compact NPP simulator. Specifically, we discuss three components: (I) Automatic Plant Mode Detection, (II) Automatic Alarm Filtering, and (III) Computerized Procedures. Each one of these components has to be carefully designed/integrated so that one can avoid the undesired effects of some known implementations of automated systems on NPP, such as the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills, which could lead to automation-induced system failures. (author)

Integration of computerized operation support systems on a nuclear power plant environment

International Nuclear Information System (INIS)

Jaime, Guilherme D.G.; Almeida, Jose C.S.; Oliveira, Mauro V.

2015-01-01

Automation of certain tasks in a Nuclear Power Plant (NPP) control room is expected to result in reduced operators' mental workload, which may induce other benefits such as enhanced situation awareness and improved system performance. The final goal should be higher level of operational safety. Thus, recent works are increasingly assessing automation. The LABIHS compact NPP simulator, though, still operates under strictly manual printed hard-copy procedures, despite of the fact that the simulator incorporates several advancements in design of digitalized Human-Interfaces (HSIs). This work presents the development, implementation and integration of selected components to achieve increased level of computerized/automated operation of the LABIHS compact NPP simulator. Specifically, we discuss three components: (I) Automatic Plant Mode Detection, (II) Automatic Alarm Filtering, and (III) Computerized Procedures. Each one of these components has to be carefully designed/integrated so that one can avoid the undesired effects of some known implementations of automated systems on NPP, such as the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills, which could lead to automation-induced system failures. (author)

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

Administrative Reorganization, Modification And Enlargement The Personal Plant And The Functions Manual Of The Documentation Center And Nuclear Information Of The Institute Of Nuclear Matters; Reorganizacion administrativa, Modificacion y Amipliacion de la planta de personal y del Manual de Funciones del Centro de Documentacion e Informacion Nuclear del Instituto de Asuntos Nucleares

Energy Technology Data Exchange (ETDEWEB)

De Escobar, Cecilia

1991-07-01

This document is a project of administrative reorganization, modification and amplification of the personal plant and the functions manual of of the Center of Documentation and Nuclear Information of the IAN. The methodology used to develop this work was constituted by an analysis of the statutes and objectives of the institution. A study of the objectives that the CDIN of the flowchart of the IAN should complete. Interview with the Boss of the CDIN to define necessities as soon as administrative organization, modification of the plant of personal and of the manual of functions of the Center, interview the officials of the Documentation Center, tending efficiently to gather information on the current conditions of work and their proposals for the benefit of the more services. Surveys of the Center users to diagnose like they are come lending the services and their recommendations for the improvement of the same ones.

NV/YMP RADIOLOGICAL CONTROL MANUAL

Energy Technology Data Exchange (ETDEWEB)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

2004-11-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

NV/YMP RADIOLOGICAL CONTROL MANUAL

International Nuclear Information System (INIS)

2004-01-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual

Tubular wells perforation manual for investigation and training of Guarani Aquifer System

International Nuclear Information System (INIS)

2007-01-01

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

Operator's Manual for SHEBA Powered Tether Balloon System

Science.gov (United States)

Lappen, Cara-Lyn; Randall, David A.

1998-01-01

The Surface Heat and Energy Budget of the Arctic (SHEBA) was an intensive field project which took place in the Arctic Ocean from October 1997 through October 1998. Its purpose was to measure as many facets of the Arctic environment as possible so that we would be able to better understand the interaction between the ice, atmosphere, and ocean and their interactions with global climate. One aspect of the atmospheric field component was launching tethered balloons to monitor the profiles of temperature, wind, pressure, and humidity, as well as examine the vertical structure of cloud droplet sizes and distributions. The tethered balloon that we used was one specially designed for use in freezing climates by SPEC Corporation in Boulder, Colorado. A special winch that was able to withstand Arctic temperature and weather became necessary when the testing of simple winch systems used in warmer climates failed under these extreme conditions. The purpose of this manual is to acquaint any new user to the powered tethered balloon system deployed at the The Surface Heat and Energy Budget of the Arctic (SHEBA ice camp. It includes a description of the preparations necessary to get ready for a launch, the mechanics of the actual launch, and an account of the proper procedure for taking down the equipment when finished. It will also include tips on how to minimize potential equipment failures, some trouble shooting, and some safety ideas. This manual is designed so that new operators can use the system with minimal previous training. At the end of this manual, the reader will find a quick checklist.

Automation system for optical counting of nuclear tracks

Energy Technology Data Exchange (ETDEWEB)

Boulyga, S.F.; Boulyga, E.G.; Lomonosova, E.M.; Zhuk, I.V

1999-06-01

An automation system consisting of the microscope, video camera and Pentium PC with frame recorder was created. The system provides counting of nuclear tracks on the SSNTD surface with a resolution of 752 x 582 points, determination of the surface area and main axis of the track. The pattern recognition program was developed for operation in Windows 3.1 (or higher) ensuring a convenient interface with the user. In a comparison of the results on automatic track counting with the more accurate hand mode it was shown that the program enables the tracks to be detected even on images with a rather high noise level. It ensures a high accuracy of track counting being comparable with the accuracy of manual counting for densities of tracks in the range of up to 2{center_dot}10{sup 5} tracks/cm{sup 2}. The automatic system was applied in the experimental investigation of uranium and transuranium elements.

Automation system for optical counting of nuclear tracks

International Nuclear Information System (INIS)

Boulyga, S.F.; Boulyga, E.G.; Lomonosova, E.M.; Zhuk, I.V.

1999-01-01

An automation system consisting of the microscope, video camera and Pentium PC with frame recorder was created. The system provides counting of nuclear tracks on the SSNTD surface with a resolution of 752 x 582 points, determination of the surface area and main axis of the track. The pattern recognition program was developed for operation in Windows 3.1 (or higher) ensuring a convenient interface with the user. In a comparison of the results on automatic track counting with the more accurate hand mode it was shown that the program enables the tracks to be detected even on images with a rather high noise level. It ensures a high accuracy of track counting being comparable with the accuracy of manual counting for densities of tracks in the range of up to 2·10 5 tracks/cm 2 . The automatic system was applied in the experimental investigation of uranium and transuranium elements

Automation system for optical counting of nuclear tracks

CERN Document Server

Boulyga, S F; Lomonosova, E M; Zhuk, I V

1999-01-01

An automation system consisting of the microscope, video camera and Pentium PC with frame recorder was created. The system provides counting of nuclear tracks on the SSNTD surface with a resolution of 752 x 582 points, determination of the surface area and main axis of the track. The pattern recognition program was developed for operation in Windows 3.1 (or higher) ensuring a convenient interface with the user. In a comparison of the results on automatic track counting with the more accurate hand mode it was shown that the program enables the tracks to be detected even on images with a rather high noise level. It ensures a high accuracy of track counting being comparable with the accuracy of manual counting for densities of tracks in the range of up to 2 centre dot 10 sup 5 tracks/cm sup 2. The automatic system was applied in the experimental investigation of uranium and transuranium elements.

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...

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

Programmer`s manual for CAMCON: Compliance Assessment Methodology CONtroller

Energy Technology Data Exchange (ETDEWEB)

Rechard, R.P. [Sandia National Labs., Albuquerque, NM (United States); Gilkey, A.P.; Rudeen, D.K.; Byle, K.A. [New Mexico Engineering Research Inst., Albuquerque, NM (United States); Iuzzolino, H.J. [Geo-Centers, Inc., Albuquerque, NM (United States)

1993-05-01

CAMCON, the Compliance Assessment Methodology CONtroller, is an analysis system that assists in assessing the compliance of the Waste Isolation Pilot Plant (WIPP) with applicable long-term regulations of the US Environmental Protection Agency, including Subpart B of the Environmental Standards for the Management and Disposal of spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191 and 40CFR268.6, which is the portion of the Land Disposal Restrictions implementing the Resource, Conservative, and Recovery Act of 1976, as amended that states the conditions for disposal of hazardous chemical wastes. This manual provides an architectural overview of the CAMCON system. Furthermore this manual presents guidelines and presents suggestions for programmers developing the many different types of software necessary to investigate various events and physical processes of the WIPP. These guidelines include user interface requirements, minimum quality assurance requirements, coding style suggestions, and the use of numerous software libraries developed specifically for or adapted for the CAMCON system.

Operations Manual for Incident and Emergency Communication. Date Effective: 1 June 2012 (Spanish Edition); Manual de Operaciones para la Comunicacion de Incidentes y Emergencias. Fecha de Validez: 1 Junio de 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-06-01

years, the Unified System for Information Exchange in Incidents and Emergencies (USIE) for Contact Points and for INES national officers, revision of the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan), and changes to better reflect that emergency situations can arise from both accidents and criminal and other unauthorized acts. The General Conference of the IAEA in resolution GC(49)/RES/9 requested the Secretariat to continue to review and, as necessary, streamline its mechanisms for reporting and for sharing information and encouraged Member States to do the same. In 2007 the General Conference of the IAEA, in resolution GC(51)/RES/11, welcomed the decision to develop a global, unified incident and emergency reporting system which combines the Emergency Notification and Assistance Technical Operations Manual (ENATOM) arrangements and the Nuclear Events Web-based System (NEWS) mechanism. In resolution GC(54)/RES/7 the General Conference of the IAEA requested the Secretariat to continue its efforts to finalize and implement a global and unified system for reporting and sharing information on nuclear and radiological accidents and incidents, and to act upon the feedback provided by Member States. The General Conference of the IAEA, in resolution GC(54)/RES/7, also encouraged all Member States to enhance, where necessary, their own preparedness and response capabilities for nuclear and radiological incidents and emergencies, by improving capabilities to prevent accidents, to respond to emergencies and to mitigate any harmful consequences and, where necessary, to request support from the Secretariat or from other Member States in developing national capabilities consistent with international standards, and urges all Member States to take part in these exercises. The General Conference in resolution GC(55)/RES/9 urges Member States to reinforce emergency notification, reporting and information sharing arrangements and capabilities

National Waste Terminal Storage Program, planning and control system manual

International Nuclear Information System (INIS)

1976-09-01

This manual contains a brief description of the NWTS program in order to define the environment within which the system must function; an overview of the system, and the concepts and techniques that were utilized in its development; and OWI implementation on the NWTS Program

EXFOR systems manual: Nuclear reaction data exchange format. Revision 97/1

International Nuclear Information System (INIS)

McLane, V.

1997-07-01

This document describes EXFOR, the exchange format designed to allow transmission of nuclear reaction data between the members of the Nuclear Data Center Network. In addition to storing the data and its' bibliographic information, experimental information, including source of uncertainties, is also compiled. The status and history of the data set is also included, e.g., the source of the data, any updates which have been made, and correlations to other data sets. EXFOR is designed for flexibility rather than optimization of data processing in order to meet the diverse needs of the nuclear reaction data centers. The exchange format should not be confused with a center-to-user format. Although users may obtain data from the centers in the EXFOR format, other center-to-user formats have been developed to meet the needs of the users within each center's own sphere of responsibility. The exchange format, as outlined, is designed to allow a large variety of numerical data tables with explanatory and bibliographic information to be transmitted in an easily machine-readable format (for checking and indicating possible errors) and a format that can be read by personnel (for passing judgment on and correcting any errors indicated by the machine)

Guidance for the application of an assessment methodology for Innovative Nuclear Energy Systems. INPRO manual - Economics. Vol. 2 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This publication elaborates on the guidance given in the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1434 (2004), and the previous INPRO report 'Guidance for the evaluation for innovative nuclear reactors and fuel cycles', IAEA-TECDOC-1362 (2003) in the area of economics. The information presented in Volume 1 of the INPRO manual should be considered to be an integral part of this volume and the user should be familiar with that information. The goal of the INPRO Manual for the area of economics (Volume 2) is to provide guidance for performing an INPRO assessment, as described in Volume 1 of the INPRO manual, in the area of economics. The manual is not intended to provide guidance on how to design an INS to meet the INPRO requirements in the area of economics: rather, the focus is on the assessment method and the evaluation of the INPRO criteria in the area of economics. The INPRO assessor, i.e. the individual or group of individuals carrying out the assessment, is assumed to be knowledgeable in the area of economics and financial analysis. The INPRO assessment will either confirm that the INPRO economic criteria are fulfilled

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

International Nuclear Information System (INIS)

1966-01-01

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

Method for fault diagnosis of digital control systems in nuclear power plant

International Nuclear Information System (INIS)

Suzuki, Satoshi; Nagaoka, Yukio; Ohga, Yukiharu; Ito, Tetsuo

1990-01-01

This paper presents a method for localizing faulty components of control systems by replaceable parts such as print boards and cables, in a large scale plant like a nuclear power plant. Most of today's control systems form a distributed configuration including many digital controllers interconnected by data communication networks. Usually, to localize the faulty components in nuclear plant control systems, suspected faulty components are narrowed down by executing manual tests to examine whether the objects are normal or abnormal based on design documents and personnel know-how, besides the uses of self-diagnosis functions built into the control systems. In the present method, procedures of various tests including the know-how and checking of self-diagnosis functions are provided as knowledge of tests. The tests to be executed is determined by considering failure probabilities of objects, and easiness and effectiveness of testing. Then, the suspects are narrowed down sequentially based on the test result. In checking feasibility of this diagnosis method for a simulated control system, intended faults are satisfactorily localized. This method is confirmed to be practicable for diagnosis of large scale digital control systems. (author)

Advanced training course on state systems of accounting for and control of nuclear materials. Volume I. Program for technical assistance to IAEA safeguards

International Nuclear Information System (INIS)

Sorenson, R.J.; Schneider, R.A.

1979-01-01

Purpose of the course was to provide practical training in the implementation and operation of a national system of accounting for and control of nuclear materials in a bulk processing facility, in the context of international safeguards. This course extends the training received in the basic course on State Systems of Accounting for and Control of Nuclear Materials to a practical, illustrative example utilizing the Exxon Nuclear low enriched uranium fabrication plant. Volume I of this manual contains the text of the presentations following the outline of the syllabus. Sample problems and answers are also included, along with some visual aids

Comparison of Battery-Powered and Manual Bone Biopsy Systems for Core Needle Biopsy of Sclerotic Bone Lesions.

Science.gov (United States)

Cohen, Micah G; McMahon, Colm J; Kung, Justin W; Wu, Jim S

2016-05-01

The purpose of this study was to compare manual and battery-powered bone biopsy systems for diagnostic yield and procedural factors during core needle biopsy of sclerotic bone lesions. A total of 155 consecutive CT-guided core needle biopsies of sclerotic bone lesions were performed at one institution from January 2006 to November 2014. Before March 2012, lesions were biopsied with manual bone drill systems. After March 2012, most biopsies were performed with a battery-powered system and either noncoaxial or coaxial biopsy needles. Diagnostic yield, crush artifact, CT procedure time, procedure radiation dose, conscious sedation dose, and complications were compared between the manual and battery-powered core needle biopsy systems by Fisher exact test and t test. One-way ANOVA was used for subgroup analysis of the two battery-powered systems for procedure time and radiation dose. The diagnostic yield for all sclerotic lesions was 60.0% (93/155) and was significantly higher with the battery-powered system (73.0% [27/37]) than with the manual systems (55.9% [66/118]) (p = 0.047). There was no significant difference between the two systems in terms of crush artifact, procedure time, radiation dose, conscious sedation administered, or complications. In subgroup analysis, the coaxial battery-powered biopsies had shorter procedure times (p = 0.01) and lower radiation doses (p = 0.002) than the coaxial manual systems, but the noncoaxial battery-powered biopsies had longer average procedure times and higher radiation doses than the coaxial manual systems. In biopsy of sclerotic bone lesions, use of a battery-powered bone drill system improves diagnostic yield over use of a manual system.

Instrumentation and Control Life Cycle Management Plan Methodology. Volume 1, Manual: Final report

International Nuclear Information System (INIS)

Quick, D.S.; Murray, S.; Florio, F.; Bliss, M.J.

1995-08-01

This methodology manual describes how to develop a Life Cycle Management Plan (LCMP). An LCMP is a long-term strategic plan that can be developed for a nuclear power plant to cost-effectively maintain and upgrade its aging or obsolete Instrumentation and Control (I ampersand C) systems. An LCMP defines the utility's mission and objectives in regards to long range I ampersand C planning, as well as the plant's present configuration (I ampersand C systems, networks, man machine interfaces, etc.), its desired future I ampersand C systems, a long term I ampersand C maintenance strategy, and initial upgrade priorities and schedules to cost-effectively implement system upgrades. This manual is accompanied by a workbook (EPRI TR-105555-V2) which contains various worksheets, outlines, and generic interview questions that aid in the LCNW development process

SHARP User Manual

Energy Technology Data Exchange (ETDEWEB)

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

2016-03-31

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

SHARP User Manual

International Nuclear Information System (INIS)

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

2016-01-01

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

Administrative Reorganization, Modification And Enlargement The Personal Plant And The Functions Manual Of The Documentation Center And Nuclear Information Of The Institute Of Nuclear Matters

International Nuclear Information System (INIS)

De Escobar, Cecilia

1991-01-01

This document is a project of administrative reorganization, modification and amplification of the personal plant and the functions manual of of the Center of Documentation and Nuclear Information of the IAN. The methodology used to develop this work was constituted by an analysis of the statutes and objectives of the institution. A study of the objectives that the CDIN of the flowchart of the IAN should complete. Interview with the Boss of the CDIN to define necessities as soon as administrative organization, modification of the plant of personal and of the manual of functions of the Center, interview the officials of the Documentation Center, tending efficiently to gather information on the current conditions of work and their proposals for the benefit of the more services. Surveys of the Center users to diagnose like they are come lending the services and their recommendations for the improvement of the same ones

FRMAC Operations Manual

Energy Technology Data Exchange (ETDEWEB)

Frandsen, K.

2010-05-01

In the event of a major radiological incident, the Federal Radiological Monitoring and Assessment Center (FRMAC) will coordinate the federal agencies that have various statutory responsibilities. The FRMAC is responsible for coordinating all environmental radiological monitoring, sampling, and assessment activities for the response. This manual describes the FRMAC’s response activities in a radiological incident. It also outlines how FRMAC fits in the National Incident Management System (NIMS) under the National Response Framework (NRF) and describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the affected areas. In the event of a potential or existing major radiological incident, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is responsible for establishing and managing the FRMAC during the initial phases.

Wisconsin System for Instructional Management: Teachers' Manual for the Unified System. Practical Paper No. 18.

Science.gov (United States)

Bozeman, William C.; And Others

Individualized instruction including continuous progress education and team teaching requires a complexity of organizational structure dissimilar to that of traditional schools. In such systems, teachers must maintain extensive and complex student record systems. This teachers' manual provides an example of a computerized record system developed…

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

Science.gov (United States)

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

1981-11-01

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

Operations Manual for Incident and Emergency Communication. Date Effective: 1 June 2012 (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

years, the Unified System for Information Exchange in Incidents and Emergencies (USIE) for Contact Points and for INES national officers, revision of the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan), and changes to better reflect that emergency situations can arise from both accidents and criminal and other unauthorized acts. The General Conference of the IAEA in resolution GC(49)/RES/9 requested the Secretariat to continue to review and, as necessary, streamline its mechanisms for reporting and for sharing information and encouraged Member States to do the same. In 2007 the General Conference of the IAEA, in resolution GC(51)/RES/11, welcomed the decision to develop a global, unified incident and emergency reporting system which combines the Emergency Notification and Assistance Technical Operations Manual (ENATOM) arrangements and the Nuclear Events Web-based System (NEWS) mechanism. In resolution GC(54)/RES/7 the General Conference of the IAEA requested the Secretariat to continue its efforts to finalize and implement a global and unified system for reporting and sharing information on nuclear and radiological accidents and incidents, and to act upon the feedback provided by Member States. The General Conference of the IAEA, in resolution GC(54)/RES/7, also encouraged all Member States to enhance, where necessary, their own preparedness and response capabilities for nuclear and radiological incidents and emergencies, by improving capabilities to prevent accidents, to respond to emergencies and to mitigate any harmful consequences and, where necessary, to request support from the Secretariat or from other Member States in developing national capabilities consistent with international standards, and urges all Member States to take part in these exercises. The General Conference in resolution GC(55)/RES/9 urges Member States to reinforce emergency notification, reporting and information sharing arrangements and capabilities

Operations Manual for Incident and Emergency Communication. Date Effective: 1 June 2012 (Chinese Edition)

International Nuclear Information System (INIS)

2013-01-01

years, the Unified System for Information Exchange in Incidents and Emergencies (USIE) for Contact Points and for INES national officers, revision of the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan), and changes to better reflect that emergency situations can arise from both accidents and criminal and other unauthorized acts. The General Conference of the IAEA in resolution GC(49)/RES/9 requested the Secretariat to continue to review and, as necessary, streamline its mechanisms for reporting and for sharing information and encouraged Member States to do the same. In 2007 the General Conference of the IAEA, in resolution GC(51)/RES/11, welcomed the decision to develop a global, unified incident and emergency reporting system which combines the Emergency Notification and Assistance Technical Operations Manual (ENATOM) arrangements and the Nuclear Events Web-based System (NEWS) mechanism. In resolution GC(54)/RES/7 the General Conference of the IAEA requested the Secretariat to continue its efforts to finalize and implement a global and unified system for reporting and sharing information on nuclear and radiological accidents and incidents, and to act upon the feedback provided by Member States. The General Conference of the IAEA, in resolution GC(54)/RES/7, also encouraged all Member States to enhance, where necessary, their own preparedness and response capabilities for nuclear and radiological incidents and emergencies, by improving capabilities to prevent accidents, to respond to emergencies and to mitigate any harmful consequences and, where necessary, to request support from the Secretariat or from other Member States in developing national capabilities consistent with international standards, and urges all Member States to take part in these exercises. The General Conference in resolution GC(55)/RES/9 urges Member States to reinforce emergency notification, reporting and information sharing arrangements and capabilities

Operations Manual for Incident and Emergency Communication. Date Effective: 1 June 2012 (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

years, the Unified System for Information Exchange in Incidents and Emergencies (USIE) for Contact Points and for INES national officers, revision of the Joint Radiation Emergency Management Plan of the International Organizations (Joint Plan), and changes to better reflect that emergency situations can arise from both accidents and criminal and other unauthorized acts. The General Conference of the IAEA in resolution GC(49)/RES/9 requested the Secretariat to continue to review and, as necessary, streamline its mechanisms for reporting and for sharing information and encouraged Member States to do the same. In 2007 the General Conference of the IAEA, in resolution GC(51)/RES/11, welcomed the decision to develop a global, unified incident and emergency reporting system which combines the Emergency Notification and Assistance Technical Operations Manual (ENATOM) arrangements and the Nuclear Events Web-based System (NEWS) mechanism. In resolution GC(54)/RES/7 the General Conference of the IAEA requested the Secretariat to continue its efforts to finalize and implement a global and unified system for reporting and sharing information on nuclear and radiological accidents and incidents, and to act upon the feedback provided by Member States. The General Conference of the IAEA, in resolution GC(54)/RES/7, also encouraged all Member States to enhance, where necessary, their own preparedness and response capabilities for nuclear and radiological incidents and emergencies, by improving capabilities to prevent accidents, to respond to emergencies and to mitigate any harmful consequences and, where necessary, to request support from the Secretariat or from other Member States in developing national capabilities consistent with international standards, and urges all Member States to take part in these exercises. The General Conference in resolution GC(55)/RES/9 urges Member States to reinforce emergency notification, reporting and information sharing arrangements and capabilities

Establishment of quality system program for the manufacture of nuclear grade steels

International Nuclear Information System (INIS)

Saito, Toru

1978-01-01

Recently, the pressure vessels employed in the fields of nuclear power generation, petroleum refining, and chemical industry tend to be large size and high performance, therefore thick steel plates and forgings of high quality are demanded, and the establishment and maintenance of strict quality assurance system for material production are required. In Mizushima Works, Kawasaki Steel Corp., the installations for large forgings and thick plates were constructed from 1969 to 1976, and the researches on the development of production techniques were forwarded in parallel. A Quality System Certificate (Material) has been granted to Mizushima Works on March 11, 1977, by the American Society of Mechanical Engineers for the manufacture of steel plates and forgings of nuclear grade. The quality system manual as the basis of quality assurance activities, the organization for quality assurance, its responsibility and authority, the discrimination of materials, the control of manufacturing processes, the qualification of workers in charge of nondestructive test, welding, heat treatment and others, the management of tests and inspections, the management of products with faults and repairing measures, and internal supervisory system are explained. The wide use of computers is novel in the field of quality system program. (Kako, I.)

Naturalistic driving observations of manual and visual-manual interactions with navigation systems and mobile phones while driving.

NARCIS (Netherlands)

Christoph, M. Nes, N. van & Knapper, A.

2014-01-01

This paper discusses a naturalistic driving study on the use of mobile phones and navigation systems while driving. Manual interactions with these devices while driving can cause distraction from the driving task and reduce traffic safety. In this study 21 subjects were observed for 5 weeks. Their

Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-IV. User's manual

International Nuclear Information System (INIS)

2001-01-01

As a continuation of its efforts to provide methodologies and tools to Member States to carry out comparative assessment and analyse priority environmental issues related to the development of the electric power sector, the IAEA has completed a new version of the Wien Automatic System Planning (WASP) Package WASP-IV for carrying out power generation expansion planning taking into consideration fuel availability and environmental constraints. This manual constitutes a part of this work and aims to provide users with a guide to use effectively the new version of the model WASP-IV. WASP was originally developed in 1972 by the Tennessee Valley Authority and the Oak Ridge National Laboratory in the USA to meet the IAEA needs to analyse the economic competitiveness of nuclear power in comparison to other generation expansion alternatives for supplying the future electricity requirements of a country or region. Previous versions of the model were used by Member States in many national and regional studies to analyse the electric power system expansion planning and the role of nuclear energy in particular. Experience gained from its application allowed development of WASP into a very comprehensive planning tool for electric power system expansion analysis. New, improved versions were developed, which took into consideration the needs expressed by the users of the programme in order to address important emerging issues being faced by the electric system planners. In 1979, WASP-IV was released and soon after became an indispensable tool in many Member States for generation expansion planning. The WASP-IV version was continually upgraded and the development of version WASP-III Plus commenced in 1992. By 1995, WASP-III Plus was completed, which followed closely the methodology of the WASP-III but incorporated new features. In order to meet the needs of electricity planners and following the recommendations of the Helsinki symposium, development of a new version of WASP was

User's manual of SECOM2: a computer code for seismic system reliability analysis

International Nuclear Information System (INIS)

Uchiyama, Tomoaki; Oikawa, Tetsukuni; Kondo, Masaaki; Tamura, Kazuo

2002-03-01

This report is the user's manual of seismic system reliability analysis code SECOM2 (Seismic Core Melt Frequency Evaluation Code Ver.2) developed at the Japan Atomic Energy Research Institute for systems reliability analysis, which is one of the tasks of seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs). The SECOM2 code has many functions such as: Calculation of component failure probabilities based on the response factor method, Extraction of minimal cut sets (MCSs), Calculation of conditional system failure probabilities for given seismic motion levels at the site of an NPP, Calculation of accident sequence frequencies and the core damage frequency (CDF) with use of the seismic hazard curve, Importance analysis using various indicators, Uncertainty analysis, Calculation of the CDF taking into account the effect of the correlations of responses and capacities of components, and Efficient sensitivity analysis by changing parameters on responses and capacities of components. These analyses require the fault tree (FT) representing the occurrence condition of the system failures and core damage, information about response and capacity of components and seismic hazard curve for the NPP site as inputs. This report presents the models and methods applied in the SECOM2 code and how to use those functions. (author)

EXFOR basics. A short guide to the nuclear reaction data exchange format

International Nuclear Information System (INIS)

McLane, Victoria

2000-01-01

EXFOR is the agreed exchange format for the transmission of experimental nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. This report is intended as a guide to data users. For a complete guide to the EXFOR system see: EXFOR Systems Manual, IAEA-NDS-207 (BNL-NCS-63330-00/04-Rev.) (author)

Activity Management System user reference manual. Revision 1

International Nuclear Information System (INIS)

Gates, T.A.; Burdick, M.B.

1994-01-01

The Activity Management System (AMS) was developed in response to the need for a simple-to-use, low-cost, user interface system for collecting and logging Hanford Waste Vitrification Plant Project (HWVP) activities. This system needed to run on user workstations and provide common user access to a database stored on a local network file server. Most important, users wanted a system that provided a management tool that supported their individual process for completing activities. Existing system treated the performer as a tool of the system. All AMS data is maintained in encrypted format. Users can feel confident that any activities they have entered into the database are private and that, as the originator, they retain sole control over who can see them. Once entered into the AMS database, the activities cannot be accessed by anyone other than the originator, the designated agent, or by authorized viewers who have been explicitly granted the right to look at specific activities by the originator. This user guide is intended to assist new AMS users in learning how to use the application and, after the initial learning process, will serve as an ongoing reference for experienced users in performing infrequently used functions. Online help screens provide reference to some of the key information in this manual. Additional help screens, encompassing all the applicable material in this manual, will be incorporated into future AMS revisions. A third, and most important, source of help is the AMS administrator(s). This guide describes the initial production version of AMS, which has been designated Revision 1.0

Nuclear materials management procedures

International Nuclear Information System (INIS)

Veevers, K.; Silver, J.M.; Quealy, K.J.; Steege, E. van der.

1987-10-01

This manual describes the procedures for the management of nuclear materials and associated materials at the Lucas Heights Research Laboratories. The procedures are designed to comply with Australia's nuclear non-proliferation obligations to the International Atomic Energy Agency (IAEA), bilateral agreements with other countries and ANSTO's responsibilities under the Nuclear Non-Proliferation (Safeguards) Act, 1987. The manual replaces those issued by the Australian Atomic Energy Commission in 1959, 1960 and 1969

Operation and maintenance manual for data acquisition system of MIDAS

International Nuclear Information System (INIS)

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

2001-09-01

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

Manual of program operation for data analysis from radiometer system

International Nuclear Information System (INIS)

Silva Mello, L.A.R. da; Migliora, C.G.S.

1987-12-01

This manual describes how to use the software to retrieve and analyse data from radiometer systems and raingauges used in the 12 GHz PROPAGATION MEASUREMENTS/CANADA - TELEBRAS COOPERATION PROGRAM. The data retrieval and analisys is being carried out by CETUC, as part of the activities of the project Simulacao de Enlaces Satelite (SES). The software for these tasks has been supplied by the Canadian Research Centre (CRC), together with the measurement equipment. The two following sections describe the use of the data retrieval routines and the data analysis routines of program ATTEN. Also, a quick reference guide for commands that can be used when a microcomputer is local or remotely connected to a radiometer indoor unit is included as a last section. A more detailed description of these commands, their objectives and cautions that should de taken when using them can be found in the manual ''12 GHz Propagation Measurements System - Volume 1 - Dual Slope Radiometer and Data Aquisition System'', supplied by Diversitel Communications Inc. (author) [pt

Emerging nuclear energy systems and nuclear weapon proliferation

International Nuclear Information System (INIS)

Gsponer, A.; Sahin, S.; Jasani, B.

1983-01-01

Generally when considering problems of proliferation of nuclear weapons, discussions are focused on horizontal proliferation. However, the emerging nuclear energy systems currently have an impact mainly on vertical proliferation. The paper indicates that technologies connected with emerging nuclear energy systems, such as fusion reactors and accelerators, enhance the knowledge of thermonuclear weapon physics and will enable production of military useful nuclear materials (including some rare elements). At present such technologies are enhancing the arsenal of the nuclear weapon states. But one should not forget the future implications for horizontal proliferation of nuclear weapons as some of the techniques will in the near future be within the technological and economic capabilities of non-nuclear weapon states. Some of these systems are not under any international control. (orig.) [de

Manual editing of automatically recorded data in an anesthesia information management system.

Science.gov (United States)

Wax, David B; Beilin, Yaakov; Hossain, Sabera; Lin, Hung-Mo; Reich, David L

2008-11-01

Anesthesia information management systems allow automatic recording of physiologic and anesthetic data. The authors investigated the prevalence of such data modification in an academic medical center. The authors queried their anesthesia information management system database of anesthetics performed in 2006 and tabulated the counts of data points for automatically recorded physiologic and anesthetic parameters as well as the subset of those data that were manually invalidated by clinicians (both with and without alternate values manually appended). Patient, practitioner, data source, and timing characteristics of recorded values were also extracted to determine their associations with editing of various parameters in the anesthesia information management system record. A total of 29,491 cases were analyzed, 19% of which had one or more data points manually invalidated. Among 58 attending anesthesiologists, each invalidated data in a median of 7% of their cases when working as a sole practitioner. A minority of invalidated values were manually appended with alternate values. Pulse rate, blood pressure, and pulse oximetry were the most commonly invalidated parameters. Data invalidation usually resulted in a decrease in parameter variance. Factors independently associated with invalidation included extreme physiologic values, American Society of Anesthesiologists physical status classification, emergency status, timing (phase of the procedure/anesthetic), presence of an intraarterial catheter, resident or certified registered nurse anesthetist involvement, and procedure duration. Editing of physiologic data automatically recorded in an anesthesia information management system is a common practice and results in decreased variability of intraoperative data. Further investigation may clarify the reasons for and consequences of this behavior.

Uranium concentration monitor manual: 2300 system

International Nuclear Information System (INIS)

Russo, P.A.; Sprinkle, J.K. Jr.; Stephens, M.M.

1985-04-01

This manual describes the design, operation, and procedures for measurement control for the automated uranium concentration monitor on the 2300 solvent extraction system at the Oak Ridge Y-12 Plant. The nonintrusive monitor provides a near-real time readout of uranium concentration at two locations simultaneously in the solvent extraction system for process monitoring and control. Detectors installed at the top of the extraction column and at the bottom of the backwash column acquire spectra of gamma rays from the solvent extraction solutions in the columns. Pulse-height analysis of these spectra gives the concentration of uranium in the organic product of the extraction column and in the aqueous product of the solvent extraction system. The visual readouts of concentrations for process monitoring are updated every 2 min for both detection systems. Simultaneously, the concentration results are shipped to a remote computer that has been installed by Y-12 to demonstrate automatic control of the solvent extraction system based on input of near-real time process operation information. 8 refs., 13 figs., 4 tabs

EMSL Operations Manual

Energy Technology Data Exchange (ETDEWEB)

Foster, Nancy S.

2009-06-18

This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

EMSL Operations Manual

Energy Technology Data Exchange (ETDEWEB)

Foster, Nancy S.

2009-03-25

This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

Fluor Hanford Nuclear Material Stabilization Project Welding Manual

International Nuclear Information System (INIS)

BERKEY, J.R.

2000-01-01

The purpose of this section of the welding manual is to: (1) Provide a general description of the major responsibilities of the organizations involved with welding. (2) Provide general guidance concerning the application of codes related to welding. This manual contains requirements for welding for all Fluor Hanford (FH) welding operators working on the W460 Project, in the Plutonium Finishing Plant (PFP) at the U. S. Department of Energy (DOE) Hanford facilities. These procedures and any additional requirements for these joining processes can be used by all FH welding operators that are qualified. The Welding Procedure Specifications (WPS) found in this document were established from Procedure Qualification Records (PQR) qualified by FH specifically for the W460 Project. PQRs are permanent records of the initial testing and qualification program and are used to backup, and support, the WPS. The identification numbers of the supporting PQR(s) are recorded on each WPS. All PQRs are permanently stored under the supervision of the Fluor Hanford Welding Engineer (FHWE). New PQRs and WPSs will continue to be developed as necessary. The qualification of welders, welding operators and welding procedures will be performed for FH under supervision and concurrent of the FHWE. All new welding procedures to be entered in this manual or welder personnel to be added to the welder qualification database, shall be approved by the FHWE

Radiation protection in nuclear facilities. The Caise environmental surveillance system

International Nuclear Information System (INIS)

Witt, H. de; Voelz, E.

1995-01-01

The Computer Aided Surveillance System for the Environment of Nuclear Installations (Caise) has been designed for permanent surveillance of the environment of nuclear installations under normal operating conditions and for unusual events on the basis of radiological and meteorological measured data. In normal operation, the data measured on line are fed to the system by way of a defined interface, while off-line data can be entered manually in the dialog mode. Subsequently, the measured data are stored, filed away, and secured. Short-time dispersion factors can be calculated permanently in the on-line mode, while the off-line mode allows short-term and long-term dispersions to be calculated for randomly selectable periods of time under the General Administrative Rule of Sec. 45 of the German Radiation Protection Ordinance. The corresponding dose distributions in the environment of the plant can be determined next. Under conditions of increased emissions (accidents, failures), Caise assists in quick decision-making by its capacity for real-time dispersion calculations including current on-line and off-line emission sample measurements. In this way, the contributions by various different exposure pathways to the calculated dose can be determined more accurately. (orig.) [de

Energy management information systems - planning manual and tool

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

An Energy Management Information System (EMIS) provides relevant information that makes energy, performance visible to various levels of an organization, enabling individuals and departments to plan, make decisions and take effective action to manage energy. This manual has two objectives: 1. To enable companies to conduct EMIS audits and prepare EMIS implementation plans; 2. To provide companies with the tools to prepare a financial business case for EMIS implementation. This manual consists of four parts: 1. EMIS Audit is theoretical and provides the methodology to be used by outside or in-house engineers and consultants to do a thorough EMIS Audit. 2. Implementation Plan is to help industry do the work themselves. 3. Appendices is to help the user develop an EMIS Audit, gather data and score their company, prepare a conceptual and detailed design, as well as a business and financial plan for implementation.

Nevada National Security Site Radiological Control Manual

International Nuclear Information System (INIS)

2012-01-01

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

Nevada National Security Site Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers’ Council

2012-03-26

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

MARS code manual volume I: code structure, system models, and solution methods

International Nuclear Information System (INIS)

Chung, Bub Dong; Kim, Kyung Doo; Bae, Sung Won; Jeong, Jae Jun; Lee, Seung Wook; Hwang, Moon Kyu; Yoon, Churl

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 theory manual provides a complete list of overall information of code structure and major function of MARS including code architecture, hydrodynamic model, heat structure, trip / control system and point reactor kinetics model. Therefore, this report would be very useful for the code users. 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

EXFOR systems manual

International Nuclear Information System (INIS)

McLane, Victoria

2000-01-01

EXFOR is the exchange format for the transmission of experimental nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. This report contains the agreed coding rules and format. The present version is identical to the report BNL-NCS-63330 (April 2000) except for very few minor corrections introduced by IAEA-NDS. (author)

INES: The International Nuclear and Radiological Event Scale User's Manual. 2008 Edition

International Nuclear Information System (INIS)

2009-05-01

The International Nuclear and Radiological Event Scale is used for promptly and consistently communicating to the public the safety significance of events associated with sources of radiation. It covers a wide spectrum of practices, including industrial use such as radiography, use of radiation sources in hospitals, activities at nuclear facilities, and the transport of radioactive material. By putting events from all these practices into a proper perspective, use of INES can facilitate a common understanding between the technical community, the media and the public. The scale was developed in 1990 by international experts convened by the IAEA and the OECD Nuclear Energy Agency (OECD/NEA). It originally reflected the experience gained from the use of similar scales in France and Japan as well as consideration of possible scales in several countries. Since then, the IAEA has managed its development in cooperation with the OECD/NEA and with the support of more than 60 designated National Officers who officially represent the INES member States in the biennial technical meeting of INES. Initially the scale was applied to classify events at nuclear power plants, and then was extended and adapted to enable it to be applied to all installations associated with the civil nuclear industry. More recently, it has been extended and adapted further to meet the growing need for communication of the significance of all events associated with the transport, storage and use of radioactive material and radiation sources. This revised manual brings together the guidance for all uses into a single document. Events are classified on the scale at seven levels: Levels 4-7 are termed 'accidents' and Levels 1-3 'incidents'. Events without safety significance are classified as 'Below Scale/Level 0'. Events that have no safety relevance with respect to radiation or nuclear safety are not classified on the scale. For communication of events to the public, a distinct phrase has been

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.

US Nuclear Regulatory Commission region IV

International Nuclear Information System (INIS)

Vanderburch, C.

1996-01-01

The NRC has established a policy to provide for the timely through and systematic inspection of significant operational events at nuclear power plants. This includes the use of an Augmented Inspection Team to determine the causes, conditions, and circumstances relevant to an event and to communicate its findings and conclusions to NRC management. In accordance with NRC Inspection Manual Chapter 0325. The Region IV Regional Administrator dispatched an Augmented Inspection Team to the Wolf Creek Nuclear Generating Station to review the circumstances surrounding a manual reactor trip on January 30, 1996, with the failure of five control rods to fully insert into the core, a failure of the turbine-driven auxiliary feedwater pump, and the subsequent loss of one train of the essential service water system

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.

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.)

Manual on decontamination of surfaces

International Nuclear Information System (INIS)

1979-01-01

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

Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power Plant

International Nuclear Information System (INIS)

Kang, Hyun Gook; Jang, Seung-Cheol

2006-01-01

A practical approach to develop a more realistic fault-tree model with a consideration of various conditions endured by a human operator is proposed. In safety-critical systems, the generation failure of an actuation signal is caused by the concurrent failures of the automated systems and an operator action. These two sources of safety signals are complicatedly correlated. The failures of sensors or automated systems will cause a lack of necessary information for a human operator and result in error-forcing contexts such as the loss of corresponding alarms and indications. It is well known that the error-forcing contexts largely affect the operator's performance. An automated system which consists of multiple processing channels and complex components is also affected by the availability of the sensors. This paper proposes a condition-based human reliability assessment (CBHRA) method in order to address these complicated conditions in a practical way. We apply the CBHRA method to the manual actuation of the safety features such as a reactor trip and auxiliary feedwater actuation in Korean Standard Nuclear Power Plants. Even the human error probability of each given condition is simply assumed, the application results prove that the CBHRA effectively accommodates the complicated error-forcing contexts into the fault trees

Computerized low-level waste assay system operation manual

International Nuclear Information System (INIS)

Jones, D.F.; Cowder, L.R.; Martin, E.R.

1976-01-01

An operation and maintenance manual for the computerized low-level waste box counter is presented, which describes routine assay techniques as well as theory of operation treated in sufficient depth so that an experienced assayist can make nonroutine assays. In addition, complete system schematics are included, along with a complete circuit description to facilitate not only maintenance and troubleshooting, but also reproduction of the instrument if desired. Complete software system descriptions are included so far as calculational algorithms are concerned, although detailed instruction listings would have to be obtained from Group R-1 at LASL in order to make machine-language code changes

User's manual for the reactor burnup system, REBUS

International Nuclear Information System (INIS)

Olson, A.P.; Regis, J.P.; Meneley, D.A.; Hoover, L.J.

1972-01-01

A user's manual for the REBUS System (REactor BUrnup System) is presented. Its primary purpose is to provide sufficient information about the REBUS capability to the user to ensure its efficient utilization. The current REBUS System either solves for the infinite time (equilibrium) operating conditions of a recycle system under fixed conditions, or solves for operating conditions during a single time step (non-equilibrium). The capability of studying various in-reactor fuel management and ex-reactor fuel management schemes has been included. REBUS has been operated with one- and two-dimensional diffusion theory neutronics solutions up to the present time. The model was specifically designed for extension to other neutronics models such as three-dimensional diffusion or transport theory and direct or synthesis solutions

The OCaml system release 4.04: Documentation and user's manual

OpenAIRE

Leroy, Xavier; Doligez, Damien; Frisch, Alain; Garrigue, Jacques; Rémy, Didier; Vouillon, Jérôme

2016-01-01

This manual documents the release 4.04 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

The OCaml system release 4.02: Documentation and user's manual

OpenAIRE

Leroy, Xavier; Doligez, Damien; Frisch, Alain; Garrigue, Jacques; Rémy, Didier; Vouillon, Jérôme

2014-01-01

This manual documents the release 4.02 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

The OCaml system release 4.06: Documentation and user's manual

OpenAIRE

Leroy , Xavier; Doligez , Damien; Frisch , Alain; Garrigue , Jacques; Rémy , Didier; Vouillon , Jérôme

2017-01-01

This manual documents the release 4.06 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

Comparison of Inoculation with the InoqulA and WASP Automated Systems with Manual Inoculation

Science.gov (United States)

Croxatto, Antony; Dijkstra, Klaas; Prod'hom, Guy

2015-01-01

The quality of sample inoculation is critical for achieving an optimal yield of discrete colonies in both monomicrobial and polymicrobial samples to perform identification and antibiotic susceptibility testing. Consequently, we compared the performance between the InoqulA (BD Kiestra), the WASP (Copan), and manual inoculation methods. Defined mono- and polymicrobial samples of 4 bacterial species and cloudy urine specimens were inoculated on chromogenic agar by the InoqulA, the WASP, and manual methods. Images taken with ImagA (BD Kiestra) were analyzed with the VisionLab version 3.43 image analysis software to assess the quality of growth and to prevent subjective interpretation of the data. A 3- to 10-fold higher yield of discrete colonies was observed following automated inoculation with both the InoqulA and WASP systems than that with manual inoculation. The difference in performance between automated and manual inoculation was mainly observed at concentrations of >106 bacteria/ml. Inoculation with the InoqulA system allowed us to obtain significantly more discrete colonies than the WASP system at concentrations of >107 bacteria/ml. However, the level of difference observed was bacterial species dependent. Discrete colonies of bacteria present in 100- to 1,000-fold lower concentrations than the most concentrated populations in defined polymicrobial samples were not reproducibly recovered, even with the automated systems. The analysis of cloudy urine specimens showed that InoqulA inoculation provided a statistically significantly higher number of discrete colonies than that with WASP and manual inoculation. Consequently, the automated InoqulA inoculation greatly decreased the requirement for bacterial subculture and thus resulted in a significant reduction in the time to results, laboratory workload, and laboratory costs. PMID:25972424

Nuclear fuel cycle system analysis

International Nuclear Information System (INIS)

Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

2012-04-01

The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

The influence of image setting on intracranial translucency measurement by manual and semi-automated system.

Science.gov (United States)

Zhen, Li; Yang, Xin; Ting, Yuen Ha; Chen, Min; Leung, Tak Yeung

2013-09-01

To investigate the agreement between manual and semi-automated system and the effect of different image settings on intracranial translucency (IT) measurement. A prospective study was conducted on 55 women carrying singleton pregnancy who attended first trimester Down syndrome screening. IT was measured both manually and by semi-automated system at the same default image setting. The IT measurements were then repeated with the post-processing changes in the image setting one at a time. The difference in IT measurements between the altered and the original images were assessed. Intracranial translucency was successfully measured on 55 images both manually and by semi-automated method. There was strong agreement in IT measurements between the two methods with a mean difference (manual minus semi-automated) of 0.011 mm (95% confidence interval--0.052 mm-0.094 mm). There were statistically significant variations in both manual and semi-automated IT measurement after changing the Gain and the Contrast. The greatest changes occurred when the Contrast was reduced to 1 (IT reduced by 0.591 mm in semi-automated; 0.565 mm in manual), followed by when the Gain was increased to 15 (IT reduced by 0.424 mm in semi-automated; 0.524 mm in manual). The image settings may affect IT identification and measurement. Increased Gain and reduced Contrast are the most influential factors and may cause under-measurement of IT. © 2013 John Wiley & Sons, Ltd.

Facilitating Navigation in Quality Manuals by Providing Bookmarks or Similar

International Nuclear Information System (INIS)

Shaharum bin Ramli

2012-01-01

Nuclear Malaysia level quality manuals need to be shared with all divisions. A manual is usually distributed in the form of an electronic document that contains all procedures. Navigation from one heading or procedure to another should be facilitated by providing bookmarks or similar. This paper shows how to do it for Microsoft Word and PDF documents. (author)

User's manual of self learning gas puffing system for plasma density control

International Nuclear Information System (INIS)

Tanahashi, S.

1989-04-01

Pre-programmed gas puffing is often used to get adequet plasma density wave forms in the pulse operating devices for fusion experiments. This method has a defect that preset values have to be adjusted manually in accordance with changes of out gassing rate in successive shots. In order to remove this defect, a self learning system has been developed so as to keep the plasma density close to a given reference waveform. After a few succesive shots, it accomplishes self learning and is ready to keep up with a gradual change of the wall condition. This manual gives the usage of the system and the program list written in BASIC and ASSEMBLER languages. (author)

Evaluation of manual and automatic manually triggered ventilation performance and ergonomics using a simulation model.

Science.gov (United States)

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

2014-05-01

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

Bulgarian Emergency Response System (BERS) in case of nuclear accident with exposure doses estimation

Energy Technology Data Exchange (ETDEWEB)

Syrakov, D.; Prodanova, M.; Slavov, K.; Veleva, B.

2015-07-01

A PC-oriented Emergency Response System in case of nuclear accident (BERS) is developed and works operationally in the National Institute of Meteorology and Hydrology (NIMH). The creation and development of BERS was highly stimulated by the ETEX (European Tracer Experiment) project. BERS comprises two main parts - the operational and the accidental ones. The operational part, run automatically every 12 hours, prepares the input meteorological file used by both trajectory and dispersion models, runs the trajectory models, visualizes the results and uploads the maps of trajectories to a dedicated web-site. The accidental part is activated manually when a real radioactive releases occur or during emergency exercises. Its core is the Bulgarian dispersion models EMAP. Outputs are concentration, accumulated deposition and selected doses fields. In the paper, the BERS overall structure is described and examples of its products are presented. Key words: nuclear accident, emergency response, early warning system, air dispersion models, radioactive exposure dose. (Author)

Upgradation of nuclear medical equipment in the developing countries and its impact in Bangladesh

International Nuclear Information System (INIS)

Jahangir, Saleh Mahmud; Xie, Y.; Uddin, Md. Rokon; Haque, Mohammod Abu Sayid; Hoq, Mahbubul; Mawla, Yasmeen; Alom, Md. Zahangir; Morium, Tasnim

2002-11-01

Bangladesh has thirteen Nuclear Medical Centres and one Institute of Nuclear Medicine in the country which are being run and maintained by the physicians scientists and engineers of Bangladesh Atomic Energy Commission. The peaceful application of atomic energy was initiated through all these Centres with the use of clinical isotopes for thyroid and kidney studies. The equipment used for these purposes were the thyroid uptake system, rectilinear scanner and the multiprobe renogram system. The first gamma camera was installed in the country in 1980 at the Institute of Nuclear Medicine, Dhaka. That was the turning point for the country in the field of nuclear medicine. Presently all the nuclear medical establishments are equipped least with a gamma camera, thyroid uptake system and a renogram system. In the last two decades there has been a tremendous development in the design of nuclear medical equipment. Most of the old equipments were slow and manually operated. In the beginning of nineties of the past century there was an uprising in the computer technology and most of the manually operated machines were brought under computerization. It was basically done with a custom built processor to perform only the specific job and spare the users from doing some extra manual work. But the performances of the recent models of the same computerized equipment are by far the best as compared with the past ones. This report describes the role of the IAEA in the upgradation of medical equipment, PC interfacing, upgrading of old gamma cameras and the technological and socio-economic impact in Bangladesh

System design for safe robotic handling of nuclear materials

International Nuclear Information System (INIS)

Drotning, W.; Wapman, W.; Fahrenholtz, J.; Kimberly, H.; Kuhlmann, J.

1996-01-01

Robotic systems are being developed by the Intelligent Systems and Robotics Center at Sandia National Laboratories to perform automated handling tasks with radioactive nuclear materials. These systems will reduce the occupational radiation exposure to workers by automating operations which are currently performed manually. Because the robotic systems will handle material that is both hazardous and valuable, the safety of the operations is of utmost importance; assurance must be given that personnel will not be harmed and that the materials and environment will be protected. These safety requirements are met by designing safety features into the system using a layered approach. Several levels of mechanical, electrical and software safety prevent unsafe conditions from generating a hazard, and bring the system to a safe state should an unexpected situation arise. The system safety features include the use of industrial robot standards, commercial robot systems, commercial and custom tooling, mechanical safety interlocks, advanced sensor systems, control and configuration checks, and redundant control schemes. The effectiveness of the safety features in satisfying the safety requirements is verified using a Failure Modes and Effects Analysis. This technique can point out areas of weakness in the safety design as well as areas where unnecessary redundancy may reduce the system reliability

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-11-01

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

Combating illicit trafficking in nuclear and other radioactive material. Reference material

International Nuclear Information System (INIS)

2007-01-01

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

Nuclear material control systems for nuclear power plants

International Nuclear Information System (INIS)

1975-06-01

Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

Instruction manual for operating the Sensys System for temporary traffic counts

Science.gov (United States)

2010-01-01

This instruction manual provides information and the procedures for using the Sensys System, which was initially designed to operate in a server controlled network, for temporary traffic counts. The instructions will allow the user to fully understan...

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

Literature study regarding fire protection in nuclear power plants. Part 2: Fire detection and -extinguishing systems

International Nuclear Information System (INIS)

Isaksson, S.

1996-01-01

This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Detection and extinguishing systems in Swedish nuclear power plants have only to a limited extent been designed after functional demands, such as a maximum acceptable damage or a maximum time to detect a fire. The availability of detection systems is difficult to assess, partly because of lack of statistics. The user interface is very important in complex systems as nuclear plants. An extinguishing system designed according to the insurance companies' regulations will only fulfill the basic demands. It should be noted that normal sprinkler design does not aim for extinguishing fires, the objective is to control fire until manual extinguishment is possible. There is a great amount of statistics on wet and dry pipe sprinkler systems, while statistics are more scarce for deluge systems. The statistics on the reliability of gaseous extinguishing systems have been found very scarce. A drawback of these systems is that they are normally designed for one shot only. There are both traditional and more recent extinguishing systems that can replace halons. From now on there will be a greater need for a thorough examination of the properties needed for the individual application and a quantification of the acceptable damage. There are several indications on the importance of a high quality maintenance program as well as carefully developed routines for testing and surveillance to ensure the reliability of detection and extinguishing systems. 78 refs, 8 figs, 10 tabs

Automatic testing technologies for I and C systems for nuclear power plants

International Nuclear Information System (INIS)

Yoshida, Motoko; Sugio, Takayuki; Konishi, Tadao

2014-01-01

With the aim of enhancing the global competitiveness of instrumentation and control (I and C) systems for nuclear power plants, Toshiba has been making efforts to reduce the worker hours required for the testing of such systems and improve the quality of the tests. Display screen tests, which include many routine, repetitive tests and manual tests requiring a large number of operators to monitor multiple screen displays of the I and C system, are an essential element of the testing process. The introduction of automatic testing technologies is expected to substantially improve the efficiency of such display screen tests. We have now developed automatic testing technologies for display screen tests that can be applied without the need to change the I and C system. These technologies contribute to both the reduction of worker hours for testing and improvement of the quality of the tests. (author)

Application of Safety Instrumented System (SIS) approach in older nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Nasimi, Elnara; Gabbar, Hossam A., E-mail: hossam.gabbar@uoit.ca

2016-05-15

Highlights: • Study Safety Instrumented System (SIS) design for older nuclear power plant. • Apply SIS on Reheater Drains (RD) system. • Apply IEC 61508/61511 to design safety system. • Evaluate risk reduction based on proposed SIS design. - Abstract: In order to remain economically effective and financially profitable, the modern industries have to take their safety culture to a higher level and consider production losses in addition to simple accident prevention techniques. Ideally, compliance with safety requirements start during early design stages, but in some older facilities provisions for Safety Instrumented Systems (SIS) may not have been originally included. In this paper, a case study of a Reheater Drains (RD) system is used to illustrate such an example. Frequent failures of tank level controller lead to transients where the operation of shutting down RD pumps requires operators to manually isolate the quenching water and to close the main steam admission valves. Water in this system is at saturation temperature for the reheater steam side pressure, and any manual operation of the system is highly undesirable due to hazards of working with wet steam at approximately 758 kPa(g) pressure, preheated to 237 °C. Additionally, losses of inventory are highly undesirable as well and challenge other systems in the plant. In this paper, it is suggested that RD system can benefit from installation of an independent SIS system in order to address current challenges. This idea is being explored using IEC 61508 framework for “Functional safety of electrical/electronic/programmable electronic safety-related systems” to provide assurance that the SIS will offer the necessary risk reduction required to achieve required safety for the equipment.

Radioactive material defense construction using wind fan system against nuclear fallout in the aspect of nano-scopic dispersion

International Nuclear Information System (INIS)

Woo, Tae Ho

2012-01-01

Highlights: ► A realistic radiation protection system using aerodynamics is suggested. ► Manual formation procedure is constructed by this modeling. ► Chemical and natural accidents by wind fan are applicable. ► Nuclear disaster is avoided by national defense system. ► A sample case is realistically modeled. -- Abstract: Radioactive fallout defense system (RFDS) is suggested against possible nuclear accidents. A procedure consisting of several stages is considered. In particular, the dispersion of radioactive material is investigated for the case of wind fan operation where the radioactive molecules are considered as nano-scopic material. The modeling is done for one country dealing with a possible nuclear accident in another country. This study is thus applicable to regions where westerlies are prevailing. An aerodynamic fan analysis is performed. The incoming free wind stream is characterized by random sampling in Monte-Carlo simulation. The velocity of the fan is a critical aspect of the model. This model is applicable for volcanic ashes, nuclear bomb fallout, chemical material dispersion, and any other material combined with airflow. In addition, this fan could be studied, with nano-scale considerations, by a multi-scale technique.

BLOCKAGE 2.5 reference manual

International Nuclear Information System (INIS)

Shaffer, C.J.; Brideau, J.; Rao, D.V.; Bernahl, W.

1996-12-01

The BLOCKAGE 2.5 code was developed by the US Nuclear Regulatory Commission (NRC) as a tool to evaluate license compliance regarding the design of suction strainers for emergency core cooling system (ECCS) pumps in boiling water reactors (BWR) as required by NRC Bulletin 96-03, ''Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors''. Science and Engineering Associates, Inc. (SEA) and Software Edge, Inc. (SE) developed this PC-based code. The instructions to effectively use this code to evaluate the potential of debris to sufficiently block a pump suction strainer such that a pump could lose NPSH margin was documented in a User's Manual (NRC, NUREG/CR-6370). The Reference Manual contains additional information that supports the use of BLOCKAGE 2.5. It contains descriptions of the analytical models contained in the code, programmer guides illustrating the structure of the code, and summaries of coding verification and model validation exercises that were performed to ensure that the analytical models were correctly coded and applicable to the evaluation of BWR pump suction strainers. The BLOCKAGE code was developed by SEA and programmed in FORTRAN as a code that can be executed from the DOS level on a PC. A graphical users interface (GUI) was then developed by SEA to make BLOCKAGE easier to use and to provide graphical output capability. The GUI was programmed in the C language. The user has the option of executing BLOCKAGE 2.5 with the GUI or from the DOS level and the Users Manual provides instruction for both methods of execution

Explosives Classifications Tracking System User Manual

Energy Technology Data Exchange (ETDEWEB)

Genoni, R.P.

1993-10-01

The Explosives Classification Tracking System (ECTS) presents information and data for U.S. Department of Energy (DOE) explosives classifications of interest to EM-561, Transportation Management Division, other DOE facilities, and contractors. It is intended to be useful to the scientist, engineer, and transportation professional, who needs to classify or transport explosives. This release of the ECTS reflects upgrading of the software which provides the user with an environment that makes comprehensive retrieval of explosives related information quick and easy. Quarterly updates will be provided to the ECTS throughout its development in FY 1993 and thereafter. The ECTS is a stand alone, single user system that contains unclassified, publicly available information, and administrative information (contractor names, product descriptions, transmittal dates, EX-Numbers, etc.) information from many sources for non-decisional engineering and shipping activities. The data is the most up-to-date and accurate available to the knowledge of the system developer. The system is designed to permit easy revision and updating as new information and data become available. These, additions and corrections are welcomed by the developer. This user manual is intended to help the user install, understand, and operate the system so that the desired information may be readily obtained, reviewed, and reported.

Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0: Integrated Reliability and Risk Analysis System (IRRAS) reference manual. Volume 2

International Nuclear Information System (INIS)

Russell, K.D.; Kvarfordt, K.J.; Skinner, N.L.; Wood, S.T.; Rasmuson, D.M.

1994-07-01

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the use the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification to report generation. Version 1.0 of the IRRAS program was released in February of 1987. Since then, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 5.0 and is the subject of this Reference Manual. Version 5.0 of IRRAS provides the same capabilities as earlier versions and ads the ability to perform location transformations, seismic analysis, and provides enhancements to the user interface as well as improved algorithm performance. Additionally, version 5.0 contains new alphanumeric fault tree and event used for event tree rules, recovery rules, and end state partitioning

Some perspectives in nuclear robotics

International Nuclear Information System (INIS)

Ollier, J.L.; Mercier, O.

1992-01-01

Radiation exposure imposes close limits upon human activities in maintenance work in nuclear reactors. Manual or automated tool systems thus are becoming more and more important, especially for work on reactor cooling systems, in pressurizers, or in reactor vessels. Robot systems can be used the more universally, the easier it is to program them. Yet, special applications will require tailor-made solutions, up to and including self-controlling computer systems. Because of the great expense involved in developing them, the robot systems now available for use in nuclear power plants are the results of joint research by various European manufacturers and operators, sometimes with the support of the European Communities. Aramis is used, e.g., for manipulators, Frastar for mobile applications. (orig.) [de

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

Science.gov (United States)

Martorello, Laura; Swanson, Edward

2006-01-01

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

Performance of MSRE Nuclear Power Control Systems (MSRE Test Report 5.2.1)

International Nuclear Information System (INIS)

Gabbard, C. H.

1968-01-01

The nuclear power control systems of the MSRE were evaluated by observing the steady-state operation of the reactor and by conducting a series of transient tests. The temperature servo was found capable of controlling all the transients that were introduced. However, because of the relatively slow response and inherent stability of the reactor system, the temperature servo was found to be relatively inactive during many of the load change transients. The automatic load control operated as expected except that the minimum power available to the automatic control was about 2 Mw instead of l Mw as had been planned. This has not caused a problem in the reactor operation because the load control has normally been operated in 'manual'.

Development of robots for nuclear power plants

International Nuclear Information System (INIS)

Sasaki, Masayoshi

1982-01-01

In nuclear power plants, the reduction of maintenance time, the reduction of radiation exposure and man-power saving are increasingly required. To achieve these purposes, various remote-controlled devices, such as robots in a broad sense, have been earnestly developed. Of these, three machines for replacing, four devices for inspection, two systems for cleaning, and two equipment for processing are tabulated in this paper. Typical eight machines or equipment are briefly introduced, mainly describing their features or characteristics. Those are: a remotely handling machine for control rod drive mechanism, an automatic refueling machine, an automatic ultrasonic flaw detection system replacing for a manually operated testing system for the welded parts of primary cooling system, an automatic cask washing machine for decontamination, a floor-type remote inspection vehicle for various devices operating inside power plants, a monorail-type remote inspection vehicle for inspection in spaces where floor space is short, and a remote-controlled automatic pipe welding machine for welding operations in a radioactive environment such as replacing the piping of primary cooling system. Most of these devices serves for radiation exposure reduction at the same time. Existing nuclear power plant design assumes direct manual maintenance, which limits the introduction of robots. Future nuclear power plants should be designed on the assumption of automatic remote-controlled tools and devices being used in maintenance work. (Wakatsuki, Y.)

Statistical methods for nuclear material management

International Nuclear Information System (INIS)

Bowen, W.M.; Bennett, C.A.

1988-12-01

This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems

Statistical methods for nuclear material management

Energy Technology Data Exchange (ETDEWEB)

Bowen W.M.; Bennett, C.A. (eds.)

1988-12-01

This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems.

SIDA - System for importation distribution and acquisition of radioisotope - User manual

International Nuclear Information System (INIS)

1991-01-01

The SIDA manual (system for importation, distribution and acquisition of radioisotopes) is presented. The SIDA is a system of consult and update to control importation and distribution of radioisotopes in the country. It allows to accompany processes from importation requirement to distribution of radioisotopes, executing the accountancy of I-125, which is distributed for several interprises. The system was developed in CLIPPER87 using DBASE III PLUS data base management. (M.C.K.)

Manual estimation of fallout casualties. Final report

International Nuclear Information System (INIS)

Gant, K.S.; Haaland, C.M.

1978-08-01

A method is described for enabling Emergency Operating Centers (EOCs) to estimate nuclear fallout casualties (fatalities and injuries) during and after nuclear attack without the aid of computers. This method is compatible with the current manual method for estimating initial weapons effects. The new technique requires that the EOCs have information on nuclear detonations and upper wind conditions and that they have maps, a protractor, map overlay material, grease pencils, worksheets, and pencils. In addition, they will need two tables of data and a fallout casualty (FC) template, all supplied in this report. Five steps are involved in the estimation of fallout casualties for an area: sketching fallout wind streamlines on a map overlay; plotting locations of nuclear detonations and their fallout streamlines; measuring crosswind and upwind distances to detonation points from the point of interest; reading radiation exposure tables and summing the contributions from different weapons to obtain the exposure at that point; and using the FC template with the protection factor profile for the area to estimate fatalities and injuries. The tables of radiation exposure are based on a modified Weapons Systems Evaluation Group-10 (WSEG-10) fallout model. The table of county protection factor profiles (PFPs) assumes a Community Shelter Plan (CSP) posture

Manual and automatic locomotion scoring systems in dairy cows: A review

NARCIS (Netherlands)

Schlageter-Tello, A.; Bokkers, E.A.M.; Groot Koerkamp, P.W.G.; Hertem, van T.; Viazzi, S.; Romanini Bites, E.; Halachmi, I.; Bahr, C.; Berckmans, D.; Lokhorst, K.

2014-01-01

The objective of this review was to describe, compare and evaluate agreement, reliability, and validity of manual and automatic locomotion scoring systems (MLSSs and ALSSs, respectively) used in dairy cattle lameness research. There are many different types of MLSSs and ALSSs. Twenty-five MLSSs were

Quality Management System at the Nuclear Regulatory Authority of the Slovak Republic

International Nuclear Information System (INIS)

Husarcek, J.; Novak, S.

2008-01-01

The process-oriented quality management system (QMS) implemented at the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in compliance with the EN ISO 9001:2001 standard is described. The history of the establishment and development of the QMS is given. The main, managerial and supporting processes with respect to defined activities are specified, and a scheme of their interactions is presented. The contents of the Quality Manual content and the structure of the system documentation are briefly described. The responsibilities for the operation and improvements of the QMS are described along with the methods applied (internal and external audits, self-assessment - Common Assessment Framework (CAF)). Examples of established quality objectives and indicators for some processes are provided. A future development of the QMS is expected in accordance with the relevant ISO Standard and IAEA recommendations and based on evaluation of the effectiveness of the critical system. (orig.)

Interactive hypermedia training manual for spent-fuel bundle counters

International Nuclear Information System (INIS)

Basso, R.A.

1990-07-01

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

Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

International Nuclear Information System (INIS)

Downey, N.J.

1994-01-01

This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User's Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered

Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Downey, N.J.

1994-12-14

This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User`s Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered.

Manual of selected physico-chemical analytical methods. IV

International Nuclear Information System (INIS)

Beran, M.; Klosova, E.; Krtil, J.; Sus, F.; Kuvik, V.; Vrbova, L.; Hamplova, M.; Lengyel, J.; Kelnar, L.; Zakouril, K.

1990-11-01

The Central Testing Laboratory of the Nuclear Research Institute at Rez has for a decade been participating in the development of analytical procedures and has been providing analyses of samples of different types and origin. The analytical procedures developed have been published in special journals and a number of them in the Manuals of analytical methods, in three parts. The 4th part of the Manual contains selected physico-chemical methods developed or modified by the Laboratory in the years 1986-1990 within the project ''Development of physico-chemical analytical methods''. In most cases, techniques are involved for non-nuclear applications. Some can find wider applications, especially in analyses of environmental samples. Others have been developed for specific cases of sample analyses or require special instrumentation (mass spectrometer), which partly restricts their applicability by other institutions. (author)

EXFOR Manual. Center-to-Center Exchange Format. Version 89-1

International Nuclear Information System (INIS)

McLane, V.

1989-09-01

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. EXFOR is a database with several million data records containing the world's experimental nuclear reaction data induced by neutrons, photons or charged particles. Data retrievals can be obtained from the IAEA Nuclear Data Section (NDS) or from one of the co-operating data centers whose names and addresses can be found inside the manual. Their contributions and co-operative efforts are gratefully acknowledged. (author). Refs

Equipment Qualification Data Base user manual

International Nuclear Information System (INIS)

Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

1985-09-01

This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

Module type plant system dynamics analysis code (MSG-COPD). Code manual

International Nuclear Information System (INIS)

Sakai, Takaaki

2002-11-01

MSG-COPD is a module type plant system dynamics analysis code which involves a multi-dimensional thermal-hydraulics calculation module to analyze pool type of fast breeder reactors. Explanations of each module and the methods for the input data are described in this code manual. (author)

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

International Nuclear Information System (INIS)

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

1983-07-01

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

Nuclear power plant diagnostic system

International Nuclear Information System (INIS)

Prokop, K.; Volavy, J.

1982-01-01

Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

Design and control of electromagnetic clutch actuation system for automated manual transmission

Science.gov (United States)

Ranjan, Ashish; Prasanth, S.; Cherian, Fenin; Baskar, P.

2017-11-01

There is a growing interest towards Automatic Transmission in India as it provides better comfort and drivability. But the high cost of this system is limiting itself to be successful in the Indian markets. Due to this, Automated Manual Transmission (AMT) is considered which provides a better solution towards automation as it enhances the drivability and fuel consumption characteristics of a manual transmission at lower costs. However, torque lag and comfort are major issues with AMT which can be addressed by reducing the shift time. In this paper we describe an Electromagnetic Linear Clutch Actuator as a replacement to current electrohydraulic and electromechanical actuator. A control system for the actuator is presented and a clutch engagement strategy is also implemented which reduces the engagement time to 0.78 seconds while reducing jerk and torque lag. The actuator and control system is simulated on a MATLAB Simulink and agreeable results have been obtained.

Computer-aided method for recognition of proton track in nuclear emulsion

International Nuclear Information System (INIS)

Ruan Jinlu; Li Hongyun; Song Jiwen; Zhang Jianfu; Chen Liang; Zhang Zhongbing; Liu Jinliang

2014-01-01

In order to overcome the shortcomings of the manual method for proton-recoil track recognition in nuclear emulsions, a computer-aided track recognition method was studied. In this method, image sequences captured by a microscope system were processed through image convolution with composite filters, binarization by multi thresholds, track grains clustering and redundant grains removing to recognize the track grains in the image sequences. Then the proton-recoil tracks were reconstructed from the recognized track grains through track reconstruction. The proton-recoil tracks in the nuclear emulsion irradiated by the neutron beam at energy of 14.9 MeV were recognized by the computer-aided method. The results show that proton-recoil tracks reconstructed by this method consist well with those reconstructed by the manual method. This compute-raided track recognition method lays an important technical foundation of developments of a proton-recoil track automatic recognition system and applications of nuclear emulsions in pulsed neutron spectrum measurement. (authors)

User's manual of JT-60 experimental data analysis system

International Nuclear Information System (INIS)

Hirayama, Takashi; Morishima, Soichi; Yoshioka, Yuji

2010-02-01

In the Japan Atomic Energy Agency Naka Fusion Institute, a lot of experiments have been conducted by using the large tokamak device JT-60 aiming to realize fusion power plant. In order to optimize the JT-60 experiment and to investigate complex characteristics of plasma, JT-60 experimental data analysis system was developed and used for collecting, referring and analyzing the JT-60 experimental data. Main components of the system are a data analysis server and a database server for the analyses and accumulation of the experimental data respectively. Other peripheral devices of the system are magnetic disk units, NAS (Network Attached Storage) device, and a backup tape drive. This is a user's manual of the JT-60 experimental data analysis system. (author)

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Min, E-mail: jewellee@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Lee, Hyun Chul, E-mail: leehc@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Ha, Jun Su, E-mail: junsu.ha@kustar.ac.ae [Department of Nuclear Engineering, Khalifa University of Science Technology and Research, Abu Dhabi P.O. Box 127788 (United Arab Emirates); Seong, Poong Hyun, E-mail: phseong@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

2016-10-15

Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Min; Lee, Hyun Chul; Ha, Jun Su; Seong, Poong Hyun

2016-01-01

Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

Operation manual for the INEL on-line mass-separator facility

International Nuclear Information System (INIS)

Anderl, R.A.

1984-06-01

This report is an operation manual for an on-line mass-separator facility which is located in Building 661 at the Test Reactor Area of the Idaho National Engineering Laboratory. The facility provides mass-separated sources of short-lived fission-product radionuclides whose decay properties can be studied using a variety of nuclear spectroscopic techniques. This facility is unique in that it utilizes the gas-jet technique to transport fission products from a 252 Cf source located in a hot cell to the ion source of the mass separator. This document includes the following: (a) a detailed description of the facility, (b) identification of equipment hazards and safety controls, (c) detailed operating procedures for startup, continuous operation and shutdown, (d) operating procedures for the californium hot cell, and (e) an operator's manual for the automated moving tape collector/data acquisition system. 7 references, 16 figures, 8 tables

Nuclear power plant steam pipes repairing with TIRANT 3 robot system

International Nuclear Information System (INIS)

Soto Tomas, Marcelo; Curiel Nieva, Marceliano; Monzo Blasco, Enrique; Rodriguez, Salvador Pineda; Vaquer Perez, Juan I.

2011-01-01

A typical application functions covering the steam pipes inner surface in coal-fired power station and nuclear power plants. The results of this process are spectacular in terms of protection against corrosion and abrasion, but its application has conditioning factors, such as: Severe application conditions for workers. Due to the postural position (usually kneeling) in small diameter pipes and working with fireproof clothing and masks with outdoor air supplying, due to fumes, sparks and molten metal particles, radiological contamination, confined space, poor lighting... Coating uniformity. As metallization is a manual process, the carried out measurements show small variations in the thickness of the coating, always within the tolerance limits established by the applicable regulations and quality assurance. For all these reasons, Grupo Dominguis has developed the TIRANT 3 robot, a worldwide innovative system, for metallization of steam pipes inner surface. TIRANT 3 robot is teleoperated from outside of the pipe, so that human intervention is reduced to the operations of robot positioning and change of metallization wire. As it is an independent system of the human factor, metallization process performance is significantly increased by reducing rest periods due only to the robot maintenance. Likewise, TIRANT 3 system permits to increase resulting coating uniformity, and thus its resistance, keeping selected parameters constant depending on required type and thickness of wire. TIRANT 3 system has successfully worked in 2010 during the stops refueling of the Units I and II of Laguna Verde nuclear power plant in Mexico. (author)

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.

A training manual for event history data management using Health and Demographic Surveillance System data.

Science.gov (United States)

Bocquier, Philippe; Ginsburg, Carren; Herbst, Kobus; Sankoh, Osman; Collinson, Mark A

2017-06-26

The objective of this research note is to introduce a training manual for event history data management. The manual provides a first comprehensive guide to longitudinal Health and Demographic Surveillance System (HDSS) data management that allows for a step-by-step description of the process of structuring and preparing a dataset for the calculation of demographic rates and event history analysis. The research note provides some background information on the INDEPTH Network, and the iShare data repository and describes the need for a manual to guide users as to how to correctly handle HDSS datasets. The approach outlined in the manual is flexible and can be applied to other longitudinal data sources. It facilitates the development of standardised longitudinal data management and harmonization of datasets to produce a comparative set of results.

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.)

Nevada Test Site Radiological Control Manual, Revision 1

International Nuclear Information System (INIS)

2010-01-01

Management. The NTS has been the primary location for testing nuclear explosives in the continental United States since 1951. The topographical and geological characteristics of the NTS afford some protection to the inhabitants of the surrounding areas from potential radiation exposure as a result of release of radioactivity or contamination from nuclear testing operations. Historically, testing programs at the NTS have included atmospheric testing in the 1950s and early 1960s; underground testing in drilled, vertical holes and horizontal tunnels; earth-cratering experiments; and open air nuclear reactor and engine testing. Current activities include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures. The Tenant Organizations (TOs) that are responsible for conducting operations, according to this manual, include National Security Technologies, LLC (NSTec), Defense Threat Reduction Agency, Desert Research Institute, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Navarro Nevada Environmental Services, LLC, Sandia National Laboratories, and WSI. These organizations operate under this manual only when they are performing activities under the purview of NNSA/NSO. To ensure that the appropriate procedures

Innovative nuclear energy systems roadmap

International Nuclear Information System (INIS)

2007-12-01

Developing nuclear energy that is sustainable, safe, has little waste by-product, and cannot be proliferated is an extremely vital and pressing issue. To resolve the four issues through free thinking and overall vision, research activities of 'innovative nuclear energy systems' and 'innovative separation and transmutation' started as a unique 21st Century COE Program for nuclear energy called the Innovative Nuclear Energy Systems for Sustainable Development of the World, COE-INES. 'Innovative nuclear energy systems' include research on CANDLE burn-up reactors, lead-cooled fast reactors and using nuclear energy in heat energy. 'Innovative separation and transmutation' include research on using chemical microchips to efficiently separate TRU waste to MA, burning or destroying waste products, or transmuting plutonium and other nuclear materials. Research on 'nuclear technology and society' and 'education' was also added in order for nuclear energy to be accepted into society. COE-INES was a five-year program ending in 2007. But some activities should be continued and this roadmap detailed them as a rough guide focusing inventions and discoveries. This technology roadmap was created for social acceptance and should be flexible to respond to changing times and conditions. (T. Tanaka)

Main-coolant-pump shaft-seal guidelines. Volume 1. Maintenance-manual guidelines. Final report

International Nuclear Information System (INIS)

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

1983-03-01

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

Information Resources; A Searcher's Manual. MOREL Regional Information System for Educators.

Science.gov (United States)

Grimes, George; Doyle, James

This document is one of a series describing the background, functions, and utilization of the Regional Information System (RIS) developed by the Michigan-Ohio Regional Educational Laboratory (MOREL). The purpose of this manual is to detail a procedure for performing a productive search of information resources which can satisfy the informational…

Nuclear steam supply system and method of installation

International Nuclear Information System (INIS)

Tower, S.N.; Christenson, J.A.; Braun, H.E.

1989-01-01

This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

Thermal performance advisor expert system development

International Nuclear Information System (INIS)

McClintock, M.; Hirota, N.; Metzinger, R.

1991-01-01

In recent years the electric industry has developed an increased interest in improving efficiency of nuclear power plants. EPRI has embarked upon a research project RP2407, Nuclear Plant Performance Improvements which is designed to address needs in this area. One product of this project has been the Thermal Performance Diagnostic Manual for Nuclear Power Plants (NP-4990P). The purpose of this manual is to provide engineering personnel at nuclear power plants with a consistent way in which to identify thermal performance problems. General Physics is also involved in the development of another computer system called Fossil Thermal Performance Advisor (FTPA) which helps operators improve performance for fossil power plants. FTPA is a joint venture between General Physics and New York State Electric and Gas Company. This paper describes both of these computer systems and uses the FTPA as an interesting comparison that illustrates the considerations required for the development of a computer system that effectively addresses the needs of the users

Nuclear and related techniques in parasitology: A laboratory manual

Energy Technology Data Exchange (ETDEWEB)

Hayunga, E.G.; Stek, M. Jr. (eds.)

1986-01-01

The course, entitled ''Atomic Energy Applications in Parasitology'', was offered by the Division of Tropical Public Health, Department of Preventive Medicine, and Biometrics, Uniformed Services University of the Health Sciences, Bethesda, Maryland. It was an intensive 3-week endeavor during which students attended lectures and acquired practical hands-on experience with the most recent laboratory tools. The course began with an exhaustive introduction to radiation physics, then encompassed a variety of practical applications including irradiation attenuation, radioisotope labeling, tracer techniques and radioimmunoassays. This laboratory manual was written by the faculty in an attempt to document the learning experience of the training course and to provide a detailed description of state-of-the-art technology with up-to-date references. Clearly, the manual has value as a historical document. However, the chapters were written with the explicit intention that they be useful to future investigators who wish to apply these methods to their particular research problem.

HANSF 1.3 user's manual

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

PFP MICON maintenance manual. Revision 1

International Nuclear Information System (INIS)

Silvan, G.R.

1995-01-01

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

Integrated information system for analysis of nuclear power plants

International Nuclear Information System (INIS)

Galperin, A.

1994-01-01

Performing complicated engineering analyses of a nuclear power plant requires storage and manipulation of a large amount of information, both data and knowledge. This information is characterized by its multidisciplinary nature, complexity, and diversity. The problems caused by inefficient and lengthy manual operations involving the data flow management within the frame-work of the safety-related analysis of a power plant can be solved by applying the computer aided engineering principles. These principles are the basis of the design of an integrated information storage system (IRIS). The basic idea is to create a computerized environment, which includes both database and functional capabilities. Consideration and analysis of the data types and required data manipulation capabilities as well as operational requirements, resulted in the choice of an object-oriented data-base management system (OODBMS) as a development platform for solving the software engineering problems. Several advantages of OODBMSs over conventional relations database systems were found of crucial importance, especially providing the necessary flexibility for different data types and extensibility potential. A detailed design of a data model is produced for the plant technical data and for the storage of analysis results. The overall system architecture was designed to assure the feasibility of integrating database capabilities with procedures and functions written in conventional algorithmic programming languages

Development of an information systems to manage the fuel elements of a nuclear reactor

International Nuclear Information System (INIS)

Neira Orellana, Alicia Cristina

1999-01-01

The development of a computerized information system is presented that administers the fuel elements of a nuclear reactor. This system automates the mathematical calculations of the nuclear reactor's configuration, which have been manually controlled for many years, and it also manages the inventory of these elements for each one of the different deposits of nuclear materials. This system was designed and built based on an Object Oriented Focus (OOF), which fully meets the requirements requested and aims to facilitate the interaction between the user and the machine. The OOF methodology is based on that proposed by Peter Coad and Edward Yourdon and the development tool used is DELPHI version 3.0 (object oriented programming graphics tool that uses Pascal Object language and a Windows '98 platform). To implement the prepared tool the different stages as indicated by the authors of the above-mentioned methodology were carried out step by step, concluding with the practical benefits associated with the use of the proposed focus. A Graphic Interactive Tool is obtained that will be used in part by the people who directly operate the nuclear reactor and who do the mathematical calculations for the configuration of its nucleus. The system will allow them to considerably reduce the time needed for administering the fuel elements with the automated configuration of the operating cycle. The importance of the combination of these elements varies depending on experimental needs. All those processes linked to the configuration of the nucleus are very important, particularly the calculation of fuel element wear (burned) and the coefficient calculation that validates this configuration. These processes were used during the development of this thesis work. The system also manages an inventory of all the elements with their respective histories, facilitating follow-ups and analyses (C.W)

Methane measurements manual; Handbok metanmaetningar

Energy Technology Data Exchange (ETDEWEB)

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

2011-02-15

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

Handbook of laboratory techniques; Manual de tecnicas de laboratorio

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The Nuclear Regulatory Authority in Argentina have laboratories of support to regulations functions on radiological and nuclear safety, safeguards and physical protection, that have a surface of 2950 m{sup 2} in the Ezeiza Atomic Center. The manual describes in seven chapters the different techniques developed and applied in the laboratories along four decades of existence. The chapter 1: Dedicated to the treatment of environmental samples, described the procedures associated with the different types of samples: deposits, waters, sediments, vegetables, milk, fish and diet. The chapter 2: Details 48 radiochemical techniques associated to the measurements of americium 241, carbon 16, strontium 90, iodine 129, plutonium, radium 226, radon, uranium, nickel and actinides. The chapter 3: Describes the measurements techniques of alpha and gamma spectrometry. The different techniques of biological and physical dosimetry are described in the chapters 5 and 6 respectively. The final chapter is dedicated the techniques of external and internal contamination. It s important to emphasize that this manual contains the standardized technologies that the Nuclear Regulatory Authority of Argentina submits regularly to international comparisons.

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

International Nuclear Information System (INIS)

2011-01-01

The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

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

International Nuclear Information System (INIS)

2012-01-01

The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

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

International Nuclear Information System (INIS)

2012-01-01

The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

Mobile nuclear power systems

International Nuclear Information System (INIS)

Andersson, B.

1988-11-01

This report is meant to present a general survey of the mobile nuclear power systems and not a detailed review of their technical accomplishments. It is based in published material mainly up to 1987. Mobile nuclear power systems are of two fundamentally different kinds: nuclear reactors and isotopic generators. In the reactors the energy comes from nuclear fission and in the isotopic generators from the radioactive decay of suitable isotopes. The reactors are primarily used as power sourves on board nuclear submarines and other warships but have also been used in the space and in remote places. Their thermal power has ranged from 30 kWth (in a satellite) to 175 MWth (on board an aircraft carrier). Isotopic generators are suitable only for small power demands and have been used on board satellites and spaceprobes, automatic weatherstations, lighthouses and marine installations for navigation and observation. (author)

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

Comparison of manual versus semiautomatic milk recording systems in dairy goats.

Science.gov (United States)

Ait-Saidi, A; Caja, G; Carné, S; Salama, A A K; Ghirardi, J J

2008-04-01

A total of 24 Murciano-Granadina dairy goats in early-midlactation were used to compare the labor time and data collection efficiency of using manual (M) vs. semiautomated (SA) systems for milk recording. Goats were milked once daily in a 2 x 12 parallel platform, with 6 milking units on each side. The M system used visual identification (ID) by large plastic ear tags, on-paper data recording, and data manually uploaded to a computer. The SA system used electronic ID, automatic ID, manual data recording on reader keyboard, and automatic data uploading to computer by Bluetooth connection. Data were collected for groups of 2 x 12 goats for 15 test days of each system during a period of 70 d. Time data were converted to a decimal scale. No difference in milk recording time between M and SA (1.32 +/- 0.03 and 1.34 +/- 0.03 min/goat, respectively) was observed. Time needed for transferring data to the computer was greater for M when compared with SA (0.20 +/- 0.01 and 0.05 +/- 0.01 min/goat). Overall milk recording time was greater in M than in SA (1.52 +/- 0.04 vs. 1.39 +/- 0.04 min/goat), the latter decreasing with operator training. Time for transferring milk recording data to the computer was 4.81 +/- 0.34 and 1.09 +/- 0.10 min for M and SA groups of 24 goats, respectively, but only increased by 0.19 min in SA for each additional 24 goats. No difference in errors of data acquisition was detected between M and SA systems during milk recording (0.6%), but an additional 1.1% error was found in the M system during data uploading. Predicted differences between M and SA increased with the number of goats processed on the test-day. Reduction in labor time cost ranged from euro0.5 to 12.9 (US$0.7 to 17.4) per milk recording, according to number of goats from 24 to 480 goats and accounted for 40% of the electronic ID costs. In conclusion, electronic ID was more efficient for labor costs and resulted in fewer data errors, the benefit being greater with trained operators and

Nuclear imaging system

International Nuclear Information System (INIS)

Barrett, H.H.; Horrigan, F.A.

1975-01-01

This invention relates to a nuclear imaging system for mapping the source of high energy nuclear particles from a living organ which has selectively absorbed a radioactive compound by spatially coding the energy from the source in a Fresnel pattern on a detector and decoding the detector output to prouce an image of the source. The coding is produced by a Fresnel zone plate interposed between the nuclear energy source and the detector whose position is adjustable with respect to the detector to focus the slices of the nuclear source on the detector. By adjusting the zone plate to a plurality of positions, data from a plurality of cross-sectional slices are produced from which a three-dimensional image of the nuclear source may be obtained. (Patent Office Record)

Managing bottlenecks in manual automobile assembly systems using discrete event simulation

Directory of Open Access Journals (Sweden)

Dewa, M.

2013-08-01

Full Text Available Batch model lines are quite handy when the demand for each product is moderate. However, they are characterised by high work-in-progress inventories, lost production time when changing over models, and reduced flexibility when it comes to altering production rates as product demand changes. On the other hand, mixed model lines can offer reduced work-in-progress inventory and increased flexibility. The object of this paper is to illustrate that a manual automobile assembling system can be optimised through managing bottlenecks by ensuring high workstation utilisation, reducing queue lengths before stations and reducing station downtime. A case study from the automobile industry is used for data collection. A model is developed through the use of simulation software. The model is then verified and validated before a detailed bottleneck analysis is conducted. An operational strategy is then proposed for optimal bottleneck management. Although the paper focuses on improving automobile assembly systems in batch mode, the methodology can also be applied in single model manual and automated production lines.

User Manual for the AZ-101 Data Acquisition System (AS-101 DAS)

Energy Technology Data Exchange (ETDEWEB)

BRAYTON, D.D.

2000-02-17

User manual for the TK AZ-101 Waste Retrieval System Data Acquisition System. The purpose of this document is to describe use of the AZ-101 Data Acquisition System (AZ-101 DAS). The AZ-101 DAS is provided to fulfill the requirements for data collection and monitoring as defined in Letters of Instruction (LOI) from Numatec Hanford Corporation (NHC) to Fluor Federal Services (FFS). For a complete description of the system, including design, please refer to the AZ-101 DAS System Description document, RPP-5572.

User Manual for the AZ-101 Data Acquisition System (AS-101 DAS)

International Nuclear Information System (INIS)

BRAYTON, D.D.

2000-01-01

User manual for the TK AZ-101 Waste Retrieval System Data Acquisition System. The purpose of this document is to describe use of the AZ-101 Data Acquisition System (AZ-101 DAS). The AZ-101 DAS is provided to fulfill the requirements for data collection and monitoring as defined in Letters of Instruction (LOI) from Numatec Hanford Corporation (NHC) to Fluor Federal Services (FFS). For a complete description of the system, including design, please refer to the AZ-101 DAS System Description document, RPP-5572

STATE ACID RAIN RESEARCH AND SCREENING SYSTEM - VERSION 1.0 USER'S MANUAL

Science.gov (United States)

The report is a user's manual that describes Version 1.0 of EPA's STate Acid Rain Research and Screening System (STARRSS), developed to assist utility regulatory commissions in reviewing utility acid rain compliance plans. It is a screening tool that is based on scenario analysis...

Future nuclear systems technology

International Nuclear Information System (INIS)

Brooks, H.

1979-01-01

Five directions can be identified for evolution of nuclear systems, possibly a sixth. These are, first, and perhaps most important, toward a means of extending fissile resources through improvement of the efficiency of their use; second, improvements in nuclear safety; third, reduction in the environmental impacts of nuclear electric power generation, particularly water requirements; fourth, improvements in proliferation resistance of the nuclear fuel cycle; and fifth, improvements in economics. And added in a sixth, and somewhat more speculative direction, the use of nuclear power for purposes other than the direct generation of electricity

Protection against malevolent use of vehicles at Nuclear Power Plants. Vehicle barrier system selection guidance

International Nuclear Information System (INIS)

Nebuda, D.T.

1994-08-01

This manual provides a simplified procedure for selecting land vehicle barriers that will stop the design basis vehicle threat adopted by the U.S. Nuclear Regulatory Commission. Proper selection and construction of vehicle barriers should prevent intrusion of the design basis vehicle. In addition, vital safety related equipment should survive a design basis vehicle bomb attack when vehicle barriers are properly selected, sited, and constructed. This manual addresses passive vehicle barriers, active vehicle barriers, and site design features that can be used to reduce vehicle impact velocity

A data communications systems for tamper-protected special nuclear materials (SNM) inventory management

International Nuclear Information System (INIS)

Hurkamp, A.C.

1995-01-01

The Department of Energy (D.O.E.) is responsible for the long term storage and protection of large quantities of Special Nuclear Material (SNM). This material is stored within individual containers located in vaults. Security measures are required to ensure that the SNM remains within the canisters where it is stored and that it is not disturbed in any manner. Conventional security and inventory techniques are manpower intensive and often require exposure to radiation hazards. The Purpose of this D.O.E sponsored project is to develop a cost effective system to monitor Special Nuclear Materials that, when fielded, would result in an extension of manual inventory cycles at a wide variety of SNM storage locations. The system consists of a computer, radio frequency interrogator, and individual miniaturized radio frequency transponders (tags) that are co-located with individual SNM containers. Each tag can perform SNM inventory, tamper alarm, and multiple sensor data transmission to the interrogator under the control of software designed by the user. SNM custodians can customize the system by their choice of packaging, software, and sensors. When implemented in accordance with current department of energy (D.O.E.) Policy on SNM inventory extension, the system has the potential to qualify for maximum extension times thus saving considerable resources through reduction of radiation exposure

Nuclear management in manual small incision cataract surgery by snare technique

Directory of Open Access Journals (Sweden)

Bhattacharya Debasish

2009-01-01

Full Text Available Manual small incision cataract surgery has evolved into a popular method of cataract surgery in India. However, in supra hard cataract, bringing out the whole nucleus through the sclerocorneal flap valve incision becomes difficult. A bigger incision required in such cataracts loses its value action, as the internal incision and corneal valve slips beyond the limbus into sclera. Struggling with the supra hard cataracts through a regular small incision. Phacofracture in the anterior chamber becomes a useful option in these cases. In the snare technique, a stainless steel wire loop when lassoed around the nucleus in the anterior chamber constricts from the equator, easily dividing the hardest of the nuclei into two halves. The wire loop constricts in a controlled way when the second cannula of snare is pulled. The divided halves can easily be brought out by serrated crocodile forceps. This nuclear management can be safely performed through a smaller sclerocorneal flap valve incision where the corneal valve action is retained within the limbus without sutures, and the endothelium or the incision is not disturbed. However, the technique requires space in the anterior chamber to maneuver the wire loop and anterior chamber depth more than 2.5 mm is recommended. Much evidence to this wonderful technique is not available in literature, as its popularity grew through live surgical workshops and small interactive conferences.

Nuclear containment systems and in-service inspection status of Korea nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Jihong, Park; Jaekeun, Hong; Banuk, Park [Korea Institute of Machinery and Materials, Dept. of Authorized Test and Evaluation, Kyungnam (Korea, Republic of)

2007-07-01

20 unit nuclear power plants in Korea have been operated and maintained since the first unit started in commercial service in 1978. Most recently 4 units were under construction and several units were planned to be constructed. by industries. 4 types of nuclear containment systems have been constructed until now: first, metal containments, then pre-stressed concrete containments with grouted tendon systems, followed by pre-stressed concrete containments with un-grouted tendon systems, and Korea standard nuclear containments. All the nuclear containments should be inspected periodically. Therefore for periodic in-service inspection, several appropriate technical requirements should be applied differently depending on the specific nuclear containment types. With the changes of times, nuclear containment systems have undergone a remarkable change, and finally nuclear containment system of Korea standard nuclear power plant was settled down, and as a matter of course it dominates the trend of present and future nuclear containment systems. Overall in-service inspection results of most Korea nuclear containments have not showed any serious evidence of degradation.

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

Regulatory perspective on digital instrumentation and control systems for future advanced nuclear power plants

International Nuclear Information System (INIS)

Chiramal, M.

1993-01-01

This paper deals with the question of using digital technology in instrumentation and control systems for modern nuclear power reactors. The general opinion in the industry and among NRC staff is that such technology provides the opportunity for enhanced safety and reliable reactor operations. The major concern is the safe application of this technology so as to avoid common mode or common cause failures in systems. There are great differences between digital and analog system components. SECY-91-292 identifies some general regulatory concerns with regard to digital systems. There is clearly a lack of adequate regulatory direction on the application of digital equipment at this time, but the issue is being addressed by the industry, outside experts, and NRC staff. NRC staff presents a position on the issue of defense-in-depth and diversity with regard to insuring plant safety. Independent manual controls and readouts must be available to allow safe shutdown and monitoring of the plant in the event of safety system failures

Nuclear Systems Kilopower Overview

Science.gov (United States)

Palac, Don; Gibson, Marc; Mason, Lee; Houts, Michael; McClure, Patrick; Robinson, Ross

2016-01-01

The Nuclear Systems Kilopower Project was initiated by NASAs Space Technology Mission Directorate Game Changing Development Program in fiscal year 2015 to demonstrate subsystem-level technology readiness of small space fission power in a relevant environment (Technology Readiness Level 5) for space science and human exploration power needs. The Nuclear Systems Kilopower Project consists of two elements. The primary element is the Kilopower Prototype Test, also called the Kilopower Reactor Using Stirling Technology(KRUSTY) Test. This element consists of the development and testing of a fission ground technology demonstrator of a 1 kWe fission power system. A 1 kWe system matches requirements for some robotic precursor exploration systems and future potential deep space science missions, and also allows a nuclear ground technology demonstration in existing nuclear test facilities at low cost. The second element, the Mars Kilopower Scalability Study, consists of the analysis and design of a scaled-up version of the 1 kWe reference concept to 10 kWe for Mars surface power projected requirements, and validation of the applicability of the KRUSTY experiment to key technology challenges for a 10 kWe system. If successful, these two elements will lead to initiation of planning for a technology demonstration of a 10 kWe fission power capability for Mars surface outpost power.

21 CFR 892.1310 - Nuclear tomography system.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Nuclear tomography system. 892.1310 Section 892...) MEDICAL DEVICES RADIOLOGY DEVICES Diagnostic Devices § 892.1310 Nuclear tomography system. (a) Identification. A nuclear tomography system is a device intended to detect nuclear radiation in the body and...

Systematic safety evaluation of old nuclear power plants

International Nuclear Information System (INIS)

Dredemis, G.; Fourest, B.

1984-01-01

The French safety authorities have undertaken a systematic evaluation of the safety of old nuclear power plants. Apart from a complete revision of safety documents (safety analysis report, general operating rules, incident and accident procedures, internal emergency plan, quality organisation manual), this examination consisted of analysing the operating experience of systems frequently challenged and a systematic examination of the safety-related systems. This paper is based on an exercise at the Ardennes Nuclear Power Plant which has been in operation for 15 years. This paper also summarizes the main surveys and modifications relating to this power plant. (orig.)

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.

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.

Renewable Electric Plant Information System user interface manual: Paradox 7 Runtime for Windows

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The Renewable Electric Plant Information System (REPiS) is a comprehensive database with detailed information on grid-connected renewable electric plants in the US. The current version, REPiS3 beta, was developed in Paradox for Windows. The user interface (UI) was developed to facilitate easy access to information in the database, without the need to have, or know how to use, Paradox for Windows. The UI is designed to provide quick responses to commonly requested sorts of the database. A quick perusal of this manual will familiarize one with the functions of the UI and will make use of the system easier. There are six parts to this manual: (1) Quick Start: Instructions for Users Familiar with Database Applications; (2) Getting Started: The Installation Process; (3) Choosing the Appropriate Report; (4) Using the User Interface; (5) Troubleshooting; (6) Appendices A and B.

Nuclear Space Power Systems Materials Requirements

International Nuclear Information System (INIS)

Buckman, R.W. Jr.

2004-01-01

High specific energy is required for space nuclear power systems. This generally means high operating temperatures and the only alloy class of materials available for construction of such systems are the refractory metals niobium, tantalum, molybdenum and tungsten. The refractory metals in the past have been the construction materials selected for nuclear space power systems. The objective of this paper will be to review the past history and requirements for space nuclear power systems from the early 1960's through the SP-100 program. Also presented will be the past and present status of refractory metal alloy technology and what will be needed to support the next advanced nuclear space power system. The next generation of advanced nuclear space power systems can benefit from the review of this past experience. Because of a decline in the refractory metal industry in the United States, ready availability of specific refractory metal alloys is limited

Nuclear data information system for nuclear materials

International Nuclear Information System (INIS)

Fujita, Mitsutane; Noda, Tetsuji; Utsumi, Misako

1996-01-01

The conceptual system for nuclear material design is considered and some trials on WWW server with functions of the easily accessible simulation of nuclear reactions are introduced. Moreover, as an example of the simulation on the system using nuclear data, transmutation calculation was made for candidate first wall materials such as 9Cr-2W steel, V-5Cr-5Ti and SiC in SUS316/Li 2 O/H 2 O(SUS), 9Cr-2W/Li 2 O/H 2 O(RAF), V alloy/Li/Be(V), and SiC/Li 2 ZrO 3 /He(SiC) blanket/shield systems based on ITER design model. Neutron spectrum varies with different blanket/shield compositions. The flux of low energy neutrons decreases in order of V< SiC< RAF< SUS blanket/shield systems. Fair amounts of W depletion in 9Cr-2W steel and the increase of Cr content in V-5Cr-5Ti were predicted in SUS or RAF systems. Concentration change in W and Cr is estimated to be suppressed if Li coolant is used in place of water. Helium and hydrogen production are not strongly affected by the different blanket/shield compositions. (author)

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...

Experience with Nuclear Medicine Information System

Directory of Open Access Journals (Sweden)

Bilge Volkan-Salanci

2012-12-01

Full Text Available Objective: Radiology information system (RIS is basically evolved for the need of radiologists and ignores the vital steps needed for a proper work flow of Nuclear Medicine Department. Moreover, CT/MRI oriented classical PACS systems are far from satisfying Nuclear Physicians like storing dynamic data for reprocessing and quantitative analysis of colored images. Our purpose was to develop a workflow based Nuclear Medicine Information System (NMIS that fulfills the needs of Nuclear Medicine Department and its integration to hospital PACS system. Material and Methods: Workflow in NMIS uses HL7 (health level seven and steps include, patient scheduling and retrieving information from HIS (hospital information system, radiopharmacy, acquisition, digital reporting and approval of the reports using Nuclear Medicine specific diagnostic codes. Images and dynamic data from cameras of are sent to and retrieved from PACS system (Corttex© for reprocessing and quantitative analysis. Results: NMIS has additional functions to the RIS such as radiopharmaceutical management program which includes stock recording of both radioactive and non-radioactive substances, calculation of the radiopharmaceutical dose for individual patient according to body weight and maximum permissible activity, and calculation of radioactivity left per unit volume for each radionuclide according their half lives. Patient scheduling and gamma camera patient work list settings were arranged according to specific Nuclear Medicine procedures. Nuclear Medicine images and reports can be retrieved and viewed from HIS. Conclusion: NMIS provides functionality to standard RIS and PACS system according to the needs of Nuclear Medicine. (MIRT 2012;21:97-102

Nuclear propulsion systems engineering

International Nuclear Information System (INIS)

Madsen, W.W.; Neuman, J.E.: Van Haaften, D.H.

1992-01-01

The Nuclear Energy for Rocket Vehicle Application (NERVA) program of the 1960's and early 1970's was dramatically successful, with no major failures during the entire testing program. This success was due in large part to the successful development of a systems engineering process. Systems engineering, properly implemented, involves all aspects of the system design and operation, and leads to optimization of theentire system: cost, schedule, performance, safety, reliability, function, requirements, etc. The process must be incorporated from the very first and continued to project completion. This paper will discuss major aspects of the NERVA systems engineering effort, and consider the implications for current nuclear propulsion efforts

Manual for SFR R and D and Technology Monitoring System Administrator

Energy Technology Data Exchange (ETDEWEB)

Lee, Dong Uk; Lee, Yong Bum; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

2008-05-15

This report is a administrator manual on R and D and technology monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. First of all, enterprise project management solution is introduced and then enterprise resources and data creation method are described. Also it made a description of project web assess design, data management method etc.

Manual for SFR R and D and Technology Monitoring System Administrator

International Nuclear Information System (INIS)

Lee, Dong Uk; Lee, Yong Bum; Won, Byung Chool; Kim, Young In; Hahn, Do Hee

2008-05-01

This report is a administrator manual on R and D and technology monitoring system that is applicable for managing the generation IV sodium-cooled fast reactor development. First of all, enterprise project management solution is introduced and then enterprise resources and data creation method are described. Also it made a description of project web assess design, data management method etc

SOKRATOR manual. Format of the recommended nuclear data library for reactor calculations

International Nuclear Information System (INIS)

Kolesov, V.E.; Nikolaev, M.N.

1977-08-01

The formats represent a generalization and extension of the English formats ''Parker, K., the Aldermaston Nuclear Data Library as at May 1963''. (AWRE 0-70/63, September 1963). An important feature of the formats proposed here is the introduction of a special classification of the information according to the type of representation. This makes the system of nuclear data storage more flexible and allows the capabilities of modern computers to be more fully utilized. This complete format description of the SOKRATOR library (Soviet Library of Evaluated Nuclear Data) is a translation from Russian original and its supplement. The document will help the user of SOKRATOR files to understand the physics definitions and coding conventions for the various types of numerical data

Nuclear information access system

International Nuclear Information System (INIS)

Ham, C. H.; Yang, M. H.; Yoon, S. W.

1998-01-01

The energy supply in the countries, which have abundant energy resources, may not be affected by accepting the assertion of anti-nuclear and environment groups. Anti-nuclear movements in the countries which have little energy resources may cause serious problem in securing energy supply. Especially, it is distinct in Korea because she heavily depends on nuclear energy in electricity supply(nuclear share in total electricity supply is about 40%).The cause of social trouble surrounding nuclear energy is being involved with various circumstances. However, it is very important that we are not aware of the importance of information access and prepared for such a situation from the early stage of nuclear energy's development. In those matter, this paper analyzes the contents of nuclear information access system in France and Japan which have dynamic nuclear development program and presents the direction of the nuclear access regime through comparing Korean status and referring to progresses of the regime

Nuclear reactor with makeup water assist from residual heat removal system

International Nuclear Information System (INIS)

Schulz, T.L.; Corletti, M.M.

1994-01-01

A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit by pumping water from an in-containment refueling water storage tank during staged depressurization of the coolant circuit, the final stage including passive emergency cooling by gravity feed from the refueling water storage tank to the coolant circuit and to flood the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and avoids the final stage of depressurization with its flooding of the containment when such action is not necessary, but does not prevent the final stage when it is necessary. A high pressure makeup water storage tank coupled to the reactor coolant circuit holds makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal system can also be coupled in a loop with the refueling water supply tanks for cooling the tank. (Author)

Advanced nuclear systems. Review study

International Nuclear Information System (INIS)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

1999-04-01

The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

Manual on public health action in radiation emergencies

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

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

Manual on public health action in radiation emergencies

International Nuclear Information System (INIS)

1994-01-01

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

Users Manual for the FEHMN application

International Nuclear Information System (INIS)

Zyvoloski, G.A.; Robinson, B.A.; Dash, Z.V.; Trease, L.L.

1996-01-01

The user's manual documents the use of the Yucca Mountain Site Characterization Projects Finite element heat and mass transfer code (FEHMN) application. The manual covers: Program considerations, data files, input data, output, system interface, and examples

Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

International Nuclear Information System (INIS)

Van Den Durpel, Luc; Roelofs, Ferry; Yacout, Abdellatif

2009-01-01

Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

INES: The International Nuclear Event Scale. User's manual

International Nuclear Information System (INIS)

1990-08-01

The International Nuclear Event Scale (INES) is being introduced for a trial period, the primary purpose being to facilitate communication between the nuclear community, the media and the public on such events. The scale runs from zero, for events with no safety significance, to seven for a major accident. The scale has been circulated to Member States of the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development and it is presently anticipated that the trial period will last until late 1991. Provision has been made for the scale to be refined thereafter in the light of experience. It is designed as an important tool in providing prompt, clear and consistent information on nuclear events wherever and whenever they may occur. 2 figs, 2 tabs

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Proliferation resistance. Vol. 5 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (laid out in this report) (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). This volume of the INPRO manual is based on the results of an INPRO study on proliferation resistance of the DUPIC fuel cycle performed by the Republic of Korea during 2005 and 2006, recommendations from IAEA consultancy meetings, and on a special service agreement with G. Pshakin (Russian Federation). The INPRO Manual starts with an introduction in Chapter 1. In Chapter 2, the necessary information is described to perform an INPRO assessment in the area of proliferation resistance. Explanatory notes on the INPRO basic principles (BP) and user requirements (UR) in the area of proliferation resistance, are reproduced in Chapter 3 to provide context for the assessor; additionally, background of each criterion (CR) and a corresponding procedure is described how to perform an INPRO assessment. The

Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Waste management. Vol. 4 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

International Nuclear Information System (INIS)

2008-11-01

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. The INPRO manual is comprised of an overview volume (No. 1), and eight additional volumes covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (laid out in this report) (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of nuclear reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). This volume of the INPRO manual is based on the results of an INPRO study on proliferation resistance of the DUPIC fuel cycle performed by the Republic of Korea during 2005 and 2006, recommendations from IAEA consultancy meetings, and on a special service agreement with G. Pshakin (Russian Federation). The INPRO Manual starts with an introduction in Chapter 1. In Chapter 2, the necessary information is described to perform an INPRO assessment in the area of proliferation resistance. Explanatory notes on the INPRO basic principles (BP) and user requirements (UR) in the area of proliferation resistance, are reproduced in Chapter 3 to provide context for the assessor; additionally, background of each criterion (CR) and a corresponding procedure is described how to perform an INPRO assessment. The

For establishment on nuclear disaster prevention system

International Nuclear Information System (INIS)

Anon.

2000-01-01

For increasing requirement of peoples for review of nuclear disaster countermeasure at a chance of the JCO critical accident, the Japanese Government newly established the 'Special Measure Act on Nuclear Disaster Countermeasure', which was enacted on July 16, 2000. The nuclear business relatives such as electric power company and so forth established the Business program on nuclear disaster prevention in nuclear business relatives' after their consultation with local communities at their construction, under their co-operation. Simultaneously, the electric power industry field decided to intend to provide some sufficient countermeasures to incidental formation of nuclear accident such as start of the Co-operative agreement on nuclear disaster prevention among the nuclear business relatives' and so forth. Here were described on nuclear safety and disaster prevention, nuclear disaster prevention systems at the electric power industry field, abstract on 'Business program on nuclear disaster prevention in nuclear business relatives', preparation of technical assistance system for nuclear disaster prevention, executive methods and subjects on nuclear disaster prevention at construction areas, recent business on nuclear disaster prevention at the Nuclear Technical Center, and subjects on establishment of nuclear disaster prevention system. (G.K.)

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.

Concept of an immersive assistance system with augmented reality for the support of manual activities in radioactive production environments

International Nuclear Information System (INIS)

Eursch, Andreas A.

2010-01-01

The thesis on an immersive assistance system concept with augmented reality for the support of manual activities in radioactive production environments covers the following topics: analysis of the situation: production and use of radioactive materials, problem analysis of the work in the production facilities, necessity of manual activities, automation, prediction in hot cells; status of research and development; assistance system concept, immersive camera system; augmented reality support in hot cells; economic evaluation and generalization.

The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

International Nuclear Information System (INIS)

Moon, Joo Hyun

2011-01-01

Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

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.

A Study on User-Centered Approach to Design an Augmented Reality Maintenance Support System in Nuclear Power Plant

International Nuclear Information System (INIS)

Koo, Jwa Jin; Seong, Poong Hyun

2007-01-01

In nuclear power plants (NPPs), as the plants become more reliable and complex, their inspection, maintenance and repair become increasingly challenging problems, and this requires many well experienced and well trained maintenance crew. On the other hands, reduction of life cycle costs of the plants is strongly required, and many crews are required to take charge of various kinds of devices, including their unfamiliar ones. Their task must be done under the strong time pressure of rigid maintenance schedule. This may cause human errors even by even the well experienced crews. Maintenance processes are both very important to guarantee quality for safety and often quite cumbersome. In the case of nuclear power plants, such processes usually demand access to documentation such as technical manuals, either in traditional paper form or electronic form. This is especially important where and when the procedures are performed infrequently. These considerations lead to considering Augmented Reality (AR) systems as an alternative to paper-based systems

User's manual of Tokamak Simulation Code

International Nuclear Information System (INIS)

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

1992-12-01

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

The double nuclear system is a new object of nuclear physics studies

International Nuclear Information System (INIS)

Volkov, V.V.

1980-01-01

Deep inelastic collisions of two complex nuclei result in formation of the specific nuclear complex - a double nuclear system which is a new unit of nuclear microworld. In this paper we consider the conditions under which the double nuclear system is formed, its properties, the statistical regularities of its disintegration, and the nuclear shell structure effect on its evolution. The possibility of using deep inelastic transfer reactions to produce nuclear far from the region of β-stability and nuclei with high angular momentum is discussed. (author)

The system of nuclear material control of Kazakhstan

International Nuclear Information System (INIS)

Yeligbayeva, G.Zh.

2001-01-01

Full text: The State system for nuclear material control consists of three integral components. The efficiency of each is to guarantee the non-proliferation regime in Kazakhstan. The components are the following: accounting, export and import control and physical protection of nuclear materials. First, the implementation of the goals of accounting and control bring into force, by the organization of the system for accounting and measurement of nuclear materials to determine present quantity. Organizing the accounting for nuclear material at facilities will ensure the efficiency of accountancy and reporting information. This defines the effectiveness of the state system for the accounting for the Kazakhstan's nuclear materials. Currently, Kazakhstan's nuclear material is fully safeguarded in designated secure locations. Kazakhstan has a nuclear power plant, 4 research reactors and a fuel fabrication plant. The governmental information system for nuclear materials control consist of two level: Governmental level - KAEA collects reports from facilities and prepares the reports for International Atomic Energy Agency, keeping of supporting documents and other necessary information, a data base of export and import, a data base of nuclear material inventory. Facility level - registration and processing information from key measurement points, formation the facility's nuclear materials accounting database. All facilities have computerized systems. Currently, all facilities are safeguarded under IAEA safeguarding standards, through IAEA inspections. Annually, IAEA verifies all nuclear materials at all Kazakhstan nuclear facilities. The government reporting system discloses the existence of all nuclear material and its transfer intended for interaction through the export control system and the nuclear control accounting system. Nuclear material export is regulated by the regulations of the Nuclear Export Control Law. The standard operating procedure is the primary means for

Long-term monitoring of soil gas fluxes with closed chambers using automated and manual systems

Energy Technology Data Exchange (ETDEWEB)

Scott, A.; Crichton, I.; Ball, B.C.

1999-10-01

The authors describe two gas sample collection techniques, each of which is used in conjunction with custom made automated or manually operated closed chambers. The automated system allows automatic collection of gas samples for simultaneous analysis of multiple trace gas efflux from soils, permitting long-term monitoring. Since the manual system is cheaper to produce, it can be replicated more than the automated and used to estimate spatial variability of soil fluxes. The automated chamber covers a soil area of 0.5 m{sup 2} and has a motor driven lid that remains operational throughout a range of weather conditions. Both systems use gas-tight containers of robust metal construction, which give good sample retention, thereby allowing long-term storage and convenience of transport from remote locations. The containers in the automated system are filled by pumping gas from the closed chamber via a multiway rotary valve. Stored samples from both systems are analyzed simultaneously for N{sub 2}O and CO{sub 2} using automated injection into laboratory-based gas chromatographs. The use of both collection systems is illustrated by results from a field experiment on sewage sludge disposal to land where N{sub 2}O fluxes were high. The automated gas sampling system permitted quantification of the marked temporal variability of concurrent N{sub 2}O and CO{sub 2} fluxes and allowed improved estimation of cumulative fluxes. The automated measurement approach yielded higher estimates of cumulative flux because integration of manual point-in-time observations missed a number of transient high-flux events.

HANSF 1.3 user's manual; TOPICAL

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

Real-time reactor coolant system pressure/temperature limit system

International Nuclear Information System (INIS)

Newton, D.G.; Schemmel, R.R.; Van Scooter, W.E. Jr.

1991-01-01

This patent describes an system, used in controlling the operating of a nuclear reactor coolant system, which automatically calculates and displays allowable reactor coolant system pressure/temperature limits within the nuclear reactor coolant system based upon real-time inputs. It comprises: means for producing signals representative of real-time operating parameters of the nuclear reactor cooling system; means for developing pressure and temperature limits relating the real-time operating parameters of the nuclear reactor coolant system, for normal and emergency operation thereof; means for processing the signals representative of real-time operating parameters of the nuclear reactor coolant system to perform calculations of a best estimate of signals, check manual inputs against permissible valves and test data acquisition hardware for validity and over/under range; and means for comparing the representative signals with limits for the real-time operating parameters to produce a signal for a real-time display of the pressure and temperature limits and of the real-time operating parameters use an operator in controlling the operation of the nuclear reactor coolant system

Minimizing human error in radiopharmaceutical preparation and administration via a bar code-enhanced nuclear pharmacy management system.

Science.gov (United States)

Hakala, John L; Hung, Joseph C; Mosman, Elton A

2012-09-01

The objective of this project was to ensure correct radiopharmaceutical administration through the use of a bar code system that links patient and drug profiles with on-site information management systems. This new combined system would minimize the amount of manual human manipulation, which has proven to be a primary source of error. The most common reason for dosing errors is improper patient identification when a dose is obtained from the nuclear pharmacy or when a dose is administered. A standardized electronic transfer of information from radiopharmaceutical preparation to injection will further reduce the risk of misadministration. Value stream maps showing the flow of the patient dose information, as well as potential points of human error, were developed. Next, a future-state map was created that included proposed corrections for the most common critical sites of error. Transitioning the current process to the future state will require solutions that address these sites. To optimize the future-state process, a bar code system that links the on-site radiology management system with the nuclear pharmacy management system was proposed. A bar-coded wristband connects the patient directly to the electronic information systems. The bar code-enhanced process linking the patient dose with the electronic information reduces the number of crucial points for human error and provides a framework to ensure that the prepared dose reaches the correct patient. Although the proposed flowchart is designed for a site with an in-house central nuclear pharmacy, much of the framework could be applied by nuclear medicine facilities using unit doses. An electronic connection between information management systems to allow the tracking of a radiopharmaceutical from preparation to administration can be a useful tool in preventing the mistakes that are an unfortunate reality for any facility.

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

Development of a personal computer-based state system of accounting for/and control of nuclear materials

International Nuclear Information System (INIS)

Markov, A.

1986-09-01

An IBM-PC and compatible based state system of accounting for and control of nuclear materials under international safeguards (state-level SSAC) is presented. The system works under DOS version 2.0 and above. It consists of a single-module Safeguards Report Editor which is a multi-function menu-driven code written in BASIC. The Editor may be run both in interactive mode and as an EXEC module. The output represents four types of material accounting reports on diskette, suitable for direct input into the IAEA Safeguards Information System (ISIS). In the first part of the report presented, a general description of the system is given. This is complemented with a detailed User Manual where a Guide to Applications, an Operator's Guide, a Programmer's Guide and Listings are included. The system is now available. It is maintained by the Bulgarian Committee on the Uses of Atomic Energy for Peaceful Purposes

A user's manual for managing database system of tensile property

International Nuclear Information System (INIS)

Ryu, Woo Seok; Park, S. J.; Kim, D. H.; Jun, I.

2003-06-01

This manual is written for the management and maintenance of the tensile database system for managing the tensile property test data. The data base constructed the data produced from tensile property test can increase the application of test results. Also, we can get easily the basic data from database when we prepare the new experiment and can produce better result by compare the previous data. To develop the database we must analyze and design carefully application and after that, we can offer the best quality to customers various requirements. The tensile database system was developed by internet method using Java, PL/SQL, JSP(Java Server Pages) tool

The Northern States Power Company welding manual advisor

International Nuclear Information System (INIS)

Lu, Yi; Wood, R.M.

1993-01-01

The Welding Manual Advisor (WMA) is an object oriented expert system designed to assist Northern States Power (NSP) personnel in implementing the company's Welding Manual. The expert system captures the knowledge of welding experts, addresses important issues in welding activities and automates the use of the Welding Manual. It is estimated that use of the WMA will save $81,000 over the next six years at NSP, because of the reduction of labor and errors in the use of the Welding Manual, and facilitation of training of NSP personnel. The important features of the WMA include the accuracy and consistency in determining welding procedure and requirements, update capability, user friendly interface, on-line help function, back-up capability, and well-documented manuals

Preinspection of nuclear power plant systems

International Nuclear Information System (INIS)

1975-01-01

The general plans of the systems affecting the safety of the nuclear power plants are accepted by the Institute of Radiation Protection (IRP) on the basis of the preinspection of the systems. This is the prerequisite of the preinspection of the structures and components belonging to these systems. Exceptionally, when separately agreed, the IRP may perform the preinspection of a separate structure or component, although the preinspection documentation of the whole system, e.g. the nuclear heat generating system, has not been accepted. This guide applies to the nuclear power plant systems that have been defined to be preinspected in the classification document accepted by the IRP

Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

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

2014-06-01

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

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

Nuclear reactor with makeup water assist from residual heat removal system

Science.gov (United States)

Corletti, Michael M.; Schulz, Terry L.

1993-01-01

A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path.

Nuclear reactor with makeup water assist from residual heat removal system

International Nuclear Information System (INIS)

Corletti, M.M.; Schulz, T.L.

1993-01-01

A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path. 2 figures

Nuclear reactor with makeup water assist from residual heat removal system

Science.gov (United States)

Corletti, M.M.; Schulz, T.L.

1993-12-07

A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path. 2 figures.

78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

Science.gov (United States)

2013-06-27

... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

Hydrogen Mixing Studies (HMS), user's manual

International Nuclear Information System (INIS)

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

1994-12-01

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

Quality Assurance in the Vandellos 1 Nuclear Power Plant Dismantling and Decommissioning Project

International Nuclear Information System (INIS)

Soto Lanuza, A.

2000-01-01

General description of the Quality Assurance System established and implemented for the efficient development of the current activities specified in the Dismantling and Decommissioning Plan for Vandellos I Nuclear Power Plant. Aspects related to the Quality organization, scope and applicability on the established Quality Assurance Manual, availability of requirements and recommendations on quality as well as actions to be taken for the correct verification on the quality and practical application of the Manual should be described. (Author)

Application of point system in the project control of Ling'ao Nuclear Power Station

International Nuclear Information System (INIS)

Xie ahai

2005-01-01

Schedule control and cost control are very complicated issues even we set up the detail schedules and engineering measurements requirements for erection of a nuclear power project. In order to solve these problems, a Point System is used in Ling Ao (LA) Nuclear Power Project. This paper introduces the method. The Point System is a measurement system of workload. The measurement unit of any erection works is a Point only. A Point of workload is defined as the equivalent measurement quantities, which could be completed by a relevant skill worker within an hour. A set of procedure manuals for different installations has been set up. The calculation models of equipment installation, piping, cabling are addressed for example in the paper. The application of the Point System in the schedule control is shown in the paper. The following issues are highlighted: to define the duration of a piping activity in the Project Level 2 Schedule, to draught the curves of Point Schedules for different erection fields, to analyze the productive efficiency, to define erection quota of each month for different erection teams, to follow up the erection progress on site. The application of the Point System in the payment of erection contract is outlined. The calculation formula of a monthly payment is given. The advantage of the payment calculation method is discussed, for example, more accurate, very easy and clearly to check the measurement quantities completed on site, to control lump-sum cost. (authors)

Nuclear power plants documentation system

International Nuclear Information System (INIS)

Schwartz, E.L.

1991-01-01

Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

Quality Assurance in the Vandellos 1 Nuclear Power Plant Dismantling and Decommissioning Project; La garantia de calidad en el proyecto de desmantelamiento y clausura de la Central Nuclear de Vandellos I

Energy Technology Data Exchange (ETDEWEB)

Soto Lanuza, A

2000-07-01

General description of the Quality Assurance System established and implemented for the efficient development of the current activities specified in the Dismantling and Decommissioning Plan for Vandellos I Nuclear Power Plant. Aspects related to the Quality organization, scope and applicability on the established Quality Assurance Manual, availability of requirements and recommendations on quality as well as actions to be taken for the correct verification on the quality and practical application of the Manual should be described. (Author)

Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE) Version 5.0. Fault tree, event tree, and piping ampersand instrumentation diagram (FEP) editors reference manual: Volume 7

International Nuclear Information System (INIS)

McKay, M.K.; Skinner, N.L.; Wood, S.T.

1994-07-01

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The Fault Tree, Event Tree, and Piping and Instrumentation Diagram (FEP) editors allow the user to graphically build and edit fault trees, and event trees, and piping and instrumentation diagrams (P and IDs). The software is designed to enable the independent use of the graphical-based editors found in the Integrated Reliability and Risk Assessment System (IRRAS). FEP is comprised of three separate editors (Fault Tree, Event Tree, and Piping and Instrumentation Diagram) and a utility module. This reference manual provides a screen-by-screen guide of the entire FEP System

Computer-based system for inspection of water chemistry regimes in WWER-type nuclear power plants

International Nuclear Information System (INIS)

Burcl, R.; Novak, M.; Malenka, P.

1993-01-01

The unsatisfactory situation in water chemistry testing at nuclear power plants with WWER type reactors is described. The testing primarily relies on laboratory analyses of manually taken samples. About 40 samples from one unit are tested per shift, which comprises approximately 250 determinations of various parameters. The time between two determinations is no shorter than 4 to 6 hours, thus rapid parameter changes between two determinations fail to be monitored. A novel system of automated chemistry monitoring is outlined, feasible for WWER type reactors. The system comprises 10 sets of sensors for monitoring all the relevant chemistry parameters of both the primary and secondary coolant circuits. Each sensor set has its own autonomous computer which secures its function even in case of loss of the chemical information network. The entire system is controlled by a master computer which also collects the results and provides contact with the power plant's information system. (Z.S.). 1 fig

Nuclear energy an introduction to the concepts, systems, and applications of nuclear processes

CERN Document Server

Murray, Raymond L; Murphy, Arthur T; Rosenthal, Daniel I

1987-01-01

Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes introduces the reader to the concepts, systems, and applications of nuclear processes. It provides a factual description of basic nuclear phenomena, as well as devices and processes that involve nuclear reactions. The problems and opportunities that are inherent in a nuclear age are also highlighted.Comprised of 27 chapters, this book begins with an overview of fundamental facts and principles, with emphasis on energy and states of matter, atoms and nuclei, and nuclear reactions. Radioactivi

Method of controlling ECCS system in reactors

International Nuclear Information System (INIS)

Oohashi, Hideaki; Ikehara, Morihiko.

1982-01-01

Purpose: To eliminate the risk of misoperation and thereby improve the reliability of ECCS system upon accident. Method: ECCS system for nuclear reactor is automatically started by either of signals from a water level detector in a pressure vessel or from a pressure detector in a reactor container. Further, the ECCS system is started or stopped by the manual operation irrespective of the signals, and the signals from the pressure detector are isolated from the ECCS-starting signal by the contacts which actuate interlocked with the stopping operation of the manual operation switch. Then, after stopping the ECCS system by the manual operation, the ECCS system is started by the signals from the water level detector irrespective of the signals from the pressure detector. (Seki, T.)

Human-robot collaborative navigation for autonomous maintenance management of nuclear installation

International Nuclear Information System (INIS)

Nugroho, Djoko Hari

2002-01-01

Development of human and robot collaborative navigation for autonomous maintenance management of nuclear installation has been conducted. The human-robot collaborative system is performed using a switching command between autonomous navigation and manual navigation that incorporate a human intervention. The autonomous navigation path is conducted using a novel algorithm of MLG method based on Lozano-Perez s visibility graph. The MLG optimizes the shortest distance and safe constraints. While the manual navigation is performed using manual robot tele operation tools. Experiment in the MLG autonomous navigation system is conducted for six times with 3-D starting point and destination point coordinate variation. The experiment shows a good performance of autonomous robot maneuver to avoid collision with obstacle. The switching navigation is well interpreted using open or close command to RS-232C constructed using LabVIEW

Establishment of nuclear data evaluation system (I)

International Nuclear Information System (INIS)

Chang, Jong Hwa; Lee, Chang Kun; Kim, Jeong Do; Kim, Young Sik; Kim, Young Jin; Kim, Hyung Guk; Kil, Chung Sup; Kim, Kang Suk

1994-08-01

Nuclear data is fundamental data for development of new type of nuclear, upgrade of nuclear fuel, treatment of radwaste, research on fusion reactor, radioisotope usage, and nuclear medical therapy. Nuclear data is produced with experiments. However rack of experimental data for thousands of nuclides and various reaction types makes it essential to do statistical evaluation and theoretical interpolation. This study is intended to join international cooperation after establishing domestic basis for nuclear data evaluation work. This project is the first year of five year plan to do followings: 1) Establishment of database system to collect experimental data, 2) Setup of computer assistance system for evaluation work, 3) Verification of established system by test evaluation of selected nuclide reaction. The system has a collection of mass data of nuclides, computer codes for test evaluation of total cross section of 0-16 and collection of EXFOR format data for 0-16. This system will be improved continuously on next years. (Author)

Integrated nuclear and radiation protection systems

International Nuclear Information System (INIS)

Oprea, I.; Oprea, M.; Stoica, V.; Cerga, V.; Pirvu, V.; Badea, E.

1993-01-01

A multifunctional radiation monitoring equipment, flexible and capable to meet virtually environmental radiation monitoring, activity measurement and computational requirements, for nuclear laboratories has been designed. It can be used as a radiation protection system, for radionuclide measurement in isotope laboratories, nuclear technology, health physics and nuclear medicine, nuclear power stations and nuclear industry. The equipment is able to measure, transmit and record gamma dose rate and isotope activities. Other parameters and functions are optionally available, such as: self-contained alarm level, system self-test, dose integrator, syringe volume calculation for a given dose corrected for decay, calibration factor, 99 Mo assays performing and background subtraction

Towards Automatic Capturing of Manual Data Processing Provenance

NARCIS (Netherlands)

Wombacher, Andreas; Huq, M.R.

2011-01-01

Often data processing is not implemented by a work ow system or an integration application but is performed manually by humans along the lines of a more or less specified procedure. Collecting provenance information during manual data processing can not be automated. Further, manual collection of

Study on interface between nuclear material accounting system and national nuclear forensic library

International Nuclear Information System (INIS)