WorldWideScience

Sample records for facility design information

  1. Design of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

    2001-05-01

    We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system.

  2. Design of safeguards information treatment system at the facility level

    International Nuclear Information System (INIS)

    Song, Dae Yong; Lee, Byung Doo; Kwack, Eun Ho; Choi, Young Myong

    2001-05-01

    We are developing Safeguards Information Treatment System at the facility level(SITS) to manage synthetically safeguards information and to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, we described the contents of the detailed design of SITS such as database, I/O layout and program. In the present, we are implementing the SITS based on the contents of the design of SITS, and then we plan to provide the system for the facilities after we finish implementing and testing the system

  3. Report Of The Workshop On Nuclear Facility Design Information Examination And Verification For Safeguards

    International Nuclear Information System (INIS)

    Metcalf, Richard; Bean, Robert

    2009-01-01

    The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA's Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility's general character, purpose, capacity, and location; (2) Description of the facility's layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future

  4. REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS

    Energy Technology Data Exchange (ETDEWEB)

    Richard Metcalf; Robert Bean

    2009-10-01

    Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards

  5. Design information questionnaire for a model mixed oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Glancy, J.E.

    1976-05-01

    The model fuel plant is based on the proposed Westinghouse Anderson, S.C., plant and is typical of plants that will be constructed and operated in 1980 to 1990. A number of plant systems and procedures are uncertain, and in these cases judgment was used in describing relevant parameters in order to provide a complete model on which to design an inspection plan. The model plant does not, therefore, strictly represent any planned facility nor does it strictly represent the ideas of Westinghouse on plant design and material accountability. This report is divided into two sections. The first section is the IAEA Design Information Questionnaire form that contains an outline of all information requested. The second section is a complete listing of design information

  6. Design information verification

    International Nuclear Information System (INIS)

    Johnson, Shirley

    2001-01-01

    The paper provides the bases to complete a Design Information Questionnaire (DIQ) for a research reactor. The IAEA requirements for provision of design information for nuclear facility is described. The role of the provided information for the development of the safeguards approach and for planning of the IAEA's general inspection program for a specific facility is emphasized. Content and preparation of the IAEA DIQ by the State is presented

  7. Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

    International Nuclear Information System (INIS)

    1995-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses

  8. Structure and function design for nuclear facilities decommissioning information database

    International Nuclear Information System (INIS)

    Liu Yongkuo; Song Yi; Wu Xiaotian; Liu Zhen

    2014-01-01

    The decommissioning of nuclear facilities is a radioactive and high-risk project which has to consider the effect of radiation and nuclear waste disposal, so the information system of nuclear facilities decommissioning project must be established to ensure the safety of the project. In this study, by collecting the decommissioning activity data, the decommissioning database was established, and based on the database, the decommissioning information database (DID) was developed. The DID can perform some basic operations, such as input, delete, modification and query of the decommissioning information data, and in accordance with processing characteristics of various types of information data, it can also perform information management with different function models. On this basis, analysis of the different information data will be done. The system is helpful for enhancing the management capability of the decommissioning process and optimizing the arrangements of the project, it also can reduce radiation dose of the workers, so the system is quite necessary for safe decommissioning of nuclear facilities. (authors)

  9. Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

  10. Hanford Site waste tank farm facilities design reconstitution program plan

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1994-01-01

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

  11. Design Standards for School Art Facilities

    Science.gov (United States)

    National Art Education Association, 2015

    2015-01-01

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

  12. Implementing risk-informed life-cycle design

    International Nuclear Information System (INIS)

    Hill, Ralph S.

    2009-01-01

    This paper describes a design process based on risk-informed probabilistic design methodologies that cover a facility's life-cycle from start of conceptual design through decontamination and decommissioning. The concept embodies use of probabilistic risk assessments to establish target reliabilities for facility systems and components. The target reliabilities are used for system based code margin exchange and performance simulation analyses to optimize design over all phases (design, construction, operation and decommissioning) of a facility's life-cycle. System based code margin exchange reduces excessive level of construction margins for passive components to appropriate levels resulting in a more flexible structure of codes and standards that improves facility reliability and cost. System and subsystem simulation analyses determine the optimum combination of initial system and component construction reliability, maintenance frequency, and inspection frequency for both active and passive components. The paper includes a description of these risk-informed life-cycle design processes, a summary of work being done, and a discussion of additional work needed to implement the process.

  13. Landfill gas management facilities design guidelines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-03-15

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

  14. Facility design, construction, and operation

    International Nuclear Information System (INIS)

    1995-04-01

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

  15. Information base for waste repository design. Volume 5. Decommissioning of underground facilities. Technical report

    International Nuclear Information System (INIS)

    Giuffre, M.S.; Plum, R.L.; Koplik, C.M.; Talbot, R.

    1979-03-01

    This report is Volume 5 of a seven volume document on nuclear waste repository design issues. This report discusses the requirements for decommissioning a deep underground facility for the disposal of radioactive waste. The techniques for sealing the mined excavations are presented and an information base on potential backfill materials is provided. Possible requirements for monitoring the site are discussed. The performance requirements for backfill materials are outlined. The advantages and disadvantages of each sealing method are stated

  16. Development of cloud-operating platform for detention facility design

    Science.gov (United States)

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

    2017-04-01

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

  17. Risk informed life cycle plant design

    International Nuclear Information System (INIS)

    Hill, Ralph S. III; Nutt, Mark M.

    2003-01-01

    Many facility life cycle activities including design, construction, fabrication, inspection and maintenance are evolving from a deterministic to a risk-informed basis. The risk informed approach uses probabilistic methods to evaluate the contribution of individual system components to total system performance. Total system performance considers both safety and cost considerations including system failure, reliability, and availability. By necessity, a risk-informed approach considers both the component's life cycle and the life cycle of the system. In the nuclear industry, risk-informed approaches, namely probabilistic risk assessment (PRA) or probabilistic safety assessment (PSA), have become a standard tool used to evaluate the safety of nuclear power plants. Recent studies pertaining to advanced reactor development have indicated that these new power plants must provide enhanced safety over existing nuclear facilities and be cost-competitive with other energy sources. Risk-informed approaches, beyond traditional PRA, offer the opportunity to optimize design while considering the total life cycle of the plant in order to realize these goals. The use of risk-informed design approaches in the nuclear industry is only beginning, with recent promulgation of risk-informed regulations and proposals for risk-informed codes. This paper briefly summarizes the current state of affairs regarding the use of risk-informed approaches in design. Key points to fully realize the benefit of applying a risk-informed approach to nuclear power plant design are then presented. These points are equally applicable to non-nuclear facilities where optimization for cost competitiveness and/or safety is desired. (author)

  18. Integrated safeguards and facility design and operations

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  19. Seismic design considerations for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1985-06-18

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

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  2. Implementing risk-informed life-cycle design

    International Nuclear Information System (INIS)

    Hill, Ralph S. III

    2007-01-01

    This paper describes a design process based on risk-informed probabilistic methodologies that cover a facility's life-cycle from start of conceptual design through decontamination and decommissioning. The concept uses probabilistic risk assessments to identify target reliabilities for facility systems and components. Target reliabilities are used in system and subsystem simulation analyses to determine the optimum combination of initial system and component construction reliability, maintenance frequency, and inspection frequency for both active and passive components. The target reliabilities are also used for system based code margin exchange to reduce excessive level of margins to appropriate levels resulting in a more flexible structure of codes and standards that improves facility reliability and cost. The paper includes a description of a risk informed life-cycle design process, a summary of work being done, and a discussion of work needed to implement the process. (author)

  3. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

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

  4. DESIGN INFORMATION VERIFICATION FOR NUCLEAR SAFEGUARDS

    Energy Technology Data Exchange (ETDEWEB)

    Robert S. Bean; Richard R. M. Metcalf; Phillip C. Durst

    2009-07-01

    A critical aspect of international safeguards activities performed by the International Atomic Energy Agency (IAEA) is the verification that facility design and construction (including upgrades and modifications) do not create opportunities for nuclear proliferation. These Design Information Verification activities require that IAEA inspectors compare current and past information about the facility to verify the operator’s declaration of proper use. The actual practice of DIV presents challenges to the inspectors due to the large amount of data generated, concerns about sensitive or proprietary data, the overall complexity of the facility, and the effort required to extract just the safeguards relevant information. Planned and anticipated facilities will (especially in the case of reprocessing plants) be ever larger and increasingly complex, thus exacerbating the challenges. This paper reports the results of a workshop held at the Idaho National Laboratory in March 2009, which considered technologies and methods to address these challenges. The use of 3D Laser Range Finding, Outdoor Visualization System, Gamma-LIDAR, and virtual facility modeling, as well as methods to handle the facility data issues (quantity, sensitivity, and accessibility and portability for the inspector) were presented. The workshop attendees drew conclusions about the use of these techniques with respect to successfully employing them in an operating environment, using a Fuel Conditioning Facility walk-through as a baseline for discussion.

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  6. Ultraviolet Free Electron Laser Facility preliminary design report

    Energy Technology Data Exchange (ETDEWEB)

    Ben-Zvi, I. (ed.)

    1993-02-01

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

  7. Ultraviolet Free Electron Laser Facility preliminary design report

    International Nuclear Information System (INIS)

    Ben-Zvi, I.

    1993-02-01

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

  8. Facility design: introduction

    International Nuclear Information System (INIS)

    Unger, W.E.

    1980-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

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

  10. Design and construction of the Fuels and Materials Examination Facility

    International Nuclear Information System (INIS)

    Burgess, C.A.

    1979-01-01

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

  11. Information on the Advanced Plant Experiment (APEX) Test Facility

    International Nuclear Information System (INIS)

    Smith, Curtis Lee

    2015-01-01

    The purpose of this report provides information related to the design of the Oregon State University Advanced Plant Experiment (APEX) test facility. Information provided in this report have been pulled from the following information sources: Reference 1: R. Nourgaliev and et.al, 'Summary Report on NGSAC (Next-Generation Safety Analysis Code) Development and Testing,' Idaho National Laboratory, 2011. Note that this is report has not been released as an external report. Reference 2: O. Stevens, Characterization of the Advanced Plant Experiment (APEX) Passive Residual Heat Removal System Heat Exchanger, Master Thesis, June 1996. Reference 3: J. Reyes, Jr., Q. Wu, and J. King, Jr., Scaling Assessment for the Design of the OSU APEX-1000 Test Facility, OSU-APEX-03001 (Rev. 0), May 2003. Reference 4: J. Reyes et al, Final Report of the NRC AP600 Research Conducted at Oregon State University, NUREG/CR-6641, July 1999. Reference 5: K. Welter et al, APEX-1000 Confirmatory Testing to Support AP1000 Design Certification (non-proprietary), NUREG-1826, August 2005.

  12. Design of an error-free nondestructive plutonium assay facility

    International Nuclear Information System (INIS)

    Moore, C.B.; Steward, W.E.

    1987-01-01

    An automated, at-line nondestructive assay (NDA) laboratory is installed in facilities recently constructed at the Savannah River Plant. The laboratory will enhance nuclear materials accounting in new plutonium scrap and waste recovery facilities. The advantages of at-line NDA operations will not be realized if results are clouded by errors in analytical procedures, sample identification, record keeping, or techniques for extracting samples from process streams. Minimization of such errors has been a primary design objective for the new facility. Concepts for achieving that objective include mechanizing the administrative tasks of scheduling activities in the laboratory, identifying samples, recording and storing assay data, and transmitting results information to process control and materials accounting functions. These concepts have been implemented in an analytical computer system that is programmed to avoid the obvious sources of error encountered in laboratory operations. The laboratory computer exchanges information with process control and materials accounting computers, transmitting results information and obtaining process data and accounting information as required to guide process operations and maintain current records of materials flow through the new facility

  13. Orientation to pollution prevention for facility design

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    2001-11-01

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

  15. IsoDAR@KamLAND: A Conceptual Design Report for the Technical Facility

    CERN Document Server

    Abs, M; Alonso, J R; Axani, S; Barletta, W A; Barlow, R; Bartoszek, L; Bungau, A; Calabretta, L; Calanna, A; Campo, D; Castro, G; Celona, L; Collin, G H; Conrad, J M; Gammino, S; Johnson, R; Karagiorgi, G; Kayser, S; Kleeven, W; Kolano, A; Labrecque, F; Loinaz, W A; Minervini, J; Moulai, M H; Okuno, H; Owen, H; Papavassiliou, V; Shaevitz, M H; Shimizu, I; Shokair, T M; Sorensen, K F; Spitz, J; Toups, M; Vagins, M; Van Bibber, K; Wascko, M O; Winklehner, D; Winslow, L A; Yang, J J

    2015-01-01

    This conceptual design report describes the technical facility for the IsoDAR electron-antineutrino source at KamLAND. The IsoDAR source will allow an impressive program of neutrino oscillation and electroweak physics to be performed at KamLAND. This report provides information on the physics case, the conceptual design for the subsystems, alternative designs considered, specifics of installation at KamLAND, and identified needs for future development. We discuss the risks we have identified and our approach to mitigating those risks with this design. A substantial portion of the conceptual design is based on three years of experimental efforts and on industry experience. This report also includes information on the conventional facilities.

  16. The Mixed Waste Management Facility. Preliminary design review

    International Nuclear Information System (INIS)

    1995-01-01

    This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones

  17. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  18. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    International Nuclear Information System (INIS)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  19. Translating DWPF design criteria into an engineered facility design

    International Nuclear Information System (INIS)

    Kemp, J.B.

    1986-01-01

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

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

    International Nuclear Information System (INIS)

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

    2001-02-01

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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

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

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1980-01-01

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

  3. Development of safeguards information treatment system at facility level in Korea

    International Nuclear Information System (INIS)

    So, D.S.; Lee, B.D.; Song, D.Y.

    2001-01-01

    Safeguards Information Treatment System (SITS) at Facility level was developed to implement efficiently the obligations under IAEA comprehensive Safeguards Agreement, bilateral nuclear cooperation Agreements with other countries and domestic law, and to manage efficiently the information related to safeguards implementation at facility level in Korea. Nuclear facilities in Korea are categorized into 8 types based on its accounting characteristics as follows: (1) Item counting facility or bulk handling facility; (2) Batch follow-up facility or not; (3) MUF (Material Unaccounted For) occurrence or not; (4) Nuclear production facility or not; (5) Operation status of facility; (6) Information management of nuclear material transfer status between KMPs or not; (7) Indication of inventory KMP on the inventory change of nuclear material is required or not. Hardware and Software for SITS can be loaded on a personal computer under operation system of Window 2000 or Window NT. MS SQL server 7 and MS Internet Information Server were adopted for database management system and Web server, respectively. Network environment of SITS was designed to include nuclear research institute, nuclear power plants of PWR and CANDU, nuclear fuel fabrication facilities and other facilities. SITS can be operated standalone or under the client-server system if intranet exists. More detailed contents of SITS are described elsewhere. Each module of SITS will be tested during incorporation of existing data into SITS and SITS will be distributed to nuclear facilities in Korea

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

    International Nuclear Information System (INIS)

    Smith, K.E.

    1994-01-01

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

  5. Design of the disposal facility 2012

    International Nuclear Information System (INIS)

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

    2013-11-01

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

  6. Designing Facilities for Collaborative Operations

    Science.gov (United States)

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

    2003-01-01

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

  7. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

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

  8. Design of the PRIDE Facility

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  9. 40 CFR 60.32c - Designated facilities.

    Science.gov (United States)

    2010-07-01

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

  10. Information note about the protection of nuclear facilities against aircraft crashes

    International Nuclear Information System (INIS)

    2001-01-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

  11. 40 CFR 60.32b - Designated facilities.

    Science.gov (United States)

    2010-07-01

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

  12. Accelerator-driven subcritical facility:Conceptual design development

    Science.gov (United States)

    Gohar, Yousry; Bolshinsky, Igor; Naberezhnev, Dmitry; Duo, Jose; Belch, Henry; Bailey, James

    2006-06-01

    A conceptual design development of an accelerator-driven subcritical facility has been carried out in the preparation of a joint activity with Kharkov Institute of Physics and Technology of Ukraine. The main functions of the facility are the medical isotope production and the support of the Ukraine nuclear industry. An electron accelerator is considered to drive the subcritical assembly. The neutron source intensity and spectrum have been studied. The energy deposition, spatial neutron generation, neutron utilization fraction, and target dimensions have been quantified to define the main target performance parameters, and to select the target material and beam parameters. Different target conceptual designs have been developed based the engineering requirements including heat transfer, thermal hydraulics, structure, and material issues. The subcritical assembly is designed to obtain the highest possible neutron flux level with a Keff of 0.98. Different fuel materials, uranium enrichments, and reflector materials are considered in the design process. The possibility of using low enrichment uranium without penalizing the facility performance is carefully evaluated. The mechanical design of the facility has been developed to maximize its utility and minimize the time for replacing the target and the fuel assemblies. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements, upgrades, and new missions. In addition, it has large design margins to accommodate different operating conditions and parameters. In this paper, the conceptual design and the design analyses of the facility will be presented.

  13. Design of spent fuel storage facilities

    International Nuclear Information System (INIS)

    1994-01-01

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

  14. Design of the PISCES-Upgrade facility

    International Nuclear Information System (INIS)

    Waganer, L.M.; Doerner, R.

    1994-01-01

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

  15. National Ignition Facility system design requirements conventional facilities SDR001

    International Nuclear Information System (INIS)

    Hands, J.

    1996-01-01

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

  16. The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

    International Nuclear Information System (INIS)

    1994-12-01

    The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

  17. 40 CFR 60.30d - Designated facilities.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Designated facilities. 60.30d Section... Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

  18. The Practice of Sustainable Facilities Management: Design Sentiments and the Knowledge Chasm

    Directory of Open Access Journals (Sweden)

    Abbas Elmualim

    2009-12-01

    Full Text Available The construction industry with its nature of project delivery is very fragmented in terms of the various processes that encompass design, construction, facilities and assets management. Facilities managers are in the forefront of delivering sustainable assets management and hence further the venture for mitigation and adaptation to climate change. A questionnaire survey was conducted to establish perceptions, level of commitment and knowledge chasm in practising sustainable facilities management (FM. This has significant implications for sustainable design management, especially in a fragmented industry. The majority of questionnaire respondents indicated the importance of sustainability for their organization. Many of them stated that they reported on sustainability as part of their organization annual reporting with energy efficiency, recycling and waste reduction as the main concern for them. The overwhelming barrier for implementing sound, sustainable FM is the lack of consensual understanding and focus of individuals and organizations about sustainability. There is a knowledge chasm regarding practical information on delivering sustainable FM. Sustainability information asymmetry in design, construction and FM processes render any sustainable design as a sentiment and mere design aspiration. Skills and training provision, traditionally offered separately to designers and facilities managers, needs to be re-evaluated. Sustainability education and training should be developed to provide effective structures and processes to apply sustainability throughout the construction and FM industries coherently and as common practice. Published in the Journal AEDM - Volume 5, Numbers 1-2, 2009 , pp. 91-102(12

  19. Review of the Tritium Extraction Facility design

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  20. Review of the Tritium Extraction Facility Design

    International Nuclear Information System (INIS)

    Ronald W. Barton; Farid Bamdad; Joel Blackman

    2000-01-01

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

  1. Facility Safeguardability Analysis In Support of Safeguards-by-Design

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  2. Conceptual design study advanced concepts test (ACT) facility

    Energy Technology Data Exchange (ETDEWEB)

    Zaloudek, F.R.

    1978-09-01

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

  3. Nursing Information Flow in Long-Term Care Facilities.

    Science.gov (United States)

    Wei, Quan; Courtney, Karen L

    2018-04-01

     Long-term care (LTC), residential care requiring 24-hour nursing services, plays an important role in the health care service delivery system. The purpose of this study was to identify the needed clinical information and information flow to support LTC Registered Nurses (RNs) in care collaboration and clinical decision making.  This descriptive qualitative study combines direct observations and semistructured interviews, conducted at Alberta's LTC facilities between May 2014 and August 2015. The constant comparative method (CCM) of joint coding was used for data analysis.  Nine RNs from six LTC facilities participated in the study. The RN practice environment includes two essential RN information management aspects: information resources and information spaces. Ten commonly used information resources by RNs included: (1) RN-personal notes; (2) facility-specific templates/forms; (3) nursing processes/tasks; (4) paper-based resident profile; (5) daily care plans; (6) RN-notebooks; (7) medication administration records (MARs); (8) reporting software application (RAI-MDS); (9) people (care providers); and (10) references (i.e., books). Nurses used a combination of shared information spaces, such as the Nurses Station or RN-notebook, and personal information spaces, such as personal notebooks or "sticky" notes. Four essential RN information management functions were identified: collection, classification, storage, and distribution. Six sets of information were necessary to perform RN care tasks and communication, including: (1) admission, discharge, and transfer (ADT); (2) assessment; (3) care plan; (4) intervention (with two subsets: medication and care procedure); (5) report; and (6) reference. Based on the RN information management system requirements, a graphic information flow model was constructed.  This baseline study identified key components of a current LTC nursing information management system. The information flow model may assist health information

  4. Guidelines for preparing IAEA design information questionnaires

    International Nuclear Information System (INIS)

    Swartz, J.M.; Bieber, A.M.

    1980-01-01

    The format of the IAEA Design Information Questionnaires and the SAI prepared guidelines for completing them, is described. The guidelines should assist facility operators in meeting the time constraints set forth in the Subsidiary Arrangements by effectively supplying the information needed by the IAEA and in minimizing resource allocations to the preparation effort. 8 refs

  5. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  6. Key points for the design of Mox facilities

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  7. BIM Guidelines Inform Facilities Management Databases: A Case Study over Time

    Directory of Open Access Journals (Sweden)

    Karen Kensek

    2015-08-01

    Full Text Available A building information model (BIM contains data that can be accessed and exported for other uses during the lifetime of the building especially for facilities management (FM and operations. Working under the guidance of well-designed BIM guidelines to insure completeness and compatibility with FM software, architects and contractors can deliver an information rich data model that is valuable to the client. Large owners such as universities often provide these detailed guidelines and deliverable requirements to their building teams. Investigation of the University of Southern California (USC Facilities Management Service’s (FMS website showed a detailed plan including standards, file names, parameter lists, and other requirements of BIM data, which were specifically designated for facilities management use, as deliverables on new construction projects. Three critical details were also unearthed in the reading of these documents: Revit was the default BIM software; COBie was adapted to help meet facilities management goals; and EcoDomus provided a display of the collected data viewed through Navisworks. Published accounts about the Cinema Arts Complex developed with and under these guidelines reported positive results. Further examination with new projects underway reveal the rapidly changing relational database landscape evident in the new USC “Project Record Revit Requirement Execution Plan (PRxP”.

  8. Facility information management system; Shisetsu joho kanri system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-01-10

    A facility management system (FMS) was developed as a tool for efficiently operating and managing building facilities and related equipment. The maintenance management data is designed to be collected through automatic formation of data base by using a work flow function and releasing the daily business from paper work. The data base thus formed can be retrieved and displayed by utilizing a network system. The plan view for construction facilities is made a minute plan comparable to the ground plan by taking in DXF type drawing data such as a completion drawing, making it a colored display for example to create an intuitive expression understandable at first sight. The plan is controlled by the level including equipment classification and is capable of superimposed display. Detailed management data is displayed by mouse clicking of registered icons, allowing required information to be readily taken out. (translated by NEDO)

  9. Robins Air Force Base Solar Cogeneration Facility design

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-06-01

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

  10. Use of ICT facilities for teaching library and information science ...

    African Journals Online (AJOL)

    This article investigated availability and functionality of ICT facilities and its utilization in the teaching of Library and Information Science (LIS) students in the University of Uyo. The study adopted a survey design and was guided by four objectives, four research questions, and two hypotheses. The population of the study ...

  11. Defense Waste Processing Facility staged operations: environmental information document

    International Nuclear Information System (INIS)

    1981-11-01

    Environmental information is presented relating to a staged version of the proposed Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The information is intended to provide the basis for an Environmental Impact Statement. In either the integral or the staged design, the DWPF will convert the high-level waste currently stored in tanks into: a leach-resistant form containing about 99.9% of all the radioactivity, and a residual, slightly contaminated salt, which is disposed of as saltcrete. In the first stage of the staged version, the insoluble sludge portion of the waste and the long lived radionuclides contained therein will be vitrified. The waste glass will be sealed in canisters and stored onsite until shipped to a Federal repository. In the second stage, the supernate portion of the waste will be decontaminated by ion exchange. The recovered radionuclides will be transferred to the Stage 1 facility, and mixed with the sludge feed before vitrification. The residual, slightly contaminated salt solution will be mixed with Portland cement to form a concrete product (saltcrete) which will be buried onsite in an engineered landfill. This document describes the conceptual facilities and processes for producing glass waste and decontaminated salt. The environmental effects of facility construction, normal operations, and accidents are then presented. Descriptions of site and environs, alternative sites and waste disposal options, and environmental consultations and permits are given in the base Environmental Information Document

  12. An ARM Mobile Facility Designed for Marine Deployments

    Science.gov (United States)

    Wiscombe, W. J.

    2007-05-01

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

  13. Ventilation design for new plutonium recovery facility

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  14. Designation of facility usage categories for Hanford Site facilities

    International Nuclear Information System (INIS)

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

    1991-01-01

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

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

    International Nuclear Information System (INIS)

    Shank, D.R.

    1995-01-01

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

  16. EPA Geospatial Data Download: Facility and Site Information

    Data.gov (United States)

    U.S. Environmental Protection Agency — Contains information about facilities or sites subject to environmental regulation, including key facility information along with associated environmental interests...

  17. Risk-informing safety reviews for non-reactor nuclear facilities: an example application

    International Nuclear Information System (INIS)

    Mubayi, V.; Yue, M.; Bari, R.A.; Azarm, M.A.; Mukaddam, W.; Good, G.; Gonzalez, F.

    2013-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction can be useful to help to risk-inform a safety review process and assess compliance with regulatory requirements. (authors)

  18. Decommissioning Work Modeling System for Nuclear Facility Decommissioning Design

    International Nuclear Information System (INIS)

    Park, S. K.; Cho, W. H.; Choi, Y. D.; Moon, J. K.

    2012-01-01

    During the decommissioning activities of the KRR-1 and 2 (Korea Research Reactor 1 and 2) and UCP (Uranium Conversion Plant), all information and data, which generated from the decommissioning project, were record, input and managed at the DECOMMIS (DECOMMissioning Information management System). This system was developed for the inputting and management of the data and information of the man-power consumption, operation time of the dismantling equipment, the activities of the radiation control, dismantled waste management and Q/A activities. When a decommissioning is planed for a nuclear facility, an investigation into the characterization of the nuclear facility is first required. The results of such an investigation are used for calculating the quantities of dismantled waste volume and estimating the cost of the decommissioning project. That is why, the DEFACS (DEcommissioning FAcility Characterization DB System) was established for the management of the facility characterization data. The DEWOCS (DEcommissioning WOrk-unit productivity Calculation System) was developed for the calculation of the workability on the decommissioning activities. The work-unit productivities are calculated through this system using the data from the two systems, DECOMMIS and DEFACS. This result, the factors of the decommissioning work-unit productivities, will be useful for the other nuclear facility decommissioning planning and engineering. For this, to set up the items and plan for the decommissioning of the new objective facility, the DEMOS (DEcommissioning work Modeling System) was developed. This system is for the evaluation the cost, man-power consumption of workers and project staffs and technology application time. The factor of the work-unit productivities from the DEWOCS and governmental labor cost DB and equipment rental fee DB were used for the calculation the result of the DEMOS. And also, for the total system, DES (Decommissioning Engineering System), which is now

  19. The earthquake problem in engineering design: generating earthquake design basis information

    International Nuclear Information System (INIS)

    Sharma, R.D.

    1987-01-01

    Designing earthquake resistant structures requires certain design inputs specific to the seismotectonic status of the region, in which a critical facility is to be located. Generating these inputs requires collection of earthquake related information using present day techniques in seismology and geology, and processing the collected information to integrate it to arrive at a consolidated picture of the seismotectonics of the region. The earthquake problem in engineering design has been outlined in the context of a seismic design of nuclear power plants vis a vis current state of the art techniques. The extent to which the accepted procedures of assessing seismic risk in the region and generating the design inputs have been adherred to determine to a great extent the safety of the structures against future earthquakes. The document is a step towards developing an aproach for generating these inputs, which form the earthquake design basis. (author)

  20. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

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

  1. Facility design, installation and operation

    International Nuclear Information System (INIS)

    Fleischmann, A.W.

    1985-01-01

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

  2. SNL/CA Facilities Management Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

    Rabb, David [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Clark, Eva [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

    2014-12-01

    At Sandia National Laboratories in California (SNL/CA), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/CA applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule.

  3. Exercise in completing design information questionnaire for model research reactor: model description, notes, questionnaire

    International Nuclear Information System (INIS)

    Bellinger, J.; Ho, T.

    1989-01-01

    The document which defines the inspection measures which the IAEA can deploy at any given nuclear facility is known as the Facility Attachment. For the Agency to negotiate an effective Facility Attachment it must have available certain design information, including the facility's identity, capacity and location; the form, location and flow of nuclear material and the layout of important items of equipment; and a description of the features and procedures relating to nuclear material accountancy, containment and surveillance. In practice such information is solicited in a format, standardized for each facility type, known as the Design Information Questionnaire or the D.I.Q. The nuclear activities used as a model in this course are those of a fictitious country called Pacifica. These nuclear activities bear some resemblance to those at the Australian Atomic Energy Commission's Research Establishment at Lucas Heights. Specifically, Pacifica has a 10 MW heavy water cooled and moderated research reactor using enriched uranium fuel which is very similar to the HIFAR reactor. The reactor and the associated laboratories are described and the Design Information Questionnaire for them is completed. figs., tabs

  4. Springfield Processing Plant (SPP) Facility Information

    Energy Technology Data Exchange (ETDEWEB)

    Leach, Janice; Torres, Teresa M.

    2012-10-01

    The Springfield Processing Plant is a hypothetical facility. It has been constructed for use in training workshops. Information is provided about the facility and its surroundings, particularly security-related aspects such as target identification, threat data, entry control, and response force data.

  5. Urbanonymic Design: On the Naming of City Facilities

    Directory of Open Access Journals (Sweden)

    Marina V. Golomidova

    2015-06-01

    Full Text Available The paper focuses on the problems of naming and renaming of municipal facilities: streets, squares, parks, public gardens, etc. The author’s reflections rest upon her personal experience as a member of the Facilities Naming Committee of the city of Ekaterinburg. The article seeks to suggest a new approach to the solution of controversial issues of naming city facilities based on territory branding and city image design and promotion concepts. Place names are thus considered as an important informational and communicational resource of creation of a city’s image which means that the naming of concrete city facilities should rely on a holistic urbanonymic conception defining basic features of the city’s identity and ordering themes to be reflected in names. The author argues that the rational long-term urbanonymic policy implies the existence of a consistent image-making strategy. In this case the process of naming and its results could be characterized in terms of ‘urbanonymic design’ considering the naming of city facilities as a part of the construction of the city’s identity. The policy of official naming of city-owned assets must then meet the following requirements: proportionality, functionality, orientation capacity, semantic transparency, harmonicity, which constitute the most significant principles of construction of an urbanonymic system.

  6. Design aspects of radiological safety in nuclear facilities

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  7. Practical design of gamma irradiation facility

    International Nuclear Information System (INIS)

    Sugimoto, Sen-ichi

    1976-01-01

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

  8. Exploratory Shaft Facility design basis study report

    International Nuclear Information System (INIS)

    Langstaff, A.L.

    1987-01-01

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

  9. 10 CFR 75.10 - Facility information.

    Science.gov (United States)

    2010-01-01

    ...) The identification of the facility, stating its general character, purpose, nominal capacity (thermal... used for routine purposes; (2) A description of the general arrangement of the facility with reference... information must be submitted: (1) Regarding a modification of a type described in the license or certificate...

  10. Cold Vacuum Dryer (CVD) Facility Security System Design Description. System 54

    International Nuclear Information System (INIS)

    WHITEHURST, R.

    2000-01-01

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility security system. The system's primary purpose is to provide reasonable assurance that breaches of security boundaries are detected and assessment information is provided to protective force personnel. In addition, the system is utilized by Operations to support reduced personnel radiation goals and to provide reasonable assurance that only authorized personnel are allowed to enter designated security areas

  11. Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition

    International Nuclear Information System (INIS)

    Leach, C.E.; Galbraith, J.D.; Grant, P.R.; Francuz, D.J.; Schroeder, P.J.

    1995-11-01

    This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs

  12. Information security management system planning for CBRN facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lenaeu, Joseph D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); O' Neil, Lori Ross [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Leitch, Rosalyn M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glantz, Clifford S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Landine, Guy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bryant, Janet L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lewis, John [National Nuclear Lab., Workington (United Kingdom); Mathers, Gemma [National Nuclear Lab., Workington (United Kingdom); Rodger, Robert [National Nuclear Lab., Workington (United Kingdom); Johnson, Christopher [National Nuclear Lab., Workington (United Kingdom)

    2015-12-01

    The focus of this document is to provide guidance for the development of information security management system planning documents at chemical, biological, radiological, or nuclear (CBRN) facilities. It describes a risk-based approach for planning information security programs based on the sensitivity of the data developed, processed, communicated, and stored on facility information systems.

  13. Information security management system planning for CBRN facilities

    International Nuclear Information System (INIS)

    Lenaeu, Joseph D.; O'Neil, Lori Ross; Leitch, Rosalyn M.; Glantz, Clifford S.; Landine, Guy P.; Bryant, Janet L.; Lewis, John; Mathers, Gemma; Rodger, Robert; Johnson, Christopher

    2015-01-01

    The focus of this document is to provide guidance for the development of information security management system planning documents at chemical, biological, radiological, or nuclear (CBRN) facilities. It describes a risk-based approach for planning information security programs based on the sensitivity of the data developed, processed, communicated, and stored on facility information systems.

  14. Conceptual design of tritium treatment facility

    International Nuclear Information System (INIS)

    Tachikawa, Katsuhiro

    1982-01-01

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

  15. Cold vacuum drying facility design requirements

    Energy Technology Data Exchange (ETDEWEB)

    Irwin, J.J.

    1997-09-24

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

  16. Cold vacuum drying facility design requirements

    International Nuclear Information System (INIS)

    Irwin, J.J.

    1997-01-01

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

  17. Design and evaluation guidelines for Department of Energy facilities subjected to natural phenomena hazards

    International Nuclear Information System (INIS)

    Kennedy, R.P.; Short, S.A.; McDonald, J.R.; McCann, M.W. Jr.; Murray, R.C.; Hill, J.R.

    1990-06-01

    The Department of Energy (DOE) and the DOE Natural Phenomena Hazards Panel have developed uniform design and evaluation guidelines for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of the guidelines is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. The guidelines apply to both new facilities (design) and existing facilities (evaluation, modification, and upgrading). The intended audience is primarily the civil/structural or mechanical engineers conducting the design or evaluation of DOE facilities. The likelihood of occurrence of natural phenomena hazards at each DOE site has been evaluated by the DOE Natural Phenomena Hazard Program. Probabilistic hazard models are available for earthquake, extreme wind/tornado, and flood. Alternatively, site organizations are encouraged to develop site-specific hazard models utilizing the most recent information and techniques available. In this document, performance goals and natural hazard levels are expressed in probabilistic terms, and design and evaluation procedures are presented in deterministic terms. Design/evaluation procedures conform closely to common standard practices so that the procedures will be easily understood by most engineers. Performance goals are expressed in terms of structure or equipment damage to the extent that: (1) the facility cannot function; (2) the facility would need to be replaced; or (3) personnel are endangered. 82 refs., 12 figs., 18 tabs

  18. Design and evaluation guidelines for Department of Energy facilities subjected to natural phenomena hazards

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, R.P. (Structural Mechanics Consulting, Inc., Yorba Linda, CA (USA)); Short, S.A. (ABB Impell Corp., Mission Viejo, CA (USA)); McDonald, J.R. (Texas Tech Univ., Lubbock, TX (USA)); McCann, M.W. Jr. (Benjamin (J.R.) and Associates, Inc., Mountain View, CA (USA)); Murray, R.C. (Lawrence Livermore National Lab., CA (USA)); Hill, J.R. (USDOE Assistant Secretary for Environment, Safety, and He

    1990-06-01

    The Department of Energy (DOE) and the DOE Natural Phenomena Hazards Panel have developed uniform design and evaluation guidelines for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of the guidelines is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. The guidelines apply to both new facilities (design) and existing facilities (evaluation, modification, and upgrading). The intended audience is primarily the civil/structural or mechanical engineers conducting the design or evaluation of DOE facilities. The likelihood of occurrence of natural phenomena hazards at each DOE site has been evaluated by the DOE Natural Phenomena Hazard Program. Probabilistic hazard models are available for earthquake, extreme wind/tornado, and flood. Alternatively, site organizations are encouraged to develop site-specific hazard models utilizing the most recent information and techniques available. In this document, performance goals and natural hazard levels are expressed in probabilistic terms, and design and evaluation procedures are presented in deterministic terms. Design/evaluation procedures conform closely to common standard practices so that the procedures will be easily understood by most engineers. Performance goals are expressed in terms of structure or equipment damage to the extent that: (1) the facility cannot function; (2) the facility would need to be replaced; or (3) personnel are endangered. 82 refs., 12 figs., 18 tabs.

  19. Engineering test facility design center

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

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

  20. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

  1. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    International Nuclear Information System (INIS)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L.

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R ampersand D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R ampersand D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action

  2. Preliminary Design of the AEGIS Test Facility

    CERN Document Server

    Dassa, Luca; Cambiaghi, Danilo

    2010-01-01

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

  3. Facility Safeguardability Analysis in Support of Safeguards by Design

    International Nuclear Information System (INIS)

    Wonder, E.F.

    2010-01-01

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

  4. A local area network and information management system for a submarine overhaul facility

    OpenAIRE

    Bushmire, Jeffrey D

    1990-01-01

    A preliminary design of a local area network for a submarine overhaul facility is developed using System Engineering concepts. SOFLAN, the Submarine Overhaul Facility Local Area Network, is necessary to provide more timely and accurate information to submarine overhaul managers in order to decrease the overhaul time period and become more competitive. The network is a microcomputer based system following the Ethernet and IEEE 802.3 standards with a server .. client architecture. SOFLAN serves...

  5. Delivering information: a descriptive study of Australian women's information needs for decision-making about birth facility.

    Science.gov (United States)

    Thompson, Rachel; Wojcieszek, Aleena M

    2012-06-18

    Little information is known about what information women want when choosing a birth facility. The objective of this study was to inform the development of a consumer decision support tool about birth facility by identifying the information needs of maternity care consumers in Queensland, Australia. Participants were 146 women residing in both urban and rural areas of Queensland, Australia who were pregnant and/or had recently given birth. A cross-sectional survey was administered in which participants were asked to rate the importance of 42 information items to their decision-making about birth facility. Participants could also provide up to ten additional information items of interest in an open-ended question. On average, participants rated 30 of the 42 information items as important to decision-making about birth facility. While the majority of information items were valued by most participants, those related to policies about support people, other women's recommendations about the facility, freedom to choose one's preferred position during labour and birth, the aesthetic quality of the facility, and access to on-site neonatal intensive care were particularly widely valued. Additional items of interest frequently focused on postnatal care and support, policies related to medical intervention, and access to water immersion. The women surveyed had significant and diverse information needs for decision-making about birth facility. These findings have immediate applications for the development of decision support tools about birth facility, and highlight the need for tools which provide a large volume of information in an accessible and user-friendly format. These findings may also be used to guide communication and information-sharing by care providers involved in counselling pregnant women and families about their options for birth facility or providing referrals to birth facilities.

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

    International Nuclear Information System (INIS)

    Palomaeki, J.; Ristimaeki, L.

    2013-10-01

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

  7. RAMI strategies in the IFMIF Test Facilities design

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  8. RAMI strategies in the IFMIF Test Facilities design

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  9. Institutionalizing Safeguards By Design for Nuclear Facilities

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  10. Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-09-01

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

  11. The Influence of Building Codes on Recreation Facility Design.

    Science.gov (United States)

    Morrison, Thomas A.

    1989-01-01

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

  12. Project W-441 cold vacuum drying facility design requirements document

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

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

  13. MIMI: multimodality, multiresource, information integration environment for biomedical core facilities.

    Science.gov (United States)

    Szymanski, Jacek; Wilson, David L; Zhang, Guo-Qiang

    2009-10-01

    The rapid expansion of biomedical research has brought substantial scientific and administrative data management challenges to modern core facilities. Scientifically, a core facility must be able to manage experimental workflow and the corresponding set of large and complex scientific data. It must also disseminate experimental data to relevant researchers in a secure and expedient manner that facilitates collaboration and provides support for data interpretation and analysis. Administratively, a core facility must be able to manage the scheduling of its equipment and to maintain a flexible and effective billing system to track material, resource, and personnel costs and charge for services to sustain its operation. It must also have the ability to regularly monitor the usage and performance of its equipment and to provide summary statistics on resources spent on different categories of research. To address these informatics challenges, we introduce a comprehensive system called MIMI (multimodality, multiresource, information integration environment) that integrates the administrative and scientific support of a core facility into a single web-based environment. We report the design, development, and deployment experience of a baseline MIMI system at an imaging core facility and discuss the general applicability of such a system in other types of core facilities. These initial results suggest that MIMI will be a unique, cost-effective approach to addressing the informatics infrastructure needs of core facilities and similar research laboratories.

  14. Design of GMP compliance radiopharmaceutical production facility in MINT

    International Nuclear Information System (INIS)

    Anwar Abd Rahman; Shaharum Ramli; M Rizal Mamat Ibrahim; Rosli Darmawan; Yusof Azuddin Ali; Jusnan Hashim

    2005-01-01

    In 1985, MINT built the only radiopharmaceutical production facility in Malaysia. The facility was designed based on IAEA (International Atomic Energy Agency) standard guidelines which provide radiation safety to the staff and the surrounding environment from radioactive contamination. Since 1999, BPFK (Biro Pengawalan Farmaseutikal Kebangsaan) has used the guidelines from Pharmaceutical Inspection Convention Scheme (PICS) to meet the requirements of the Good Manufacturing Practice (GMP) for Pharmaceutical Products. In the guidelines, the pharmaceutical production facility shall be designed based on clean room environment. In order to design a radiopharmaceutical production facility, it is important to combine the concept of radiation safety and clean room to ensure that both requirements from GMP and IAEA are met. The design requirement is necessary to set up a complete radiopharmaceutical production facility, which is safe, has high production quality and complies with the Malaysian and International standards. (Author)

  15. Modern tornado design of nuclear and other potentially hazardous facilities

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Zhao, Y.

    1996-01-01

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

  16. Criticality safety and facility design considerations

    International Nuclear Information System (INIS)

    Waltz, W.R.

    1991-06-01

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

  17. Waste Encapsulation and Storage Facility (WESF) Design Reconstitution Plan

    International Nuclear Information System (INIS)

    HERNANDEZ, R.

    1999-01-01

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

  18. Exploratory shaft facility preliminary designs - Permian Basin

    International Nuclear Information System (INIS)

    1983-09-01

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

  19. Specific factors influencing information system/information and communication technology sourcing strategies in healthcare facilities.

    Science.gov (United States)

    Potančok, Martin; Voříšek, Jiří

    2016-09-01

    Healthcare facilities use a number of information system/information and communication technologies. Each healthcare facility faces a need to choose sourcing strategies most suitable to ensure provision of information system/information and communication technology services, processes and resources. Currently, it is possible to observe an expansion of sourcing possibilities in healthcare informatics, which creates new requirements for sourcing strategies. Thus, the aim of this article is to identify factors influencing information system/information and communication technology sourcing strategies in healthcare facilities. The identification was based on qualitative research, namely, a case study. This study provides a set of internal and external factors with their impact levels. The findings also show that not enough attention is paid to these factors during decision-making. © The Author(s) 2015.

  20. Construction of irradiated material examination facility-basic design

    International Nuclear Information System (INIS)

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

    1989-02-01

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

  1. A Framework for Seismic Design of Items in Safety-Critical Facilities for Implementing a Risk-Informed Defense-in-Depth-Based Concept

    Directory of Open Access Journals (Sweden)

    Tatsuya Itoi

    2017-05-01

    Full Text Available Recently, especially after the 2011 off the Pacific coast of Tohoku earthquake and the Fukushima Daiichi nuclear power plant accident, the need for treating residual risks and cliff-edge effects in safety-critical facilities has been widely recognized as an extremely important issue. In this article, the sophistication of seismic designs in safety-critical facilities is discussed from the viewpoint of mitigating the consequences of accidents, such as the avoidance of cliff-edge effects. For this purpose, the implementation of a risk-informed defense-in-depth-based framework is proposed in this study. A basic framework that utilizes diversity in the dynamic characteristics of items and also provides additional seismic margin to items important for safety when needed is proposed to prevent common cause failure and to avoid cliff-edge effects as far as practicable. The proposed method is demonstrated to be effective using an example calculation.

  2. Facilities design for TIBER II

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  3. Design of a hydrogen test facility

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  4. Guide to research facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  5. Production Facility SCADA Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Holloway, Michael Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baily, Scott A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wheat, Robert Mitchell Jr. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-23

    The following report covers FY 14 activities to develop supervisory control and data acquisition (SCADA) system for the Northstar Moly99 production facility. The goal of this effort is to provide Northstar with a baseline system design.

  6. Facility design consequences of different employees’ quality perceptions

    NARCIS (Netherlands)

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

    2015-01-01

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

  7. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-04-01

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

  8. Delivering information: A descriptive study of Australian women’s information needs for decision-making about birth facility

    Directory of Open Access Journals (Sweden)

    Thompson Rachel

    2012-06-01

    Full Text Available Abstract Background Little information is known about what information women want when choosing a birth facility. The objective of this study was to inform the development of a consumer decision support tool about birth facility by identifying the information needs of maternity care consumers in Queensland, Australia. Methods Participants were 146 women residing in both urban and rural areas of Queensland, Australia who were pregnant and/or had recently given birth. A cross-sectional survey was administered in which participants were asked to rate the importance of 42 information items to their decision-making about birth facility. Participants could also provide up to ten additional information items of interest in an open-ended question. Results On average, participants rated 30 of the 42 information items as important to decision-making about birth facility. While the majority of information items were valued by most participants, those related to policies about support people, other women’s recommendations about the facility, freedom to choose one’s preferred position during labour and birth, the aesthetic quality of the facility, and access to on-site neonatal intensive care were particularly widely valued. Additional items of interest frequently focused on postnatal care and support, policies related to medical intervention, and access to water immersion. Conclusions The women surveyed had significant and diverse information needs for decision-making about birth facility. These findings have immediate applications for the development of decision support tools about birth facility, and highlight the need for tools which provide a large volume of information in an accessible and user-friendly format. These findings may also be used to guide communication and information-sharing by care providers involved in counselling pregnant women and families about their options for birth facility or providing referrals to birth facilities.

  9. MEMS/Electronic Device Design and Characterization Facility

    Data.gov (United States)

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

  10. Status and Prospect of Safeguards By Design for Pyroprocessing Facility

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  11. Conceptual design report for Central Waste Disposal Facility

    International Nuclear Information System (INIS)

    1984-01-01

    The permanent facilities are defined, and cost estimates are provided for the disposal of Low-Level Radioactive Wastes (LLW) at the Central Waste Disposal Facility (CWDF). The waste designated for the Central Waste Disposal Facility will be generated by the Y-12 Plant, the Oak Ridge Gaseous Diffusion Plant, and the Oak Ridge National Laboratory. The facility will be operated by ORNL for the Office of Defense Waste and By-Products Management of the Deparment of Energy. The CWDF will be located on the Department of Energy's Oak Ridge Reservation, west of Highway 95 and south of Bear Creek Road. The body of this Conceptual Design Report (CDR) describes the permanent facilities required for the operation of the CWDF. Initial facilities, trenches, and minimal operating equipment will be provided in earlier projects. The disposal of LLW will be by shallow land burial in engineered trenches. DOE Order 5820 was used as the performance standard for the proper disposal of radioactive waste. The permanent facilities are intended for beneficial occupancy during the first quarter of fiscal year 1989. 3 references, 9 figures, 7 tables

  12. Design requirements for new nuclear reactor facilities in Canada

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  13. Design of plutonium processing facilities

    International Nuclear Information System (INIS)

    Derbyshire, W.; Sills, R.J.

    1982-01-01

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

  14. Information rich display design

    International Nuclear Information System (INIS)

    Welch, Robin; Braseth, Alf Ove; Veland, Oeystein

    2004-01-01

    This paper presents the concept Information Rich Displays. The purpose of Information Rich Displays (IRDs) is to condensate prevailing information in process displays in such a way that each display format (picture) contains more relevant information for the user. Compared to traditional process control displays, this new concept allows the operator to attain key information at a glance and at the same time allows for improved monitoring of larger portions of the process. This again allows for reduced navigation between both process and trend displays and ease the cognitive demand on the operator. This concept has been created while working on designing display prototypes for the offshore petroleum production facilities of tomorrow. Offshore installations basically consist of wells, separation trains (where oil, gas and water are separated from each other), an oil tax measurement system (where oil quality is measured and the pressure increased to allow for export), gas compression (compression of gas for export) and utility systems (water treatment, chemical systems etc.). This means that an offshore control room operator has to deal with a complex process that comprises several functionally different systems. The need for a new approach to offshore display format design is in particular based on shortcomings in today's designs related to the keyhole effect, where the display format only reveals a fraction of the whole process. Furthermore, the upcoming introduction of larger off- and on-shore operation centres will increase the size and complexity of the operators' work domain. In the light of the increased demands on the operator, the proposed IRDs aim to counter the negative effects this may have on the workload. In this work we have attempted to classify the wide range of different roles an operator can have in different situations. The information content and amount being presented to the operator in a display should be viewed in context of the roles the

  15. Design Guide for Category I reactors critical facilities

    International Nuclear Information System (INIS)

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

    1978-08-01

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

  16. Hanford facility dangerous waste permit application, general information portion. Revision 3

    International Nuclear Information System (INIS)

    Sonnichsen, J.C.

    1997-01-01

    For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy's contractors are identified as ''co-operators'' and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ''operator'' elsewhere in the application is not meant to conflict with the contractors' designation as co-operators but rather is based on the contractors' contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which

  17. Hanford facility dangerous waste permit application, general information portion. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Sonnichsen, J.C.

    1997-08-21

    For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy`s contractors are identified as ``co-operators`` and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ``operator`` elsewhere in the application is not meant to conflict with the contractors` designation as co-operators but rather is based on the contractors` contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  19. Information and Communication Technology (ICT) Facilities and ...

    African Journals Online (AJOL)

    The library is at the centre of academic activities in every university. It is being transformed from the traditional operations to a service organization with the use of information and communication technology facilities. In this study, the researchers x-rayed ICT facilities and the skills level of the staff in the three universities in ...

  20. Design study of underground facility of the Underground Research Laboratory

    International Nuclear Information System (INIS)

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

    1998-03-01

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

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  2. Cold vacuum drying facility design requirements

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-07-01

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

  3. Cold vacuum drying facility design requirements

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    1982-09-01

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

  5. Energy Systems Integration Facility (ESIF) Facility Stewardship Plan: Revision 2.1

    Energy Technology Data Exchange (ETDEWEB)

    Torres, Juan [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Anderson, Art [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-01-02

    The U.S. Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy (EERE), has established the Energy Systems Integration Facility (ESIF) on the campus of the National Renewable Energy Laboratory (NREL) and has designated it as a DOE user facility. This 182,500-ft2 research facility provides state-of-the-art laboratory and support infrastructure to optimize the design and performance of electrical, thermal, fuel, and information technologies and systems at scale. This Facility Stewardship Plan provides DOE and other decision makers with information about the existing and expected capabilities of the ESIF and the expected performance metrics to be applied to ESIF operations. This plan is a living document that will be updated and refined throughout the lifetime of the facility.

  6. Interior Design Factors in Library Facilities.

    Science.gov (United States)

    Jackson, Patricia Ann

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

  7. AERIAL DELIVERY DESIGN AND FABRICATION FACILITY

    Data.gov (United States)

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

  8. National Ignition Facility Title II Design Plan

    International Nuclear Information System (INIS)

    Kumpan, S

    1997-01-01

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

  9. National Ignition Facility subsystem design requirements optics assembly building (OAB) SSDR 1.2.2.3

    International Nuclear Information System (INIS)

    Kempel, P.; Hands, J.

    1996-01-01

    This Subsystem Design Requirement (SSDR) document establishes the performance, design, and verification requirements 'for the conventional building systems and subsystems of the Optics Assembly Building (OAB). These building system requirements are associated with housing and supporting the operational flow of personnel and materials throughout the OAB for preparing and repairing optical and mechanical components used in the National Ignition Facility (NIF) Laser and Target Building (LTAB). This SSDR addresses the following subsystems associated with the OAB: * Structural systems for the building spaces and operational-support equipment and building- support equipment. * Architectural building features associated with housing the space, operational cleanliness, and functional operation of the facility. * Heating, Ventilating, and Air Conditioning (HVAC) systems for maintaining a clean and thermally stable ambient environment within the facility. * Plumbing systems that provide potable water and sanitary facilities for the occupants and stormwater drainage for transporting rainwater. * Fire Protection systems that guard against fire damage to the facility and its contents. * Material handling equipment for transferring optical assemblies and other materials within building areas and to the LTAB. * Mechanical process piping systems for liquids and gases that provide cooling, cleaning, and other service to optical and mechanical components. * Electrical power and grounding systems that provide service to the building and equipment, including lighting distribution and communications systems for the facilities. * Instrumentation and control systems that ensure the safe operation of conventional facilities systems, such as those listed above. Generic design criteria, such as siting data, seismic requirements, utility availability, and other information that contributes to the OAB design, are not addressed in this document

  10. Facility information system `SOINS-IIS`; Shisetsu joho kanri system `SOINS-IIS`

    Energy Technology Data Exchange (ETDEWEB)

    Shimaoka, S.; Watanabe, M.; Mizuno, Y. [Fuji Electric Co. Ltd., Tokyo (Japan)

    1998-07-10

    With the informatization in the industry, office space is becoming the center of business activities. Also as to the facility control, a facility control system is required which is added with functions of information service to users and the management support system, in addition to the conventional system used mainly for equipment maintenance. Fuji Electric Co. developed a facility information control system, SOINS-IIS (social information system-infrastructure information system), into which the above-mentioned functions were integrated. The features of the system were presented in examples of the introduction to Ichibankan, YRP (Yokosuka Research Park) Center and R and D Center, NTT DoCoMo. The system roughly has an information service function for facility users, function of management for office staff such as tenant management and bill management, management support function for facility owners and planning departments. Beside the above-mentioned functions, in case of YRP Center, for example, the system has functions of management of reservation of meeting rooms, etc., terminal display of common use information and terminal display of information, and many other management support functions. 10 figs.

  11. Implications of system usability on intermodal facility design.

    Science.gov (United States)

    2010-08-01

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

  12. Waste Management Facilities Cost Information Report

    Energy Technology Data Exchange (ETDEWEB)

    Feizollahi, F.; Shropshire, D.

    1992-10-01

    The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options.

  13. Waste Management Facilities Cost Information Report

    International Nuclear Information System (INIS)

    Feizollahi, F.; Shropshire, D.

    1992-10-01

    The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options

  14. Design considerations for the Yucca Mountain project exploratory shaft facility

    International Nuclear Information System (INIS)

    Bullock, R.L. Sr.

    1990-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-10-01

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

  16. Conceptual layout design of CFETR Hot Cell Facility

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-11-15

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

  17. Knowledge management and information tools for building maintenance and facility management

    CERN Document Server

    Talamo, Cinzia

    2015-01-01

    This book describes the latest methods and tools for the management of information within facility management services and explains how it is possible to collect, organize, and use information over the life cycle of a building in order to optimize the integration of these services and improve the efficiency of processes. The coverage includes presentation and analysis of basic concepts, procedures, and international standards in the development and management of real estate inventories, building registries, and information systems for facility management. Models of strategic management are discussed and the functions and roles of the strategic management center, explained.  Detailed attention is also devoted to building information modeling (BIM) for facility management and potential interactions between information systems and BIM applications. Criteria for evaluating information system performance are identified, and guidelines of value in developing technical specifications for facility management service...

  18. Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion

    International Nuclear Information System (INIS)

    Dyer, R.S.; Diamante, J.M.

    1996-07-01

    The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility's capacity from 1,200 m 3 per year to 5,000 m 3 per year, will permit the facility to process high-salt wastes from the Russian Navy's Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted

  19. Status and Prospect of Safeguards By Design for the Pyroprocessing Facility

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  20. High level radioactive waste management facility design criteria

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  1. CIF---Design basis for an integrated incineration facility

    International Nuclear Information System (INIS)

    Bennett, G.F.

    1991-01-01

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

  2. Proposed BISOL Facility - a Conceptual Design

    Science.gov (United States)

    Ye, Yanlin

    2018-05-01

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

  3. 6 CFR 27.200 - Information regarding security risk for a chemical facility.

    Science.gov (United States)

    2010-01-01

    ... chemical facility. 27.200 Section 27.200 Domestic Security DEPARTMENT OF HOMELAND SECURITY, OFFICE OF THE SECRETARY CHEMICAL FACILITY ANTI-TERRORISM STANDARDS Chemical Facility Security Program § 27.200 Information regarding security risk for a chemical facility. (a) Information to determine security risk. In order to...

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

    Science.gov (United States)

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

    1981-01-01

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

  5. Design of special facility for liquor irradiation

    International Nuclear Information System (INIS)

    Yao Shibin; Chen Zigen

    1989-01-01

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

  6. 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.

  7. Analyses in support of risk-informed natural gas vehicle maintenance facility codes and standards :

    Energy Technology Data Exchange (ETDEWEB)

    Ekoto, Isaac W.; Blaylock, Myra L.; LaFleur, Angela Christine; LaChance, Jeffrey L.; Horne, Douglas B.

    2014-03-01

    Safety standards development for maintenance facilities of liquid and compressed gas fueled large-scale vehicles is required to ensure proper facility design and operation envelopes. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase I work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest. Finally, scenario analyses were performed using detailed simulations and modeling to estimate the overpressure hazards from HAZOP defined scenarios. The results from Phase I will be used to identify significant risk contributors at NGV maintenance facilities, and are expected to form the basis for follow-on quantitative risk analysis work to address specific code requirements and identify effective accident prevention and mitigation strategies.

  8. Designation of facility usage categories for Hanford Site facilities

    International Nuclear Information System (INIS)

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

    1991-10-01

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

  9. Design and construction of a fast critical facility

    International Nuclear Information System (INIS)

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

    1962-01-01

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

  10. Mortality monitoring design for utility-scale solar power facilities

    Science.gov (United States)

    Huso, Manuela; Dietsch, Thomas; Nicolai, Chris

    2016-05-27

    IntroductionSolar power represents an important and rapidly expanding component of the renewable energy portfolio of the United States (Lovich and Ennen, 2011; Hernandez and others, 2014). Understanding the impacts of renewable energy development on wildlife is a priority for the U.S. Fish and Wildlife Service (FWS) in compliance with Department of Interior Order No. 3285 (U.S. Department of the Interior, 2009) to “develop best management practices for renewable energy and transmission projects on the public lands to ensure the most environmentally responsible development and delivery of renewable energy.” Recent studies examining effects of renewable energy development on mortality of migratory birds have primarily focused on wind energy (California Energy Commission and California Department of Fish and Game, 2007), and in 2012 the FWS published guidance for addressing wildlife conservation concerns at all stages of land-based wind energy development (U.S. Fish and Wildlife Service, 2012). As yet, no similar guidelines exist for solar development, and no published studies have directly addressed the methodology needed to accurately estimate mortality of birds and bats at solar facilities. In the absence of such guidelines, ad hoc methodologies applied to solar energy projects may lead to estimates of wildlife mortality rates that are insufficiently accurate and precise to meaningfully inform conversations regarding unintended consequences of this energy source and management decisions to mitigate impacts. Although significant advances in monitoring protocols for wind facilities have been made in recent years, there remains a need to provide consistent guidance and study design to quantify mortality of bats, and resident and migrating birds at solar power facilities (Walston and others, 2015).In this document, we suggest methods for mortality monitoring at solar facilities that are based on current methods used at wind power facilities but adapted for the

  11. Probabilistic risk assessment for the Los Alamos Meson Physics Facility worst-case design-basis accident

    International Nuclear Information System (INIS)

    Sharirli, M.; Butner, J.M.; Rand, J.L.; Macek, R.J.; McKinney, S.J.; Roush, M.L.

    1992-01-01

    This paper presents results from a Los Alamos National Laboratory Engineering and Safety Analysis Group assessment of the worse-case design-basis accident associated with the Clinton P. Anderson Meson Physics Facility (LAMPF)/Weapons Neutron Research (WNR) Facility. The primary goal of the analysis was to quantify the accident sequences that result in personnel radiation exposure in the WNR Experimental Hall following the worst-case design-basis accident, a complete spill of the LAMPF accelerator 1L beam. This study also provides information regarding the roles of hardware systems and operators in these sequences, and insights regarding the areas where improvements can increase facility-operation safety. Results also include confidence ranges to incorporate combined effects of uncertainties in probability estimates and importance measures to determine how variations in individual events affect the frequencies in accident sequences

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  13. A Facilities Manager's Guide to Green Building Design.

    Science.gov (United States)

    Simpson, Walter

    2001-01-01

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

  14. Use of risk information to safety regulation. Reprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  15. Waste Management Facilities Cost Information report for Greater-Than-Class C and DOE equivalent special case waste

    Energy Technology Data Exchange (ETDEWEB)

    Feizollahi, F.; Shropshire, D.

    1993-07-01

    This Waste Management Facility Cost Information (WMFCI) report for Greater-Than-Class C low-level waste (GTCC LLW) and DOE equivalent special case waste contains preconceptual designs and planning level life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities needed for management of GTCC LLW and DOE equivalent waste. The report contains information on 16 facilities (referred to as cost modules). These facilities are treatment facility front-end and back-end support functions (administration support, and receiving, preparation, and shipping cost modules); seven treatment concepts (incineration, metal melting, shredding/compaction, solidification, vitrification, metal sizing and decontamination, and wet/air oxidation cost modules); two storage concepts (enclosed vault and silo); disposal facility front-end functions (disposal receiving and inspection cost module); and four disposal concepts (shallow-land, engineered shallow-land, intermediate depth, and deep geological cost modules). Data in this report allow the user to develop PLCC estimates for various waste management options. A procedure to guide the U.S. Department of Energy (DOE) and its contractor personnel in the use of estimating data is also included in this report.

  16. Waste Management Facilities Cost Information report for Greater-Than-Class C and DOE equivalent special case waste

    International Nuclear Information System (INIS)

    Feizollahi, F.; Shropshire, D.

    1993-07-01

    This Waste Management Facility Cost Information (WMFCI) report for Greater-Than-Class C low-level waste (GTCC LLW) and DOE equivalent special case waste contains preconceptual designs and planning level life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities needed for management of GTCC LLW and DOE equivalent waste. The report contains information on 16 facilities (referred to as cost modules). These facilities are treatment facility front-end and back-end support functions (administration support, and receiving, preparation, and shipping cost modules); seven treatment concepts (incineration, metal melting, shredding/compaction, solidification, vitrification, metal sizing and decontamination, and wet/air oxidation cost modules); two storage concepts (enclosed vault and silo); disposal facility front-end functions (disposal receiving and inspection cost module); and four disposal concepts (shallow-land, engineered shallow-land, intermediate depth, and deep geological cost modules). Data in this report allow the user to develop PLCC estimates for various waste management options. A procedure to guide the U.S. Department of Energy (DOE) and its contractor personnel in the use of estimating data is also included in this report

  17. Design and operation of radiation facilities

    International Nuclear Information System (INIS)

    Gay, H.G.

    1983-01-01

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

  18. The FAO/IAEA interactive spreadsheet for design and operation of insect mass rearing facilities

    International Nuclear Information System (INIS)

    Caceres, Carlos; Rendon, Pedro

    2006-01-01

    An electronic spreadsheet is described which helps users to design, equip and operate facilities for the mass rearing of insects for use in insect pest control programmes integrating the sterile insect technique. The spreadsheet was designed based on experience accumulated in the mass rearing of the Mediterranean fruit fly, Ceratitis capitata (Wiedemann), using genetic sexing strains based on a temperature sensitive lethal (tsl) mutation. The spreadsheet takes into account the biological, production, and quality control parameters of the species to be mass reared, as well as the diets and equipment required. All this information is incorporated into the spreadsheet for user-friendly calculation of the main components involved in facility design and operation. Outputs of the spreadsheet include size of the different rearing areas, rearing equipment, volumes of diet ingredients, other consumables, as well as personnel requirements. By adding cost factors to these components, the spreadsheet can estimate the costs of facility construction, equipment, and operation. All the output parameters can be easily generated by simply entering the target number of sterile insects required per week. For other insect species, the biological and production characteristics need to be defined and inputted accordingly to obtain outputs relevant to these species. This spreadsheet, available under http://www-naweb.iaea.org/nafa/ipc/index.html, is a powerful tool for project and facility managers as it can be used to estimate facility cost, production cost, and production projections under different rearing efficiency scenarios. (author)

  19. The FAO/IAEA interactive spreadsheet for design and operation of insect mass rearing facilities

    Energy Technology Data Exchange (ETDEWEB)

    Caceres, Carlos, E-mail: carlos.e.caceres@aphis.usda.co [International Atomic Energy Agency (IAEA), Seibersdorf (Austria). Agency' s Labs. Programme of Nuclear Techniques in Food and Agriculture; Rendon, Pedro [U.S. Department of Agriculture (USDA/APHIS/CPHST), Guatemala City (Guatemala). Animal and Plant Health Inspection. Center for Plant Health Science and Technology

    2006-07-01

    An electronic spreadsheet is described which helps users to design, equip and operate facilities for the mass rearing of insects for use in insect pest control programmes integrating the sterile insect technique. The spreadsheet was designed based on experience accumulated in the mass rearing of the Mediterranean fruit fly, Ceratitis capitata (Wiedemann), using genetic sexing strains based on a temperature sensitive lethal (tsl) mutation. The spreadsheet takes into account the biological, production, and quality control parameters of the species to be mass reared, as well as the diets and equipment required. All this information is incorporated into the spreadsheet for user-friendly calculation of the main components involved in facility design and operation. Outputs of the spreadsheet include size of the different rearing areas, rearing equipment, volumes of diet ingredients, other consumables, as well as personnel requirements. By adding cost factors to these components, the spreadsheet can estimate the costs of facility construction, equipment, and operation. All the output parameters can be easily generated by simply entering the target number of sterile insects required per week. For other insect species, the biological and production characteristics need to be defined and inputted accordingly to obtain outputs relevant to these species. This spreadsheet, available under http://www-naweb.iaea.org/nafa/ipc/index.html, is a powerful tool for project and facility managers as it can be used to estimate facility cost, production cost, and production projections under different rearing efficiency scenarios. (author)

  20. Design of good manufacturing facility for sterile radioactive pharmaceuticals

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  1. UTN's gamma irradiation facility: design and concept

    International Nuclear Information System (INIS)

    Mohamad Noor Mohamad Yunus

    1986-01-01

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

  2. Conceptual Design of an In-Space Cryogenic Fluid Management Facility

    Science.gov (United States)

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

    1981-01-01

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

  3. Proactive information provision for reducing social construct risk of nuclear facility

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Takahashi, Makoto; Hashizume, Hidetoshi; Shiraishi, Natsuki; Yagi, Ekou

    2006-01-01

    Outlines of, and the empirical observations from, an action research project aiming at improvement of relationship between nuclear community and the public have been reported in this paper. Ultimate goal of the project is effective reduction of social construct risk of nuclear power plants. As an initial approach to the goal, a proactive information provision scheme has been designed based on the knowledge acquired during our previous attempt of public communication named repetitive dialogue forum. The information contents consistent with the actual need of local citizens has been derived from the previous experiences and provided in the present project. Although the project is in its incipient stage, the observations are informative enough to develop the project further to attain the ultimate purpose of reducing the social construct component of technological risk of nuclear facilities. (author)

  4. Evaluation of seismic criteria used in design of INEL facilities

    International Nuclear Information System (INIS)

    Young, G.A.

    1977-01-01

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

  5. Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

  6. Biological Information Document, Radioactive Liquid Waste Treatment Facility

    International Nuclear Information System (INIS)

    Biggs, J.

    1995-01-01

    This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposed Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area

  7. Biological Information Document, Radioactive Liquid Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Biggs, J.

    1995-12-31

    This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposed Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area.

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

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

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

  9. PIMS sequencing extension: a laboratory information management system for DNA sequencing facilities

    Directory of Open Access Journals (Sweden)

    Baldwin Stephen A

    2011-03-01

    Full Text Available Abstract Background Facilities that provide a service for DNA sequencing typically support large numbers of users and experiment types. The cost of services is often reduced by the use of liquid handling robots but the efficiency of such facilities is hampered because the software for such robots does not usually integrate well with the systems that run the sequencing machines. Accordingly, there is a need for software systems capable of integrating different robotic systems and managing sample information for DNA sequencing services. In this paper, we describe an extension to the Protein Information Management System (PIMS that is designed for DNA sequencing facilities. The new version of PIMS has a user-friendly web interface and integrates all aspects of the sequencing process, including sample submission, handling and tracking, together with capture and management of the data. Results The PIMS sequencing extension has been in production since July 2009 at the University of Leeds DNA Sequencing Facility. It has completely replaced manual data handling and simplified the tasks of data management and user communication. Samples from 45 groups have been processed with an average throughput of 10000 samples per month. The current version of the PIMS sequencing extension works with Applied Biosystems 3130XL 96-well plate sequencer and MWG 4204 or Aviso Theonyx liquid handling robots, but is readily adaptable for use with other combinations of robots. Conclusions PIMS has been extended to provide a user-friendly and integrated data management solution for DNA sequencing facilities that is accessed through a normal web browser and allows simultaneous access by multiple users as well as facility managers. The system integrates sequencing and liquid handling robots, manages the data flow, and provides remote access to the sequencing results. The software is freely available, for academic users, from http://www.pims-lims.org/.

  10. PIMS sequencing extension: a laboratory information management system for DNA sequencing facilities.

    Science.gov (United States)

    Troshin, Peter V; Postis, Vincent Lg; Ashworth, Denise; Baldwin, Stephen A; McPherson, Michael J; Barton, Geoffrey J

    2011-03-07

    Facilities that provide a service for DNA sequencing typically support large numbers of users and experiment types. The cost of services is often reduced by the use of liquid handling robots but the efficiency of such facilities is hampered because the software for such robots does not usually integrate well with the systems that run the sequencing machines. Accordingly, there is a need for software systems capable of integrating different robotic systems and managing sample information for DNA sequencing services. In this paper, we describe an extension to the Protein Information Management System (PIMS) that is designed for DNA sequencing facilities. The new version of PIMS has a user-friendly web interface and integrates all aspects of the sequencing process, including sample submission, handling and tracking, together with capture and management of the data. The PIMS sequencing extension has been in production since July 2009 at the University of Leeds DNA Sequencing Facility. It has completely replaced manual data handling and simplified the tasks of data management and user communication. Samples from 45 groups have been processed with an average throughput of 10000 samples per month. The current version of the PIMS sequencing extension works with Applied Biosystems 3130XL 96-well plate sequencer and MWG 4204 or Aviso Theonyx liquid handling robots, but is readily adaptable for use with other combinations of robots. PIMS has been extended to provide a user-friendly and integrated data management solution for DNA sequencing facilities that is accessed through a normal web browser and allows simultaneous access by multiple users as well as facility managers. The system integrates sequencing and liquid handling robots, manages the data flow, and provides remote access to the sequencing results. The software is freely available, for academic users, from http://www.pims-lims.org/.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-11-15

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  13. Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)

    International Nuclear Information System (INIS)

    VINCENT, Andrew

    2005-01-01

    In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the

  14. Designing information systems

    CERN Document Server

    Blethyn, Stanley G

    2014-01-01

    Designing Information Systems focuses on the processes, methodologies, and approaches involved in designing information systems. The book first describes systems, management and control, and how to design information systems. Discussions focus on documents produced from the functional construction function, users, operators, analysts, programmers and others, process management and control, levels of management, open systems, design of management information systems, and business system description, partitioning, and leveling. The text then takes a look at functional specification and functiona

  15. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

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

  16. Design of the target area for the National Ignition Facility

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  17. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Elder, J.; Graf, J.M.

    1984-01-01

    DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

  18. The arrangement of the seismic design method of the underground facility

    International Nuclear Information System (INIS)

    Tanai, Kenji; Horita, Masakuni; Dewa, Katsuyuki; Gouke, Mitsuo

    2002-03-01

    Earthquake resistance for the underground structure is higher than the ground structure. Therefore, the case of examining the earthquake resistance of underground structure was little. However, it carries out the research on the aseismic designing method of underground structure, since the tunnel was struck by Hyogo-ken Nanbu Earthquake, and it has obtained a much knowledge. However, an object of the most study was behavior at earthquake of the comparatively shallow underground structure in the alluvial plain board, and it not carry out the examination on behavior at earthquake of underground structure in the deep rock mass. In the meantime, underground disposal facility of the high level radioactive waste constructs in the deep underground, and it carries out the operation in these tunnels. In addition, it has made almost the general process of including from the construction start to the backfilling to be about 60 years (Japan Nuclear Fuel Cycle Development Institute, 1999). During these periods, it is necessary to also consider the earthquake resistance as underground structure from the viewpoint of the safety of facilities. Then, it extracted future problem as one of the improvement of the basis information for the decision of the safety standard and guideline of the country on earthquake-resistant design of the underground disposal facility, while it carried out investigation and arrangement of earthquake-resistant design cases, guidelines and analysis method on existing underground structure, etc. And, the research items for the earthquake resistance assessment of underground structure as case study of the underground research laboratory. (author)

  19. Adding Value to Facilities Management with Information Technology

    DEFF Research Database (Denmark)

    Ebbesen, Poul

    2016-01-01

    This PhD project investigates implementation and use of Information Systems (IS) and Information Technologies (IT) in the Facilities management (FM) business domain. This investigation is relevant because implementation and use of IS/IT in FM has potentials for improvements which can provide...

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

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  1. Conceptual design of the National Ignition Facility

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  2. The 'MELUSINE' reactor at Grenoble, France, and associated hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the MELUSINE reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities and specialized irradiation devices (loops and capsules). The information is presented in the form of six information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities

  3. Exploratory shaft facility preliminary designs - Paradox Basin. Technical report

    International Nuclear Information System (INIS)

    1983-09-01

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

  4. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  5. Determinants of quality of shared sanitation facilities in informal settlements: case study of Kisumu, Kenya

    Directory of Open Access Journals (Sweden)

    Sheillah Simiyu

    2017-01-01

    Full Text Available Abstract Background Shared facilities are not recognised as improved sanitation due to challenges of maintenance as they easily can be avenues for the spread of diseases. Thus there is need to evaluate the quality of shared facilities, especially in informal settlements, where they are commonly used. A shared facility can be equated to a common good whose management depends on the users. If users do not work collectively towards keeping the facility clean, it is likely that the quality may depreciate due to lack of maintenance. This study examined the quality of shared sanitation facilities and used the common pool resource (CPR management principles to examine the determinants of shared sanitation quality in the informal settlements of Kisumu, Kenya. Methods Using a multiple case study design, the study employed both quantitative and qualitative methods. In both phases, users of shared sanitation facilities were interviewed, while shared sanitation facilities were inspected. Shared sanitation quality was a score which was the dependent variable in a regression analysis. Interviews during the qualitative stage were aimed at understanding management practices of shared sanitation users. Qualitative data was analysed thematically by following the CPR principles. Results Shared facilities, most of which were dirty, were shared by an average of eight households, and their quality decreased with an increase in the number of households sharing. The effect of numbers on quality is explained by behaviour reflected in the CPR principles, as it was easier to define boundaries of shared facilities when there were fewer users who cooperated towards improving their shared sanitation facility. Other factors, such as defined management systems, cooperation, collective decision making, and social norms, also played a role in influencing the behaviour of users towards keeping shared facilities clean and functional. Conclusion Apart from hardware factors, quality

  6. Information Design Theories

    Science.gov (United States)

    Pettersson, Rune

    2014-01-01

    Information design has practical and theoretical components. As an academic discipline we may view information design as a combined discipline, a practical theory, or as a theoretical practice. So far information design has incorporated facts, influences, methods, practices, principles, processes, strategies, and tools from a large number of…

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

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  8. Final design of ITER port plug test facility

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-11-01

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

  9. Designing Animation Facilities for gCSP

    NARCIS (Netherlands)

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

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

  10. 75 FR 78952 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-12-17

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants; Commonwealth of Virginia; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative... Quality, 629 East Main Street, Richmond, Virginia 23219. FOR FURTHER INFORMATION CONTACT: James B. Topsale...

  11. The 'SILOE' reactor at Grenoble, France and associated hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the SILOE reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  12. The 'OSIRIS' reactor at Saclay, France and available hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the OSIRIS reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

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

    International Nuclear Information System (INIS)

    Austad, Stephanie Lee

    2015-01-01

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

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

    International Nuclear Information System (INIS)

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

    2012-04-01

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

  15. Shielding design for positron emission tomography facility

    International Nuclear Information System (INIS)

    Abdallah, I.I.

    2007-01-01

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

  16. Corrosion behaviour of steel rebars embedded in a concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    Directory of Open Access Journals (Sweden)

    Schulz F.M.

    2013-07-01

    Full Text Available The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on an instrumented reinforced concrete prototype specifically designed for this purpose, to study the behaviour of an intermediate level radioactive waste disposal facility from the rebar corrosion point of view. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

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

    International Nuclear Information System (INIS)

    1986-11-01

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

  18. Hanford Facility dangerous waste permit application, general information

    International Nuclear Information System (INIS)

    1993-05-01

    The current Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, number DOE/RL-91-28) and a treatment, storage, and/or disposal Unit-Specific Portion, which includes documentation for individual TSD units (e.g., document numbers DOE/RL-89-03 and DOE/RL-90-01). Both portions consist of a Part A division and a Part B division. The Part B division consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. Documentation contained in the General Information Portion (i.e., this document, number DOE/RL-91-28) is broader in nature and applies to all treatment, storage, and/or disposal units for which final status is sought. Because of its broad nature, the Part A division of the General Information Portion references the Hanford Facility Dangerous Waste Part A Permit Application (document number DOE/RL-88-21), a compilation of all Part A documentation for the Hanford Facility

  19. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

    Science.gov (United States)

    Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

    1981-01-01

    A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

  20. Improving emergency management through shared information processing - considerations in Emergency Operations Center design

    International Nuclear Information System (INIS)

    DeBusk, R.E.; Walker, J.A.

    1987-01-01

    An Emergency Operations Center (EOC) is a shared information processing facility. Although seemingly obvious, many EOCs are designed and operated based on other criteria. The results, measured in terms of response effectiveness, are difficult to determine. A review of some recent disasters reveals a pattern of poor performance for the EOCs involved. These conclusions are tentative because so little research has been done on the design, operation, or evaluation of emergency operations centers. The EOC is not an onsite response command post but a facility removed from the response where tactical and strategic decisions are made based on information from the response site and elsewhere. The EOC is therefore the central focus of emergency information processing and higher-level decision making. Examining existing EOCs, several common functions emerge. These functions can be described in terms of shared information processing. However, many factors impact the design and operation of EOCs. Politics, budgets, and personal ambition are only a few such factors. Examining EOC design and operation in terms of shared information processing operationalized in the seven principal functions within the EOC provides a framework for establishing principles of EOC design and operation. In the response to emergencies such as Bhopal or Chernobyl the stakes are high. Applying new techniques and technologies of management systems can improve the probability of success. This research is a beginning step - to understand how EOCs function, to define the system. Predictive or prescriptive analysis must wait until sufficient empirical data is available to complete a descriptive model for EOC operations

  1. Assessing and addressing increased stakeholder and operator information needs in nuclear fuel cycle facilities: two concepts

    Energy Technology Data Exchange (ETDEWEB)

    Saltiel, David H. [Sandia National Laboratories, Albuquerque (United States)

    2007-12-15

    Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the 'designing-in' of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance.

  2. Assessing and addressing increased stakeholder and operator information needs in nuclear fuel cycle facilities: two concepts

    International Nuclear Information System (INIS)

    Saltiel, David H.

    2007-01-01

    Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the 'designing-in' of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance

  3. Utilities and offsites design baseline. Outside Battery Limits Facility 6000 tpd SRC-I Demonstration Plant. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-05-25

    As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials and product handling and storage information. Volume V contains wastewater treatment and solid wastes landfill systems developed by Catalytic, Inc. to supplement the information contained in Volume III. Volume VI contains proprietary information of Resources Conservation Company related to the evaporator/crystallizer system of the wastewater treatment area.

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

    International Nuclear Information System (INIS)

    1985-10-01

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

  5. 75 FR 73967 - Approval and Promulgation of State Air Quality Plans for Designated Facilities and Pollutants...

    Science.gov (United States)

    2010-11-30

    ... Promulgation of State Air Quality Plans for Designated Facilities and Pollutants, State of Delaware; Control of Emissions From Existing Hospital/Medical/Infectious Waste Incinerator (HMIWI) Units, Negative Declaration... Environmental Control, 89 Kings Highway, P.O. Box 1401, Dover, Delaware 19903. FOR FURTHER INFORMATION CONTACT...

  6. A strategic approach to the conceptual design of complex radwaste facilities

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  7. E-4 Test Facility Design Status

    Science.gov (United States)

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

    2001-01-01

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

  8. Design information verification for spent fuel conditioning plants and for geological repositories

    International Nuclear Information System (INIS)

    Myatt, J.; Ward, M.D.

    1995-01-01

    The disposal of spent fuel is a major option for the back-end of the nuclear fuel cycle. It will require the construction, operation and eventual closure of conditioning plants and geological repositories. Consequently, a safeguards approach including Design Information Verification (DIV) must be developed for these facilities. DIV Is the examination of a completed facility to verify that it has been built to the design declared by the operator. Although DIV takes place chiefly before a plant begins routine operation, there is a continuing interest in ensuring that the plant remains as declared. That is, that the continuity of knowledge of design information is maintained during the operational phase of the plant and also post closure if necessary. A major problem with DIV of a repository is that there will be continuous structural changes during its operational life requiring advanced or special techniques for reverification. Some of these are briefly reviewed. Furthermore, since a disposal facility is expected to be operational for several decades, new mining technology may also have an impact on the DIV methods employed. Another factor in the safeguards supervision of a repository is that when the fuel has been backfilled and/or scaled in place a reassay will be a very costly exercise. The role of DIV in such novel circumstances must, therefore, be fully considered

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

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

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  11. Guidelines for Management Information Systems in Canadian Health Care Facilities

    Science.gov (United States)

    Thompson, Larry E.

    1987-01-01

    The MIS Guidelines are a comprehensive set of standards for health care facilities for the recording of staffing, financial, workload, patient care and other management information. The Guidelines enable health care facilities to develop management information systems which identify resources, costs and products to more effectively forecast and control costs and utilize resources to their maximum potential as well as provide improved comparability of operations. The MIS Guidelines were produced by the Management Information Systems (MIS) Project, a cooperative effort of the federal and provincial governments, provincial hospital/health associations, under the authority of the Canadian Federal/Provincial Advisory Committee on Institutional and Medical Services. The Guidelines are currently being implemented on a “test” basis in ten health care facilities across Canada and portions integrated in government reporting as finalized.

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

    International Nuclear Information System (INIS)

    1975-12-01

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

  13. Earthquake resistant design of nuclear facilities with limited radioactive inventory

    International Nuclear Information System (INIS)

    1985-10-01

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

  14. Greening Federal Facilities: An Energy, Environmental, and Economic Resource Guide for Federal Facility Managers and Designers; Second Edition

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, A.

    2001-05-16

    Greening Federal Facilities, Second Edition, is a nuts-and-bolts resource guide compiled to increase energy and resource efficiency, cut waste, and improve the performance of Federal buildings and facilities. The guide highlights practical actions that facility managers, design and construction staff, procurement officials, and facility planners can take to save energy and money, improve the comfort and productivity of employees, and benefit the environment. It supports a national effort to promote energy and environmental efficiency in the nation's 500,000 Federal buildings and facilities. Topics covered include current Federal regulations; environmental and energy decision-making; site and landscape issues; building design; energy systems; water and wastewater; materials; waste management, and recycling; indoor environmental quality; and managing buildings.

  15. Design of an integrated non-destructive plutonium assay facility

    International Nuclear Information System (INIS)

    Moore, C.B.

    1984-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-09-01

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

  17. Hanford facility dangerous waste permit application, general information portion

    International Nuclear Information System (INIS)

    Hays, C.B.

    1998-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in this report)

  18. Configuration system development of site and environmental information for radwaste disposal facility

    International Nuclear Information System (INIS)

    Park, Se-Moon; Yoon, Bong-Yo; Kim, Chang-Lak

    2005-01-01

    License for the nuclear facilities such as radioactive waste repository demands documents of site characterization, environmental assessment and safety assessment. This performance will produce bulk of the relevant data. For the safe management of radioactive waste repository, data of the site and environment have to be collected and managed systematically. Particularly for the radwaste repository, which has to be institutionally controlled for a long period after closure, the data will be collected and maintained through the monitoring programme. To meet this requirement, a new programme called 'Site Information and Total Environmental data management System (SITES)' has been developed. The scope and function of the SITES is issued in data DB, safety assessment and monitoring system. In this respect, SITES is designed with two modules of the SITES Database Module (SDM) and the Monitoring and Assesment (M and A). The SDM module is composed of three sub-modules. One is the Site Information Management System (SIMS), which manages data of site characterization such as topography, geology, hydrogeology, engineering geology, etc. The other is the ENVironmental Information management System (ENVIS) and Radioactive ENVironmental Information management System (RENVIS), which manage environmental data required for environmental assessment performance. ENVIS and RENVIS covered almost whole items of environmental assessment report required by Korean government. The SDM was constructed based on Entity Relationship Diagram produced from each item. Also using ArcGIS with the spatial characteristics of the data, it enables groundwater and water property monitoring networks, etc. To be analyzed in respect of every theme. The sub-modules of M and A called the Site and Environment Monitoring System (SEMS) and the Safety Assessment System (SAS) were developed. SEMS was designed to manage the inspection records of the individual measuring instruments and facilities, and the on

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

    Science.gov (United States)

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

    1990-01-01

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

  20. Sound & Vibration 20 Design Guidelines for Health Care Facilities

    CERN Document Server

    Tocci, Gregory; Cavanaugh, William

    2013-01-01

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

  1. Conceptual design of initial opacity experiments on the national ignition facility

    Science.gov (United States)

    Heeter, R. F.; Bailey, J. E.; Craxton, R. S.; Devolder, B. G.; Dodd, E. S.; Garcia, E. M.; Huffman, E. J.; Iglesias, C. A.; King, J. A.; Kline, J. L.; Liedahl, D. A.; McKenty, P. W.; Opachich, Y. P.; Rochau, G. A.; Ross, P. W.; Schneider, M. B.; Sherrill, M. E.; Wilson, B. G.; Zhang, R.; Perry, T. S.

    2017-02-01

    Accurate models of X-ray absorption and re-emission in partly stripped ions are necessary to calculate the structure of stars, the performance of hohlraums for inertial confinement fusion and many other systems in high-energy-density plasma physics. Despite theoretical progress, a persistent discrepancy exists with recent experiments at the Sandia Z facility studying iron in conditions characteristic of the solar radiative-convective transition region. The increased iron opacity measured at Z could help resolve a longstanding issue with the standard solar model, but requires a radical departure for opacity theory. To replicate the Z measurements, an opacity experiment has been designed for the National Facility (NIF). The design uses established techniques scaled to NIF. A laser-heated hohlraum will produce X-ray-heated uniform iron plasmas in local thermodynamic equilibrium (LTE) at temperatures eV and electron densities 21~\\text{cm}-3$ . The iron will be probed using continuum X-rays emitted in a ps, diameter source from a 2 mm diameter polystyrene (CH) capsule implosion. In this design, of the NIF beams deliver 500 kJ to the mm diameter hohlraum, and the remaining directly drive the CH capsule with 200 kJ. Calculations indicate this capsule backlighter should outshine the iron sample, delivering a point-projection transmission opacity measurement to a time-integrated X-ray spectrometer viewing down the hohlraum axis. Preliminary experiments to develop the backlighter and hohlraum are underway, informing simulated measurements to guide the final design.

  2. Design and Construction of a Hydroturbine Test Facility

    Science.gov (United States)

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

    2014-11-01

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

  3. Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

  4. Secure Retrieval of FFTF Testing, Design, and Operating Information

    International Nuclear Information System (INIS)

    Butner, R. Scott; Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah

    2009-01-01

    One of the goals of the Advanced Fuel Cycle Initiative (AFCI) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMR). In addition, preserving LMR information and knowledge is part of a larger international collaborative activity conducted under the auspices of the International Atomic Energy Agency (IAEA). A similar program is being conducted for EBR-II at the Idaho Nuclear Laboratory (INL) and international programs are also in progress. Knowledge preservation at the FFTF is focused on the areas of design, construction, startup, and operation of the reactor. As the primary function of the FFTF was testing, the focus is also on preserving information obtained from irradiation testing of fuels and materials. This information will be invaluable when, at a later date, international decisions are made to pursue new LMRs. In the interim, this information may be of potential use for international exchanges with other LMR programs around the world. At least as important in the United States, which is emphasizing large-scale computer simulation and modeling, this information provides the basis for creating benchmarks for validating and testing these large scale computer programs. Although the preservation activity with respect to FFTF information as discussed below is still underway, the team of authors above is currently retrieving and providing experimental and design information to the LMR modeling and simulation efforts for use in validating their computer models. On the Hanford Site, the FFTF reactor plant is one of the facilities intended for decontamination and decommissioning consistent with the cleanup mission on this site. The reactor facility has been deactivated and is being maintained in a cold and dark minimal surveillance and maintenance mode until final decommissioning is pursued. In order to ensure protection of information at risk, the program to date has focused on sequestering and secure retrieval

  5. Design Integration of Facilities Management

    DEFF Research Database (Denmark)

    Jensen, Per Anker

    2009-01-01

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

  6. DOE handbook: Design considerations

    International Nuclear Information System (INIS)

    1999-04-01

    The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline

  7. DOE handbook: Design considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-04-01

    The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline.

  8. Design and operations at the National Tritium Labelling Facility

    International Nuclear Information System (INIS)

    Morimoto, H.; Williams, P.G.

    1991-09-01

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

  9. Engineering test facility design definition

    Science.gov (United States)

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

    1980-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-10-01

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

  11. Structural design considerations for a radwaste processing facility

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  12. Incorporating design for decommissioning into the layout of nuclear facilities

    International Nuclear Information System (INIS)

    Collum, B.; Druart, A.

    2008-01-01

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

  13. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 4: Supplementary engineering data

    Science.gov (United States)

    1981-01-01

    The reference conceptual design of the Magnetohydrodynamic Engineering Test Facility (ETF), a prototype 200 MWe coal-fired electric generating plant designed to demonstrate the commercial feasibility of open cycle MHD is summarized. Main elements of the design are identified and explained, and the rationale behind them is reviewed. Major systems and plant facilities are listed and discussed. Construction cost and schedule estimates, and identification of engineering issues that should be reexamined are also given. The latest (1980-1981) information from the MHD technology program are integrated with the elements of a conventional steam power electric generating plant. Supplementary Engineering Data (Issues, Background, Performance Assurance Plan, Design Details, System Design Descriptions and Related Drawings) is presented.

  14. The DIDO-reactor at Harwell, U.K. and ancillary hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the DIDO reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  15. Important changes in medical x-ray imaging facility shielding design methodology. A brief summary of recommendations in NCRP Report No. 147

    International Nuclear Information System (INIS)

    Archer, Benjamin R.; Gray, Joel E.

    2005-01-01

    The recently published Report No. 147 of The National Council on Radiation Protection and Measurements entitled 'Structural shielding design for medical x-ray imaging facilities' provides an update of shielding recommendations for x rays used for medical imaging. The goal of this report is to ensure that the shielding in these facilities limits radiation exposures to employees and members of the public to acceptable levels. Board certified medical and health physicists, as defined in this report, are the 'qualified experts' who are competent to design radiation shielding for these facilities. As such, physicists must be aware of the new technical information and the changes from previous reports that Report No. 147 supersedes. In this article we summarize the new data, models and recommendations for the design of radiation barriers in medical imaging facilities that are presented in Report No. 147

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  17. Application of information and communication technology facilities in ...

    African Journals Online (AJOL)

    ... technology facilities in technical services operations at Bayero University library, Nigeria. ... Victoria Sokari, Umar Garba Gama, Zanaib Abba Haliru, Kemi J. Olayemi, ... This paper examines the application of Information and Communication ...

  18. A Proposal to Develop a Biotechnology Information Facility

    National Research Council Canada - National Science Library

    Spalding, John

    2002-01-01

    The objective of this grant was to develop facilities and information resources that support current research in biotechnology and to meet the goal of strengthening the biological science programs at HBCUs/Mls...

  19. People-oriented Information Visualization Design

    Science.gov (United States)

    Chen, Zhiyong; Zhang, Bolun

    2018-04-01

    In the 21st century with rapid development, in the wake of the continuous progress of science and technology, human society enters the information era and the era of big data, and the lifestyle and aesthetic system also change accordingly, so the emerging field of information visualization is increasingly popular. Information visualization design is the process of visualizing all kinds of tedious information data, so as to quickly accept information and save time-cost. Along with the development of the process of information visualization, information design, also becomes hotter and hotter, and emotional design, people-oriented design is an indispensable part of in the design of information. This paper probes information visualization design through emotional analysis of information design based on the social context of people-oriented experience from the perspective of art design. Based on the three levels of emotional information design: instinct level, behavior level and reflective level research, to explore and discuss information visualization design.

  20. Design issues for a laboratory high gain fusion facility

    International Nuclear Information System (INIS)

    Hogan, W.J.

    1987-01-01

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

  1. Exploratory shaft facility preliminary designs - Gulf Interior Region salt domes

    International Nuclear Information System (INIS)

    1983-09-01

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

  2. Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

    International Nuclear Information System (INIS)

    Dippre, M. A.

    2003-01-01

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

  3. Requirements and design concept for a facility mapping system

    International Nuclear Information System (INIS)

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

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

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

  5. Building Design Guidelines for Interior Architecture Concerned with Animal Researches Facilities

    International Nuclear Information System (INIS)

    ElDib, A.A. E.

    2014-01-01

    This paper discusses the most important design guidelines elements and characteristics for animal facilities, in order to achieve and maintain highest efficiency can be, with respect to the pivot role of Interior Architecture as one of the accurate specializations for completing the Architectural Sciences, for designer/s concerned with those types of facilities, (specially those using radioactive materials). These building types known as vivariums, are specially designed, accommodating and having sophisticated controlled environments for the care and maintenance of experimental animals, and are related to, but distinct from other research laboratories premises

  6. Spent Nuclear Fuel Cold Vacuum Drying facility comprehensive formal design review report

    International Nuclear Information System (INIS)

    HALLER, C.S.

    1999-01-01

    The majority of the Cold Vacuum Drying Facility (CVDF) design and construction is complete; isolated portions are still in the design and fabrication process. The project commissioned a formal design review to verify the sufficiency and accuracy of current design media to assure that: (1) the design completely and accurately reflects design criteria, (2) design documents are consistent with one another, and (3) the design media accurately reflects the current design. This review is a key element in the design validation and verification activities required by SNF-4396, ''Design Verification and Validation Plan For The Cold Vacuum Drying Facility''. This report documents the results of the formal design review

  7. Radiation shielding design for a hot repair facility

    International Nuclear Information System (INIS)

    Courtney, J.C.; Dwight, C.C.

    1991-01-01

    A new repair and decontamination area is being built to support operations at the demonstration fuel cycle facility for the Integral Fast Reactor program at Argonne National Laboratory's site at the Idaho National Engineering Laboratory. Provisions are made for remote, glove wall, and contact maintenance on equipment removed from hot cells where spent fuel will be electrochemically processed and recycled to the Experimental Breeder Reactor-II. The source for the shielding design is contamination from a mix of fission and activation products present on items removed from the hot cells. The repair facility also serves as a transfer path for radioactive waste produced by processing operations. Radiation shields are designed to limit dose rates to no more than 5 microSv h-1 (0.5 mrem h-1) in normally occupied areas. Point kernel calculations with buildup factors have been used to design the shielding and to position radiation monitors within the area

  8. Over facility design description for the CPDF [Centrifuge Plant Demonstration Facility]: SDD-1 [System Design Description

    International Nuclear Information System (INIS)

    1987-04-01

    The Centrifuge Plant Demonstration Facility (CPDF) is an essential part of the continuing development of first-production-plant centrifuge technology that will integrate centrifuge machines into a process and enrichment plant design. The CPDF will provide facilities for testing and continued development of a unit cascade in direct support of the commercial Gas Centrifuge Enrichment Plant (GCEP). The basic cascade-oriented equipment, feed, withdrawal, drive system, process piping, utility piping, and other auxiliary and support equipment will be tested in an operating configuration that represents, to the extent possible, GCEP arrangement and operating conditions. The objective will be to demonstrate procedures for production cascade installation, start-up, operation, and maintenance, and to provide proof of overall cascade and associated system design, construction, and operating and maintenance concepts. To the maximum possible extent, all equipment for the CPDF will be procured from commercial sources. Centrifuges will be procured from industry using government-supplied specifications and drawings. The existing Component Preparation Laboratory (CPL) located near the CPDF site will be used for centrifuge component receiving, inspection, assembly, and qualification testing of pre-production test machines. Later in the test program, samples of production machines planned for use in the GCEP will be tested in the CPDF

  9. Mechanical Design and Manufacturing Preparation of Loading Unloading Irradiation Facility in Reflector Irradiation Position

    International Nuclear Information System (INIS)

    Hasibuan, Djaruddin

    2004-01-01

    Base on planning to increase of the irradiation service quality in Multi purpose Reactor-GAS, the mechanical design and manufacturing of the (n,γ) irradiation facility has been done. The designed of (n,γ) irradiation facility is a new facility in Multi purpose Reactor-GAS. The design doing by design of stringer, guide bar and hanger. By the design installation, the continuous irradiation service of non fission reaction will be easy to be done without reactor shut down. The design of the facility needs 3 pieces Al pipe by 36 x 1.5 mm, a peace of Al round bar by 80 mm diameter and a piece of Al plate by 20 x 60 x 0.2 mm for the stringer and guide bar manufacturing. By the building of non fission irradiation facility in the reflector irradiation position, will make the irradiation service to be increased. (author)

  10. A performance goal-based seismic design philosophy for waste repository facilities

    International Nuclear Information System (INIS)

    Hossain, Q.A.

    1994-02-01

    A performance goal-based seismic design philosophy, compatible with DOE's present natural phenomena hazards mitigation and ''graded approach'' philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed

  11. Conceptual structure design of experimental facility for advanced spent fuel conditioning process

    International Nuclear Information System (INIS)

    Joo, J. S.; Koo, J. H.; Jung, W. M.; Jo, I. J.; Kook, D. H.; Yoo, K. S.

    2003-01-01

    A study on the advanced spent fuel conditioning process (ACP) is carring out for the effective management of spent fuels of domestic nuclear power plants. This study presents basic shielding design, modification of IMEF's reserve hot cell facility which reserved for future usage, conceptual and structural architecture design of ACP hot cell and its contents, etc. considering the characteristics of ACP. The results of this study will be used for the basic and detail design of ACP demonstration facility, and utilized as basic data for the safety evaluation as essential data for the licensing of the ACP facility

  12. Cancer risks near nuclear facilities: the importance of research design and explicit study hypotheses.

    Science.gov (United States)

    Wing, Steve; Richardson, David B; Hoffmann, Wolfgang

    2011-04-01

    In April 2010, the U.S. Nuclear Regulatory Commission asked the National Academy of Sciences to update a 1990 study of cancer risks near nuclear facilities. Prior research on this topic has suffered from problems in hypothesis formulation and research design. We review epidemiologic principles used in studies of generic exposure-response associations and in studies of specific sources of exposure. We then describe logical problems with assumptions, formation of testable hypotheses, and interpretation of evidence in previous research on cancer risks near nuclear facilities. Advancement of knowledge about cancer risks near nuclear facilities depends on testing specific hypotheses grounded in physical and biological mechanisms of exposure and susceptibility while considering sample size and ability to adequately quantify exposure, ascertain cancer cases, and evaluate plausible confounders. Next steps in advancing knowledge about cancer risks near nuclear facilities require studies of childhood cancer incidence, focus on in utero and early childhood exposures, use of specific geographic information, and consideration of pathways for transport and uptake of radionuclides. Studies of cancer mortality among adults, cancers with long latencies, large geographic zones, and populations that reside at large distances from nuclear facilities are better suited for public relations than for scientific purposes.

  13. Seismic design and analysis of nuclear fuel cycle facilities in France

    International Nuclear Information System (INIS)

    Sollogoub, P.

    2001-01-01

    Methodology for seismic design of nuclear fuel facilities and power plants in France is described. After the description of regulatory and normative texts for seismic design, different elements are examined: definition of ground motion, analysis methods, new trends, reevaluation and specificity of Fuel Cycle Facilities. R/D developments are explicated in each part. Their final objective are to better quantify the margins of each step which, in relation with safety analysis,lead to balanced design, analysis and retrofit rules. (author)

  14. New facility shield design criteria

    International Nuclear Information System (INIS)

    Howell, W.P.

    1981-07-01

    The purpose of the criteria presented here is to provide standard guidance for the design of nuclear radiation shields thoughout new facilities. These criteria are required to assure a consistent and integrated design that can be operated safely and economically within the DOE standards. The scope of this report is confined to the consideration of radiation shielding for contained sources. The whole body dose limit established by the DOE applies to all doses which are generally distributed throughout the trunk of the body. Therefore, where the whole body is the critical organ for an internally deposited radionuclide, the whole body dose limit applies to the sum of doses received must assure control of the concentration of radionuclides in the building atmosphere and thereby limit the dose from internal sources

  15. Cold vacuum drying facility 90% design review

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

    This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage

  16. Cold vacuum drying facility 90% design review

    Energy Technology Data Exchange (ETDEWEB)

    O`Neill, C.T.

    1997-05-02

    This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage.

  17. Decommissioning Lines-of-Inquiry for Design Review of New Nuclear Facilities

    International Nuclear Information System (INIS)

    Negin, C.A.; Urland, C.S.

    2008-01-01

    An independent review of the design of the Salt Waste Processing Facility (SWPF) at Savannah River included a requirement to address the ability to decommission the facility. This paper addresses the lines of inquiry (that were developed for the review and their use in future for reviews of other projects, referred to herein as 'DDLOI'. Decommissioning activities for almost any type of facility are well within the technological state-of-the-art. The major impacts for complications resulting from insufficient consideration during design of a new facility that involves radioactive processes and/or material is the cost of: a) gaining access to high radiation areas and b) dealing with high levels of contamination. For this reason, the DDLOI were developed as a way of raising the awareness of designers and design reviewers to design features that can impede or facilitate ultimate decommissioning. The intent is that this report can be used not only for review, but also by engineers in the early stages of design development when requirements are being assembled. The focus for the DDLOI is on types of facilities that contain nuclear and/or radioactive processes and materials. The level of detail is more specific than would be found in decommissioning plans prepared for regulatory purposes. In commencing this review, the author's could find no precedent for a systematic review of design for decommissioning that included results of a review. Therefore, it was decided to create a report that would provide detailed lines of inquiry along with the rationale for each. The resulting DDLOI report included 21 topical areas for design review. The DDLOI combined the authors' experience in developing baselines for facilities to be deactivated or demolished with prior publications by the U.S. Army and the International Atomic Energy Agency. These two references were found via an Internet search and were the only ones judged to be useful at a field application level. Most others

  18. Rethinking information handling: designing for information offload

    DEFF Research Database (Denmark)

    Hansen, Lone Koefoed; Pedersen, Peter Dalsgård; Eriksson, Eva

    2005-01-01

    This paper introduces information offload as a supplement way of responding to and designing for information. By presenting iFlush, a design concept aiming at providing the user with a possibility to offload information and then instantly dispose of it, the paper presents an approach towards desi...... designing for reflection and also serves as a critique towards information overload. Furthermore, the absence of reflection on the role played by HCI community in the constant augmenting of all spaces is addressed....

  19. Design of a system for examinations of the history of operation of selected WWER primary circuit facilities. Stage I: requirements

    International Nuclear Information System (INIS)

    Brumovsky, M.; Kraus, V.; Ruscak, M.; Vejvoda, S.

    1994-01-01

    A survey is presented of data required for the evaluation and control of nuclear power plant aging and service life, and a data acquisition and record-keeping system is proposed. The data fall in 3 classes: (i) information on the initial status, including design data and status data at the beginning of the operational lifetime of the facilities; (ii) data on the history of operation, including operating conditions at the level of the corresponding system and facility, as well as operating test and failure data; and (iii) data on the history of maintenance, including data on the monitoring of the facility condition and on maintenance. Basic information requirements for the evaluation of the service life of the pressure vessel, steam generator, pressurizer, and main circulation pipe are given; the way of processing this information is outlined. (J.B.). 2 figs

  20. An Experience of Thermowell Design in RCP Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. S.; Kim, B. D.; Youn, Y. J.; Jeon, W. J.; Kim, S.; Bae, B. U.; Cho, Y. J.; Choi, H. S.; Park, J. K; Cho, S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Flow rates for the test should vary in the range of 90% to 130% of rated flowrate under prototypic operational conditions, as shown in Table 1. Generally for the flow control, a combination of a control valve and an orifice was used in previous RCP test facilities. From the commissioning startup of the RCP test facility, it was found the combination of valve and orifice induced quite a large vibration for the RCP. As a solution to minimize the vibration and to facilitate the flowrate control, one of KAERI's staff suggested a variable restriction orifice (VRO), which controls most of the required flowrates except highest flowrates, as shown in Fig. 2. For the highest flowrates, e.g., around run-out flowrate (130%), control valves in bypass lines were also used to achieve required flowrates. From a performance test, it was found the VRO is very effective measures to control flowrates in the RCP test facility. During the commissioning startup operation, one of thermowells located at the upstream of the RCP was cracked due to high speed coolant velocity, which was - fortunately - found under a leakage test before running the RCP test loop. The cracked thermowell, whose tapered-shank was detached from the weld collar after uninstalling, is shown in Fig. 3. As can be seen the figure, most of the cross-section at the root of the thermowell shank was cracked. In this paper, an investigation of the integrity of thermowells in the RCP test facility was performed according to the current code and overall aspects on the thermowell designs were also discussed. An RCP test facility has been constructed in KAERI. During the commissioning startup operation, one of thermowells was cracked due to high speed coolant velocity. To complete the startup operation, a modified design of thermowells was proposed and all the original thermowells were replaced by the modified ones. From evaluation of the original and modified designs of thermowells according to the recent PTC code, the

  1. 78 FR 16698 - Chemical Facility Anti-Terrorism Standards (CFATS) Chemical-Terrorism Vulnerability Information...

    Science.gov (United States)

    2013-03-18

    ... DEPARTMENT OF HOMELAND SECURITY [Docket No. DHS-2012-0057] Chemical Facility Anti-Terrorism Standards (CFATS) Chemical- Terrorism Vulnerability Information (CVI) AGENCY: National Protection and... notice is also soliciting comments concerning the Information Collection Request, Chemical Facility Anti...

  2. Assessment of laboratory logistics management information system practice for HIV/AIDS and tuberculosis laboratory commodities in selected public health facilities in Addis Ababa, Ethiopia.

    Science.gov (United States)

    Desale, Adino; Taye, Bineyam; Belay, Getachew; Nigatu, Alemayehu

    2013-01-01

    Logistics management information system for health commodities remained poorly implemented in most of developing countries. To assess the status of laboratory logistics management information system for HIV/AIDS and tuberculosis laboratory commodities in public health facilities in Addis Ababa. A cross-sectional descriptive study was conducted from September 2010-January 2011 at selected public health facilities. A stratified random sampling method was used to include a total of 43 facilities which, were investigated through quantitative methods using structured questionnaires interviews. Focus group discussion with the designated supply chain managers and key informant interviews were conducted for the qualitative method. There exists a well-designed logistics system for laboratory commodities with trained pharmacy personnel, distributed standard LMIS formats and established inventory control procedures. However, majority of laboratory professionals were not trained in LMIS. Majority of the facilities (60.5%) were stocked out for at least one ART monitoring and TB laboratory reagents and the highest stock out rate was for chemistry reagents. Expired ART monitoring laboratory commodities were found in 25 (73.5%) of facilities. Fifty percent (50%) of the assessed hospitals and 54% of health centers were currently using stock/bin cards for all HIV/AIDS and TB laboratory commodities in main pharmacy store, among these only 25% and 20.8% of them were updated with accurate information matching with the physical count done at the time of visit for hospitals and health centers respectively. Even though there exists a well designed laboratory LMIS, keeping quality stock/bin cards and LMIS reports were very low. Key ART monitoring laboratory commodities were stock out at many facilities at the day of visit and during the past six months. Based on findings, training of laboratory personnel's managing laboratory commodities and keeping accurate inventory control procedures

  3. Assessment of laboratory logistics management information system practice for HIV/AIDS and tuberculosis laboratory commodities in selected public health facilities in Addis Ababa, Ethiopia

    Science.gov (United States)

    Desale, Adino; Taye, Bineyam; Belay, Getachew; Nigatu, Alemayehu

    2013-01-01

    Introduction Logistics management information system for health commodities remained poorly implemented in most of developing countries. To assess the status of laboratory logistics management information system for HIV/AIDS and tuberculosis laboratory commodities in public health facilities in Addis Ababa. Methods A cross-sectional descriptive study was conducted from September 2010-January 2011 at selected public health facilities. A stratified random sampling method was used to include a total of 43 facilities which, were investigated through quantitative methods using structured questionnaires interviews. Focus group discussion with the designated supply chain managers and key informant interviews were conducted for the qualitative method. Results There exists a well-designed logistics system for laboratory commodities with trained pharmacy personnel, distributed standard LMIS formats and established inventory control procedures. However, majority of laboratory professionals were not trained in LMIS. Majority of the facilities (60.5%) were stocked out for at least one ART monitoring and TB laboratory reagents and the highest stock out rate was for chemistry reagents. Expired ART monitoring laboratory commodities were found in 25 (73.5%) of facilities. Fifty percent (50%) of the assessed hospitals and 54% of health centers were currently using stock/bin cards for all HIV/AIDS and TB laboratory commodities in main pharmacy store, among these only 25% and 20.8% of them were updated with accurate information matching with the physical count done at the time of visit for hospitals and health centers respectively. Conclusion Even though there exists a well designed laboratory LMIS, keeping quality stock/bin cards and LMIS reports were very low. Key ART monitoring laboratory commodities were stock out at many facilities at the day of visit and during the past six months. Based on findings, training of laboratory personnel's managing laboratory commodities and keeping

  4. Utilization Of Information And Communication Technology Facilities ...

    African Journals Online (AJOL)

    The purpose of this study was to investigate the types of ICT facilities used for the provision of library and information services in Nigerian University libraries. It was also set to determine if there is any significant difference between Southern and Northern Nigeria University libraries of the first, second and third generations in ...

  5. Human engineering considerations in the design of New Virginia Power Radwaste facilities

    International Nuclear Information System (INIS)

    Bankley, A.V.; Morris, L.L.; Lippard, D.W.

    1988-01-01

    Human engineering principles were considered by Virginia Power in the recent design of new radwaste facilities (NRFs) for both the Surry and North Anna power stations. Virginia Power recognized that the rigorous application of human engineering principles to the NRF design was essential to the ultimate success or failure of the facilities. Success of the NRF should not only be measured in the volume of radwaste processed but also by other factors such as (a) availability and maintainability of preferred equipment, (b) as-low-as-reasonably-achievable considerations, (c) actual release rates versus achievable release rates, and (d) flexibility to deal with varying circumstances. Each of these success criteria would suffer as the result of operator/human inefficiencies or error. Therefore, human engineering should be applied to the maximum practical extent to minimize such inefficiencies or errors. No method is ever going to ensure a perfectly human-engineered facility design. Virginia Power believes, however, that significant strides have been made in efforts to design and construct a successful radwaste processing facility, a facility where operating success rests with the ability of the human operators to perform their jobs in an efficient and reliable fashion

  6. Waste Receiving and Processing Facility Module 1: Volume 1, Preliminary Design report

    International Nuclear Information System (INIS)

    1992-03-01

    The Preliminary Design Report (Title 1) for the Waste Receiving and Processing (WRAP) Module 1 provides a comprehensive narrative description of the proposed facility and process systems, the basis for each of the systems design, and the engineering assessments that were performed to support the technical basis of the Title 1 design. The primary mission of the WRAP 1 Facility is to characterize and certify contact-handled (CH) waste in 55-gallon drums for disposal. Its secondary function is to certify CH waste in Standard Waste Boxes (SWBs) for disposal. The preferred plan consist of retrieving the waste and repackaging as necessary in the Waste Receiving and Processing (WRAP) facility to certify TRU waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. WIPP is a research and development facility designed to demonstrate the safe and environmentally acceptable disposal of TRU waste from National Defense programs. Retrieved waste found to be Low-Level Waste (LLW) after examination in the WRAP facility will be disposed of on the Hanford site in the low-level waste burial ground. The Hanford Site TRU waste will be shipped to the WIPP for disposal between 1999 and 2013

  7. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Bong Shick; Kim, Y. S.; Lee, C. Y. and others

    1999-03-01

    The principal contents of this project are to design, fabricate and install the steady-state fuel test loop in HANARO for nuclear technology development. Procurement and fabrication of main equipment, licensing and technical review for fuel test loop have been performed during 2 years(1997, 1998) for this project. Following contents are described in the report. - Procurement and fabrication of the equipment, piping for OPS - IPS manufacture - License - Technical review and evaluation of the FTL facility. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and review ofHANARO interface have been performed respectively. (author)

  8. Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The Department of Energy (DOE) has issued an Order 420.1 which establishes policy for its facilities in the event of natural phenomena hazards (NPH) along with associated NPH mitigation requirements. This DOE Standard gives design and evaluation criteria for NPH effects as guidance for implementing the NPH mitigation requirements of DOE Order 420.1 and the associated implementation Guides. These are intended to be consistent design and evaluation criteria for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of these criteria is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. These criteria apply to the design of new facilities and the evaluation of existing facilities. They may also be used for modification and upgrading of existing facilities as appropriate. The design and evaluation criteria presented herein control the level of conservatism introduced in the design/evaluation process such that earthquake, wind, and flood hazards are treated on a consistent basis. These criteria also employ a graded approach to ensure that the level of conservatism and rigor in design/evaluation is appropriate for facility characteristics such as importance, hazards to people on and off site, and threat to the environment. For each natural phenomena hazard covered, these criteria consist of the following: Performance Categories and target performance goals as specified in the DOE Order 420.1 NPH Implementation Guide, and DOE-STD-1 021; specified probability levels from which natural phenomena hazard loading on structures, equipment, and systems is developed; and design and evaluation procedures to evaluate response to NPH loads and criteria to assess whether or not computed response is permissible.

  9. A performance goal-based seismic design philosophy for waste repository facilities

    International Nuclear Information System (INIS)

    Hossain, Q.A.

    1994-01-01

    A performance goal-based seismic design philosophy, compatible with DOE's present natural phenomena hazards mitigation and open-quotes graded approachclose quotes philosophy, has been proposed for high level nuclear waste repository facilities. The rationale, evolution, and the desirable features of this method have been described. Why and how the method should and can be applied to the design of a repository facility are also discussed

  10. Ventilation design for Yucca Mountain Exploratory Studies Facility

    International Nuclear Information System (INIS)

    Jurani, R.S.

    1995-01-01

    Yucca Mountain, located in Southern Nevada approximately 160 km northwest of Las Vegas, is currently the site of intensive surface-based and underground investigations. The investigations are required to determine if the site is suitable for long term isolation of the Nation's high level nuclear waste inventory. A major component of the program is the Exploratory Studies Facility, or ESF. The ESF, when completed, will consist of approximately 25,600 meters of tunnels and drifts. The network of tunnels and drifts will house and support a wide array of testing programs conceived to provide physical information about the site. Information on geologic, geomechanical, and hydrologic data will be used in the repository design if the site is found suitable. Besides a few special requirements, the general ESF ventilation criteria during construction are similar to that of commercial tunneling and mining operations. The minimum air velocity at the Tunnel Boring Machine (TBM) and other active mining faces is 0.51 meter per second (m/s) (100 feet per minute [fpm]). Airways, estimated leakages and ventilation controls are converted into equivalent resistances for input to mine ventilation network computer simulations. VNETPC Version 3.1 computer software is used to generate the ventilation models for optimized system design and component selection. Subsequently, actual performance of the ventilation system will be verified and validated to comply with applicable nuclear regulatory quality assurance requirements. Dust control in the ESF is dependent on effective dust collection, enclosure, and airflow dilution. Minimum use of water, as feasible, is necessary to avoid adding moisture to the potential repository horizon. The limitation of water use for test drilling and TBM operation, and the rigid compliance with applicable federal and state regulations, make the ESF a ventilation design challenge

  11. Call for information on coastal energy facility siting: an analysis of responses

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The Call for Information issued by the New Jersey Department of Environmental Protection in December 1975 consisted of an eight page questionnaire which was sent to industries, government agencies, and private organizations. Its objective was to seek the help of these groups in plans for the siting of energy facilities in the coastal zone. Potential development of oil and gas from the Baltimore Canyon region adjacent to New Jersey has made planning for energy facilities a priority issue both at the state and federal level. The Call for Information invited government and the energy industry to submit (a) suggested criteria for locating energy and energy-related facilities within the New Jersey coastal zone, (b) analyses by governmental and private agencies or groups of the need to locate energy facilities in specific sites within New Jersey's coastal zone, or in generalized portions thereof, and (c) identification of the land-use parameters, appropriate to the various types of facilities which may be proposed, now or later, for coastal siting. The findings obtained from the draft call and the final call issued seven months later are presented. The results of the industries' responses show that the electric and gas utilities gave some useful information while this was true of only a few of the oil companies. The reluctance to give informatign was perhaps aggravated by lack of clear state and federal policies. The appendices illustrate specific information on manpower, cost and facility requirements to develop oil refineries, establish a gas processing plant as well as information from the US Coast Guard and the Environmental Protection Agency. There is also a listing of the companies that bid in the August 1976 lease sale indicating which bids were accepted, a map of the offshore tracts, and a list of which companies responded to the Call for Information

  12. Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

    International Nuclear Information System (INIS)

    Groth, B.D.

    1995-01-01

    The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements

  13. The DR 3 reactor at Risoe, Denmark and its associated hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the DR 2 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of seven information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  14. Anatomy Education in Namibia: Balancing Facility Design and Curriculum Development

    Science.gov (United States)

    Wessels, Quenton; Vorster, Willie; Jacobson, Christian

    2012-01-01

    The anatomy curriculum at Namibia's first, and currently only, medical school is clinically oriented, outcome-based, and includes all of the components of modern anatomical sciences i.e., histology, embryology, neuroanatomy, gross, and clinical anatomy. The design of the facilities and the equipment incorporated into these facilities were directed…

  15. Development of Demonstration Facility Design Technology for Advanced Nuclear Fuel Cycle Process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.

    2010-04-01

    The main objective of this R and D is to develop the PRIDE (PyRoprocess Integrated inactive DEmonstration) facility for engineering-scale inactive test using fresh uranium, and to establish the design requirements of the ESPF (Engineering Scale Pyroprocess Facility) for active demonstration of the pyroprocess. Pyroprocess technology, which is applicable to GEN-IV systems as one of the fuel cycle options, is a solution of the spent fuel accumulation problems. PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. The PRIDE evaluation data, such as performance evaluation data of equipment and operation experiences, will be directly utilized for the design of ESPF

  16. Final report for fuel acquisition and design of a fast subcritical blanket facility

    International Nuclear Information System (INIS)

    Clikeman, F.M.; Ott, K.O.

    1976-01-01

    A summary is presented of work leading to the design of a subcritical facility for the study of fast reactor blankets. Included are activities related to fuel acquisition, design of the facility, and experiment planning

  17. Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

    Science.gov (United States)

    Gencer, A.; Demirköz, B.; Efthymiopoulos, I.; Yiğitoğlu, M.

    2016-07-01

    Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between 10 μA and 1.2 mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam flux. The DBL is designed to provide fluxes between 107 p /cm2 / s and 109 p /cm2 / s for performing irradiation tests in an area of 15.4 cm × 21.5 cm. The facility will be the first irradiation facility of its kind in Turkey.

  18. Design and operation of the Surry Radwaste Facility

    International Nuclear Information System (INIS)

    Morris, L.L.; Halverson, W.C.

    1993-01-01

    In September 1991, Virginia Power started processing radioactive waste with a new Radwaste Facility at the Surry Power Station near Norfolk, Virginia. The Surry Radwaste Facility (SRF) was designed to process and store liquid waste, laundry waste, dry active waste, radioactive filters and spent ion-exchange resin. It also provides on-site decontamination services and a fully equipped hot machine shop. The NRC has recognized that the amount of planning and design, and the attention to detail, that was expended on the SRF Project in order to minimize personnel exposure and ensure efficient operation, is a licensee strength. Through its first year of operation, the facility has proven very successful. Using evaporation and demineralization, over 30 million liters of liquid have been released with no chemical impurities or detectable radioactivity (excluding tritium). Over 623,000 liters of concentrated boric acid waste liquid have been processed with the Bitumen Solidification System yielding 139,880 liters (660 drums) of low level Class A-Stable waste. Additional economic benefits will be realized as the effectiveness of the processing systems continues to improve due to increased operational experience and ergonomics

  19. Proceedings of the Advanced Hadron Facility accelerator design workshop

    International Nuclear Information System (INIS)

    Thiessen, H.A.

    1989-01-01

    The International Workshop on Hadron Facility Technology was held February 22-27, 1988, at the Study Center at Los Alamos National Laboratory. The program included papers on facility plans, beam dynamics, and accelerator hardware. The parallel sessions were particularly lively with discussions of all facets of kaon factory design. The workshop provided an opportunity for communication among the staff involved in hadron facility planning from all the study groups presently active. The recommendations of the workshop include: the need to use h=1 RF in the compressor ring; the need to minimize foil hits in painting schemes for all rings; the need to consider single Coulomb scattering in injection beam los calculations; the need to study the effect of field inhomogeneity in the magnets on slow extraction for the 2.2 Tesla main ring of AHF; and agreement in principle with the design proposed for a joint Los Alamos/TRIUMF prototype main ring RF cavity

  20. Design and Shielding of Radiotherapy Treatment Facilities; IPEM Report 75, 2nd Edition

    Science.gov (United States)

    Horton, Patrick; Eaton, David

    2017-07-01

    Design and Shielding of Radiotherapy Treatment Facilities provides readers with a single point of reference for protection advice to the construction and modification of radiotherapy facilities. The book assembles a faculty of national and international experts on all modalities including megavoltage and kilovoltage photons, brachytherapy and high-energy particles, and on conventional and Monte Carlo shielding calculations. This book is a comprehensive reference for qualified experts and radiation-shielding designers in radiation physics and also useful to anyone involved in the design of radiotherapy facilities.

  1. The Influence of Older Age Groups to Sustainable Product Design Research of Urban Public Facilities

    Science.gov (United States)

    Wen-juan, Zhang; Hou-peng, Song

    2017-01-01

    Through summarize the status quo of public facilities design to older age groups in China and a variety of factors what influence on them, the essay, from different perspective, is designed to put forward basic principle to sustainable design of public facilities for the aged in the city, and thus further promote and popularize the necessity of sustainable design applications in the future design of public facilities for elderly people.

  2. Design ampersand construction innovations of the defense waste processing facility

    International Nuclear Information System (INIS)

    McKibben, J.M.; Pair, C.R.; Bethmann, H.K.

    1990-01-01

    Construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is essentially complete. The facility is designed to convert high-level radioactive waste, now contained in large steel tanks as aqueous salts and sludge, into solid borosilicate glass in stainless steel canisters. All processing of the radioactive material and operations in a radioactive environment will be done remotely. The stringent requirements dictated by remote operation and new approaches to the glassification process led to the development of a number of first-of-a-kind pieces of equipment, new construction fabrication and erection techniques, and new applications of old techniques. The design features and construction methods used in the vitrification building and its equipment were to accomplish the objective of providing a state-of-the-art vitrification facility. 3 refs., 10 figs

  3. Hospital to Post-Acute Care Facility Transfers: Identifying Targets for Information Exchange Quality Improvement.

    Science.gov (United States)

    Jones, Christine D; Cumbler, Ethan; Honigman, Benjamin; Burke, Robert E; Boxer, Rebecca S; Levy, Cari; Coleman, Eric A; Wald, Heidi L

    2017-01-01

    Information exchange is critical to high-quality care transitions from hospitals to post-acute care (PAC) facilities. We conducted a survey to evaluate the completeness and timeliness of information transfer and communication between a tertiary-care academic hospital and its related PAC facilities. This was a cross-sectional Web-based 36-question survey of 110 PAC clinicians and staff representing 31 PAC facilities conducted between October and December 2013. We received responses from 71 of 110 individuals representing 29 of 31 facilities (65% and 94% response rates). We collapsed 4-point Likert responses into dichotomous variables to reflect completeness (sufficient vs insufficient) and timeliness (timely vs not timely) for information transfer and communication. Among respondents, 32% reported insufficient information about discharge medical conditions and management plan, and 83% reported at least occasionally encountering problems directly related to inadequate information from the hospital. Hospital clinician contact information was the most common insufficient domain. With respect to timeliness, 86% of respondents desired receipt of a discharge summary on or before the day of discharge, but only 58% reported receiving the summary within this time frame. Through free-text responses, several participants expressed the need for paper prescriptions for controlled pain medications to be sent with patients at the time of transfer. Staff and clinicians at PAC facilities perceive substantial deficits in content and timeliness of information exchange between the hospital and facilities. Such deficits are particularly relevant in the context of the increasing prevalence of bundled payments for care across settings as well as forthcoming readmissions penalties for PAC facilities. Targets identified for quality improvement include structuring discharge summary information to include information identified as deficient by respondents, completion of discharge summaries

  4. Radiotherapy facilities: Master planning and concept design considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-08-15

    This publication provides guidelines on how to plan a radiotherapy facility in terms of the strategic master planning process including the legal, technical and infrastructure requirements. It outlines a risk assessment methodology, a typical project work plan and describes the professional expertise required for the implementation of such a project. Generic templates for a block design are suggested, which include possibilities for future expansion. These templates can be overlaid onto the designated site such that the most efficient workflow between the main functional areas can be ensured. A sample checklist is attached to act as a guideline for project management and to indicate the critical stages in the process where technical expert assistance may be needed. The publication is aimed at professionals and administrators involved in infrastructure development, planning and facility management, as well as engineers, building contractors and radiotherapy professionals.

  5. Radiotherapy facilities: Master planning and concept design considerations

    International Nuclear Information System (INIS)

    2014-01-01

    This publication provides guidelines on how to plan a radiotherapy facility in terms of the strategic master planning process including the legal, technical and infrastructure requirements. It outlines a risk assessment methodology, a typical project work plan and describes the professional expertise required for the implementation of such a project. Generic templates for a block design are suggested, which include possibilities for future expansion. These templates can be overlaid onto the designated site such that the most efficient workflow between the main functional areas can be ensured. A sample checklist is attached to act as a guideline for project management and to indicate the critical stages in the process where technical expert assistance may be needed. The publication is aimed at professionals and administrators involved in infrastructure development, planning and facility management, as well as engineers, building contractors and radiotherapy professionals

  6. Development of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Doo; Song, Dae Yong; So, Dong Sup; Kwack, Eun Ho [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-04-01

    Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described. 3 tabs. (Author)

  7. Design and Validation of Control Room Upgrades Using a Research Simulator Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Jeffrey C. Joe; Julius J. Persensky

    2012-11-01

    Since 1981, the United States (U.S.) Nuclear Regulatory Commission (NRC) [1] requires a plant- specific simulator facility for use in training at U.S. nuclear power plants (NPPs). These training simulators are in near constant use for training and qualification of licensed NPP operators. In the early 1980s, the Halden Man-Machine Laboratory (HAMMLab) at the Halden Reactor Project (HRP) in Norway first built perhaps the most well known set of research simulators. The HRP offered a high- fidelity simulator facility in which the simulator is functionally linked to a specific plant but in which the human-machine interface (HMI) may differ from that found in the plant. As such, HAMMLab incorporated more advanced digital instrumentation and controls (I&C) than the plant, thereby giving it considerable interface flexibility that researchers took full advantage of when designing and validating different ways to upgrade NPP control rooms. Several U.S. partners—the U.S. NRC, the Electrical Power Research Institute (EPRI), Sandia National Laboratories, and Idaho National Laboratory (INL) – as well as international members of the HRP, have been working with HRP to run control room simulator studies. These studies, which use crews from Scandinavian plants, are used to determine crew behavior in a variety of normal and off-normal plant operations. The findings have ultimately been used to guide safety considerations at plants and to inform advanced HMI design—both for the regulator and in industry. Given the desire to use U.S. crews of licensed operators on a simulator of a U.S. NPP, there is a clear need for a research simulator facility in the U.S. There is no general-purpose reconfigurable research oriented control room simulator facility in the U.S. that can be used for a variety of studies, including the design and validation of control room upgrades.

  8. Design impacts of safeguards and security requirements for a US MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Erkkila, B.H.; Rinard, P.M.; Thomas, K.E.; Zack, N.R.; Jaeger, C.D.

    1998-01-01

    The disposition of plutonium that is no longer required for the nation's defense is being structured to mitigate risks associated with the material's availability. In the 1997 Record of Decision, the US Government endorsed a dual-track approach that could employ domestic commercial reactors to effect the disposition of a portion of the plutonium in the form of mixed oxide (MOX) reactor fuels. To support this decision, the Office of Materials Disposition requested preparation of a document that would review US requirements for safeguards and security and describe their impact on the design of a MOX fuel fabrication facility. The intended users are potential bidders for the construction and operation of the facility. The document emphasizes the relevant DOE Orders but also considers the Nuclear Regulatory Commission (NRC) requirements. Where they are significantly different, the authors have highlighted this difference and provided guidance on the impact to the facility design. Finally, the impacts of International Atomic Energy Agency (IAEA) safeguards on facility design are discussed. Security and materials control and accountability issues that influence facility design are emphasized in each area of discussion. This paper will discuss the prepared report and the issues associated with facility design for implementing practical, modern safeguards and security systems into a new MOX fuel fabrication facility

  9. Fermilab HEPCloud Facility Decision Engine Design

    Energy Technology Data Exchange (ETDEWEB)

    Tiradani, Tiradani,Anthony [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Altunay, Mine [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Dagenhart, David [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Kowalkowski, Jim [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Litvintsev, Dmitry [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Lu, Qiming [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Mhashilkar, Parag [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Moibenko, Alexander [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Paterno, Marc [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Timm, Steven [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2017-05-23

    The Decision Engine is a critical component of the HEP Cloud Facility. It provides the functionality of resource scheduling for disparate resource providers, including those which may have a cost or a restricted allocation of cycles. Along with the architecture, design, and requirements for the Decision Engine, this document will provide the rationale and explanations for various design decisions. In some cases, requirements and interfaces for a limited subset of external services will be included in this document. This document is intended to be a high level design. The design represented in this document is not complete and does not break everything down in detail. The class structures and pseudo-code exist for example purposes to illustrate desired behaviors, and as such, should not be taken literally. The protocols and behaviors are the important items to take from this document. This project is still in prototyping mode so flaws and inconsistencies may exist and should be noted and treated as failures.

  10. Informal caregiving burden and perceived social support in an acute stroke care facility.

    Science.gov (United States)

    Akosile, Christopher Olusanjo; Banjo, Tosin Olamilekan; Okoye, Emmanuel Chiebuka; Ibikunle, Peter Olanrewaju; Odole, Adesola Christiana

    2018-04-05

    Providing informal caregiving in the acute in-patient and post-hospital discharge phases places enormous burden on the caregivers who often require some form of social support. However, it appears there are few published studies about informal caregiving in the acute in-patient phase of individuals with stroke particularly in poor-resource countries. This study was designed to evaluate the prevalence of caregiving burden and its association with patient and caregiver-related variables and also level of perceived social support in a sample of informal caregivers of stroke survivors at an acute stroke-care facility in Nigeria. Ethical approval was sought and obtained. Fifty-six (21 males, 35 females) consecutively recruited informal caregivers of stroke survivors at the medical ward of a tertiary health facility in South-Southern Nigeria participated in this cross-sectional survey. Participants' level of care-giving strain/burden and perceived social support were assessed using the Caregiver Strain Index and the Multidimensional Scale of Perceived Social Support respectively. Caregivers' and stroke survivors' socio-demographics were also obtained. Data was analysed using frequency count and percentages, independent t-test, analysis of variance (ANOVA) and partial correlation at α =0.05. The prevalence of care-giving burden among caregivers is 96.7% with a high level of strain while 17.9% perceived social support as low. No significant association was found between caregiver burden and any of the caregiver- or survivor-related socio-demographics aside primary level education. Only the family domain of the Multidimensional Scale of Perceived Social Support was significantly correlated with burden (r = - 0.295). Informal care-giving burden was highly prevalent in this acute stroke caregiver sample and about one in every five of these caregivers rated social support low. This is a single center study. Healthcare managers and professionals in acute care facilities

  11. Army Air and Missile Defense Network Design Facility (AAMDNDF)

    Data.gov (United States)

    Federal Laboratory Consortium — This facility provides JTIDS network designs and platform initialization load files for all Joint and Army-only tests, exercises, operations, and contingency events...

  12. Preconceptual design for a Monitored Retrievable Storage (MRS) transfer facility

    International Nuclear Information System (INIS)

    Woods, W.D.; Jowdy, A.K.; Smith, R.I.

    1990-09-01

    The contract between the DOE and the utilities specifies that the DOE will receive spent fuel from the nuclear utilities in 1998. This study investigates the feasibility of employing a simple Transfer Facility which can be constructed quickly, and operate while the full-scale MRS facilities are being constructed. The Transfer Facility is a hot cell designed only for the purpose of transferring spent fuel assemblies from the Office of Civilian Radioactive Waste Management (OCRWM) transport casks (shipped from the utility sites) into onsite concrete storage casks. No operational functions other than spent fuel assembly transfers and the associated cask handling, opening, and closing would be performed in this facility. Radioactive waste collected in the Transfer Facility during operations would be stored until the treatment facilities in the full-scale MRS facility became operational, approximately 2 years after the Transfer Facility started operation. An alternate wherein the Transfer Facility was the only waste handling building on the MRS site was also examined and evaluated. 6 figs., 26 tabs

  13. Lead coolant test facility systems design, thermal hydraulic analysis and cost estimate

    Energy Technology Data Exchange (ETDEWEB)

    Khericha, Soli, E-mail: slk2@inel.gov [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Harvego, Edwin; Svoboda, John; Evans, Robert [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Dalling, Ryan [ExxonMobil Gas and Power Marketing, Houston, TX 77069 (United States)

    2012-01-15

    The Idaho National Laboratory prepared a preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic coolant. Based on review of current world lead or lead-bismuth test facilities and research needs listed in the Generation IV Roadmap, five broad areas of requirements were identified as listed below: Bullet Develop and demonstrate feasibility of submerged heat exchanger. Bullet Develop and demonstrate open-lattice flow in electrically heated core. Bullet Develop and demonstrate chemistry control. Bullet Demonstrate safe operation. Bullet Provision for future testing. This paper discusses the preliminary design of systems, thermal hydraulic analysis, and simplified cost estimated. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 4200 Degree-Sign C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M (in 2006 $). It is also estimated that the facility will require two years to be constructed and ready for operation.

  14. Design verification and validation plan for the cold vacuum drying facility

    International Nuclear Information System (INIS)

    NISHIKAWA, L.D.

    1999-01-01

    The Cold Vacuum Drying Facility (CVDF) provides the required process systems, supporting equipment, and facilities needed for drying spent nuclear fuel removed from the K Basins. This document presents the both completed and planned design verification and validation activities

  15. Flexible Electronics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Flexible Electronics Research Facility designs, synthesizes, tests, and fabricates materials and devices compatible with flexible substrates for Army information...

  16. IAEA Guidance for Safeguards Implementation in Facility Design and Construction

    International Nuclear Information System (INIS)

    Sprinkle, J.; Hamilton, A.; Poirier, S.; Catton, A.; Ciuculescu, C.; Ingegneri, M.; Plenteda, R.

    2015-01-01

    One of the IAEA's statutory objectives is to seek to accelerate and enlarge the contribution of nuclear energy to peace, health and prosperity throughout the world. One way the IAEA works to achieve this objective is through the publication of technical series that can provide guidance to Member States. These series include the IAEA Services Series, the IAEA Safety Standard Series, the IAEA Nuclear Security Series and the IAEA Nuclear Energy Series. The Nuclear Energy Series is comprised of publications designed to encourage and assist research and development on, and practical application of, nuclear energy for peaceful purposes. This includes guidance to be used by owners and operators of utilities, academia, vendors and government officials. The IAEA has chosen the Nuclear Energy Series to publish guidance for States regarding the consideration of safeguards in nuclear facility design and construction. Historically, safeguards were often applied after a facility was designed or maybe even after it was built. However, many in the design and construction community would prefer to include consideration of these requirements from the conceptual design phase in order to reduce the need for retro-fits and modifications. One can then also take advantage of possible synergies between safeguards, security, safety and environmental protection and reduce the project risk against cost increments and schedule slippage. The IAEA is responding to this interest with a suite of publications in the IAEA Nuclear Energy Series, developed with the assistance of a number of Member State Support Programmes through a joint support programme task: · International Safeguards in Nuclear Facility Design and Construction (NP-T-2.8, 2013), · International Safeguards in the Design of Nuclear Reactors (NP-T-2.9, 2014), · International Safeguards in the Design of Spent Fuel Management (NF-T-3.1, tbd), · International Safeguards in the Design of Fuel Fabrication Plants (NF-T-4.7, tbd

  17. Design-only conceptual design report for pit disassembly and conversion facility. Rev 0

    International Nuclear Information System (INIS)

    Zygmunt, S.; Christensen, L.; Richardson, C.

    1997-01-01

    This design-only conceptual design report (DOCDR) was prepared to support a funding request by the Department of Energy (DOE)-Office of Fissile Material Disposition (OFMD) for engineering design of the Pit Disassembly and Conversion Facility (PDCF) Project No. 99-D-141. The PDCF will be used to disassemble the nation's inventory of surplus nuclear weapons pits and convert the plutonium recovered from those pits into a form suitable for storage, international inspection, and final disposition. The PDCF is a complex consisting of a hardened building that will contain the plutonium processes in a safe and secure manner, and conventional buildings and structures that will house support personnel, systems, and equipment. The PDCF uses the Advanced Recovery and Integrated Extraction System (ARIES), a low waste, modular pyroprocessing system to convert pits to plutonium oxide. The PDCF project consists of engineering and design, and construction of the buildings and structures, and engineering and design, procurement, installation, testing and start-up of equipment to disassemble pits and convert plutonium in pits to oxide form. The facility is planned to operate for 10 years, averaging 3.5 metric tons (3.86 tons) of plutonium metal per year. On conclusion of operations, the PDCF will be decontaminated and decommissioned

  18. Design-only conceptual design report for pit disassembly and conversion facility. Rev 0

    Energy Technology Data Exchange (ETDEWEB)

    Zygmunt, S.; Christensen, L.; Richardson, C.

    1997-12-12

    This design-only conceptual design report (DOCDR) was prepared to support a funding request by the Department of Energy (DOE)-Office of Fissile Material Disposition (OFMD) for engineering design of the Pit Disassembly and Conversion Facility (PDCF) Project No. 99-D-141. The PDCF will be used to disassemble the nation`s inventory of surplus nuclear weapons pits and convert the plutonium recovered from those pits into a form suitable for storage, international inspection, and final disposition. The PDCF is a complex consisting of a hardened building that will contain the plutonium processes in a safe and secure manner, and conventional buildings and structures that will house support personnel, systems, and equipment. The PDCF uses the Advanced Recovery and Integrated Extraction System (ARIES), a low waste, modular pyroprocessing system to convert pits to plutonium oxide. The PDCF project consists of engineering and design, and construction of the buildings and structures, and engineering and design, procurement, installation, testing and start-up of equipment to disassemble pits and convert plutonium in pits to oxide form. The facility is planned to operate for 10 years, averaging 3.5 metric tons (3.86 tons) of plutonium metal per year. On conclusion of operations, the PDCF will be decontaminated and decommissioned.

  19. Lessons Learned from Design and Construction of New US Nuclear Facility

    International Nuclear Information System (INIS)

    Seamans, S. E.; Horvath, D. A.

    2012-01-01

    For reasons related to licensing uncertainty, economic slowdown, and questionable financial backing, no new nuclear facility projects have been undertaken in the United States since the Three Mile Island Incident in 1979; however, a need for such facilities (both nuclear power plants and nuclear fuel facilities) continues and various incentives leading to the start of a nuclear renaissance have occurred. One incentive is a complete overhaul by the US Nuclear Regulatory Commission of the earlier two step licensing process under 10 CFR 50. The earlier approach required first a construction permit and then an operating license, whereas the new approach allows a more streamlined (one step) combined license (COL) approach utilizing Standard Design Certifications via the regulatory framework created by 10 CFR 52. Other incentives include US Government backed loan guarantees as well as private company contributions. One aspect to the new process has been consideration and implementation of many new topic-specific regulations and industry standards which have continued to evolve during the past 30 years in spite of the lack of new plant design and construction activity. Therefore, an Owner attempting a new nuclear facility project under 10 CFR 52 needs to address a myriad of new requirements previously unconsidered. Several new projects including both power plants and fuel facilities have begun the new licensing process with its many new requirements to consider, but a uranium enrichment facility has run the gamut first. This paper will summarize many of the lessons learned from designing, constructing and testing this first new nuclear facility to be built in the US in over 30 years.(author).

  20. Design description of the vacuum vessel for the Advanced Toroidal Facility

    International Nuclear Information System (INIS)

    Chipley, K.K.; Nelson, B.E.; Vinyard, L.M.; Williamson, D.F.

    1983-01-01

    The Advanced Toroidal Facility (ATF) will be a stellarator experiment to investigate improvements in toroidal confinement. The vacuum vessel for this facility will provide the appropriate evacuated region for plasma containment within the helical field (HF) coils. The vessel is designed to provide the maximum reasonable volume inside the HF coils and to provide the maximum reasonable access for future diagnostics. The vacuum vessel design is at an early phase and all of the details have not been completed. The heat transfer analysis and stress analysis completed during the conceptual design indicate that the vessel will not change drastically

  1. Safety design of the international fusion materials irradiation facility (IFMIF)

    International Nuclear Information System (INIS)

    Konishi, Satoshi; Yamaki, Daiju; Katsuta, Hiroji; Moeslang, Anton; Jameson, R.A.; Martone, Marcello; Shannon, T.E.

    1997-11-01

    In the Conceptual Design Activity of the IFMIF, major subsystems, as well as the entire facility is carefully designed to satisfy the safety requirements for any possible construction sites. Each subsystem is qualitatively analyzed to identify possible hazards to the workers, public and environments using Failure Mode and Effect Analysis (FMEA). The results are reflected in the design and operation procedure. Shielding of radiation, particularly neutron around the test cell is one of the most important issue in normal operation. Radiation due to beam halo and activation is a hazard for operation personnel in the accelerator system. For the maintenance, remote handling technology is designed to be applied in various facilities of the IFMIF. Lithium loop and target system hold the majority of the radioactive material in the facility. Tritium and beryllium-7 are generated by the nuclear reaction during operation and thus needed to be removed continuously. They are also the potential hazards of airborne source in off-normal events. Minimization of inventory, separation and immobilization, and multiple confinement are considered in the design. Generation of radioactive waste is anticipated to be minor, but waste treatment systems for gas, liquid and solid wastes are designed to minimize the environmental impact. Lithium leak followed by a fire is a major concern, and extensive prevention plan is made in the target design. One of the design option considered is composed of; primary enclosure of the lithium loop, secondary containment filled with positive pressure argon, and an air tight lithium cell made of concrete with a steel lining. This study will report some technical issues considered in the design of IFMIF. It was concluded that the IFMIF can be designed and constructed to meet or exceed current safely standards for workers, public and the environment with existing technology and reasonable construction cost. (J.P.N.)

  2. Waste receiving and processing facility module 1, detailed design report

    International Nuclear Information System (INIS)

    1993-10-01

    WRAP 1 baseline documents which guided the technical development of the Title design included: (a) A/E Statement of Work (SOW) Revision 4C: This DOE-RL contractual document specified the workscope, deliverables, schedule, method of performance and reference criteria for the Title design preparation. (b) Functional Design Criteria (FDC) Revision 1: This DOE-RL technical criteria document specified the overall operational criteria for the facility. The document was a Revision 0 at the beginning of the design and advanced to Revision 1 during the tenure of the Title design. (c) Supplemental Design Requirements Document (SDRD) Revision 3: This baseline criteria document prepared by WHC for DOE-RL augments the FDC by providing further definition of the process, operational safety, and facility requirements to the A/E for guidance in preparing the design. The document was at a very preliminary stage at the onset of Title design and was revised in concert with the results of the engineering studies that were performed to resolve the numerous technical issues that the project faced when Title I was initiated, as well as, by requirements established during the course of the Title II design

  3. Irregular Shaped Building Design Optimization with Building Information Modelling

    Directory of Open Access Journals (Sweden)

    Lee Xia Sheng

    2016-01-01

    Full Text Available This research is to recognise the function of Building Information Modelling (BIM in design optimization for irregular shaped buildings. The study focuses on a conceptual irregular shaped “twisted” building design similar to some existing sculpture-like architectures. Form and function are the two most important aspects of new buildings, which are becoming more sophisticated as parts of equally sophisticated “systems” that we are living in. Nowadays, it is common to have irregular shaped or sculpture-like buildings which are very different when compared to regular buildings. Construction industry stakeholders are facing stiff challenges in many aspects such as buildability, cost effectiveness, delivery time and facility management when dealing with irregular shaped building projects. Building Information Modelling (BIM is being utilized to enable architects, engineers and constructors to gain improved visualization for irregular shaped buildings; this has a purpose of identifying critical issues before initiating physical construction work. In this study, three variations of design options differing in rotating angle: 30 degrees, 60 degrees and 90 degrees are created to conduct quantifiable comparisons. Discussions are focused on three major aspects including structural planning, usable building space, and structural constructability. This research concludes that Building Information Modelling is instrumental in facilitating design optimization for irregular shaped building. In the process of comparing different design variations, instead of just giving “yes or no” type of response, stakeholders can now easily visualize, evaluate and decide to achieve the right balance based on their own criteria. Therefore, construction project stakeholders are empowered with superior evaluation and decision making capability.

  4. Radiological design criteria for fusion power test facilities

    International Nuclear Information System (INIS)

    Singh, M.S.; Campbell, G.W.

    1982-01-01

    The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

  5. Design of fixed and mobile PET/CT facilities: the similarities and the challenges

    International Nuclear Information System (INIS)

    Peet, Debbie J.; Pryor, M.

    2008-01-01

    Design of PET/CT facilities present particular challenges for Radiation Protection. The high energy gamma ray emitted from the radionuclides used, the prolonged uptake period with patients within the facility and the relatively high dose rates from those patients result in some shielding being required and a careful consideration of the layout within each unit. This paper will present the approach used for the design of a fixed facility and will present staff dose data demonstrating that the design has resulted in low staff doses. The approach used to design mobile facilities will then be described, and a consideration of the doses received on this type of unit will also be given. The fixed facility was installed into a wooden clad building and was extremely small. The building was shared with other non radiation workers. Walls were constructed from dense concrete blocks and the layout arranged to prevent a direct line of site between the patient and workers at any point apart from the scan room where a lead glass window was used. For the mobile facility lead was used as the shielding material. The basic approach was to maximise the distance between operators and resting patients. Because of weight restrictions and limitation on the dose rate at the scanner defined by the scanner manufacturer, a higher dose constraint had to be adopted for staff on the unit. Additional complications include the mobility of the unit which can be parked adjacent to buildings with a variety of construction materials. Results of whole body monitoring for staff in the fixed facility over 5 years will be presented with the results from the mobile units over the last year. These will demonstrate the difficulties in keeping doses as low as reasonably achievable in the mobile scenario and the importance of designing the facility with staff dose in mind from the outset. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

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

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

    International Nuclear Information System (INIS)

    1995-07-01

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

  8. Cold Vacuum Drying facility design basis accident analysis documentation

    International Nuclear Information System (INIS)

    CROWE, R.D.

    2000-01-01

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls

  9. Design study of an ERL Test Facility at CERN

    CERN Document Server

    Jensen, E; Brüning, O; Calaga, R; Catalan-Lasheras, N; Goddard, B; Klein, M; Torres-Sanchez, R; Valloni, A

    2014-01-01

    The modern concept of an Energy Recovery Linac allows providing large electron currents at large beam energy with low power consumption. This concept is used in FEL’s, electron-ion colliders and electron coolers. CERN has started a Design Study of an ERL Test Facility with the purpose of 1) studying the ERL principle, its specific beam dynamics and operational issues, as relevant for LHeC, 2) providing a test bed for superconducting cavity modules, cryogenics and integration, 3) studying beam induced quenches in superconducting magnets and protection methods, 4) providing test beams for detector R&D and other applications. It will be complementary to existing or planned facilities and is fostering international collaboration. The operating frequency of 802 MHz was chosen for performance and for optimum synergy with SPS and LHC; the design of the cryomodule has started. The ERL Test Facility can be constructed in stages from initially 150 MeV to ultimately 1 GeV in 3 passes, with beam currents of up to 8...

  10. Design for the National RF Test Facility at ORNL

    International Nuclear Information System (INIS)

    Gardner, W.L.; Hoffman, D.J.; Becraft, W.R.

    1983-01-01

    Conceptual and preliminary engineering design for the National RF Test Facility at Oak Ridge National Laboratory (ORNL) has been completed. The facility will comprise a single mirror configuration embodying two superconducting development coils from the ELMO Bumpy Torus Proof-of-Principle (EBT-P) program on either side of a cavity designed for full-scale antenna testing. The coils are capable of generating a 1.2-T field at the axial midpoint between the coils separated by 1.0 m. The vacuum vessel will be a stainless steel, water-cooled structure having an 85-cm-radius central cavity. The facility will have the use of a number of continuous wave (cw), radio-frequency (rf) sources at levels including 600 kW at 80 MHz and 100 kW at 28 GHz. Several plasma sources will provide a wide range of plasma environments, including densities as high as approx. 5 x 10 13 cm -3 and temperatures on the order of approx. 10 eV. Furthermore, a wide range of diagnostics will be available to the experimenter for accurate appraisal of rf testing

  11. Cold Vacuum Drying facility design basis accident analysis documentation

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  12. Information Technology in Facilities Management - A Literature Review

    DEFF Research Database (Denmark)

    Ebbesen, Poul

    2015-01-01

    Purpose : The aim of this paper is to present the state of the art of research in Information Technology (IT) in Facilities Management (FM). Background : Initial studies indicate that investments into IT in FM often do not add the expected value, neither to the FM department itself nor...

  13. Conceptual design of technical security systems for Russian nuclear facilities physical protection

    International Nuclear Information System (INIS)

    Izmailov, A.V.

    1995-01-01

    Conceptual design of technical security systems (TSS) used in the early stages of physical protection systems (PPS) design for Russia nuclear facilities is discussed. The importance of work carried out in the early stages was noted since the main design solutions are being made within this period (i.e. selection of a structure of TSS and its components). The methods of analysis and synthesis of TSS developed by ''Eleron'' (MINATOM of Russia) which take into account the specific conditions of Russian nuclear facilities and a scope of equipment available are described in the review. TSS effectiveness assessment is based on a probability theory and a simulation. The design procedure provides for a purposeful choice of TSS competitive options including a ''cost-benefit'' criterion and taking into account a prechosen list of design basis threats to be used for a particular facility. The attention is paid to a practical aspect of the methods application as well as to the bilateral Russian-American scientific and technical co-operation in the PPS design field

  14. Designing a Physical Security System for Risk Reduction in a Hypothetical Nuclear Facility

    International Nuclear Information System (INIS)

    Saleh, A.A.; Abd Elaziz, M.

    2017-01-01

    Physical security in a nuclear facility means detection, prevention and response to threat, the ft, sabotage, unauthorized access and illegal transfer involving radioactive and nuclear material. This paper proposes a physical security system designing concepts to reduce the risk associated with variant threats to a nuclear facility. This paper presents a study of the unauthorized removal and sabotage in a hypothetical nuclear facility considering deter, delay and response layers. More over, the study involves performing any required upgrading to the security system by investigating the nuclear facility layout and considering all physical security layers design to enhance the weakness for risk reduction

  15. Family and Consumer Sciences: A Facility Planning and Design Guide for School Systems.

    Science.gov (United States)

    Maryland State Dept. of Education, Baltimore.

    This document presents design concepts and considerations for planning and developing middle and high school family and consumer sciences education facilities. It includes discussions on family and consumer sciences education trends and the facility planning process. Design concepts explore multipurpose laboratories and spaces for food/nutrition…

  16. When More is Less: The Case of Disconnected Information Systems in Indonesian Public Health Facilities

    Science.gov (United States)

    Wahid, Fathul; Teduh Dirgahayu, Raden; Hamzah, Almed; Setiaji, Hari

    2018-03-01

    The clear majority of previous studies have found that the absence of information systems to properly manage data is one of the main challenges in improving public health management. The present study offers an alternate perspective, revealing other emerging problems in cases where there are many information systems in place but without sufficient orchestration. The national government of Indonesia has been coercive in its implementation of various information systems without involving users at public health facilities, which has created many problems on the ground. The problems identified relate to the quality of the disconnected information systems currently in use, the lack of human resource development, unclear procedures, uncoordinated reports and the absence of an incentive scheme. The present study also highlights some practical implications, including the use of a more holistic perspective in designing and developing an integrated public health information infrastructure.

  17. Information Architecture the Design of Digital Information Spaces

    CERN Document Server

    Ding, Wei

    2009-01-01

    Information Architecture is about organizing and simplifying information, designing and integrating information spaces/systems, and creating ways for people to find and interact with information content. Its goal is to help people understand and manage information and make right decisions accordingly. In the ever-changing social, organizational and technological contexts, Information Architects not only design individual information spaces (e.g., individual websites, software applications, and mobile devices), but also tackle strategic aggregation and integration of multiple information spaces

  18. Seismic design considerations of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    2001-10-01

    An Advisory Group Meeting (AGM) on Seismic Technologies of Nuclear Fuel Cycle Facilities was convened in Vienna from 12 to 14 November 1997. The main objective of the meeting was the investigation of the present status of seismic technologies in nuclear fuel cycle facilities in Member States as a starting point for understanding of the most important directions and trends of national initiatives, including research and development, in the area of seismic safety. The AGM gave priority to the establishment of a consistent programme for seismic assessment of nuclear fuel cycle facilities worldwide. A consultants meeting subsequently met in Vienna from 16 to 19 March 1999. At this meeting the necessity of a dedicated programme was further supported and a technical background to the initiative was provided. This publication provides recommendations both for the seismic design of new plants and for re-evaluation projects of nuclear fuel cycle facilities. After a short introduction of the general IAEA approach, some key contributions from Member State participants are presented. Each of them was indexed separately

  19. COMPUTER ORIENTED FACILITIES OF TEACHING AND INFORMATIVE COMPETENCE

    Directory of Open Access Journals (Sweden)

    Olga M. Naumenko

    2010-09-01

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

  20. Consistent natural phenomena design and evaluation guidelines for U.S. Department of Energy facilities

    International Nuclear Information System (INIS)

    Murray, R.C.; Short, S.A.

    1989-01-01

    Uniform design and evaluation guidelines for protection against natural phenomena hazards such as earthquakes, extreme winds, and flooding for facilities at Department of Energy (DOE) sites throughout the United States have been developed. The guidelines apply to design of new facilities and to evaluation or modification of existing facilities. These guidelines are an approach for design or evaluation for mitigating the effects of natural phenomena hazards. These guidelines are intended to control the level of conservatism introduced in the design/evaluation process such that all hazards are treated on a reasonably consistent and uniform basis and such that the level of conservatism is appropriate for facility characteristics such as importance, cost, and hazards to on-site personnel, the general public, and the environment. The philosophy and goals of these guidelines are covered by this paper

  1. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  2. Proposed design criteria for a fusion facility electrical ground system

    International Nuclear Information System (INIS)

    Armellino, C.A.

    1983-01-01

    Ground grid design considerations for a nuclear fusion reactor facility are no different than any other facility in that the basis for design must be safety first and foremost. Unlike a conventional industrial facility the available fault energy comes not only from the utility source and in-house rotating machinery, but also from energy storage capacitor banks, collapsing magnetic fields and D.C. transmission lines. It is not inconceivable for a fault condition occurrence where all available energy can be discharged. The ground grid must adequately shunt this sudden energy discharge in a way that personnel will not be exposed by step and/or touch to hazardous energy levels that are in excess of maximum tolerable levels for humans. Fault energy discharge rate is a function of the ground grid surge impedance characteristic. Closed loop paths must be avoided in the ground grid design so that during energy discharge no stray magnetic fields or large voltage potentials between remote points can be created by circulating currents. Single point connection of equipment to the ground grid will afford protection to personnel and sensitive equipment by reducing the probability of circulating currents. The overall ground grid system design is best illustrated as a wagon wheel concept with the fusion machine at the center. Radial branches or spokes reach out to the perimeter limits designated by step-and-touch high risk areas based on soil resistivity criteria considerations. Conventional methods for the design of a ground grid with all of its radial branches are still pertinent. The center of the grid could include a deep well single ground rod element the length of which is at least equivalent to the radius of an imaginary sphere that enshrouds the immediate machine area. Special facilities such as screen rooms or other shielded areas are part of the ground grid system by way of connection to radial branches

  3. LSST summit facility construction progress report: reacting to design refinements and field conditions

    Science.gov (United States)

    Barr, Jeffrey D.; Gressler, William; Sebag, Jacques; Seriche, Jaime; Serrano, Eduardo

    2016-07-01

    The civil work, site infrastructure and buildings for the summit facility of the Large Synoptic Survey Telescope (LSST) are among the first major elements that need to be designed, bid and constructed to support the subsequent integration of the dome, telescope, optics, camera and supporting systems. As the contracts for those other major subsystems now move forward under the management of the LSST Telescope and Site (T and S) team, there has been inevitable and beneficial evolution in their designs, which has resulted in significant modifications to the facility and infrastructure. The earliest design requirements for the LSST summit facility were first documented in 2005, its contracted full design was initiated in 2010, and construction began in January, 2015. During that entire development period, and extending now roughly halfway through construction, there continue to be necessary modifications to the facility design resulting from the refinement of interfaces to other major elements of the LSST project and now, during construction, due to unanticipated field conditions. Changes from evolving interfaces have principally involved the telescope mount, the dome and mirror handling/coating facilities which have included significant variations in mass, dimensions, heat loads and anchorage conditions. Modifications related to field conditions have included specifying and testing alternative methods of excavation and contending with the lack of competent rock substrate where it was predicted to be. While these and other necessary changes are somewhat specific to the LSST project and site, they also exemplify inherent challenges related to the typical timeline for the design and construction of astronomical observatory support facilities relative to the overall development of the project.

  4. Design and shielding calculation for a PET/CT facility

    International Nuclear Information System (INIS)

    Martin Escuela, J. M.; Palau San Pedro, A.; Lopez Diaz, A.

    2013-01-01

    Following the AAPM Task Group Report No. 108, the NCRP Report No. 147 recommendations and the Cuban's local regulations for nuclear medicine practice were carried out the safety planning and design of a new PET/CT facility for the Nuclear Medicine Department of 'Hermanos Ameijeiras' Hospital. It should be installed in the top floor of the NM building (3th floor), occupied by offices, classrooms and ancillaries areas, meanwhile in the second floor is working the conventional nuclear medicine department. The radiation doses were evaluated in areas of the second, third and quarter floor taking into account the pet isotope, the workload, the occupancy factors of each place, the use factors of different sources and the dose reduction factors, warranty the accomplish of the Cuban dose restrictions associated to the nuclear medicine practice. In each point of calculation was considered the contribution from each source to the total dose, as well as the contribution of the CT in the adjacent room to the imaging room. For the proper facility design was considered the transmission factors of the existing barriers, and calculated the new ones to be added between each source and the estimation point, keeping in mind the space limitations. The PET/CT design plan meet all the needs, the development of the project is consistent with the mission of the facility and the radiation protection regulations of nuclear medicine. (Author)

  5. Science design for two shafts in phase 1a of the proposed rock characterisation facility at Sellafield, UK

    International Nuclear Information System (INIS)

    Ledingham, P.; Proughten, A.J.; Saulnier, G.J. Jr.

    1998-01-01

    In 1997, United Kingdom Nirex planned to begin construction of an underground Rock Characterisation Facility (RCF) at Sellafield as part of it's ongoing assessment of the suitability of the site as a host for a deep radioactive waste repository. The RCF was to have addressed issues relating to the geology, hydrogeology and geomechanical behaviour of the site by collecting data for testing predictive models and acquiring information only available from an underground situation. In March 1997, the UK Government refused permission for Nirex to begin construction and work at Sellafield was wound down. However, the science design for Phase 1a of the RCF, two vertical access shafts, was completed to provide a set of conceptual designs which address the issues identified by Nirex. By using Sellafield as an example, the designs contribute to a series of reports which demonstrate an approach to validation using an underground facility. This paper describes the Science Design for data collection during shaft construction, which began with the information requirements specified by Nirex on the basis of it's conceptual models and predictive work. It describes the scientific measurements designed to acquire this information and the process of combining the individual measurements into test plans for each shaft. Measurements were planned in the shafts themselves and in boreholes drilled from the shafts. They were designed to provide data on formation porosity and permeability, the geochemistry of formation water and the nature of the fresh-water salt-water interface, shaft inflow, the influence of geological structures on performance, and geomechanical responses to shaft excavation. A key element of the design process was the development of test plans, requiring the co-ordination and integration of the construction and science activities so that both could be carried out in a timely and cost-effective manner

  6. Physics design of fast reactor safety test facilities for in-pile experiments

    International Nuclear Information System (INIS)

    Travelli, A.; Matos, J.E.; Snelgrove, J.L.; Shaftman, D.H.; Tzanos, C.P.; Lam, S.K.; Pennington, E.M.; Woodruff, W.L.

    1976-01-01

    A determined effort to identify and resolve current Fast Breeder Reactor safety testing needs has recently resulted in a number of conceptual designs for FBR safety test facilities which are very complex and diverse both in their features and in their purpose. The paper discusses the physics foundations common to most fast reactor safety test facilities and the constraints which they impose on the design. The logical evolution, features, and capabilities of several major conceptual designs are discussed on the basis of this common background

  7. Design, construction and monitoring of temporary storage facilities for removed contaminants

    International Nuclear Information System (INIS)

    Saegusa, Hiromitsu; Funaki, Hironori; Kurikami, Hiroshi; Sakamoto, Yoshiaki; Tokizawa, Takayuki

    2013-01-01

    Since the Fukushima Daiichi nuclear power plant accident caused by the Tohoku Region Pacific Coast Earthquake on March 11, 2011, decontamination work has been conducted in the surrounding environment within the Fukushima prefecture. Removed contaminants including soil, grass and trees are to be stored safely at temporary storage facilities for up to three years, after which they will be transferred to a planned interim storage facility. The decontamination pilot project was carried out in both the restricted and planned evacuation areas in order to assess decontamination methods and demonstrate measures for radiation protection of workers. Fourteen temporary storage facilities of different technical specifications were designed and constructed under various topographic conditions and land use. In order to support the design, construction and monitoring of temporary storage facilities for removed contaminants during the full-scale decontamination within the prefecture of Fukushima, technical know-how obtained during the decontamination pilot project has been identified and summarized in this paper. (author)

  8. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 5 Book 7, contains cost estimate information for a monitored retrievable storage (MRS) facility. Cost estimates are for onsite improvements, waste storage, and offsite improvements for the Clinch River Site

  9. Design for the second phase Rokkasho LLW burial facility

    International Nuclear Information System (INIS)

    Kumata, Tadamasa

    1997-01-01

    Rokkasho Low Level radioactive Waste management center of Japan Nuclear Fuel Limited (hereafter called JNFL) has been operating for five years and about 90,000 (200 liter) drums have already been buried. Currently, JNFL is planning the 2nd phase of the burial program. The basic design of the new facility has been completed and applied for license additionally. Wastes buried in the 2nd phase facility are mainly dry active wastes from nuclear power plants. Inflammable wastes except for plastics are incinerated before they are disposed, because organic materials can generate gas and their degraded materials affect the distribution coefficients of the radionuclides. Most of the aluminum wastes which can generate hydrogen gas by corrosion are also removed from the waste. The 2nd phase facility accepts metal, plastics and non-flammable wastes. These are solidified with mortar in the 200 liter drums at the power plants. The radioactive inventory of the 2nd phase facility is considered to be as much as that of the 1st phase facility. (author)

  10. Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

    International Nuclear Information System (INIS)

    1986-09-01

    This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

  11. Principles of Emergency Department facility design for optimal management of mass-casualty incidents.

    Science.gov (United States)

    Halpern, Pinchas; Goldberg, Scott A; Keng, Jimmy G; Koenig, Kristi L

    2012-04-01

    The Emergency Department (ED) is the triage, stabilization and disposition unit of the hospital during a mass-casualty incident (MCI). With most EDs already functioning at or over capacity, efficient management of an MCI requires optimization of all ED components. While the operational aspects of MCI management have been well described, the architectural/structural principles have not. Further, there are limited reports of the testing of ED design components in actual MCI events. The objective of this study is to outline the important infrastructural design components for optimization of ED response to an MCI, as developed, implemented, and repeatedly tested in one urban medical center. In the authors' experience, the most important aspects of ED design for MCI have included external infrastructure and promoting rapid lockdown of the facility for security purposes; an ambulance bay permitting efficient vehicle flow and casualty discharge; strategic placement of the triage location; patient tracking techniques; planning adequate surge capacity for both patients and staff; sufficient command, control, communications, computers, and information; well-positioned and functional decontamination facilities; adequate, well-located and easily distributed medical supplies; and appropriately built and functioning essential services. Designing the ED to cope well with a large casualty surge during a disaster is not easy, and it may not be feasible for all EDs to implement all the necessary components. However, many of the components of an appropriate infrastructural design add minimal cost to the normal expenditures of building an ED. This study highlights the role of design and infrastructure in MCI preparedness in order to assist planners in improving their ED capabilities. Structural optimization calls for a paradigm shift in the concept of structural and operational ED design, but may be necessary in order to maximize surge capacity, department resilience, and patient and

  12. Preliminary conceptual design and cost estimation for Korea Advanced Pyroprocessing Facility Plus (KAPF+)

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il, E-mail: nwiko@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Lee, Ho Hee, E-mail: nhhlee@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Choi, Sungyeol, E-mail: csy@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, Sung-Ki, E-mail: sgkim1@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Park, Byung Heung, E-mail: b.h.park@ut.ac.kr [Department of Chemical and Biological Engineering, Korea National University of Transportation, 50 Daehak-ro, Chungju-si, Chungbuk, 380-702 (Korea, Republic of); Lee, Hyo Jik, E-mail: hyojik@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, In Tae, E-mail: nitkim@kaeri.re.kr [Department of Chemical and Biological Engineering, Korea National University of Transportation, 50 Daehak-ro, Chungju-si, Chungbuk, 380-702 (Korea, Republic of); Lee, Han Soo, E-mail: hslee5@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

    2014-10-01

    Highlights: • Conceptual design is created for a pilot pyroprocessing plant treating PWR spent fuel. • Pilot-scale design is based on a capacity of 400 tHM/yr with 60 years lifetime. • All individual processes are integrated into a single system from feed to products. • Overall facility design is developed for a pilot pyroprocessing plant. • Unit process cost is estimated for pyroprocessing with uncertainties. - Abstract: Korea has developed pyroprocessing technology as a potential option for recycling spent fuels (SFs) from pressurized water reactors (PWRs). The pyroprocessing consists of various key unit processes and a number of research activities have been focused on each process. However, to realize the whole pyroprocessing concept, there is a critical need for integrating the individual developments and addressing a material flow from feed to final products. In addition, the advancement on overall facility design is an indispensable aspect for demonstration and commercialization of the pyroprocessing. In this study, a facility named as Korea Advanced Pyroprocess Facility Plus (KAPF+) is conceptualized with a capacity of 400 tHM/yr. The process steps are categorized based on their own characteristics while the capacities of process equipment are determined based on the current technical levels. The facility concept with a site layout of 104,000 m{sup 2} is developed by analyzing the operation conditions and materials treated in each process. As an economic approach to the proposed facility, the unit cost (781 $/kgHM denominated in 2009 USD) for KAPF+ is also analyzed with the conceptual design with preliminary sensitivity assessments including decontamination and decommissioning costs, a discount rate, staffing costs, and plant lifetime. While classifying and describing cost details of KAPF+, this study compares the unit cost of KAPF+ treating PWR SF to that of the pyroprocessing facility treating sodium-cooled fast reactor (SFR) SF.

  13. Waste Receiving and Processing Facility, Module 1: Volume 7, Project design criteria

    International Nuclear Information System (INIS)

    1992-03-01

    This Project Design Criteria document for the WRAP facility at the Hanford Site is presented within a systems format. The WRAP Module 1 facility has been categorized into eight (8) engineering systems for design purposes. These systems include: receiving, shipping and storage, nondestructive assay/nondestructive examination (NDA/NDE), waste process, internal transportation, building, heating ventilation and air conditioning (HVAC), process control, and utilities. Within each system section of this document, the system-specific requirements are identified. The scope of the system is defined, the design goals are identified and the functional requirements are detailed

  14. Development of Facility Type Information Packages for Design of Air Force Facilities.

    Science.gov (United States)

    1983-03-01

    Washington: Government Printing Office. 49. U.S. Department of the Army. Project Development Brochures ; Part I, Functional Requirements. TM 5-800-3...Washington: Government Printing Office. May, 1974. 50. U.S. Department of the Air Force. Air Force Interior Design Pamplet . AFP 88-41. Washington: Govern

  15. Conceptual design for the Waste Receiving and Processing facility Module 2A

    International Nuclear Information System (INIS)

    1992-07-01

    This is part of a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at Hanford Reservation. The mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated at WRAP Module 2A include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluenttreatment facilities, thermal treatment facility ash, other WRAP modules, and other miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume V, provides a comprehensive conceptual design level narrative description of the process, utility, ventilation, and plant control systems. The feeds and throughputs, design requirements, and basis for process selection are provided, as appropriate. Key DOE/WHC criteria and reference drawings are delineated

  16. Cyclotron Produced Radionuclides: Guidance on Facility Design and Production of [18F]Fluorodeoxyglucose (FDG)

    International Nuclear Information System (INIS)

    2012-01-01

    Positron emission tomography (PET) has advanced rapidly in recent years and is becoming an indispensable imaging modality for the evaluation and staging of cancer patients. A key component of the successful operation of a PET centre is the on-demand availability of radiotracers (radiopharmaceuticals) labelled with suitable positron emitting radioisotopes. Of the hundreds of positron labelled radiotracers, 2-[ 18 F]-fluoro-2-deoxy-D-glucose (FDG) is the most successful and widely used imaging agent in PET today. While FDG is utilized largely in oncology for the management of cancer patients, its applications in neurology and cardiology are also steadily growing. A large number of PET facilities have been established in Member States over the past few years, and more are being planned. The design and operation of a facility for the production of FDG requires attention to detail, in particular the application of good manufacturing practices (GMP) guidelines and quality assurance. The product must conform to the required quality specifications and must be safe for human use. This book is intended to be a resource manual with practical information for planning and operating an FDG production facility, including design and implementation of the laboratories, facility layout, equipment, personnel and FDG quality assessment. GMP and quality management are discussed only briefly, since these topics are covered extensively in the IAEA publication Cyclotron Produced Radionuclides: Guidelines for Setting up a Facility (Technical Reports Series No. 471). It should be noted that manufacturing processes and quality specifications for FDG are not currently globally harmonized, and these do vary to some extent. However, there is no disagreement over the need to ensure that the product is manufactured in a controlled manner, that it conforms to applicable quality specifications and that it is safe for human use. Administrators, managers, radiopharmaceutical scientists, production

  17. Shielding calculations for the design of neutron radiography facility around PARR

    International Nuclear Information System (INIS)

    Ashraf, M.M.; Khan, A.R.

    1989-06-01

    Shielding calculations for neutron radiography facility, proposed to be established around PARR have been carried out using two group diffusion theory and shielding formulae. Gamma radiation penetration calculations have been carried out using simple attenuation methods. The fabrication and installation of the neutron radiography facility would provide the basis for designing a better collimating system and would help establish under water radiography facility for the inspection of highly radioactive materials and components etc. (orig./A.B.)

  18. 77 FR 3787 - Notice of Submission of Proposed Information Collection to OMB; Office of Hospital Facilities...

    Science.gov (United States)

    2012-01-25

    ... administration and initial/final endorsement of projects undertaken by Office of Hospital Facilities. DATES... Proposed Information Collection to OMB; Office of Hospital Facilities Transactional Forms for FHA Programs... Lists the Following Information Title of Proposal: Office of Hospital Facilities Transactional Forms for...

  19. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Johnson, C.E.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is designed for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both Safeguards and Production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  20. The FR 2 reactor at Karlsruhe, F.R. Germany and associated hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the FR 2 reactor and associated hot cell facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

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

    International Nuclear Information System (INIS)

    Beller, D.E.

    1986-01-01

    A new conceptual design of a fusion reactor blanket simulation facility was developed. This design follows the principles that have been successfully employed in the Purdue Fast Breeder Blanket Facility (FBBR), because experiments conducted in it have resulted in the discovery of deficiencies in neutronics prediction methods. With this design, discrepancies between calculation and experimental data can be fully attributed to calculation methods because design deficiencies that could affect results are insignificant. Inelastic scattering cross sections are identified as a major source of these discrepancies. The conceptual design of this FBBR analog, the fusion reactor blanket facility (FRBF), is presented. Essential features are a cylindrical geometry and a distributed, cosine-shaped line source of 14-MeV neutrons. This source can be created by sweeping a deuteron beam over an elongated titanium-tritide target. To demonstrate that the design of the FRBF will not contribute significant deviations in experimental results, neutronics analyses were performed: results of comparisons of 2-dimensional to 1-dimensional predictions are reported for two blanket compositions. Expected deviations from 1-D predictions which are due to source anisotropy and blanket asymmetry are minimal. Thus, design of the FRBF allows simple and straightforward interpretation of the experimental results, without a need for coarse 3-D calculations

  2. CERN Heavy-Ion Facility design report

    International Nuclear Information System (INIS)

    Warner, D.; Angert, N.; Bourgarel, M.P.; Brouzet, E.; Cappi, R.; Dekkers, D.; Evans, J.; Gelato, G.; Haseroth, H.; Hill, C.E.; Hutter, G.; Knott, J.; Kugler, H.; Lombardi, A.; Lustig, H.; Malwitz, E.; Nitsch, F.; Parisi, G.; Pisent, A.; Raich, U.; Ratzinger, U.; Riccati, L.; Schempp, A.; Schindl, K.; Schoenauer, H.; Tetu, P.; Umstaetter, H.H.; Rooij, M. van; Weiss, M.

    1993-01-01

    The design of the CERN Heavy-Ion Facility is described. This facility will be based on a new ion linear accelerator (Linac 3), together with improvements to the other accelerators of the CERN complex to allow them to cope with heavy ions, i.e. to the Proton Synchrotron Booster (PSB), the Proton Synchrotron (PS) and the Super Proton Synchrotron (SPS). For this reference design, the pure isotope of lead, 208 Pb, is considered. The bulk of the report describes Linac 3, a purpose-built heavy-ion linac mainly designed and constructed in collaboration with several CERN member state laboratories, but also with contributions from non-member states. Modifications and improvements to existing CERN accelerators essentially concern the RF acceleration, beam control and beam monitoring (all machines), beam kickers and septa at the input and output of the PSB, and major vacuum improvements, aiming to reduce the pressure by factors of at least seven and three in the PSB and PS respectively. After injection from the Electron Cyclotron Resonance source at 2.5 keV/u the partially stripped heavy-ion beam is accelerated successively by a Radio Frequency Quadrupole and an Interdigital-H linac to 4.2 MeV/u. After stripping to 208 Pb 53+ , the beam is again accelerated, firstly in the PSB (to 98.5 MeV/u), then in the PS (to 4.25 GeV/u). The final stage of acceleration in the SPS takes the fully stripped 208 Pb 82+ ions to 177 GeV/u, delivering a beam of 4.10 8 ions per SPS supercycle (15.2 s) to the experiments. The first physics run with lead ions is scheduled for the end of 1994. Finally, some requirements for carrying out heavy-ion physics at the Large Hadron Collider are mentioned. (orig.)

  3. Effects of increased nurses' workload on quality documentation of patient information at selected Primary Health Care facilities in Vhembe District, Limpopo Province.

    Science.gov (United States)

    Shihundla, Rhulani C; Lebese, Rachel T; Maputle, Maria S

    2016-05-13

    Recording of information on multiple documents increases professional nurses' responsibilities and workload during working hours. There are multiple registers and books at Primary Health Care (PHC) facilities in which a patient's information is to be recorded for different services during a visit to a health professional. Antenatal patients coming for the first visit must be recorded in the following documents: tick register; Prevention of Mother-ToChild Transmission (PMTCT) register; consent form for HIV and AIDS testing; HIV Counselling and Testing (HCT) register (if tested positive for HIV and AIDS then this must be recorded in the Antiretroviral Therapy (ART) wellness register); ART file with an accompanying single file, completion of which is time-consuming; tuberculosis (TB) suspects register; blood specimen register; maternity case record book and Basic Antenatal Care (BANC) checklist. Nurses forget to record information in some documents which leads to the omission of important data. Omitting information might lead to mismanagement of patients. Some of the documents have incomplete and inaccurate information. As PHC facilities in Vhembe District render twenty four hour services through a call system, the same nurses are expected to resume duty at 07:00 the following morning. They are expected to work effectively and when tired a nurse may record illegible information which may cause problems when the document is retrieved by the next person for continuity of care. The objective of this study was to investigate and describe the effects of increased nurses' workload on quality documentation of patient information at PHC facilities in Vhembe District, Limpopo Province. The study was conducted in Vhembe District, Limpopo Province, where the effects of increased nurses' workload on quality documentation of information is currently experienced. The research design was explorative, descriptive and contextual in nature. The population consisted of all nurses who

  4. Present status of the conceptual design of IFMIF target facility

    International Nuclear Information System (INIS)

    Katsuta, H.; Kato, Y.; Konishi, S.; Miyauchi, Y.; Smith, D.; Hua, T.; Green, L.; Benamati, G.; Cevolani, S.; Roehrig, H.; Schutz, W.

    1998-01-01

    The conceptual design activity (CDA) for the international fusion materials irradiation facility (IFMIF) has been conducted. For the IFMIF target facility, the conceptual designs of the following two main components have been performed. The design concept of IFMIF utilizes a high energy deuteron beam of 30-40 MeV and total current of 250 mA, impinging on a flowing lithium jet to produce high energy neutrons for irradiation of candidate fusion materials. (1) The target assembly: The kinetic energy of the deuteron beam is deposited on a Li-jet target and neutrons are produced through the d-Li stripping reaction in this target. The assembly is designed to get a stable lithium jet and to prevent the onset of lithium boiling. For 40-MeV deuteron beam (total current of 250 mA) and a beam footprint of 5 x 20 cm 2 lithium jet dimensions are designed to be 2.5 cm thick and 26 cm wide. The lithium jet parameters are given. (2) Lithium loop: The loop circulates the lithium to and from the target assembly and removes the heat deposited by the deuteron beam containing systems for maintaining the-high purity of the lithium required for radiological safety and to minimize corrosion. The maximum lithium flow rate is 130 l/s and the total lithium inventory is about 21 m 3 . The IFMIF policy requires that the lithium loop system be designed to guarantee no combustion of lithium in the event of a lithium leak. This can be achieved by use of multiple confinement of the lithium carrying components. The radioactive waste generated by the target facilities is estimated. (orig.)

  5. Information and communications technology facilities at the tertiary level education in some urban universities in Bangladesh

    Directory of Open Access Journals (Sweden)

    F. M. Shahriar

    2016-07-01

    Full Text Available With the advent of digitalization, information and communications technology facilities have become an indispensable part of education especially at the universities. This study has been undertaken with dual purposes - to find the existing scenario of information and communications technology facilities and to gauge the perception of the students onthe quality of those facilities - at the universities in Bangladesh. To that end, a survey was conducted on the undergraduate and graduate students of 9 private and public universities. To assess the quality of information and communications technology services, participants’ views on various aspects like the sufficiency of computers, availability of required software, maintenance and troubleshooting, internet and data sharing facilities, etc. were collected and analyzed. The study finds that although students are on the happier side with the information and communications technology installations and equipment, they are fairly unhappy about the maintenance services and internet facilities available at their universities. It gives some valuable insights about the information and communications technology facilities scenario at the universities that can be taken into consideration while planning future action plan and development of information and communications technology at the universities in Bangladesh.

  6. Survey of neutron radiography facilities

    International Nuclear Information System (INIS)

    Imel, G.R.; McClellan, G.G.

    1996-01-01

    A directory of neutron radiography facilities around the world was informally compiled about ten years ago under the auspices of the American Society for Testing and Materials (ASTM), Subcommittee E7.05 (Radiology, Neutron). The work lay dormant for a number of years, but was revived in earnest in the fall of 1995. At that time, letters were mailed to all the facilities with available addresses in the original directory, requesting updated information. Additionally, information was gathered at the Second Topical meeting on neutron Radiography Facility System Design and Beam Characterization (November, 1995, Shonan Village, Japan). A second mailing was sent for final confirmation and updates in January, 1996. About 75% of the information in the directory has now been confirmed by the facility management. This paper presents a summary of the information contained in the facility directory. An electronic version of the directory in Wordperfect 6.1, uuencode, or rtf format is available by sending e-mail to the authors at imel at sign anl.gov or imel at sign baobab.cad.cea.fr. A WWW site for the directory is presently under construction

  7. 21 CFR 1.235 - How and when do you cancel your facility's registration information?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false How and when do you cancel your facility's... for Registration of Food Facilities § 1.235 How and when do you cancel your facility's registration information? (a) Notification of registration cancellation. A facility canceling its registration must do so...

  8. Long-Baseline Neutrino Facility (LBNF) and Deep Underground Neutrino Experiment (DUNE): Conceptual Design Report. Volume 3: Long-Baseline Neutrino Facility for DUNE

    Energy Technology Data Exchange (ETDEWEB)

    Strait, James [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); McCluskey, Elaine [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Lundin, Tracy [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Willhite, Joshua [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Hamernik, Thomas [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Papadimitriou, Vaia [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Marchionni, Alberto [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Kim, Min Jeong [National Inst. of Nuclear Physics (INFN), Frascati (Italy). National Lab. of Frascati (INFN-LNF); Nessi, Marzio [Univ. of Geneva (Switzerland); Montanari, David [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States); Heavey, Anne [Fermi National Accelerator Laboratory (FNAL), Batavia, IL (United States)

    2016-01-21

    This volume of the LBNF/DUNE Conceptual Design Report covers the Long-Baseline Neutrino Facility for DUNE and describes the LBNF Project, which includes design and construction of the beamline at Fermilab, the conventional facilities at both Fermilab and SURF, and the cryostat and cryogenics infrastructure required for the DUNE far detector.

  9. Biosafety Procedure for Safe Handling of Genetically Modified Plant Materials in Bio Design Facility

    International Nuclear Information System (INIS)

    Zaiton Ahmad; Shuhaimi Shamsudin; Mohamed Najli Mohamed Yasin; Affrida Abu Hassan; Mohd Zaid Hassan; Rusli Ibrahim

    2015-01-01

    Bio Design Facility is the specifically designed glass house for propagation, screening and analysis of high quality plant varieties developed through biotechnology or a combination of nuclear technology and biotechnology. High quality plant varieties especially genetically modified plants (GMO) require a special glass house facility for propagation and screening to isolate them from cross-pollinating with wild type varieties in surrounding ecosystem, and for carrying out evaluation of possible risks of the plants to human, animal and environment before they are proven safe for field trials or commercial release. This facility which was developed under the Ninth Malaysia Plan is classified as the Plant Containment Level 2 and is compliance with the bio safety regulations and guidance for the safe release of GMO according to Malaysian Bio safety Act 2007. Bio Design Facility is fully operational since 2010 and in 2012, it has also been certified as the glass house for post-entry quarantine by The Department of Agriculture. This paper summarizes the bio safety procedure for a safe, controlled and contained growing and evaluation of GMO in Bio Design Facility. This procedure covers the physical (containment and equipment's) and operational (including responsibility, code of practice, growing, decontamination and disposal of plant materials, emergency and contingency plan) aspects of the facility. (author)

  10. Codes, standards, and requirements for DOE facilities: natural phenomena design

    International Nuclear Information System (INIS)

    Webb, A.B.

    1985-01-01

    The basic requirements for codes, standards, and requirements are found in DOE Orders 5480.1A, 5480.4, and 6430.1. The type of DOE facility to be built and the hazards which it presents will determine the criteria to be applied for natural phenomena design. Mandatory criteria are established in the DOE orders for certain designs but more often recommended guidance is given. National codes and standards form a great body of experience from which the project engineer may draw. Examples of three kinds of facilities and the applicable codes and standards are discussed. The safety program planning approach to project management used at Westinghouse Hanford is outlined. 5 figures, 2 tables

  11. Design of facilities for processing pyrophoric radioactive material

    International Nuclear Information System (INIS)

    Bristow, H.A.S.; Hunter, S.D.

    1976-01-01

    The safe processing of large quantities of plutonium-bearing material poses difficult problems the solution of which sometimes involves conflicting requirements. The difficulties are increased when plutonium of a high burnup is used and the position becomes considerably more complicated when the chemical nature of the material being handled is such that it is pyrophoric. This paper describes the design principles and methods used to establish a facility capable of manufacturing large quantities of mixed plutonium/uranium carbide. The facility which included process stages such as milling, granulation, pellet pressing, furnacing and pin filling, was largely a conversion of an existing processing line. The paper treats the major plant hazards individually and indicates the methods used to counter them, outlining the main design principles employed and describing their application to selected items of equipment. Examples of the problems encountered with typical items of equipment are discussed. Some guide-lines are listed which should be of general value to designers and developers working on equipment for processing plutonium-bearing solids. The methods described have been successfully employed to provide a plant for the manufacture of mixed plutonium/uranium carbide on a scale of many hundreds of kilograms with no serious incident.(author)

  12. Third International Meeting on Next Generation Safeguards: Safeguards-by-Design at Enrichment Facilities

    International Nuclear Information System (INIS)

    Long, Jon D.; McGinnis, Brent R.; Morgan, James B.; Whitaker, Michael; Lockwood, Dunbar; Shipwash, Jacqueline L.

    2011-01-01

    The Third International Meeting on Next Generation Safeguards (NGS3) was hosted by the U.S. Department of Energy (DOE)/National Nuclear Security Administration's (NNSA) Office of Nonproliferation and International Security (NIS) in Washington, D.C. on 14-15 December 2010; this meeting focused on the Safeguards-by-Design (SBD) concept. There were approximately 100 participants from 13 countries, comprised of safeguards policy and technical experts from government and industry. Representatives also were present from the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), the European Atomic Energy Agency (Euratom), and the International Atomic Energy Agency (IAEA). The primary objective of this meeting was to exchange views and provide recommendations on implementation of the SBD concept for four specific nuclear fuel cycle facility types: gas centrifuge enrichment plants (GCEPs), GEN III and GEN IV reactors, aqueous reprocessing plants, and mixed oxide fuel fabrication facilities. The general and facility-specific SBD documents generated from the four working groups, which were circulated for comment among working group participants, are intended to provide a substantive contribution to the IAEA's efforts to publish SBD guidance for these specific types of nuclear facilities in the near future. The IAEA has described the SBD concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' As part of the Next Generation Safeguards Initiative (NGSI), the DOE is working to establish SBD as a global norm through DOE laboratory studies, international workshops, engagement with industry and the IAEA, and setting an example through its use in new nuclear facilities in the United States. This paper describes the discussion topics and final recommendations of the Enrichment Facilities Working

  13. Design study of the underground facilities, the Mizunami Underground Research Laboratory

    International Nuclear Information System (INIS)

    Ishizuka, Mineo; Noda, Masaru; Shiogama, Yukihiro; Adachi, Tetsuya

    1999-02-01

    Geoscientific research on the deep geological environment has been performed by Japan Nuclear Cycle Development Institute (JNC). This research is supported by the 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. The Mizunami Underground Research Laboratory (MIU) is planned to be constructed at the Shobasama-bora site belonging to JNC. A wide range of geoscientific research and development activities which have been previously performed in and around the Tono mine is planned to be expanded in the laboratory. The MIU consisted of surface and underground facilities excavated to a depth of about 1,000 meters. In this design study, the overall layout and basic design of the underground facility and the composition of the overall research program, includes the construction of the underground facility are studied. Based on the concept of the underground facility which have been developed in 1998, the research activities which will be performed in the MIU are selected and the overall research program is revised in this year. The basic construction method and the construction equipment are also estimated. (author)

  14. Design study of underground facility of the Mizunami Underground Research Laboratory

    International Nuclear Information System (INIS)

    Ishizuka, Mineo; Noda, Masaru; Shiogama, Yukihiro; Adachi, Tetsuya

    1999-02-01

    Geoscientific research on deep geological environment has been performed by Japan Nuclear Cycle Development Institute (JNC). This research is supported by the 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. The Mizunami Underground Research Laboratory (MIU) is planned to be constructed at Shobasama-bora site belonging to JNC. A wide range of geoscientific research and development activities which have been previously performed in and around the Tono mine is planned to be expanded in the laboratory. The MIU is consisted of surface and underground facilities down to the depth of about 1,000 meters. In this design study, the overall layout and basic design of the underground facility and the composition of the overall research program which includes the construction of the underground facility are studied. Based on the concept of the underground facility which have been developed last year, the research activities which will be performed in the MIU are selected and the overall research program is revised in this year. The basic construction method and the construction equipment are also estimated. (author)

  15. Decontamination and decommissioning criteria for use in design of new plutonium facilities

    International Nuclear Information System (INIS)

    Paschall, R.K.

    1975-01-01

    Decontamination and decommissioning (D and D) criteria were assembled for use in designing new plutonium facilities. These criteria were gathered from literature searches and visits to many plutonium facilities around the country. The recommendations of reports and experienced personnel were used. Since total D and D costs can be millions of dollars, improved designs to facilitate D and D will result in considerable savings in cost and time and will help to leave the site for unrestricted future use after D and D. Finally, better design will reduce hazards and improve safety during the D and D effort

  16. The FRJ 1 reactor (MERLIN) at Juelich, F.R. Germany and associated hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the FRJ 1 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  17. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD 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.

  18. Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Process Water Conditioning (PWC) System. The SDD 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), the HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the PWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD 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

  19. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD 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

  20. Need of geotechnical investigations for civil design of Nuclear Fuel Cycle Facilities

    International Nuclear Information System (INIS)

    Sharma, Sudin; Bhalerao, Sandip; Subramanyam, P.; Bhargava, Kapilesh; Agarwal, Kailash; Rao, D.A.S.; Roy, Amitava; Basu, S.

    2015-01-01

    An adequate assessment of the site geologic and geotechnical conditions is one of the most important aspects in safety evaluation of a Nuclear Fuel Cycle Facility (NFCF). Evaluation of safety of either a new or an existing NFCF requires, among other things, that its founding strata has been adequately examined, explored, and investigated so that it is as fully understood as possible. Foundation explorations should be directed towards obtaining only such information as may be important to an evaluation of Safety of the NFCF Civil structures of NFCF generally impose heavy loads on the foundation systems. Safe design of foundation aims at providing sound foundation systems for the structures so that they can fulfil their functional requirements towards the objective of nuclear safety. This paper aims at discussing various geotechnical tests and there importance in the safe evaluation and design of civil structures of NFCF in India. (author)

  1. 40 CFR 270.315 - What air emissions control information must I keep at my facility?

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What air emissions control information... Facility § 270.315 What air emissions control information must I keep at my facility? If you have air emission control equipment subject to 40 CFR part 264, subpart CC, you must keep the following information...

  2. Impact of certain safeguards considerations on fuel-cycle facility design

    International Nuclear Information System (INIS)

    Darby, J.L.; de Montmollin, J.M.

    1979-01-01

    Both physical protection and containment/surveillance systems impact plant design and operations. Effective physical protection systems can be systematically designed; work on designing containment/surveillance systems is in progress. Fuel fabrication facility designers need to be cognizant of these safeguards system developments to enable effective implementation of them with as little effect on plant functions as possible. This brief overview provides a general indication of what the impacts of the systems might be, and current thinking on their structure

  3. Design and operation of off-gas cleaning and ventilation systems in facilities handling low and intermediate level radioactive material

    International Nuclear Information System (INIS)

    1988-01-01

    The number of developing countries constructing new nuclear facilities is increasing. These facilities include the production and processing of radioisotopes, as well as all types of laboratories and installations, which handle radioactive material and deal with the treatment of radioactive wastes. Ventilation and air cleaning systems are a vital part of the general design of any nuclear facility. The combination of a well designed ventilation system with thorough cleaning of exhaust air is the main method of preventing radioactive contamination of the air in working areas and in the surrounding atmosphere. This report provides the latest information on the design and operation of off-gas cleaning and ventilation systems for designers and regulatory authorities in the control and operation of such systems in nuclear establishments. The report presents the findings of an Advisory Group Meeting held in Vienna from 1 to 5 December 1986 and attended by 12 experts from 11 Member States. Following this meeting, a revised report was prepared by the International Atomic Energy Agency Secretariat and three consultants, M.J. Kabat (Canada), W. Stotz (Federal Republic of Germany) and W.A. Fairhurst (United Kingdom). The final draft was commented upon and approved by the participants of the meeting. 69 refs, 37 figs, 12 tabs

  4. Design of the Waste Receiving and Processing (WRAP) 2A Facility

    International Nuclear Information System (INIS)

    Lamberd, D.L.; Weingardt, K.M.

    1994-07-01

    Radioactive and Hazardous Mixed Waste have accumulated at the US Department of Energy (DOE) Hanford Site in south-central Washington State. Future generated waste streams from planned facilities at the Hanford Site and off site will also generate solid wastes that contain both radiological and hazardous chemical components. Most of the low-level waste (LLW) in this category is generated in batches sized to be stored in smaller containers (mostly 55-gallon drums and boxes). To meet the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions, most of this waste will need to be treated to meet disposal requirements. In general this treatment must include stabilization/solidification either as a sole method or as part of a treatment train. A planned DOE facility, the Waste Receiving and Processing (WRAP) Module 2A, Building 2337-W, is scoped to provide this required treatment for containerized contact-handle at sign d (CH), mixed low-level waste (MLLW) at the Hanford Site. The core processes in WRAP Module 2A include cement stabilization of particulate waste, polyethylene encapsulation (via extrusion) of particulate waste, and cement encapsulation (via vibratory infilling) of hard and soft debris. A conceptual design was prepared and issued in July 1992. Since that time, process development test activities and further design iterations have evolved into the optimized process and facility design presented in this paper. This paper will discuss the revised processing scheme, equipment configuration, and facility layout. The WRAP Module 2A will begin construction in 1996 after a detailed design effort and pilot testing activities

  5. 120-D-1 (100-D) Ponds supplemental information to the Hanford Facility Contingency Plan. Revision 2

    International Nuclear Information System (INIS)

    Petersen, S.W.; Zoric, J.P.

    1997-06-01

    This document is a supplement to the Hanford Facility Contingency Plan and provides the unit-specific information needed to fully comply with the Washington Administrative Code 173-303 for contingency plans. The 100-D ponds are unlined surface impoundments that were mainly used to dispose of nondangerous wastewater, The ponds are designated as a single treatment, storage, and/or disposal unit because of potential corrosive characteristics of the wastewater. No waste is currently present at the 100-D Ponds

  6. Conceptual design for the Waste Receiving and Processing facility Module 2A

    International Nuclear Information System (INIS)

    1992-07-01

    This is part of a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at the Hanford Reservation. The mission of the facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluent treatment facilities, thermal treatment facility ash, other WRAP modules, and other miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume III is a compilation of the outline specifications that will form the basis for development of the Title design construction specifications. This volume contains abbreviated CSI outline specifications for equipment as well as non-equipment related construction and material items. For process and mechanical equipment, data sheets are provided with the specifications which indicate the equipment overall design parameters. This volume also includes a major equipment list

  7. Comparison of SBLOCA Test Results with the FESTA Facility for the SMART Design

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Hyobong; Park, Hyun--Sik; Bae, Hwang; Ryu, Sung-Uk; Ko, Young-Joo; Yi, Sung-Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The FESTA facility is a full height, 1/49-volume scaled test facility with four trains of a secondary system and PRHRS, and can be used to investigate the integral performance of the interconnected components and possible thermal-hydraulic phenomena occurring in the SMART (System-Integrated Modular Advanced Reactor) design, and to validate its safety for various design basis accidents and broad transient scenarios. The role of FESTA can be extended to examine and verify the normal, abnormal, and emergency operating procedures required during the construction phases of SMART. During the design of the FESTA facility, the height is preserved to the full scale, and its area and volume are scaled down to 1/49 compared with the prototype plant, SMART. The scaling ratios adopted in FESTA with respect to SMART are summarized in Table 1. The maximum core power is 2..0 MW, which is about 30% of the scaled full power. The design pressure and temperature of SMART-ITL can simulate the maximum operating conditions, that is, 18.0 MPa and 350 .deg. C. A preliminary analysis of small-break loss of coolant accident (SBLOCA) tests using the MARS/KS code for FESTA was previously conducted. In addition, major test results of SBLOCA scenarios with the VISTA-ITL facility for the SMART design were discussed. In this research, three SBLOCA experimental tests of a safety injection system (SIS) line break, shutdown cooling system (SCS) line break and pressurizer safety valve (PSV) line break for the SMART design were successfully performed and its major results have been compared and discussed. An integral effect test has been performed for the SBLOCA scenario for the SMART design with the FESTA facility.

  8. 1325-N Liquid Waste Disposal Facility Supplemental Information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

    International Nuclear Information System (INIS)

    Edens, V.G.

    1998-03-01

    The 1325-N Liquid Waste Disposal Facility located at the 100-N Area of the Hanford Site started receiving part of the N Reactor liquid radioactive effluent flow in 1983. In September 1985, the 1325-N Facility became the primary liquid waste disposal system for the N Reactor. The facility is located approximately 60 feet above and 2000 feet east of the shore of the Columbia River. Waste stream discharges were ceased in April 1991.Specific information on types of waste discharged to 1325-N are contained within the Part A, Form 3, Permit application of this unit

  9. National Ignition Facility site requirements

    International Nuclear Information System (INIS)

    1996-07-01

    The Site Requirements (SR) provide bases for identification of candidate host sites for the National Ignition Facility (NIF) and for the generation of data regarding potential actual locations for the facilities. The SR supplements the NIF Functional Requirements (FR) with information needed for preparation of responses to queries for input to HQ DOE site evaluation. The queries are to include both documents and explicit requirements for the potential host site responses. The Sr includes information extracted from the NIF FR (for convenience), data based on design approaches, and needs for physical and organization infrastructure for a fully operational NIF. The FR and SR describe requirements that may require new construction or may be met by use or modification of existing facilities. The SR do not establish requirements for NIF design or construction project planning. The SR document does not constitute an element of the NIF technical baseline

  10. Workshop on CEBAF [Continuous Electron Beam Accelerator Facility] spectrometer magnet design and technology: Proceedings

    International Nuclear Information System (INIS)

    1986-09-01

    The planned experimental program at CEBAF includes high-resolution, large acceptance spectrometers and a large toroidal magnetic, detector. In order to take full advantage of the high quality beam characteristics, the performances required will make these devices quite unique instruments compared to existing facilities in the same energy range. Preliminary designs have shown that such performances can be reached, but key questions concerning design concepts and most appropriate and cost-effective technologies had to be answered before going further with the designs. It was the purpose of the Workshop on CEBAF Spectrometer Magnet Design and Technology, organized by the CEBAF Research and Engineering Divisions, to provide the most complete information about the state-of-the-art tools and techniques in magnet design and construction and to discuss the ones most appropriate to the CEBAF spectrometers. In addition, it is expected that this Workshop will be the staring point for further interactions and collaborations between international magnet experts and the CEBAF staff, during the whole process of designing and building the spectrometers

  11. Effects of increased nurses’ workload on quality documentation of patient information at selected Primary Health Care facilities in Vhembe District, Limpopo Province

    Directory of Open Access Journals (Sweden)

    Rhulani C. Shihundla

    2016-05-01

    Full Text Available Background: Recording of information on multiple documents increases professional nurses’ responsibilities and workload during working hours. There are multiple registers and books at Primary Health Care (PHC facilities in which a patient’s information is to be recorded for different services during a visit to a health professional. Antenatal patients coming for the first visit must be recorded in the following documents: tick register; Prevention of Mother-ToChild Transmission (PMTCT register; consent form for HIV and AIDS testing; HIV Counselling and Testing (HCT register (if tested positive for HIV and AIDS then this must be recorded in the Antiretroviral Therapy (ART wellness register; ART file with an accompanying single file, completion of which is time-consuming; tuberculosis (TB suspects register; blood specimen register; maternity case record book and Basic Antenatal Care (BANC checklist. Nurses forget to record information in some documents which leads to the omission of important data. Omitting information might lead to mismanagement of patients. Some of the documents have incomplete and inaccurate information. As PHC facilities in Vhembe District render twenty four hour services through a call system, the same nurses are expected to resume duty at 07:00 the following morning. They are expected to work effectively and when tired a nurse may record illegible information which may cause problems when the document is retrieved by the next person for continuity of care. Objectives: The objective of this study was to investigate and describe the effects of increased nurses’ workload on quality documentation of patient information at PHC facilities in Vhembe District, Limpopo Province. Methods: The study was conducted in Vhembe District, Limpopo Province, where the effects of increased nurses’ workload on quality documentation of information is currently experienced. The research design was explorative, descriptive and contextual in

  12. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    International Nuclear Information System (INIS)

    2009-01-01

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

  13. Magnet Design Considerations for Fusion Nuclear Science Facility

    Energy Technology Data Exchange (ETDEWEB)

    Zhai, Y. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Kessel, C. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); El-Guebaly, L. [Univ. of Wisconsin, Madison, WI (United States) Fusion Technology Institute; Titus, P. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

    2016-06-01

    The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement facility that provides a fusion environment with components of the reactor integrated together to bridge the technical gaps of burning plasma and nuclear science between the International Thermonuclear Experimental Reactor (ITER) and the demonstration power plant (DEMO). Compared with ITER, the FNSF is smaller in size but generates much higher magnetic field, i.e., 30 times higher neutron fluence with three orders of magnitude longer plasma operation at higher operating temperatures for structures surrounding the plasma. Input parameters to the magnet design from system code analysis include magnetic field of 7.5 T at the plasma center with a plasma major radius of 4.8 m and a minor radius of 1.2 m and a peak field of 15.5 T on the toroidal field (TF) coils for the FNSF. Both low-temperature superconductors (LTS) and high-temperature superconductors (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion magnet technology. The higher magnetic field can be achieved by using the high-performance ternary restacked-rod process Nb3Sn strands for TF magnets. The circular cable-in-conduit conductor (CICC) design similar to ITER magnets and a high-aspect-ratio rectangular CICC design are evaluated for FNSF magnets, but low-activation-jacket materials may need to be selected. The conductor design concept and TF coil winding pack composition and dimension based on the horizontal maintenance schemes are discussed. Neutron radiation limits for the LTS and HTS superconductors and electrical insulation materials are also reviewed based on the available materials previously tested. The material radiation limits for FNSF magnets are defined as part of the conceptual design studies for FNSF magnets.

  14. A Supply Chain Design Problem Integrated Facility Unavailabilities Management

    Directory of Open Access Journals (Sweden)

    Fouad Maliki

    2016-08-01

    Full Text Available A supply chain is a set of facilities connected together in order to provide products to customers. The supply chain is subject to random failures caused by different factors which cause the unavailability of some sites. Given the current economic context, the management of these unavailabilities is becoming a strategic choice to ensure the desired reliability and availability levels of the different supply chain facilities. In this work, we treat two problems related to the field of supply chain, namely the design and unavailabilities management of logistics facilities. Specifically, we consider a stochastic distribution network with consideration of suppliers' selection, distribution centres location (DCs decisions and DCs’ unavailabilities management. Two resolution approaches are proposed. The first approach called non-integrated consists on define the optimal supply chain structure using an optimization approach based on genetic algorithms (GA, then to simulate the supply chain performance with the presence of DCs failures. The second approach called integrated approach is to consider the design of the supply chain problem and unavailabilities management of DCs in the same model. Note that, we replace each unavailable DC by performing a reallocation using GA in the two approaches. The obtained results of the two approaches are detailed and compared showing their effectiveness.

  15. Preliminary design of a Tandem-Mirror-Next-Step facility

    International Nuclear Information System (INIS)

    Damm, C.C.; Doggett, J.N.; Bulmer, R.H.

    1980-01-01

    The Tandem-Mirror-Next-Step (TMNS) facility is designed to demonstrate the engineering feasibility of a tandem-mirror reactor. The facility is based on a deuterium-tritium (D-T) burning, tandem-mirror device with a fusion power output of 245 MW. The fusion power density in the central cell is 2.1 MW/m 3 , with a resultant neutron wall loading of 0.5 MW/m 2 . Overall machine length is 116 m, and the effective central-cell length is 50.9 m. The magnet system includes end cells with yin-yang magnets to provide magnetohydrodynamic (MHD) stability and thermal-barrier cells to help achieve a plasma Q of 4.7 (where Q = fusion power/injected power). Neutral beams at energies up to 200 keV are used for plasma heating, fueling, and barrier pumping. Electron cyclotron resonant heating at 50 and 100 GHz is used to control the electron temperature in the barriers. Based on the resulting engineering design, the overall cost of the facility is estimated to be just under $1 billion. Unresolved physics issues include central-cell β-limits against MHD ballooning modes (the assumed reference value of β exceeds the current theory-derived limit), and the removal of thermalized α-particles from the plasma

  16. Field test facility for monitoring water/radionuclide transport through partially saturated geologic media: design, construction, and preliminary description

    International Nuclear Information System (INIS)

    Phillips, S.J.; Campbell, A.C.; Campbell, M.D.; Gee, G.W.; Hoober, H.H.; Schwarzmiller, K.O.

    1979-11-01

    Shallow land burial has been a common practice for disposing radioactive waste materials since the beginning of plutonium production operations. Accurate monitoring of radionuclide transport and factors causing transport within the burial sites is essential to minimizing risks associated with disposal. However, monitoring has not always been adequate. Consequently, the Department of Energy (DOE) has begun a program aimed at better assuring and evaluating containment of radioactive wastes at shallow land burial sites. This program includes a technological base for monitoring transport. As part of the DOE program, Pacific Northwest Laboratory (PNL) is developing geohydrologic monitoring systems to evaluate burial sites located in arid regions. For this project, a field test facility was designed and constructed to assess monitoring systems for near-surface disposal of radioactive waste and to provide information for evaluating site containment performance. The facility is an integrated network of monitoring devices and data collection instruments. This facility is used to measure water and radionuclide migration under field conditions typical of arid regions. Monitoring systems were developed to allow for measurement of both mass and energy balance. Work on the facility is ongoing. Continuing work includes emplacement of prototype monitoring instruments, data collection, and data synthesis. At least 2 years of field data are needed to fully evaluate monitoring information

  17. Adaptation of the ITER facility design to a Canadian site

    International Nuclear Information System (INIS)

    Smith, S.

    2001-01-01

    This paper presents the status of Canadian efforts to adapt the newly revised ITER facility design to suit the specific characteristics of the proposed Canadian site located in Clarington, west of Toronto, Ontario. ITER Canada formed a site-specific design team in 1999, comprising participants from three Canadian consulting companies to undertake this work. The technical aspects of this design activity includes: construction planning, geotechnical investigations, plant layout, heat sink design, electrical system interface, site-specific modifications and tie-ins, seismic design, and radwaste management. These areas are each addressed in this paper. (author)

  18. World Energy Data System (WENDS). Volume VII. Nuclear facility profiles, AG--CH. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  19. World Energy Data System (WENDS). Volume VIII. Nuclear facility profiles, CO--HU. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  20. World Energy Data System (WENDS). Volume IX. Nuclear facility profiles, IN--PL. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  1. World Energy Data System (WENDS). Volume X. Nuclear facility profiles, PO--ZA. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  2. 9 CFR 93.309 - Horse quarantine facilities; payment information.

    Science.gov (United States)

    2010-01-01

    ...; payment information. (a) Privately operated quarantine facilities. The importer, or his or her agent, of... and sanitary to the satisfaction of the inspector assigned to supervise the quarantine. If for any... accordance with the procedure described in paragraph (b) of this section. The importer, or his or her agent...

  3. Conceptual design report for the away from reactor spent fuel storage facility, Savannah River Plant

    International Nuclear Information System (INIS)

    1978-12-01

    The Department of Energy (DOE) requested that Du Pont prepare a conceptual design and appraisal of cost for Federal budget planning for an away from reactor spent fuel storage facility that could be ready to store fuel by December 1982. This report describes the basis of the appraisal of cost in the amount of $270,000,000 for all facilities. The proposed action is to provide a facility at the Savannah River Plant. The facility will have an initial storage capacity of 5000 metric tons of spent fuel and will be capable of receiving 1000 metric tons per year. The spent fuel will be stored in water-filled concrete basins that are lined with stainless steel. The modular construction of the facility will allow future expansion of the storage basins and auxiliary services in a cost-effective manner. The facility will be designed to receive, handle, decontaminate and reship spent fuel casks; to remove irradiated fuel from casks; to place the fuel in a storage basin; and to cool and control the quality of the water. The facility will also be designed to remove spent fuel from storage basins, load the spent fuel into shipping casks, decontaminated loaded casks and ship spent fuel. The facility requires a license by the Nuclear Regulatory Commission (NRC). Features of the design, construction and operations that may affect the health and safety of the workforce and the public will conform with NRC requirements. The facility would be ready to store fuel by January 1983, based on normal Du Pont design and construction practices for DOE. The schedule does not include the effect of licensing by the NRC. To maintain this option, preparation of the documents and investigation of a site at the Savannah River Plant, as required for licensing, were started in FY '78

  4. DESIGN OF FILL AND FINISH FACILITY FOR ACTIVE PHARMACEUTICAL INGREDIENTS (API

    Directory of Open Access Journals (Sweden)

    NUUR LAILA KHAIRUDDIN

    2016-08-01

    Full Text Available Fill and finish operations continue to be one of the most heavily outsourced activities in the biopharmaceutical manufacturing market today. There are a few aspects that need to be consider in outsource activities like logistic, storage condition, facility certification and audit as regulations and standards which the manufacturer should adhere. Risk would be greater and extra care should be taken when outsource from foreign fill and finish facility. Thus, the internal aseptic fill and finish facility with audit checklist will help to minimize the risk during logistic and storage and also minimize the cost for outsource fill and finish facility. The data collections are through survey and conceptual design with simulation as the execution part.

  5. The design of diagnostic medical facilities using ionizing radiation

    International Nuclear Information System (INIS)

    1988-03-01

    This Code, setting out the general principles of radiological protection as applied to diagnostic radiation facilities in hospitals and clinics, is intended as a guide to architects and to works departments concerned with their design and construction, and with the modification of existing units

  6. How to implement security controls for an information security program at CBRN facilities

    International Nuclear Information System (INIS)

    Lenaeus, Joseph D.; O'Neil, Lori Ross; Leitch, Rosalyn M.; Glantz, Clifford S.; Landine, Guy P.; Bryant, Janet L.; Lewis, John; Mathers, Gemma; Rodger, Robert; Johnson, Christopher

    2015-01-01

    This document was prepared by PNNL within the framework of Project 19 of the European Union Chemical Biological Radiological and Nuclear Risk Mitigation Centres of Excellence Initiative entitled, ''Development of procedures and guidelines to create and improve secure information management systems and data exchange mechanisms for CBRN materials under regulatory control.'' It provides management and workers at CBRN facilities, parent organization managers responsible for those facilities, and regulatory agencies (governmental and nongovernmental) with guidance on the best practices for protecting information security. The security mitigation approaches presented in this document were chosen because they present generally accepted guidance in an easy-to-understand manner, making it easier for facility personnel to grasp key concepts and envision how security controls could be implemented by the facility. This guidance is presented from a risk management perspective.

  7. How to implement security controls for an information security program at CBRN facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lenaeus, Joseph D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); O' Neil, Lori Ross [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Leitch, Rosalyn M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glantz, Clifford S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Landine, Guy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bryant, Janet L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lewis, John [National Nuclear Lab., Workington (United Kingdom); Mathers, Gemma [National Nuclear Lab., Workington (United Kingdom); Rodger, Robert [National Nuclear Lab., Workington (United Kingdom); Johnson, Christopher [National Nuclear Lab., Workington (United Kingdom)

    2015-12-01

    This document was prepared by PNNL within the framework of Project 19 of the European Union Chemical Biological Radiological and Nuclear Risk Mitigation Centres of Excellence Initiative entitled, ''Development of procedures and guidelines to create and improve secure information management systems and data exchange mechanisms for CBRN materials under regulatory control.'' It provides management and workers at CBRN facilities, parent organization managers responsible for those facilities, and regulatory agencies (governmental and nongovernmental) with guidance on the best practices for protecting information security. The security mitigation approaches presented in this document were chosen because they present generally accepted guidance in an easy-to-understand manner, making it easier for facility personnel to grasp key concepts and envision how security controls could be implemented by the facility. This guidance is presented from a risk management perspective.

  8. 48 CFR 3004.470 - Security requirements for access to unclassified facilities, Information Technology resources...

    Science.gov (United States)

    2010-10-01

    ... access to unclassified facilities, Information Technology resources, and sensitive information. 3004.470... Technology resources, and sensitive information. ... ACQUISITION REGULATION (HSAR) GENERAL ADMINISTRATIVE MATTERS Safeguarding Classified and Sensitive Information...

  9. American Health Information Management Association. Position statement. Issue: managing health information in facility mergers and acquisitions.

    Science.gov (United States)

    1994-04-01

    Healthcare facility mergers and acquisitions are becoming more common as the industry consolidates. Many critical issues must be considered in mergers and acquisitions, including the management of patient health information. In addition to operational issues, licensure, regulatory, and accreditation requirements must be addressed. To ensure availability of health information to all legitimate users, patient records should be consolidated or linked in the master patient index. A record retention policy should be developed and implemented to meet user needs and assure compliance with legal, regulatory, and accreditation requirements. If health information from closed facilities will be stored for a period of time, its integrity and confidentiality must be preserved, and it must be readily accessible for patient care. The compatibility and functionality of existing information systems should be assessed, and a plan should be formulated for integration of the systems to the extent possible. Such integration may be essential for the organization to successfully meet the demands of integrated delivery systems. Existing databases should be maintained in an accessible form to meet anticipated future needs.

  10. Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

    International Nuclear Information System (INIS)

    Soli T. Khericha

    2006-01-01

    This report presents preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T and FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420 C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation

  11. Staff Technical Position on geological repository operations area underground facility design: Thermal loads

    International Nuclear Information System (INIS)

    Nataraja, M.S.

    1992-12-01

    The purpose of this Staff Technical Position (STP) is to provide the US Department of Energy (DOE) with a methodology acceptable to the Nuclear Regulatory Commission staff for demonstrating compliance with 10 CFR 60.133(i). The NRC staff's position is that DOE should develop and use a defensible methodology to demonstrate the acceptability of a geologic repository operations area (GROA) underground facility design. The staff anticipates that this methodology will include evaluation and development of appropriately coupled models, to account for the thermal, mechanical, hydrological, and chemical processes that are induced by repository-generated thermal loads. With respect to 10 CFR 60.133(i), the GROA underground facility design: (1) should satisfy design goals/criteria initially selected, by considering the performance objectives; and (2) must satisfy the performance objectives 10 CFR 60.111, 60.112, and 60.113. The methodology in this STP suggests an iterative approach suitable for the underground facility design

  12. Design of neutron radiography facility in pool for the reactor RA-10

    International Nuclear Information System (INIS)

    Peirone, M.; Coleff, A.; Sanchez, F.; Chiaraviglio, N.

    2013-01-01

    RA-10 project consists in the design and construction of a multipurpose reactor for multiple applications, including radioisotopes production, material testing and an in pool facility for neutron imaging. Neutron imaging is a powerful tool for studies of materials and offer several advantages among other attenuation-based techniques. In this study mechanical and neutronic requirements for the RA-10 in pool neutron imaging facility are described. The MCNP neutronic model and the mechanical design satisfying these requirements in a first engineering stage are described. (author)

  13. Cyclotron Produced Radionuclides: Guidance on Facility Design and Production of [{sup 18}F]Fluorodeoxyglucose (FDG)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-01-15

    Positron emission tomography (PET) has advanced rapidly in recent years and is becoming an indispensable imaging modality for the evaluation and staging of cancer patients. A key component of the successful operation of a PET centre is the on-demand availability of radiotracers (radiopharmaceuticals) labelled with suitable positron emitting radioisotopes. Of the hundreds of positron labelled radiotracers, 2-[{sup 18}F]-fluoro-2-deoxy-D-glucose (FDG) is the most successful and widely used imaging agent in PET today. While FDG is utilized largely in oncology for the management of cancer patients, its applications in neurology and cardiology are also steadily growing. A large number of PET facilities have been established in Member States over the past few years, and more are being planned. The design and operation of a facility for the production of FDG requires attention to detail, in particular the application of good manufacturing practices (GMP) guidelines and quality assurance. The product must conform to the required quality specifications and must be safe for human use. This book is intended to be a resource manual with practical information for planning and operating an FDG production facility, including design and implementation of the laboratories, facility layout, equipment, personnel and FDG quality assessment. GMP and quality management are discussed only briefly, since these topics are covered extensively in the IAEA publication Cyclotron Produced Radionuclides: Guidelines for Setting up a Facility (Technical Reports Series No. 471). It should be noted that manufacturing processes and quality specifications for FDG are not currently globally harmonized, and these do vary to some extent. However, there is no disagreement over the need to ensure that the product is manufactured in a controlled manner, that it conforms to applicable quality specifications and that it is safe for human use. Administrators, managers, radiopharmaceutical scientists

  14. Overview of the main challenges for the engineering design of the test facilities system of IFMIF

    International Nuclear Information System (INIS)

    Molla, J.; Nakamura, K.

    2009-01-01

    High intense radiation fields were demanded to IFMIF to address the lack of information on effects in materials due to radiation fields with fusion reactor features. Such intense radiation fields will also produce a number of unwanted effects in exposed materials and components. The main difficulties to achieve a reliable engineering design of the Test Facilities System during the Engineering Validation and the Engineering Design phase of IFMIF now under development are reviewed in this paper. The most challenging activities will be the design of the high flux test module, the creep fatigue test module, the test cell and the remote handling system. The intense radiation fields in the irradiation area and the high availability required for IFMIF (70%) are the main reasons for these difficulties.

  15. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1976-01-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially severe impacts on plant operations are to be averted. A facilities safeguards system suitable for a production plant is described in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides an information and actions at the safeguards/operations interface

  16. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1978-06-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially-severe impacts on plant operations are to be averted. This paper describes a facilities safeguards system suitable for production plant, in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely-coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides information and actions at the safeguards/operations interface

  17. Design guides for radioactive-material-handling facilities and equipment

    International Nuclear Information System (INIS)

    Doman, D.R.; Barker, R.E.

    1980-01-01

    Fourteen key areas relating to facilities and equipment for handling radioactive materials involved in examination, reprocessing, fusion fuel handling and remote maintenance have been defined and writing groups established to prepare design guides for each areas. The guides will give guidance applicable to design, construction, operation, maintenance and safety, together with examples and checklists. Each guide will be reviewed by an independent review group. The guides are expected to be compiled and published as a single document

  18. Design of Test Facility to Evaluate Boric Acid Precipitation Following a LOCA

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Jeong-Kwan; Song, Yong-Jae [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The U.S.NRC has identified a concern that debris associated with generic safety issue (GSI) - 191 may affect the potential precipitation of boric acid due to one or more of the following phenomena: - Reducing mass transport (i.e. mixing) between the core and the lower plenum (should debris accumulate at the core inlet) - Reduced lower plenum volume (should debris settle in the lower plenum), and, - Increased potential for boric acid precipitation (BAP) in the core (should debris accumulate in suspension in the core) To address these BAP issues, KHNP is planning to conduct validation tests by constructing a BAP test facility. This paper describes the design of test facility to evaluate BAP following a LOCA. The design of BAP test facility has been developed by KHNP. To design the test facility, test requirements and success criteria were established, and scaling analysis of power-to-volume method, Ishii-Kataoka method, and hierarchical two-tiered method were investigated. The test section is composed of two fuel assemblies with half of full of prototypic FA height. All the fuel rods are heated by the electric power supplier. The BAP tests in the presence of debris, buffering agents, and boron will be performed following the test matrix.

  19. Taking into account of dismantling constraints in the design of nuclear facilities

    International Nuclear Information System (INIS)

    Gouhier, E.; Moitrier, C.; Girones, P.; Pitrou, Y.; Poncet, P.; O'Sullivan, P.

    2014-01-01

    The taking into account of dismantling constraints in the design of nuclear facilities allows the reduction of the dosimetry during the dismantling operations, the reduction of the amount of wastes to manage and the saving of time and money by foreseeing an adequate and simple solution for each component. It is to notice that the strategy of life-extension strengthens that of dismantling because life-extension implies the possibility for any component of the reactor except the pressure vessel to be replaced. The feedback experience capitalized on various types of nuclear facilities have enabled IAEA and OECD to publish recommendations to facilitate dismantling. For instance, pipes and ventilation ducts must be designed to minimize the deposit of dust and residues, the natural porosity of concrete must be limited through the use of polishing products or a metal liner, the type and concentrations of impurities present in the structure materials must be controlled to limit radioactivation, the documentation describing the facility must be kept up to date, or the history of contamination events must be recorded all along the life of the facility. The integration of the dismantling constraints in the design stage is illustrated with 3 examples: the Georges Besse 2 enrichment fuel plant, new reactors (EPR, ASTRID and RJH), and ITER. (A.C.)

  20. Large scale sodium interactions. Part 1. Test facility design

    International Nuclear Information System (INIS)

    King, D.L.; Smaardyk, J.E.; Sallach, R.A.

    1977-01-01

    During the design of the test facility for large scale sodium interaction testing, an attempt was made to keep the system as simple and yet versatile as possible; therefore, a once through design was employed as opposed to any type of conventional sodium ''loop.'' The initial series of tests conducted at the facility call for rapidly dropping from 20 kg to 225 kg of sodium at temperatures from 825 0 K to 1125 0 K into concrete crucibles. The basic system layout is described. A commercial drum heater is used to melt the sodium which is in 55 gallon drums and then a slight argon pressurization is used to force the liquid sodium through a metallic filter and into a dump tank. Then the sodium dump tank is heated to the desired temperature. A diaphragm is mechanically ruptured and the sodium is dumped into a crucible that is housed inside a large steel test chamber

  1. Progress report on the design of a Low-Level Waste Pilot Facility at ORNL

    International Nuclear Information System (INIS)

    Hensley, L.C.; Turner, V.L.; Pruitt, A.S.

    1980-01-01

    All low-level radioactive solid wastes, excluding TRU wastes, are disposed of by shallow land burial at the Oak Ridge National Laboratory. Contaminated liquids and sludges are hydrofractures. The TRU wastes are stored in a retrievable fashion in concrete storage facilities. Currently, the capacity for low-level radioactive waste burial at the Oak Ridge National Laboratory is adequate for another six years of service at the current solids disposal rate which ranges between 80,000 and 100,000 cu ft per year. Decontamination and decommissioning of a number of ORNL facilities will be a significant activity in the next few years. Quantities of radioactive materials to be stored or disposed of as a result of these activities will be large; therefore, the technology to dispose of large quantities of low-level radioactive wastes must be demonstrated. The UCC-ND Engineering Division, in concert with divisions of the Oak Ridge National Laboratory, has been requested to prepare a conceptual design for a facility to both dispose of the currently produced low-level radioactive waste and also to provide a test bed for demonstration of other processes which may be used in future low-level radioactive wastes disposal facilities. This facility is designated as the Low-Level Waste Pilot Facility (LLWPF). This paper describes the status of the conceptual design of a facility for disposal of the subject radioactive waste

  2. Incorporating Workflow Interference in Facility Layout Design: The Quartic Assignment Problem

    OpenAIRE

    Wen-Chyuan Chiang; Panagiotis Kouvelis; Timothy L. Urban

    2002-01-01

    Although many authors have noted the importance of minimizing workflow interference in facility layout design, traditional layout research tends to focus on minimizing the distance-based transportation cost. This paper formalizes the concept of workflow interference from a facility layout perspective. A model, formulated as a quartic assignment problem, is developed that explicitly considers the interference of workflow. Optimal and heuristic solution methodologies are developed and evaluated.

  3. Construction of BIM-based SMART-ITL Facility Management System

    International Nuclear Information System (INIS)

    Jeon, Woo-Jin; Yi, Sung-Jae; Park, Hyun-Sik; Ryu, Sung-Uk; Bae, Hwang; Hwang, Sang-Chul; Min, Byung-Eui

    2015-01-01

    The flow area and volume are scaled down to 1/49. The ratio of the hydraulic diameter is 1/7. Therefore, SMART-ITL is a large-scale thermalhydraulic test facility with about 45 m height, which is consisted of 10 m underground and 35 m from the ground level. Until now, the management of design data and maintenance of large scale test facilities have been managed based on hard-copy information. Recently, Thermal Hydraulics Safety Research Division (THSRD) at Korea Atomic Energy Research Institute (KAERI) has developed Facility Management System (FMS) based Building Information Modeling (BIM) to manage its design data more effectively for these large scale test facilities of SMART-ITL and ATLAS, and this BIM technology has been applied to SMART-ITL at the first. This study proposed a method of effective management and maintenance of design data applied to the SMART-ITL. That is, a FMS was developed based on the BIM technology for SMART-ITL. Figure 2 shows an overview of FMS development process based on BIM technology. SMART-ITL FMS facilitates its management and maintenance more effectively and accurately by 3- dimensional visualization. It enables the shape information of large scale test facilities to be visualized intuitively in a virtual space, and the efficient maintenance of data and instruments is possible by linking 3D shape information

  4. Construction of BIM-based SMART-ITL Facility Management System

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Woo-Jin; Yi, Sung-Jae; Park, Hyun-Sik; Ryu, Sung-Uk; Bae, Hwang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Hwang, Sang-Chul; Min, Byung-Eui [DDRsoft Co., Daejeon (Korea, Republic of)

    2015-10-15

    The flow area and volume are scaled down to 1/49. The ratio of the hydraulic diameter is 1/7. Therefore, SMART-ITL is a large-scale thermalhydraulic test facility with about 45 m height, which is consisted of 10 m underground and 35 m from the ground level. Until now, the management of design data and maintenance of large scale test facilities have been managed based on hard-copy information. Recently, Thermal Hydraulics Safety Research Division (THSRD) at Korea Atomic Energy Research Institute (KAERI) has developed Facility Management System (FMS) based Building Information Modeling (BIM) to manage its design data more effectively for these large scale test facilities of SMART-ITL and ATLAS, and this BIM technology has been applied to SMART-ITL at the first. This study proposed a method of effective management and maintenance of design data applied to the SMART-ITL. That is, a FMS was developed based on the BIM technology for SMART-ITL. Figure 2 shows an overview of FMS development process based on BIM technology. SMART-ITL FMS facilitates its management and maintenance more effectively and accurately by 3- dimensional visualization. It enables the shape information of large scale test facilities to be visualized intuitively in a virtual space, and the efficient maintenance of data and instruments is possible by linking 3D shape information.

  5. Facility model for the Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

    1986-01-01

    The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

  6. Forum Guide to Facilities Information Management: A Resource for State and Local Education Agencies. NFES 2012-808

    Science.gov (United States)

    National Forum on Education Statistics, 2012

    2012-01-01

    Safe and secure facilities that foster learning are crucial to providing quality education services, and developing and maintaining these facilities requires considerable resources and organization. Facility information systems allow education organizations to collect and manage data that can be used to inform and guide decisionmaking about the…

  7. 17 CFR 37.8 - Information relating to transactions on derivatives transaction execution facilities.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 1 2010-04-01 2010-04-01 false Information relating to transactions on derivatives transaction execution facilities. 37.8 Section 37.8 Commodity and Securities Exchanges COMMODITY FUTURES TRADING COMMISSION DERIVATIVES TRANSACTION EXECUTION FACILITIES § 37.8...

  8. Value Engineering. "A Working Tool for Cost Control in the Design of Educational Facilities."

    Science.gov (United States)

    Lawrence, Jerry

    Value Engineering (VE) is a cost optimizing technique used to analyze design quality and cost-effectiveness. The application of VE procedures to the design and construction of school facilities has been adopted by the state of Washington. By using VE, the optimum value for every life cycle dollar spent on a facility is obtained by identifying not…

  9. Design and evaluation of physical protection systems of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    An, Jin Soo; Lee, Hyun Chul; Hwang, In Koo; Kwack, Eun Ho; Choi, Yung Myung

    2001-06-01

    Nuclear material and safety equipment of nuclear facilities are required to be protected against any kind of theft or sabotage. Physical protection is one of the measures to prevent such illegally potential threats for public security. It should cover all the cases of use, storage, and transportation of nuclear material. A physical protection system of a facility consists of exterior intrusion sensors, interior intrusion sensors, an alarm assessment and communication system, entry control systems, access delay equipment, etc. The design of an effective physical protection system requires a comprehensive approach in which the designers define the objective of the system, establish an initial design, and evaluate the proposed design. The evaluation results are used to determine whether or not the initial design should be modified and improved. Some modelling techniques are commonly used to analyse and evaluate the performance of a physical protection system. Korea Atomic Energy Research Institute(KAERI) has developed a prototype of software as a part of a full computer model for effectiveness evaluation for physical protection systems. The input data elements for the prototype, contain the type of adversary, tactics, protection equipment, and the attributes of each protection component. This report contains the functional and structural requirements defined in the development of the evaluation computer model.

  10. Towards Identification of Rotordynamic Properties for Seals in Multiphase Flow Using Active Magnetic Bearings. Design and Commissioning of a Novel Test Facility

    DEFF Research Database (Denmark)

    Voigt, Andreas Jauernik

    important contact free force measurement capabilities. The third module houses the smooth annular test seals and the fourth module adds a single phase air flow supply to the test facility infrastructure. For experimental identification purposes the ability to acquire precise information of the forces...... developed and refined, however a pronounced lack of experimental data renders benchmarking and validation impossible. This thesis focusses on documenting the design and commissioning of a test facility enabling the much needed experimental identification of rotordynamic properties for turbomachinery seals...... in both single phase and multiphase flow. The commissioning phase of the test facility solely employs single phase air flow for performance assessment of the test facility and no experimental multiphase results are included in the thesis. The test facility consists of four modules of which an industrial...

  11. Design of 500kW grate fired test facility using CFD

    DEFF Research Database (Denmark)

    Rosendahl, Lasse Aistrup; Kær, Søren Knudsen; Jørgensen, K.

    2005-01-01

    A 500kW vibrating grate fired test facility for solid biomass fuels has been designed using numerical models including CFD. The CFD modelling has focussed on the nozzle layout and flowpatterns in the lower part of the furnace, and the results have established confidence in the chosen design...

  12. Compilation of historical information of 300 Area facilities and activities

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1992-12-01

    This document is a compilation of historical information of the 300 Area activities and facilities since the beginning. The 300 Area is shown as it looked in 1945, and also a more recent (1985) look at the 300 Area is provided

  13. Compilation of historical information of 300 Area facilities and activities

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S.

    1992-12-01

    This document is a compilation of historical information of the 300 Area activities and facilities since the beginning. The 300 Area is shown as it looked in 1945, and also a more recent (1985) look at the 300 Area is provided.

  14. Using Executive Information Systems to Manage Capital Projects and Facilities.

    Science.gov (United States)

    Kaynor, Robert

    1993-01-01

    In higher education, facilities data are essential for long-term capital and financial planning and for testing assumptions underlying anticipated policy change. Executive information systems should incorporate life-cycle considerations (planning, construction, renovation, and management) and resource linkages (describing interrelationships of…

  15. Regulatory requirements for designing PET-CT facility in India

    International Nuclear Information System (INIS)

    Tandon, Pankaj

    2010-01-01

    In India, cyclotron-produced radionuclides are gaining importance in molecular imaging in Nuclear Medicine (NM) departments. The importance of this modality among others is due to the fact that it provides valuable clinical information, which was lacking in other available modalities. Presently, every well-established hospital would like to procure Medical Cyclotron or positron emission tomography-computed tomography (PET-CT) facility in their NM department. Because cyclotron-produced radionuclides have higher energy than the other routinely used radionuclides for diagnosis, it becomes essential for the user to know about the regulatory requirement and radiation safety precautions that one has to take for the installation of this new modality in their premises. The various stages of approval of PET-CT facility by the Atomic Energy Regulatory Board (AERB) and important steps that one has to know/follow before planning for this new facility are summarized

  16. The Potential of Open Source Information in Supporting Acquisition Pathway Analysis to Design IAEA State Level Approaches

    International Nuclear Information System (INIS)

    Renda, G.; Kim, L.; Jungwirth, R.; Pabian, F.; Wolfart, E.; Cojazzi, G.G.M.; )

    2015-01-01

    International Atomic Energy Agency (IAEA) safeguards designed to deter nuclear proliferation are constantly evolving to respond to new challenges. Within its State Level Concept, the IAEA envisions an objective-based and information-driven approach for designing and implementing State Level Approaches (SLAs), using all available measures to improve the effectiveness and efficiency of safeguards. The main Objectives of a SLA are a) to detect undeclared nuclear material or activities in the State, b) to detect undeclared production or processing of nuclear materials in declared facilities or locations outside facilities (LOFs), c) to detect diversion of declared nuclear material in declared facilities or LOFs. Under the SLA, States will be differentiated based upon objective State-Specific Factors that influence the design, planning, conduct and evaluation of safeguards activities. Proposed categories of factors include both technical and legal aspects, spanning from the deployed fuel cycle and the related state's technical capability to the type of safeguards agreements in force and the IAEA experience in implementing safeguards in that state. To design a SLA, the IAEA foresees the use of Acquisition Path Analysis (APA) to identify the plausible routes for acquiring weapons-usable material and to assess their safeguards significance. In order to achieve this goal, APA will have to identify possible acquisition paths, characterize them and eventually prioritize them. This paper will provide an overview of how the use of open source information (here loosely defined as any type of non-classified or proprietary information and including, but not limited to, media sources, government and non-governmental reports and analyzes, commercial data, satellite imagery, scientific/ technical literature, trade data) can support this activity in the various aspects of a typical APA approach. (author)

  17. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Harris, W.J.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  18. Analysis Methods for Extracting Knowledge from Large-Scale WiFi Monitoring to Inform Building Facility Planning

    DEFF Research Database (Denmark)

    Ruiz-Ruiz, Antonio; Blunck, Henrik; Prentow, Thor Siiger

    2014-01-01

    realistic data to inform facility planning. In this paper, we propose analysis methods to extract knowledge from large sets of network collected WiFi traces to better inform facility management and planning in large building complexes. The analysis methods, which build on a rich set of temporal and spatial......The optimization of logistics in large building com- plexes with many resources, such as hospitals, require realistic facility management and planning. Current planning practices rely foremost on manual observations or coarse unverified as- sumptions and therefore do not properly scale or provide....... Spatio-temporal visualization tools built on top of these methods enable planners to inspect and explore extracted information to inform facility-planning activities. To evaluate the methods, we present results for a large hospital complex covering more than 10 hectares. The evaluation is based on Wi...

  19. Design-Build Process for the Research Support Facility (RSF) (Book)

    Energy Technology Data Exchange (ETDEWEB)

    2012-06-01

    An in-depth look at how the U.S. DOE and NREL used a performance-based design-build contract to build the Research Support Facility (RSF); one of the most energy efficient office buildings in the world.

  20. Consideration of external events in the design of nuclear facilities other than nuclear power plants, with emphasis on earthquakes

    International Nuclear Information System (INIS)

    2003-03-01

    The design of nuclear facilities other than nuclear power plants in relation to external events is not a well harmonized practice around the world. Traditionally, the design of these facilities has either been left to the provisions collected in national building codes and other industrial codes not specifically intended for nuclear facilities, or it has been the subject of complex analyses of the type usually performed for nuclear power plants. The IAEA has recently started a programme of development of safety standards for such facilities. The need to define the appropriate safety requirements for nuclear installations prompted a generic review of siting and design approaches for these facilities in relation to external events. Therefore the assessment methods for siting and design were reviewed by the engineering community to provide the overall design of such facilities with the necessary reliability level. This report aims to provide guidelines for the assessment of the safety of nuclear facilities other than nuclear power plants in relation to external events through the application of simplified methods and procedures for their siting and design. The approach adopted is both simplified and conservative compared with that used for power reactors. It seeks to provide a rational balance for a suitable combination of sustainable effort in site investigations and refinement in design procedures, compatible with the assigned safety objectives. This publication is related to IAEA-TECDOC-348 'Earthquake Resistant Design of Nuclear Facilities with Limited Radioactive Inventory' (1985) which focused on the seismic design of nuclear facilities with limited radioactive inventory. After some 17 years, parts of IAEA-TECDOC-348 needed modification, as new operational data have become available from many facilities. In addition, sophisticated design methodologies are now more easily obtainable, and experts felt that the trade-off between sustainable investment in the

  1. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

  2. SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

    International Nuclear Information System (INIS)

    Achilli, A.; Congiu, C.; Ferri, R.; Bianchi, F.; Meloni, P.; Grgic, D.; Dzodzo, M.

    2012-01-01

    An Italian MSE R and D programme on Nuclear Fission is funding, through ENEA, the design and testing of SPES3 facility at SIET, for IRIS reactor simulation. IRIS is a modular, medium size, advanced, integral PWR, developed by an international consortium of utilities, industries, research centres and universities. SPES3 simulates the primary, secondary and containment systems of IRIS, with 1:100 volume scale, full elevation and prototypical thermal-hydraulic conditions. The RELAP5 code was extensively used in support to the design of the facility to identify criticalities and weak points in the reactor simulation. FER, at Zagreb University, performed the IRIS reactor analyses with the RELAP5 and GOTHIC coupled codes. The comparison between IRIS and SPES3 simulation results led to a simulation-design feedback process with step-by-step modifications of the facility design, up to the final configuration. For this, a series of sensitivity cases was run to investigate specific aspects affecting the trend of the main parameters of the plant, as the containment pressure and EHRS removed power, to limit fuel clad temperature excursions during accidental transients. This paper summarizes the sensitivity analyses on the containment system that allowed to review the SPES3 facility design and confirm its capability to appropriately simulate the IRIS plant.

  3. SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

    Directory of Open Access Journals (Sweden)

    Andrea Achilli

    2012-01-01

    Full Text Available An Italian MSE R&D programme on Nuclear Fission is funding, through ENEA, the design and testing of SPES3 facility at SIET, for IRIS reactor simulation. IRIS is a modular, medium size, advanced, integral PWR, developed by an international consortium of utilities, industries, research centres and universities. SPES3 simulates the primary, secondary and containment systems of IRIS, with 1:100 volume scale, full elevation and prototypical thermal-hydraulic conditions. The RELAP5 code was extensively used in support to the design of the facility to identify criticalities and weak points in the reactor simulation. FER, at Zagreb University, performed the IRIS reactor analyses with the RELAP5 and GOTHIC coupled codes. The comparison between IRIS and SPES3 simulation results led to a simulation-design feedback process with step-by-step modifications of the facility design, up to the final configuration. For this, a series of sensitivity cases was run to investigate specific aspects affecting the trend of the main parameters of the plant, as the containment pressure and EHRS removed power, to limit fuel clad temperature excursions during accidental transients. This paper summarizes the sensitivity analyses on the containment system that allowed to review the SPES3 facility design and confirm its capability to appropriately simulate the IRIS plant.

  4. Seismic design and evaluation criteria for DOE facilities (DOE-STD-1020-XX)

    International Nuclear Information System (INIS)

    Short, S.A.; Kennedy, R.P.; Murray, R.C.

    1993-01-01

    Seismic design and evaluation criteria for DOE facilities are provided in DOE-STD-1020-XX. The criteria include selection of design/evaluation seismic input from probabilistic seismic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. Conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior and by a seismic load factor. These criteria are based on the performance or risk goals specified in DOE 5480.28. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of desired behavior and of the probability of not achieving that behavior. Following the seismic design/evaluation criteria of DOE-STD-1020-XX is sufficient to demonstrate that the probabilistic performance or risk goals are achieved. The criteria are simple procedures but with a sound, rigorous basis for the achievement of goals

  5. Optimal capacity design of LID facility for conserving natural water cycle and its sensitivity analysis

    Science.gov (United States)

    Lee, O.; Choi, J.; Lee, J.; Kim, S.

    2017-12-01

    Since the 20th century, urbanization has resulted in increased impermeable land surface and reduced infiltration capacity in catchment scale. Especially, when agriculture area or forest area would be developed into urban area, it can cause more runoff in the same climate condition. Such urbanization causes problems such as changes in hydrological cycle and ecosystem disturbance. Various methods have been proposed worldwide to reduce the impact of such urbanization. Among the various strategies, the low-impact development is a development strategy that aims to return to pre-development state by minimizing the change of the hydrological cycle due to urbanization. In this strategy, the infiltration and/or surface storage of stormwater runoff can be increased through the installation of various facilities. In this study, a facility capacity design strategy is proposed to return into the natural water cycle through the installation of various LID facilities. This is accomplished by determining the optimal LID facility design capacity through which flow duration curves remain the same before and after urban development. For this purpose, EPA-SWMM is constructed with a part of Busan Metropolitan City Noksan Industrial Complex as a virtual processing area. Under the various land-use scenarios, the optimum design capacity of various LID facilities capable of retaining the flow duration curve before and after development is determined. In addition, the sensitivity of the optimal design capacity of LID facilities is analyzed according to the design specifications of various LID facilities, the local rainfall characteristics, and the size of the treatment area. Acknowledgement This research was supported by a grant (2016000200002) from Public Welfare Technology Development Program funded by Ministry of Environment of Korean government.

  6. Migrating the facility profile information management system into the world wide web

    Energy Technology Data Exchange (ETDEWEB)

    Kero, R.E.; Swietlik, C.E.

    1994-09-01

    The Department of Energy - Office of Special Projects and Argonne National Laboratory (ANL), along with the Department of Energy - office of Scientific and Technical Information have previously designed and implemented the Environment, Safety and Health Facility Profile Information Management System (FPIMS) to facilitate greater efficiency in searching, analyzing and disseminating information found within environment, safety and health oversight documents. This information retrieval based system serves as a central repository for full-text electronic oversight documents, as well as a management planning and decision making tool that can assist in trend and root cause analyses. Continuous improvement of environment, safety and health programs are currently aided through this personal computer-based system by providing a means for the open communication of lessons learned across the department. Overall benefits have included reductions in costs and improvements in past information management capabilities. Access to the FPIMS has been possible historically through a headquarters-based local area network equipped with modems. Continued demand for greater accessibility of the system by remote DOE field offices and sites, in conjunction with the Secretary of Energy` s call for greater public accessibility to Department of Energy (DOE) information resources, has been the impetus to expand access through the use of Internet technologies. Therefore, the following paper will discuss reasons for migrating the FPIMS system into the World Wide Web (Web), various lessons learned from the FPIMS migration effort, as well as future plans for enhancing the Web-based FPIMS.

  7. Design of the MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Johnson, J.V.; Brabazon, E.J.

    2001-01-01

    A consortium of Duke Engineering and Services, Inc., COGEMA, Inc. and Stone and Webster (DCS) are designing a mixed oxide fuel fabrication facility (MFFF) for the U.S. Department of Energy (DOE) to convert surplus plutonium to mixed oxide (MOX) fuel to be irradiated in commercial nuclear power plants based on the proven European technology of COGEMA and BELGONUCLEAIRE. This paper describes the MFFF processes, and how the proven MOX fuel fabrication technology is being adapted as required to comply with U.S. requirements. (author)

  8. Design of the MOX fuel fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, J.V. [MFFF Technical Manager, U.S. dept. of Energy, Washington, DC (United States); Brabazon, E.J. [MFFF Engineering Manager, Duke Cogema Stone and Webster, Charlotte, NC (United States)

    2001-07-01

    A consortium of Duke Engineering and Services, Inc., COGEMA, Inc. and Stone and Webster (DCS) are designing a mixed oxide fuel fabrication facility (MFFF) for the U.S. Department of Energy (DOE) to convert surplus plutonium to mixed oxide (MOX) fuel to be irradiated in commercial nuclear power plants based on the proven European technology of COGEMA and BELGONUCLEAIRE. This paper describes the MFFF processes, and how the proven MOX fuel fabrication technology is being adapted as required to comply with U.S. requirements. (author)

  9. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant Conceptual Design Engineering Report (CDER)

    Science.gov (United States)

    1981-01-01

    The reference conceptual design of the magnetohydrodynamic (MHD) Engineering Test Facility (ETF), a prototype 200 MWe coal-fired electric generating plant designed to demonstrate the commercial feasibility of open cycle MHD, is summarized. Main elements of the design, systems, and plant facilities are illustrated. System design descriptions are included for closed cycle cooling water, industrial gas systems, fuel oil, boiler flue gas, coal management, seed management, slag management, plant industrial waste, fire service water, oxidant supply, MHD power ventilating

  10. Design of a BNCT facility at HANARO

    International Nuclear Information System (INIS)

    Jun, Byung Jin; Lee, Byung Chul

    1998-01-01

    Based on the feasibility study of the BNCT at HANARO, it was confirmed that only thermal BNCT is possible at the IR beam tube if appropriate filtering system be installed. Medical doctors in Korea Cancer Center Hospital agreed that the thermal BNCT facility would be worthwhile for the BNCT technology development in Korea as well as superficial cancer treatment. For the thermal BNCT to be effective, the thermal neutron flux should be high enough for patient treatment during relatively short time and also the fast neutron and gamma-ray fluxes should be as low as possible. In this point of view, the following design requirements are set up: 1) thermal neutron flux at the irradiation position should be higher than 3x10 9 n/cm 2 -sec, 2) ratio of the fast neutrons and gamma-rays to the thermal neutrons should be minimized, and 3) patient treatment should be possible without interrupt to the reactor operation. To minimize the fast neutrons and gamma-rays with the required thermal neutrons at the irradiation position, a radiation filter consisting of single crystals of silicon and bismuth at liquid nitrogen temperature is designed. For the shielding purpose around the irradiation position, polyethylene, lead, LiF, etc., are appropriately arranged around the radiation filter. A water shutter in front of the radiation filter is adopted so as to avoid interrupt to the reactor operation. At present, detail design of the radiation filter is ongoing. Cooling capabilities of the filter will be tested through a mockup experiment. Dose rate distributions around the radiation filter and a prompt gamma-ray activation analysis system for the analyses of boron content in the biological samples are under design. The construction of this facility will be started from next year if it is permitted from the regulatory body this year. Some other future works exist and are described in the paper. (author)

  11. COMPUTER ORIENTED FACILITIES OF TEACHING AND INFORMATIVE COMPETENCE

    OpenAIRE

    Olga M. Naumenko

    2010-01-01

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

  12. Design concept of radiation control system for the high intensity proton accelerator facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyamoto, Yukihiro; Ikeno, Koichi; Akiyama, Shigenori; Harada, Yasunori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    Description is given for the characteristic radiation environment for the High Intensity Proton Accelerator Facility and the design concept of the radiation control system of it. The facility is a large scale accelerator complex consisting of high energy proton accelerators carrying the highest beam intensity in the world and the related experimental facilities and therefore provides various issues relevant to the radiation environment. The present report describes the specifications for the radiation control system for the facility, determined in consideration of these characteristics. (author)

  13. Radiotherapy Facilities: Master Planning and Concept Design Considerations (Russian Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidelines on how to plan a radiotherapy facility in terms of the strategic master planning process including the legal, technical and infrastructure requirements. It outlines a risk assessment methodology and a typical project work plan, and describes the professional expertise required for the implementation of such a project. Generic templates for a block design are suggested, which include possibilities for future expansion. These templates can be overlaid onto the designated site such that the most efficient workflow between the main functional areas can be ensured. A sample checklist is attached to act as a guideline for project management and to indicate the critical stages in the process where technical expert assistance may be needed. The publication is aimed at professionals and administrators involved in infrastructure development, planning and facility management, as well as engineers, building contractors and radiotherapy professionals

  14. Bottoms up design of the Elmo Bumpy Torus - proof of principal (EBT-P) fusion research facility

    International Nuclear Information System (INIS)

    Erickson, D.T.

    1981-01-01

    The McDonnell Douglas Astronautics Company, under subcontract to the Union Carbide Corporation Nuclear Division at the DOE Oak Ridge National Laboratory has committed to furnish the EBT-P research facility. Gilbert Associates, Inc. of Reading, Pennysylvania, as the Architect and Engineering subcontractor has been selected for design and construction of this facility. The bottoms up effort to provide the EBT-P facility is now alive and well, with the property purchased, dedication ceremonies conducted, the Preliminary Design effort completed and detail design currently active

  15. Neutron streaming analysis for shield design of FMIT Facility

    International Nuclear Information System (INIS)

    Carter, L.L.

    1980-12-01

    Applications of the Monte Carlo method have been summarized relevant to neutron streaming problems of interest in the shield design for the FMIT Facility. An improved angular biasing method has been implemented to further optimize the calculation of streaming and this method has been applied to calculate streaming within a double bend pipe

  16. Nuclear Fuel Cycle Information System. A directory of nuclear fuel cycle facilities. 2009 ed

    International Nuclear Information System (INIS)

    2009-04-01

    The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities, published online as part of the Integrated Nuclear Fuel Cycle Information System (iNFCIS: http://www-nfcis.iaea.org/). This is the fourth hardcopy publication in almost 30 years and it represents a snapshot of the NFCIS database as of the end of 2008. Together with the attached CD-ROM, it provides information on 650 civilian nuclear fuel cycle facilities in 53 countries, thus helping to improve the transparency of global nuclear fuel cycle activities

  17. Analyses in Support of Risk-Informed Natural Gas Vehicle Maintenance Facility Codes and Standards: Phase II.

    Energy Technology Data Exchange (ETDEWEB)

    Blaylock, Myra L.; LaFleur, Chris Bensdotter; Muna, Alice Baca; Ehrhart, Brian David

    2018-03-01

    Safety standards development for maintenance facilities of liquid and compressed natural gas fueled vehicles is required to ensure proper facility design and operating procedures. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase II work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest using risk ranking. Detailed simulations and modeling were performed to estimate the location and behavior of natural gas releases based on these scenarios. Specific code conflicts were identified, and ineffective code requirements were highlighted and resolutions proposed. These include ventilation rate basis on area or volume, as well as a ceiling offset which seems ineffective at protecting against flammable gas concentrations. ACKNOWLEDGEMENTS The authors gratefully acknowledge Bill Houf (SNL -- Retired) for his assistance with the set-up and post-processing of the numerical simulations. The authors also acknowledge Doug Horne (retired) for his helpful discussions. We would also like to acknowledge the support from the Clean Cities program of DOE's Vehicle Technology Office.

  18. Explore the design style of oriented facility based on user evaluation

    OpenAIRE

    Zhang, Ye; Liu, Yang; Yu, Hui

    2015-01-01

    This paper employs Kansei engineering to analyze the relationship between user preference and the given architectural design scheme. In this study, we first divide architectural styles into seven different categories. Then we classify the key factors in the oriented facility design into 7 types with 39 subcategories. On that basis, we explore which design factor plays main roles in the harmony and unity between the user-oriented type and the given architectural design among seven different ar...

  19. National Ignition Facility subsystem design requirements NIF site improvements SSDR 1.2.1

    International Nuclear Information System (INIS)

    Kempel, P.; Hands, J.

    1996-01-01

    This Subsystem Design Requirements (SSDR) document establishes the performance, design, and verification requirements associated with the NIF Project Site at Lawrence Livermore National Laboratory (LLNL) at Livermore, California. It identifies generic design conditions for all NIF Project facilities, including siting requirements associated with natural phenomena, and contains specific requirements for furnishing site-related infrastructure utilities and services to the NIF Project conventional facilities and experimental hardware systems. Three candidate sites were identified as potential locations for the NIF Project. However, LLNL has been identified by DOE as the preferred site because of closely related laser experimentation underway at LLNL, the ability to use existing interrelated infrastructure, and other reasons. Selection of a site other than LLNL will entail the acquisition of site improvements and infrastructure additional to those described in this document. This SSDR addresses only the improvements associated with the NIF Project site located at LLNL, including new work and relocation or demolition of existing facilities that interfere with the construction of new facilities. If the Record of Decision for the PEIS on Stockpile Stewardship and Management were to select another site, this SSDR would be revised to reflect the characteristics of the selected site. Other facilities and infrastructure needed to support operation of the NIF, such as those listed below, are existing and available at the LLNL site, and are not included in this SSDR. Office Building. Target Receiving and Inspection. General Assembly Building. Electro- Mechanical Shop. Warehousing and General Storage. Shipping and Receiving. General Stores. Medical Facilities. Cafeteria services. Service Station and Garage. Fire Station. Security and Badging Services

  20. National Ignition Facility (NIF) Control Network Design and Analysis

    International Nuclear Information System (INIS)

    Bryant, R M; Carey, R W; Claybourn, R V; Pavel, G; Schaefer, W J

    2001-01-01

    The control network for the National Ignition Facility (NIF) is designed to meet the needs for common object request broker architecture (CORBA) inter-process communication, multicast video transport, device triggering, and general TCP/IP communication within the NIF facility. The network will interconnect approximately 650 systems, including the embedded controllers, front-end processors (FEPs), supervisory systems, and centralized servers involved in operation of the NIF. All systems are networked with Ethernet to serve the majority of communication needs, and asynchronous transfer mode (ATM) is used to transport multicast video and synchronization triggers. CORBA software infra-structure provides location-independent communication services over TCP/IP between the application processes in the 15 supervisory and 300 FEP systems. Video images sampled from 500 video cameras at a 10-Hz frame rate will be multicast using direct ATM Application Programming Interface (API) communication from video FEPs to any selected operator console. The Ethernet and ATM control networks are used to broadcast two types of device triggers for last-second functions in a large number of FEPs, thus eliminating the need for a separate infrastructure for these functions. Analysis, design, modeling, and testing of the NIF network has been performed to provide confidence that the network design will meet NIF control requirements

  1. Design and study of Engineering Test Facility - Helium Circulator

    International Nuclear Information System (INIS)

    Jiang Huijing; Ye Ping; Zhao Gang; Geng Yinan; Wang Jie

    2015-01-01

    Helium circulator is one of the key equipment of High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM). In order to simulate most normal and accident operating conditions of helium circulator in HTR-PM, a full scale, rated flow rate and power, engineering test loop, which was called Engineering Test Facility - Helium Circulator (ETF-HC), was designed and established. Two prototypes of helium circulator, which was supported by Active Magnetic Bearing (AMB) or sealed by dry gas seals, would be tested on ETF-HC. Therefore, special interchangeable design was under consideration. ETF-HC was constructed compactly, which consisted of eleven sub-systems. In order to reduce the flow resistance of the circuit, special ducts, elbows, valves and flowmeters were selected. Two stages of heat exchange loops were designed and a helium - high pressure pure water heat exchanger was applied to ensure water wouldn't be vaporized while simulating accident conditions. Commissioning tests were carried out and operation results showed that ETF-HC meets the requirement of helium circulator operation. On this test facility, different kinds of experiments were supposed to be held, including mechanical and aerodynamic performance tests, durability tests and so on. These tests would provide the features and performance of helium circulator and verify its feasibility, availability and reliability. (author)

  2. Safeguards and security design guidelines for conceptual monitored retrievable storage (MRS) facilities

    International Nuclear Information System (INIS)

    Byers, K.R.; Clark, R.G.; Harms, N.L.; Roberts, F.P.

    1984-07-01

    Existing safeguards/security regulations and licensing requirements that may be applicable to an MRS facility are not currently well-defined. Protection requirements consistent with the NRC-graded safeguards approach are identified, as a baseline safeguards system with a comparison of the impacts on safeguards and security of salient features of the different storage concepts. In addition, MRS facility design features and operational considerations are proposed that would enhance facility protection and provide additional assurance that protection systems and procedures would be effectively implemented. 3 figures

  3. Designing the visualization of information

    CSIR Research Space (South Africa)

    Engelbrecht, L

    2015-04-01

    Full Text Available The construction of an artifact to visually represent information is usually required by Information Visualization research projects. The end product of design science research is also an artifact and therefore it can be argued that design science...

  4. Physics constraints on the design of fast reactor safety test facilities

    International Nuclear Information System (INIS)

    Travelli, A.; Meneghetti, D.; Matos, J.; Snelgrove, J.; Shaftman, D.H.; Tzanos, C.; Lam, S.K.; Pennington, E.M.; Woodruff, W.L.

    1976-01-01

    This paper discusses the physics foundations common to all fast reactor safety test facilities and the constraints which they impose on the design. While detailed design discussions are confined to the experience with six ANL designs, available data from other designs are used to confirm the validity of the considerations and to broaden the scope of the discussion. This helps to view the various designs as a unified effort, to define their potential capabilities, and to assess how they could best complement each other

  5. Use of information technology for medication management in residential care facilities: correlates of facility characteristics.

    Science.gov (United States)

    Bhuyan, Soumitra S; Chandak, Aastha; Powell, M Paige; Kim, Jungyoon; Shiyanbola, Olayinka; Zhu, He; Shiyanbola, Oyewale

    2015-06-01

    The effectiveness of information technology in resolving medication problems has been well documented. Long-term care settings such as residential care facilities (RCFs) may see the benefits of using such technologies in addressing the problem of medication errors among their resident population, who are usually older and have numerous chronic conditions. The aim of this study was two-fold: to examine the extent of use of Electronic Medication Management (EMM) in RCFs and to analyze the organizational factors associated with the use of EMM functionalities in RCFs. Data on RCFs were obtained from the 2010 National Survey of Residential Care Facilities. The association between facility, director and staff, and resident characteristics of RCFs and adoption of four EMM functionalities was assessed through multivariate logistic regression. The four EMM functionalities included were maintaining lists of medications, ordering for prescriptions, maintaining active medication allergy lists, and warning of drug interactions or contraindications. About 12% of the RCFs adopted all four EMM functionalities. Additionally, maintaining lists of medications had the highest adoption rate (34.5%), followed by maintaining active medication allergy lists (31.6%), ordering for prescriptions (19.7%), and warning of drug interactions or contraindications (17.9%). Facility size and ownership status were significantly associated with adoption of all four EMM functionalities. Medicaid certification status, facility director's age, education and license status, and the use of personal care aides in the RCF were significantly associated with the adoption of some of the EMM functionalities. EMM is expected to improve the quality of care and patient safety in long-term care facilities including RCFs. The extent of adoption of the four EMM functionalities is relatively low in RCFs. Some RCFs may strategize to use these functionalities to cater to the increasing demands from the market and also to

  6. 40 CFR 60.540 - Applicability and designation of affected facilities.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) AIR PROGRAMS (CONTINUED) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for the Rubber Tire Manufacturing Industry § 60.540 Applicability and designation of affected... each of the following affected facilities in rubber tire manufacturing plants that commence...

  7. Design of Safety Parameter Monitoring Function in a Research Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

  8. Design of Safety Parameter Monitoring Function in a Research Reactor Facility

    International Nuclear Information System (INIS)

    Park, Jaekwan; Suh, Yongsuk

    2014-01-01

    The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

  9. Design Basis Provisions for New and Existing Nuclear Power Plants and Nuclear Fuel Cycle Facilities in India

    International Nuclear Information System (INIS)

    Soni, R.S.

    2013-01-01

    India has 3-Stage Nuclear Power Program. • Various facilities under design, construction or operation. • Design Basis Knowledge Management (DBKM) is an important and challenging task. • Design Basis Knowledge contributes towards: - Safe operation of running plants; - Design and construction of new facilities; - Addresses issues related to future decommissioning activities

  10. Cold Vacuum Drying Facility Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    PIEPHO, M.G.

    1999-01-01

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR

  11. Facility design consideration for continuous mix production of class 1.3 propellant

    Science.gov (United States)

    Williamson, K. L.; Schirk, P. G.

    1994-01-01

    In November of 1989, NASA awarded the Advanced Solid Rocket Motor (ASRM) contract to Lockheed Missiles and Space Company (LMSC) for production of advanced solid rocket motors using the continuous mix process. Aerojet ASRM division (AAD) was selected as the facility operator and RUST International Corporation provided the engineering, procurement, and construction management services. The continuous mix process mandates that the mix and cast facilities be 'close-coupled' along with the premix facilities, creating unique and challenging requirements for the facility designer. The classical approach to handling energetic materials-division into manageable quantities, segregation, and isolation-was not available due to these process requirements and quantities involved. This paper provides a description of the physical facilities, the continuous mix process, and discusses the monitoring and detection techniques used to mitigate hazards and prevent an incident.

  12. Design of a Facility to Test the Advanced Stirling Radioisotope Generator Engineering Unit

    Science.gov (United States)

    Lewandowski, Edward J.; Schreiber, Jeffrey G.; Oriti, Salvatore M.; Meer, David W.; Brace, Michael H.; Dugala, Gina

    2009-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) is being considered to power deep space missions. An engineering unit, the ASRG-EU, was designed and fabricated by Lockheed Martin under contract to the Department of Energy. This unit is currently on an extended operation test at NASA Glenn Research Center to generate performance data and validate the life and reliability predictions for the generator and the Stirling convertors. A special test facility was designed and built for testing the ASRG-EU. Details of the test facility design are discussed. The facility can operate the convertors under AC bus control or with the ASRG-EU controller. It can regulate input thermal power in either a fixed temperature or fixed power mode. An enclosure circulates cooled air around the ASRG-EU to remove heat rejected from the ASRG-EU by convection. A custom monitoring and data acquisition system supports the test. Various safety features, which allow 2417 unattended operation, are discussed.

  13. Guidelines for the development of natural phenomena hazards design criteria for surface facilities

    International Nuclear Information System (INIS)

    Nelson, T.A.; Hossain, Q.A.; Murray, R.C.

    1992-01-01

    This paper discusses the rationale behind the guidelines, criteria, and methodologies that are currently used for natural phenomena hazard design and evaluation of DOE nuclear and non-nuclear facilities. The bases for the performance goals and usage categories specified in UCRL-15910 are examined, and the sources of intentional conservatism in the analyses, design, and evaluation methods and criteria are identified. Outlines of recent developments/changes in DOE Orders related to Natural Phenomena hazard mitigation are also presented. Finally, the authors recommend the use of DOE methodologies as embodied in UCRL-15910 for design and evaluation of surface facilities of the high level nuclear waste repository site

  14. Conceptual design of an RTG Shipping and Receiving Facility Transportation System

    International Nuclear Information System (INIS)

    Black, S.J.; Gentzlinger, R.C.; Lujan, R.E.

    1994-01-01

    The conceptual design of an RTG Facility Transportation System which is part of the overall RTG Transportation System has been completed and is described in detail. The Facility Transportation System serves to provide locomotion, cooling, shock protection and data acquisition for the RTG package during onloading and offloading sequences. The RTG Shipping ampersand Receiving Facility Transportation System consists of a Transporter Subsystem, a Package Cooling Subsystem, and a Shock Limiting Transit Device Subsystem. The Transporter Subsystem is a custom designed welded steel cart combined with a pneumatically-driven hand tug for locomotion. The Package Cooling Subsystem provides five kilowatts of active liquid cooling via an on-board refrigeration system. The Shock Limiting Transit Device Subsystem consists of a consumable honeycomb anti-shock frame which provides shock protection for the 3855 kg (8500 LB) RTG package. These subsystems have been combined into an integrated system which will facilitate the offloading and onloading of the RTG Package into and out of the semitrailer as well as meet ALARA (as low as reasonably achievable) radiation exposure guidelines

  15. Conceptual design of an RTG shipping and receiving facility transportation system

    International Nuclear Information System (INIS)

    Black, S.J.; Gentzlinger, R.C.; Lujan, R.E.

    1995-01-01

    The conceptual design of an RTG Facility Transportation System which is part of the overall RTG Transportation System has been completed and is described in detail. The Facility Transportation System serves to provide locomotion, cooling, shock protection and data acquisition for the RTG package during onloading and offloading sequences. The RTG Shipping ampersand Receiving Facility Transportation System consists of a Transporter Subsystem, a Package Cooling Subsystem, and a Shock Limiting Transit Device Subsystem. The Transporter Subsystem is a custom designed welded steel cart combined with a pneumatically-driven hand tug for locomotion. The Package Cooling Subsystem provides five kilowatts of active liquid cooling via an on-board refrigeration system. The Shock Limiting Transit Device Subsystem consists of a consumable honeycomb anti-shock frame which provides shock protection for the 3855 kg (8500 LB) RTG package. These subsystems have been combined into an integrated system which will facilitate the offloading and onloading of the RTG Package into and out of the semitrailer as well as meet ALARA (as low as reasonably achievable) radiation exposure guidelines. copyright 1995 American Institute of Physics

  16. Study on the development of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B. D.; Song, D. Y.; So, D. S.; Kwak, E. H. [KAERI, Taejon (Korea, Republic of)

    2000-05-01

    Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this paper, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described.

  17. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 1: Executive summary

    Science.gov (United States)

    1981-01-01

    Main elements of the design are identified and explained, and the rationale behind them was reviewed. Major systems and plant facilities are listed and discussed. Construction cost and schedule estimates are presented, and the engineering issues that should be reexamined are identified. The latest (1980-1981) information from the MHD technology program is integrated with the elements of a conventional steam power electric generating plant.

  18. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

  19. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers

  20. Comparison of Design and Practices for Radiation Safety among Five Synchrotron Radiation Facilities

    International Nuclear Information System (INIS)

    Liu, James C.; Rokni, Sayed H.; SLAC; Asano, Yoshihiro; JAERI-RIKEN, Hyogo; Casey, William R.; Brookhaven; Donahue, Richard J.

    2005-01-01

    There are more and more third-generation synchrotron radiation (SR) facilities in the world that utilize low emittance electron (or positron) beam circulating in a storage ring to generate synchrotron light for various types of experiments. A storage ring based SR facility consists of an injector, a storage ring, and many SR beamlines. When compared to other types of accelerator facilities, the design and practices for radiation safety of storage ring and SR beamlines are unique to SR facilities. Unlike many other accelerator facilities, the storage ring and beamlines of a SR facility are generally above ground with users and workers occupying the experimental floor frequently. The users are generally non-radiation workers and do not wear dosimeters, though basic facility safety training is required. Thus, the shielding design typically aims for an annual dose limit of 100 mrem over 2000 h without the need for administrative control for radiation hazards. On the other hand, for operational and cost considerations, the concrete ring wall (both lateral and ratchet walls) is often desired to be no more than a few feet thick (with an even thinner roof). Most SR facilities have similar operation modes and beam parameters (both injection and stored) for storage ring and SR beamlines. The facility typically operates almost full year with one-month start-up period, 10-month science program for experiments (with short accelerator physics studies and routine maintenance during the period of science program), and a month-long shutdown period. A typical operational mode for science program consists of long periods of circulating stored beam (which decays with a lifetime in tens of hours), interposed with short injection events (in minutes) to fill the stored current. The stored beam energy ranges from a few hundreds MeV to 10 GeV with a low injection beam power (generally less than 10 watts). The injection beam energy can be the same as, or lower than, the stored beam energy

  1. Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

    International Nuclear Information System (INIS)

    1995-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information

  2. Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

  3. Hanford Facility Annual Dangerous Waste Report Calendar Year 2002

    International Nuclear Information System (INIS)

    FR-EEMAN, D.A.

    2003-01-01

    Hanford CY 2002 dangerous waste generation and management forms. The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Information and Tracking System (SWITS) database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, electronic copies of the report are also transmitted to the regulatory agency

  4. Cold Vacuum Dryer (CVD) Facility Fire Protection System Design Description (SYS 24)

    Energy Technology Data Exchange (ETDEWEB)

    SINGH, G.

    2000-10-17

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility fire protection system (FPS). The primary features of the FPS for the CVD are a fire alarm and detection system, automatic sprinklers, and fire hydrants. The FPS also includes fire extinguishers located throughout the facility and fire hydrants to assist in manual firefighting efforts. In addition, a fire barrier separates the operations support (administrative) area from the process bays and process bay support areas. Administrative controls to limit combustible materials have been established and are a part of the overall fire protection program. The FPS is augmented by assistance from the Hanford Fire Department (HED) and by interface systems including service water, electrical power, drains, instrumentation and controls. This SDD, when used in conjunction with the other elements of the definitive design package, provides a complete picture of the FPS for the CVD Facility.

  5. Preventing Airborne Disease Transmission: Review of Methods for Ventilation Design in Health Care Facilities

    Science.gov (United States)

    Aliabadi, Amir A.; Rogak, Steven N.; Bartlett, Karen H.; Green, Sheldon I.

    2011-01-01

    Health care facility ventilation design greatly affects disease transmission by aerosols. The desire to control infection in hospitals and at the same time to reduce their carbon footprint motivates the use of unconventional solutions for building design and associated control measures. This paper considers indoor sources and types of infectious aerosols, and pathogen viability and infectivity behaviors in response to environmental conditions. Aerosol dispersion, heat and mass transfer, deposition in the respiratory tract, and infection mechanisms are discussed, with an emphasis on experimental and modeling approaches. Key building design parameters are described that include types of ventilation systems (mixing, displacement, natural and hybrid), air exchange rate, temperature and relative humidity, air flow distribution structure, occupancy, engineered disinfection of air (filtration and UV radiation), and architectural programming (source and activity management) for health care facilities. The paper describes major findings and suggests future research needs in methods for ventilation design of health care facilities to prevent airborne infection risk. PMID:22162813

  6. Methods and techniques for decontamination design and construction of facilities

    International Nuclear Information System (INIS)

    Augustin, X.; Cohen, S.

    1986-01-01

    TECHNICATOME and STMI have jointly solved a wide range of problems specific to decontamination from the very design studies up to operation. TECHNICATOME has brought its expertise in the design and construction of nuclear facilities concerned in particular with decontamination and radwaste management. STMI is an experienced operator with expertise in designing tools and developing advanced techniques in the same fields. The expertise of both companies in this field cumulated for many years has resulted in developing techniques and tools adapted to most of the decontamination problems including specific cases [fr

  7. Design of a RESTful web information system for drug prescription and administration.

    Science.gov (United States)

    Bianchi, Lorenzo; Paganelli, Federica; Pettenati, Maria Chiara; Turchi, Stefano; Ciofi, Lucia; Iadanza, Ernesto; Giuli, Dino

    2014-05-01

    Drug prescription and administration processes strongly impact on the occurrence of risks in medical settings for they can be sources of adverse drug events (ADEs). A properly engineered use of information and communication technologies has proven to be a promising approach to reduce these risks. In this study, we propose PHARMA, a web information system which supports healthcare staff in the secure cooperative execution of drug prescription, transcription and registration tasks. PHARMA allows the easy sharing and management of documents containing drug-related information (i.e., drug prescriptions, medical reports, screening), which is often inconsistent and scattered across different information systems and heterogeneous organization domains (e.g., departments, other hospital facilities). PHARMA enables users to access such information in a consistent and secure way, through the adoption of REST and web-oriented design paradigms and protocols. We describe the implementation of the PHARMA prototype, and we discuss the results of the usability evaluation that we carried out with the staff of a hospital in Florence, Italy.

  8. Conceptual design for the Waste Receiving And Processing facility Module 2A

    International Nuclear Information System (INIS)

    1992-07-01

    This Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility. The mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. This volume provides the detailed cost estimate for the WRAP 2A facility. Included in this volume is the project construction schedule

  9. Cold Vacuum Drying Facility Condensate Collection System Design Description. System 19

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    2000-01-01

    The Cold Vacuum Drying (CVD) Facility of Spent Nuclear Fuel (SNF) provides required process systems, supporting equipment, and facilities to support the SNF Project mission. This system design description (SDD) addresses the Condensate Collection System (CCS). This is a general service system. The CCS begins at the condensate outlet of the general process air-handling unit (AHU) and the condensate outlets for the active process bays AHUs. The system terminates at each condensate collection tank (5 total)

  10. An M/M/c/K State-Dependent Model for Pedestrian Flow Control and Design of Facilities.

    Directory of Open Access Journals (Sweden)

    Khalidur Rahman

    Full Text Available Pedestrian overflow causes queuing delay and in turn, is controlled by the capacity of a facility. Flow control or blocking control takes action to avoid queues from building up to extreme values. Thus, in this paper, the problem of pedestrian flow control in open outdoor walking facilities in equilibrium condition is investigated using M/M/c/K queuing models. State dependent service rate based on speed and density relationship is utilized. The effective rate of the Poisson arrival process to the facility is determined so as there is no overflow of pedestrians. In addition, the use of the state dependent queuing models to the design of the facilities and the effect of pedestrian personal capacity on the design and the traffic congestion are discussed. The study does not validate the sustainability of adaptation of Western design codes for the pedestrian facilities in the countries like Bangladesh.

  11. Ford motor company NDE facility shielding design

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  12. Ford Motor Company NDE facility shielding design.

    Science.gov (United States)

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

    2005-01-01

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

  13. Radiological design guide

    International Nuclear Information System (INIS)

    Evans, R.A.

    1994-01-01

    The purpose of this design guide is to provide radiological safety requirements, standards, and information necessary for designing facilities that will operate without unacceptable risk to personnel, the public, or the environment as required by the US Department of Energy (DOE). This design guide, together with WHC-CM-4-29, Nuclear Criticality Safety, WHC-CM-4-46, Nonreactor Facility Safety Analysis, and WHC-CM-7-5, Environmental Compliance, covers the radiation safety design requirements at Westinghouse Hanford Company (WHC). This design guide applies to the design of all new facilities. The WHC organization with line responsibility for design shall determine to what extent this design guide shall apply to the modifications to existing facilities. In making this determination, consideration shall include a cost versus benefit study. Specifically, facilities that store, handle, or process radioactive materials will be covered. This design guide replaces WHC-CM-4-9 and is designated a living document. This design guide is intended for design purposes only. Design criteria are different from operational criteria and often more stringent. Criteria that might be acceptable for operations might not be adequate for design

  14. The ITER neutral beam test facility: Designs of the general infrastructure, cryosystem and cooling plant

    International Nuclear Information System (INIS)

    Cordier, J.J.; Hemsworth, R.; Chantant, M.; Gravil, B.; Henry, D.; Sabathier, F.; Doceul, L.; Thomas, E.; Houtte, D. van; Zaccaria, P.; Antoni, V.; Bello, S. Dal; Marcuzzi, D.; Antipenkov, A.; Day, C.; Dremel, M.; Mondino, P.L.

    2005-01-01

    The CEA Association is involved, in close collaboration with ENEA, FZK, IPP and UKAEA European Associations, in the first ITER neutral beam (NB) injector and the ITER neutral beam test facility design (EFDA task ref. TW3-THHN-IITF1). A total power of about 50 MW will have to be removed in steady state on the neutral beam test facility (NBTF). The main purpose of this task is to make progress with the detailed design of the first ITER NB injector and to start the conceptual design of the ITER NBTF. The general infrastructure layout of a generic site for the NBTF includes the test facility itself equipped with a dedicated beamline vessel [P.L. Zaccaria, et al., Maintenance schemes for the ITER neutral beam test facility, this conference] and integration studies of associated auxiliaries such as cooling plant, cryoplant and forepumping system

  15. A conceptual subsurface facility design for a high-level nuclear waste repository at Yucca Mountain

    International Nuclear Information System (INIS)

    McKenzie, D.G., III; Bhattacharyya, K.K.; Segrest, A.M.

    1996-01-01

    The US Department of Energy is responsible for the design, construction, operation and closure of a repository in which to permanently dispose of the nation's high level nuclear waste. In addition to the objective of safely isolating the waste inventory, the repository must provide a safe working environment for its workforce, and protect the public. The conceptual design for this facility is currently being developed. Tunnel Boring Machine will be used to excavate 228 kilometers of tunneling to construct the facility over a 30 year period. The excavation operations will be physically separated from the waste emplacement operations, and each operation will have its own dedicated ventilation system. The facility is being designed to remain open for 150 years

  16. Moderator Demonstration Facility Design and Optimization

    Energy Technology Data Exchange (ETDEWEB)

    McClanahan, Tucker C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gallmeier, Franz X. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Iverson, Erik B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-02-01

    The Spallation Neutron Source (SNS) facility at Oak Ridge National Laboratory (ORNL) is implementing a Moderator Demonstration Facility (MDF) to demonstrate the performance characteristics of advanced moderators central to the Second Target Station (STS) for SNS. The MDF will use the "spare" front-end installation within the SNS accelerator support complex – an ion source, radio-frequency quadrupole (RFQ) accelerator, and medium-energy beam transport (MEBT) chopper - to provide a 2.5 MeV proton beam of peak current 50 mA and maximum pulse length of less than 10 s at a repetition rate of no more than 60 Hz to a suitable neutron-producing target to demonstrate those aspects of moderator performance necessary to meet the goals of the STS design e ort. The accelerator beam parameters are not open to variation beyond that described above - they are fixed by the nature of the spare front-end installation (the Integrated Test Stand Facility; ITSF). Accordingly, there are some neutronic challenges in developing prototypic moderator illumination from a very non-prototypic primary neutron source; the spallation source we are attempting to mimic has an extended neutron source volume approximately 40 cm long (in the direction of the proton beam), approximately 10 cm wide (horizontally transverse to the proton beam) and approximately 5 cm high (vertically transverse to the proton beam), and an isotropic evaporation energy spectrum with mean energy above 1 MeV. In contrast, the primary neutron source available from the 7Li(p,n) reaction (the most prolific at 2.5 MeV proton energy by more than an order of magnitude) is strongly anisotropic, with an energy spectrum that is both strongly dependent on emission angle and kinematically limited to less than 700 keV, and the interaction zone between the incident protons and any target material (neutron-producing or not) is intrinsically limited to a few tens of microns. The MDF will be unique and innovative amongst the world

  17. 77 FR 74685 - Chemical Facility Anti-Terrorism Standards (CFATS) Chemical-Terrorism Vulnerability Information...

    Science.gov (United States)

    2012-12-17

    ... DEPARTMENT OF HOMELAND SECURITY [Docket No. DHS-2012-0057] Chemical Facility Anti-Terrorism Standards (CFATS) Chemical- Terrorism Vulnerability Information (CVI) AGENCY: National Protection and...: Comments that include trade secrets, confidential commercial or financial information, Chemical-terrorism...

  18. Los Alamos Experimental Engineering Waste Burial Facility: design considerations and preliminary experimental plan

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1981-01-01

    The Experimental Engineered Waste Burial Facility is a field test site where generic experiments can be performed on several scales to get the basic information necessary to understand the processes occurring in low-level waste disposal facilities. The experiments include hydrological, chemical, mechanical, and biological factors. In order to separate these various factors in the experiments and to extrapolate the experimental results to actual facilities, experiments will be performed on several different scales

  19. Design of generic coal conversion facilities: Indirect coal liquefaction, Fischer-Tropsch synthesis

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    A comprehensive review of Fischer-Tropsch (F-T) technology, including fixed, fluidized, and bubble column reactors, was undertaken in order to develop an information base before initiating the design of the Fischer-Tropsch indirect liquefaction PDU as a part of the Generic Coal Conversion Facilities to be built at the Pittsburgh Energy Technology Center (PETC). The pilot plant will include a fixed bed and slurry bubble column reactor for the F-T mode of operation. The review encompasses current status of both these technologies, their key variables, catalyst development, future directions, and potential improvement areas. However, more emphasis has been placed on the slurry bubble column reactor since this route is likely to be the preferred technology for commercialization, offering process advantages and, therefore, better economics than fixed and fluidized bed approaches.

  20. Design and Evaluation of Wood Processing Facilities Using Object-Oriented Simulation

    Science.gov (United States)

    D. Earl Kline; Philip A. Araman

    1992-01-01

    Managers of hardwood processing facilities need timely information on which to base important decisions such as when to add costly equipment or how to improve profitability subject to time-varying demands. The overall purpose of this paper is to introduce a tool that can effectively provide such timely information. A simulation/animation modeling procedure is described...

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