Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force.

Test facilities for evaluating nuclear thermal propulsion systems

International Nuclear Information System (INIS)

Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C.; Todosow, M.

1992-01-01

Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized

Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

International Nuclear Information System (INIS)

Bowman, B.R.

1994-01-01

This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design

Relative evaluation on decommissioning accident scenarios of nuclear facilities

International Nuclear Information System (INIS)

Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jei-Kwon; Hyun, Dong-Jun; Kim, Geun-Ho; Kim, Tae-Hyoung; Jo, Kyung-Hwa; Seo, Jae-Seok; Jeong, Seong-Young; Lee, Jung-Jun

2012-01-01

Highlights: ► This paper suggests relative importance on accident scenarios during decommissioning of nuclear facilities. ► The importance of scenarios can be performed by using AHP and Sugeno fuzzy method. ► The AHP and Sugeno fuzzy method guarantee reliability of the importance evaluation. -- Abstract: This paper suggests the evaluation method of relative importance on accident scenarios during decommissioning of nuclear facilities. The evaluation method consists of AHP method and Sugeno fuzzy integral method. This method will guarantee the reliability of relative importance evaluation for decommissioning accident scenarios.

Technical Evaluation of Oak Ridge Filter Test Facility

CERN Document Server

Kriskovich, J R

2002-01-01

Two evaluations of the Oak Ridge Department of Energy (DOE) Filter Test Facility (FTF) were performed on December 11 and 12, 2001, and consisted of a quality assurance and a technical evaluation. This report documents results of the technical evaluation.

Monitored Retrievable Storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume

Monitored retrievable storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document

Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs{hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document.

Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-09-01

This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{sup 2}) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.

Evaluating building performance in healthcare facilities: an organizational perspective.

Science.gov (United States)

Steinke, Claudia; Webster, Lynn; Fontaine, Marie

2010-01-01

Using the environment as a strategic tool is one of the most cost-effective and enduring approaches for improving public health; however, it is one that requires multiple perspectives. The purpose of this article is to highlight an innovative methodology that has been developed for conducting comprehensive performance evaluations in public sector health facilities in Canada. The building performance evaluation methodology described in this paper is a government initiative. The project team developed a comprehensive building evaluation process for all new capital health projects that would respond to the aforementioned need for stakeholders to be more accountable and to better integrate the larger organizational strategy of facilities. The Balanced Scorecard, which is a multiparadigmatic, performance-based business framework, serves as the underlying theoretical framework for this initiative. It was applied in the development of the conceptual model entitled the Building Performance Evaluation Scorecard, which provides the following benefits: (1) It illustrates a process to link facilities more effectively to the overall mission and goals of an organization; (2) It is both a measurement and a management system that has the ability to link regional facilities to measures of success and larger business goals; (3) It provides a standardized methodology that ensures consistency in assessing building performance; and (4) It is more comprehensive than traditional building evaluations. The methodology presented in this paper is both a measurement and management system that integrates the principles of evidence-based design with the practices of pre- and post-occupancy evaluation. It promotes accountability and continues throughout the life cycle of a project. The advantage of applying this framework is that it engages health organizations in clarifying a vision and strategy for their facilities and helps translate those strategies into action and measurable performance

Evaluation of existing United States' facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition

International Nuclear Information System (INIS)

Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

1995-01-01

A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications

Monitored Retrievable Storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs {hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume.

Post-Occupancy Evaluation of Facilities Change

NARCIS (Netherlands)

van der Voordt, Theo; de Been, I.; Maarleveld, M.; Finch, E

2012-01-01

This chapter discusses possible aims, tools and deliverables of Post-Occupancy Evaluations (POE) (otherwise known as building-in-use studies), with a focus on interventions in supporting facilities. POE has a long tradition and has been applied in different fields (e.g. offices, educational

Professional Development through Organizational Assessment: Using APPA's Facilities Management Evaluation Program

Science.gov (United States)

Medlin, E. Lander; Judd, R. Holly

2013-01-01

APPA's Facilities Management Evaluation Program (FMEP) provides an integrated system to optimize organizational performance. The criteria for evaluation not only provide a tool for organizational continuous improvement, they serve as a compelling leadership development tool essential for today's facilities management professional. The senior…

Seismic evaluation of critical facilities at the Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Murray, R.C.; Tokarz, F.J.

1976-01-01

The performance of critical facilities at the Lawrence Livermore Laboratory (LLL) are being evaluated for severe earthquake loading. Facilities at Livermore, Site-300 and the Nevada Test Site are included in this study. These facilities are identified, the seismic criteria used for the analysis are indicated, the various methods used for structural analysis are discussed and a summary of the results of facilities analyzed to date are presented

Evaluation of the Netherlands' International Test Facility for Smart Grids

Energy Technology Data Exchange (ETDEWEB)

Palmintier, Bryan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Pratt, Annabelle [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-06-01

The Netherlands Enterprise Agency (Rijksdienst voor Ondernemend Nederland, or RVO) engaged the U.S. National Renewable Energy Laboratory (NREL) for two primary purposes: to evaluate the International Test Facility for Smart Grids (ITF) sponsored by RVO and to learn best practices for integrated test facilities from NREL's Energy Systems Integration Facility (ESIF). This report covers the ITF evaluation and is largely based on a one-week visit to the Netherlands in November 2014.

Engineering evaluation/cost analysis for the 105-DR and 105-F Reactor facilities and ancillary facilities

International Nuclear Information System (INIS)

Coenenberg, E.T.

1998-01-01

This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives to address final disposition of the 105-DR and 105-F Reactor Buildings (subsequently referred to as facilities), including the fuel storage basins (FSB) and below-grade portions of the reactors, excluding the reactor blocks. The reactor blocks will remain in a safe storage mode for up to 75 years as identified in the Record the Decision (ROD) (58 FR 48509) for the Environmental Impact Statement (EIS), Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington (DOE 1992a). This EE/CA also addresses final disposition of four ancillary facilities: 116-D and 116-DR Exhaust Air Stacks, 117-DR Exhaust Filter Building, and 119-DR Exhaust Air Sample Building. The 105-DR and 105-F facilities are located in the 100-D and 100-F Areas of the Hanford Site. In November 1989, the 100 Area of the Hanford Site was placed on the U.S. Environmental Protection Agency's (EPA) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The 100 Area NPL includes the 100-D Area (which includes the 100-DR site) and the 100-F Area, which are in various stages of the remediation process. It has been determined by DOE that hazardous substances in the 105-DR, 105-F, and the four ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, DOE, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the 105-DR and 105-F facilities and the four ancillary facilities. The 116-DR and 117-DR facilities are located within the boundaries of the 105-DR Large Sodium Fire Facility Treatment, Storage, and Disposal (TSD) unit, which is

Experimental Facilities for Performance Evaluation of Fast Reactor Components

International Nuclear Information System (INIS)

Chandramouli, S.; Kumar, V.A. Suresh; Shanmugavel, M.; Vijayakumar, G.; Vinod, V.; Noushad, I.B.; Babu, B.; Kumar, G. Padma; Nashine, B.K.; Rajan, K.K.

2013-01-01

Brief details about various experimental facilities catering to the testing and performance evaluation requirements of fast reactor components have been brought out. These facilities have been found to be immensely useful to continue research and development activities in the areas of component development and testing, sodium technology, thermal hydraulics and sodium instrumentation for the SFR’s. In addition new facilities which have been planned will be of great importance for the developmental activities related to future SFR’s

Evaluating Past and Future USCG Use of Ohmsett Test Facility

Science.gov (United States)

2016-10-01

of Pages 22 22. Price Evaluating Past and Future USCG Use of Ohmsett Test Facility iv UNCLAS//Public | | CG-926 RDC | M. Fitzpatrick, et al...Opportunity Skimming System WEC Wave energy converter Evaluating Past and Future USCG Use of Ohmsett Test Facility x UNCLAS//Public | | CG-926 RDC | M...Date Summary of Effort OCT-NOV 1993 Vessel of Opportunity Skimming System (VOSS) (5 Weeks) APR-JUN 1996 Spilled Oil Recovery System (SORS) (8 Weeks

A model for evaluating the environmental benefits of elementary school facilities.

Science.gov (United States)

Ji, Changyoon; Hong, Taehoon; Jeong, Kwangbok; Leigh, Seung-Bok

2014-01-01

In this study, a model that is capable of evaluating the environmental benefits of a new elementary school facility was developed. The model is composed of three steps: (i) retrieval of elementary school facilities having similar characteristics as the new elementary school facility using case-based reasoning; (ii) creation of energy consumption and material data for the benchmark elementary school facility using the retrieved similar elementary school facilities; and (iii) evaluation of the environmental benefits of the new elementary school facility by assessing and comparing the environmental impact of the new and created benchmark elementary school facility using life cycle assessment. The developed model can present the environmental benefits of a new elementary school facility in terms of monetary values using Environmental Priority Strategy 2000, a damage-oriented life cycle impact assessment method. The developed model can be used for the following: (i) as criteria for a green-building rating system; (ii) as criteria for setting the support plan and size, such as the government's incentives for promoting green-building projects; and (iii) as criteria for determining the feasibility of green building projects in key business sectors. Copyright © 2013 Elsevier Ltd. All rights reserved.

Seismic evaluation of existing nuclear facilities. Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

Programmes for re-evaluation and upgrading of safety of existing nuclear facilities are presently under way in a number of countries around the world. An important component of these programmes is the re-evaluation of the seismic safety through definition of new seismic parameters at the site and evaluation of seismic capacity of structures, equipment and distribution systems following updated information and criteria. The Seminar is intended to provide a forum for the exchange of information and discussion of the state-of-the-art on seismic safety of nuclear facilities in operation or under construction. Both analytical and experimental techniques for the evaluation of seismic capacity of structures, equipment and distribution systems are discussed. Full scale and field tests of structures and components using shaking tables, mechanical exciters, explosive and shock tests, and ambient vibrations are included in the seminar programme with emphasis on recent case histories. Presentations at the Seminar also include analytical techniques for the determination of dynamic properties of soil-structure systems from experiments as well as calibration of numerical models. Methods and criteria for seismic margin assessment based on experience data obtained from the behaviour of structures and components in real earthquakes are discussed. Guidelines for defining technical requirements for capacity re-evaluation (i.e. acceptable behaviour limits and design and implementation of structure and components upgrades are also presented and discussed. The following topics were covered during 7 sessions: earthquake experience and seismic re-evaluation; country experience in seismic re-evaluation programme; generic WWER studies; analytical methods for seismic capacity re-evaluation; experimental methods for seismic capacity re-evaluation; case studies.

Seismic evaluation of existing nuclear facilities. Proceedings

International Nuclear Information System (INIS)

1995-01-01

Programmes for re-evaluation and upgrading of safety of existing nuclear facilities are presently under way in a number of countries around the world. An important component of these programmes is the re-evaluation of the seismic safety through definition of new seismic parameters at the site and evaluation of seismic capacity of structures, equipment and distribution systems following updated information and criteria. The Seminar is intended to provide a forum for the exchange of information and discussion of the state-of-the-art on seismic safety of nuclear facilities in operation or under construction. Both analytical and experimental techniques for the evaluation of seismic capacity of structures, equipment and distribution systems are discussed. Full scale and field tests of structures and components using shaking tables, mechanical exciters, explosive and shock tests, and ambient vibrations are included in the seminar programme with emphasis on recent case histories. Presentations at the Seminar also include analytical techniques for the determination of dynamic properties of soil-structure systems from experiments as well as calibration of numerical models. Methods and criteria for seismic margin assessment based on experience data obtained from the behaviour of structures and components in real earthquakes are discussed. Guidelines for defining technical requirements for capacity re-evaluation (i.e. acceptable behaviour limits and design and implementation of structure and components upgrades are also presented and discussed. The following topics were covered during 7 sessions: earthquake experience and seismic re-evaluation; country experience in seismic re-evaluation programme; generic WWER studies; analytical methods for seismic capacity re-evaluation; experimental methods for seismic capacity re-evaluation; case studies

Evaluation of natural phenomena hazards as part of safety assessments for nuclear facilities

International Nuclear Information System (INIS)

Kot, C.A.; Hsieh, B.J.; Srinivasan, M.G.; Shin, Y.W.

1995-02-01

The continued operation of existing US Department of Energy (DOE) nuclear facilities and laboratories requires a safety reassessment based on current criteria and guidelines. This also includes evaluations for the effects of Natural Phenomena Hazards (NPH), for which these facilities may not have been designed. The NPH evaluations follow the requirements of DOE Order 5480.28, Natural Phenomena Hazards Mitigation (1993) which establishes NPH Performance Categories (PCs) for DOE facilities and associated target probabilistic performance goals. These goals are expressed as the mean annual probability of exceedance of acceptable behavior for structures, systems and components (SSCs) subjected to NPH effects. The assignment of an NPH Performance Category is based on the overall hazard categorization (low, moderate, high) of a facility and on the function of an SSC under evaluation (DOE-STD-1021, 1992). Detailed guidance for the NPH analysis and evaluation criteria are also provided (DOE-STD-1020, 1994). These analyses can be very resource intensive, and may not be necessary for the evaluation of all SSCs in existing facilities, in particular for low hazard category facilities. An approach relying heavily on screening inspections, engineering judgment and use of NPH experience data (S. J. Eder et al., 1993), can minimize the analytical effort, give reasonable estimates of the NPH susceptibilities, and yield adequate information for an overall safety evaluation of the facility. In the following sections this approach is described in more detail and is illustrated by an application to a nuclear laboratory complex

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.

Defense-in-depth evaluation for the New Waste Transfer Facility

International Nuclear Information System (INIS)

Hayes, T.G.; Kelly, J.L.

1995-01-01

This report fulfills part of the requirements of References 2 and 3 by documenting a Defense-In-Depth evaluation for the New Waste Transfer Facility (NWTF). This evaluation was performed using methodology similar to that used in an evaluation for the Defense Waste Processing Facility (DWPF). It differs because the DWPF evaluation was based on an existing Process Hazards Analysis (PHA) while NWTF's is based on a Preoperational Process Hazards Review (PHR) (Ref. 1). The accidents in the Process Hazards Review (PHR) were reviewed to determine those that might have significant consequences. Significance was based on the findings of the PHR, The facility design was reviewed to determine the Structures, Systems, and Components (SSCs) and administrative controls available before and after each accident. From this was developed a list of the Lines of Defense (LODs) available to contain the hazard associated with the accident. A summary of these LODs is given in Appendix C. Items are tabulated that are suggested for consideration in the functional classification as worker protection items. The specific criteria used in the evaluation is given in the methodology section of this report. The results are documented in Appendices A, B, C, and D

Evaluation verification facilities (EVF) at MINT: concept and implementation

International Nuclear Information System (INIS)

Mohamed Hairul Hasmoni; Abd Nassir Ibrahim; Ab Razak Hamzah

2003-01-01

EVF facilities and components available are described comprehensively. Objective of establishing EVF as a National Centre for non-destructive testing (NDT) are discussed for various activities of method and equipment validation, R and D on quantitative NDT technique, training and certification, and defect characterization. For a successful activity available at EVF, it is vital that industry participates through input of funding, sponsorship and knowledge sharing. The Malaysian Institute for Nuclear Technology Research (MINT) invested a lot in this facility and ready to share this facility under various mechanisms such as memorandum of understanding (MOU), memorandum of agreement (MOA), contract research or letter of agreement. The facility would be open to industry. Member of NDT community are welcomed to conduct trial and discuss particular areas of interest with others in the industry. Optimising the facility by utilising the facility available and adding new components would make EVF a national centre for NDT and centre of excellence. This paper reviews the concept and implementation of an Evaluation Verification Facility (EVF) at MINT. The types and designs of facilities available are described and characterised by usage NDT. (Author)

A heuristic approach to handle capacitated facility location problem evaluated using clustering internal evaluation

Science.gov (United States)

Sutanto, G. R.; Kim, S.; Kim, D.; Sutanto, H.

2018-03-01

One of the problems in dealing with capacitated facility location problem (CFLP) is occurred because of the difference between the capacity numbers of facilities and the number of customers that needs to be served. A facility with small capacity may result in uncovered customers. These customers need to be re-allocated to another facility that still has available capacity. Therefore, an approach is proposed to handle CFLP by using k-means clustering algorithm to handle customers’ allocation. And then, if customers’ re-allocation is needed, is decided by the overall average distance between customers and the facilities. This new approach is benchmarked to the existing approach by Liao and Guo which also use k-means clustering algorithm as a base idea to decide the facilities location and customers’ allocation. Both of these approaches are benchmarked by using three clustering evaluation methods with connectedness, compactness, and separations factors.

Risk evaluation system for facility safeguards and security planning

International Nuclear Information System (INIS)

Udell, C.J.; Carlson, R.L.

1987-01-01

The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planing assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily

Risk evaluation system for facility safeguards and security planning

International Nuclear Information System (INIS)

Udell, C.J.; Carlson, R.L.

1987-01-01

The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planning assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily

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

Nuclear power plant simulation facility evaluation methodology

International Nuclear Information System (INIS)

Haas, P.M.; Carter, R.J.; Laughery, K.R. Jr.

1985-01-01

A methodology for evaluation of nuclear power plant simulation facilities with regard to their acceptability for use in the US Nuclear Regulatory Commission (NRC) operator licensing exam is described. The evaluation is based primarily on simulator fidelity, but incorporates some aspects of direct operator/trainee performance measurement. The panel presentation and paper discuss data requirements, data collection, data analysis and criteria for conclusions regarding the fidelity evaluation, and summarize the proposed use of direct performance measurment. While field testing and refinement of the methodology are recommended, this initial effort provides a firm basis for NRC to fully develop the necessary methodology

Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

1997-01-01

The deactivated 233-S Plutonium Concentration Facility (233-S Facility) is located in the 200 Area. The facility has undergone severe degradation due to exposure to extreme weather conditions. A rapid freeze and thaw cycle occurred at the Hanford Site during February 1996, which caused cracking to occur on portions of the building's roof. This has resulted in significantly infiltration of water into the facility, which provides a pathway for potential release of radioactive material into the environment (air and/or ground). The weather caused several existing cracks in the concrete portions of the structure to lengthen, increasing the potential for failed confinement of the radioactive material in the building. Differential settlement has also occurred, causing portions of the facility to separate from the main building structure thus creating a potential for release of radioactive material t the environment. An expedited removal action is proposed to ensure that a release from the 233-S Facility does not occur. The US Department of Energy (DOE), Richland Operations Office (RL), in cooperation with the EPA, has prepared this Engineering Evaluation/Cost Analysis (EE/CA) pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health and/or the environment, and that an expedited removal action is warranted. The purpose of the EE/CA is to provide the framework for the evaluation and selection of a technology from a viable set of alternatives for a removal action

SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility

International Nuclear Information System (INIS)

Rathbun, R.

1993-01-01

Separate review of NMP-NCS-930058, open-quotes Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility (U), August 17, 1993,close quotes was requested of SRTC Applied Physics Group. The NCSE is a criticality assessment to determine waste container uranium limits in the Uranium Solidification Facility's Waste Handling Facility. The NCSE under review concludes that the NDA room remains in a critically safe configuration for all normal and single credible abnormal conditions. The ability to make this conclusion is highly dependent on array limitation and inclusion of physical barriers between 2x2x1 arrays of boxes containing materials contaminated with uranium. After a thorough review of the NCSE and independent calculations, this reviewer agrees with that conclusion

Study on uncertainty evaluation system for the safety evaluation of interim spent fuel storage facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Myung Hyeon; Shin, Myeong Won; Rhy, Seok Jin; Cho, Dong Keon; Park, Dong Hwan [Kyunghee Univ., Seoul (Korea, Republic of); Cheong, Beom Jin [Minstry of Science and Technology, Gwacheon (Korea, Republic of)

1998-03-15

The main objective os to develop a technical standards for the facility operation of the interm, spent fuel storage facility and to develop a draft for the technical criteria to be legislated. The another objective os to define a uncertainty evaluation system for burn up credit application in criticality analysis and to investigate an applicability of this topic for future regulatory activity. Investigate a status of art for the operational criteria of spent fuel interm wet storage. Collect relevant laws, decree, notices and standards related to the operation of storage facility and study on the legislation system. Develop a draft of technical standards and criteria to be legislated. Define an evaluation system for the uncertainty analysis and study on the status of art in the field of criticality safety analysis. Develop an uncertainty evaluation system in criticality analysis with burnup credit and investigate an applicability as well as its benefits of this policy.

Development and evaluation of fully automated demand response in large facilities

Energy Technology Data Exchange (ETDEWEB)

Piette, Mary Ann; Sezgen, Osman; Watson, David S.; Motegi, Naoya; Shockman, Christine; ten Hope, Laurie

2004-03-30

This report describes the results of a research project to develop and evaluate the performance of new Automated Demand Response (Auto-DR) hardware and software technology in large facilities. Demand Response (DR) is a set of activities to reduce or shift electricity use to improve electric grid reliability, manage electricity costs, and ensure that customers receive signals that encourage load reduction during times when the electric grid is near its capacity. The two main drivers for widespread demand responsiveness are the prevention of future electricity crises and the reduction of electricity prices. Additional goals for price responsiveness include equity through cost of service pricing, and customer control of electricity usage and bills. The technology developed and evaluated in this report could be used to support numerous forms of DR programs and tariffs. For the purpose of this report, we have defined three levels of Demand Response automation. Manual Demand Response involves manually turning off lights or equipment; this can be a labor-intensive approach. Semi-Automated Response involves the use of building energy management control systems for load shedding, where a preprogrammed load shedding strategy is initiated by facilities staff. Fully-Automated Demand Response is initiated at a building or facility through receipt of an external communications signal--facility staff set up a pre-programmed load shedding strategy which is automatically initiated by the system without the need for human intervention. We have defined this approach to be Auto-DR. An important concept in Auto-DR is that a facility manager is able to ''opt out'' or ''override'' an individual DR event if it occurs at a time when the reduction in end-use services is not desirable. This project sought to improve the feasibility and nature of Auto-DR strategies in large facilities. The research focused on technology development, testing

Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

International Nuclear Information System (INIS)

Rugg, J.E.

1996-08-01

The 100, 200, 300 and 1100 Areas of the Hanford Site were placed on the U. S. Environmental Protection Agency's National Priorities List in November 1989 under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Located in the 200 Area is the deactivated 233-S Plutonium Concentration Facility (used in the REDOX process). The facility has undergone severe degradation due to exposure to extreme weather conditions. An expedited response is proposed to ensure protection of human health and the environment. The Department of Energy, Richland Operations Office (RL) in cooperation with the Washington State Department of Ecology, has prepared this Engineering Evaluation/Cost Analysis pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health or the environment, and that an expedited removal action is warranted for decommissioning of the facility

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

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.

Practical evaluations of low-level waste disposal facilities

International Nuclear Information System (INIS)

Rogers, V.C.

1989-01-01

In general, there have been about four main tools that have been used to assist in selecting a disposal technology and in evaluating that technology: Legislative direction; Operator selection; Multiattribute utility estimation; and Risk assessment and cost benefit evaluation. The first technique, legislative direction, is an important factor in determining the range of disposal technologies that may be considered. Some host state entities have chosen not to participate in the disposal technology selection, but will let the facility operator propose and defend his preferred facility concept in the license application. Multiattribute utility estimation is a widely used tool for evaluating technologies, particularly in the preliminary stages of selecting a disposal technology when significant technical and institutional information is missing. Many factors, including a range of technical, safety, environmental, societal, political, and economic concerns must be considered in the selection process. Many of these are hard to quantify and not all are of equal importance. Multiattrubute utility estimation allows for these factors to be considered in selecting a technology with incomplete information. This chapter provides description of two analysis techniques: multiattribute utility estimation and cost benefit evaluation. Both can be used to help profile disposal alternatives in relation to specific factors or criteria

Test facility for the evaluation of microwave transmission components

International Nuclear Information System (INIS)

Fong, C.G.; Poole, B.R.

1985-01-01

A Low Power Test Facility (LPTF) was developed to evaluate the performance of Electron Cyclotron Resonance Heating (ECRH) microwave transmission components for the Mirror Fusion Test Facility (MFTF-B). The facility generates 26 to 60 GHz in modes of TE 01 , TE 02 , or TE 03 launched at power levels of 1/2 milliwatt. The propagation of the rf as it radiates from either transmitting or secondary reflecting microwave transmission components is recorded by a discriminating crystal detector mechanically manipulated at constant radius in spherical coordinates. The facility is used to test, calibrate, and verify the design of overmoded, circular waveguide components, quasi-optical reflecting elements before high power use. The test facility consists of microwave sources and metering components, such as VSWR, power and frequency meters, a rectangular TE 10 to circular TE 01 mode transducer, mode filter, circular TE 01 to 2.5 in. diameter overmoded waveguide with mode converters for combination of TE 01 to TE 03 modes. This assembly then connects to a circular waveguide launcher or the waveguide component under test

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

Validity evaluation of internal exposure in nuclear facility decommission

International Nuclear Information System (INIS)

Wang Xiaoli; Chen Dahua; You Zeyun

2012-01-01

During nuclear facility decommission under construction, it is very important for workers to wear respirator to avoid harm of Am aerosols. So the protection effect of respirator is very important. The protection effect of respirator was calculated and evaluated according to the data achieved from engineering practice. The result shows that the protection effect is better than target management value and the respirator is effective to protect workers from harm of Am aerosols. The respirator is applied to other nuclear facility decommission. (authors)

Evaluation of scaling concepts for integral system test facilities

International Nuclear Information System (INIS)

Condie, K.G.; Larson, T.K.; Davis, C.B.

1987-01-01

A study was conducted by EG and G Idaho, Inc., to identify and technically evaluate potential concepts which will allow the U.S. Nuclear Regulatory Commission to maintain the capability to conduct future integral, thermal-hydraulic facility experiments of interest to light water reactor safety. This paper summarizes the methodology used in the study and presents a rankings for each facility concept relative to its ability to simulate phenomena identified as important in selected reactor transients in Babcock and Wilcox and Westinghouse large pressurized water reactors. Established scaling methodologies are used to develop potential concepts for scaled integral thermal-hydraulic experiment facilities. Concepts selected included: full height, full pressure water; reduced height, reduced pressure water; reduced height, full pressure water; one-tenth linear, full pressure water; and reduced height, full scaled pressure Freon. Results from this study suggest that a facility capable of operating at typical reactor operating conditions will scale most phenomena reasonably well. Local heat transfer phenomena is best scaled by the full height facility, while the reduced height facilities provide better scaling where multi-dimensional phenomena are considered important. Although many phenomena in facilities using Freon or water at nontypical pressure will scale reasonably well, those phenomena which are heavily dependent on quality can be distorted. Furthermore, relation of data produced in facilities operating with nontypical fluids or at nontypical pressures to large plants will be a difficult and time-consuming process

Evaluation of radiological dispersion/consequence codes supporting DOE nuclear facility SARs

International Nuclear Information System (INIS)

O'Kula, K.R.; Paik, I.K.; Chung, D.Y.

1996-01-01

Since the early 1990s, the authorization basis documentation of many U.S. Department of Energy (DOE) nuclear facilities has been upgraded to comply with DOE orders and standards. In this process, many safety analyses have been revised. Unfortunately, there has been nonuniform application of software, and the most appropriate computer and engineering methodologies often are not applied. A DOE Accident Phenomenology and Consequence (APAC) Methodology Evaluation Program was originated at the request of DOE Defense Programs to evaluate the safety analysis methodologies used in nuclear facility authorization basis documentation and to define future cost-effective support and development initiatives. Six areas, including source term development (fire, spills, and explosion analysis), in-facility transport, and dispersion/ consequence analysis (chemical and radiological) are contained in the APAC program. The evaluation process, codes considered, key results, and recommendations for future model and software development of the Radiological Dispersion/Consequence Working Group are summarized in this paper

CSER 94-012: Criticality safety evaluation report for 340 Facility

International Nuclear Information System (INIS)

Altschuler, S.J.

1995-01-01

This Criticality Safety Evaluation Report (CSER) covers the 340 Facility which acts as a collecting point for liquid and solid waste from various facilities in the 300 Area. Criticality safety is achieved by controlling the amount and concentration of the fissionable material sent to the 340 Facility from the originating facilities in the 300 Area, a method similar to that used elsewhere at Hanford for the waste tank farms. Unlike those, however, the waste received at the 340 Facility will be far less radioactive. It is concluded that present operations meet the two contingency criterion. The facility will still be safely subcritical even after two independent and concurrent failures (either of equipment or administrative controls). The solid waste storage and liquid waste will be managed separately. The solid waste storage area is classified as exempt because it contains less than 15 grams of fissionable materials. The Radioactive Liquid Waste System is classified as isolated because it contains less than one third of a minimum critical mass. The criticality safety of the 340 Facility devoted to the Radioactive Liquid Waste System (RLWS) is assured by the form and concentration of the fissile material and could also be classified as a limited control facility. However, the 340 Facility has been operated as an isolated facility which results in a more conservative limit

Evaluation of physical facilities and processing operations of major ...

African Journals Online (AJOL)

... of these abattoirs were evaluated based on their presence and functional status. ... of safe and wholesome meat and meat products for human consumption. Keywords: Abattoir, Butcher, Meat, Physical facilities, Public health, Standard ...

Evaluation of Nuclear Facility Decommissioning Projects program

International Nuclear Information System (INIS)

Baumann, B.L.

1983-01-01

The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

International symposium on seismic evaluation of existing nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Orbovic, N.; Bouchon, M. [Institut de Radioprotection et de Surete Nucleaire, IRSN, 92 - Fontenay aux Roses (France); Vendel, J.; Gelain, T. [IRSN/DPEA/SERAC, 91 - Gif sur Yvette (France)

2003-10-01

Below are summarized the works of Mrs N. Orbovic and M. Bouchon; B. Stojadinovic, N. Orbovic, M.Bouchon and J.T. Wiley; M. Bouchon, N. Orbovic and B. Foure; T. Gelain, F. Gensdarmes, R. Sestier-Carlin, J. Vendel and M. Bouchon dealing respectively with: 1) seismic assessment of existing nuclear facility: a case study position of the IRSN 2) static and dynamic evaluation of an existing nuclear facility reinforced concrete frame structure 3) experimental study of cracking of low-rise reinforced concrete shear walls 4) aeraulics study of crack networks on low-rise reinforced concrete walls subject to static cycling loading. The summaries are followed: 1) The Institute for Radioprotection and Nuclear Safety (IRSN) has the task of evaluating the seismic safety of existing building inventory in French nuclear facilities. Some of the existing structures are reinforced concrete frame buildings with masonry or reinforced concrete in-fill walls built during the 1960's, 70's and 80's following different building codes and seismic input data applicable at the time of construction. The studied building is a laboratory that was built in 1962. The building is composed of three different and independent blocks. The structure is a reinforced concrete frame with masonry in-fills and few stiff concrete elements. Moreover, the building contains an independent massive concrete cell. Structurally, the building has a number of irregularities. From the detailing standpoint, well known deficiencies of low-ductile reinforced concrete structures are evident especially, a lack of transverse reinforcement in the structural joints of the frame. A number of sensitivity studies were conducted using 2D and 3D linear models to evaluate seismic demand. Ambient vibration and regional earthquake records were used to check the soil nature and the existence or not of a possible site effect around the installation as well as to characterize the dynamic behavior of the building. 3D models

Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.

1993-01-01

This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

Environmental, economic, and energy impacts of material recovery facilities. A MITE Program evaluation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This report documents an evaluation of the environmental, economic, and energy impacts of material recovery facilities (MRFs) conducted under the Municipal Solid Waste Innovative Technology Evaluation (MITE) Program. The MITE Program is sponsored by the US Environmental Protection Agency to foster the demonstration and development of innovative technologies for the management of municipal solid waste (MSW). This project was also funded by the National Renewable Energy Laboratory (NREL). Material recovery facilities are increasingly being used as one option for managing a significant portion of municipal solid waste (MSW). The owners and operators of these facilities employ a combination of manual and mechanical techniques to separate and sort the recyclable fraction of MSW and to transport the separated materials to recycling facilities.

Evaluate of environment quality for γ irradiation facilities using fuzzy comprehensive judgment method

International Nuclear Information System (INIS)

Ha Yiming

2002-01-01

The environment quality of Jining Irradiation Centre new γ radiation facility was evaluated by fuzzy comprehensive judgment method. The result showed that the place of γ radiation facility was well and the measures of radiate shelter and environment protect were effective. The environment quality of its area was not obvious change and the result of environment evaluation was first-rate

Exploratory Shaft Facility quality assurance impact evaluation

International Nuclear Information System (INIS)

1987-08-01

This report addresses the impact of the quality assurance practices used for the Exploratory Shaft Facility (ESF) design, and construction in licensing as part of the repository. Acceptance criteria used for evaluating the suitability of ESF QA practices are based on documents that had not been invoked for repository design or construction activities at the time of this evaluation. This report identifies the QA practices necessary for ESF design and construction licensability. A review and evaluation of QA practices for ESF design and construction resulted in the following conclusions. QA practices were found to be acceptable with a few exceptions. QA practices for construction activities were found to be insufficiently documented in implementing procedures to allow a full and effective evaluation for licensing purposes. Recommendations are provided for mitigating impacts to ensure compatibility of the QA practices with those considered necessary for repository licensing. 8 refs., 3 tabs

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

International symposium on seismic evaluation of existing nuclear facilities

International Nuclear Information System (INIS)

Orbovic, N.; Bouchon, M.; Vendel, J.; Gelain, T.

2003-10-01

Below are summarized the works of Mrs N. Orbovic and M. Bouchon; B. Stojadinovic, N. Orbovic, M.Bouchon and J.T. Wiley; M. Bouchon, N. Orbovic and B. Foure; T. Gelain, F. Gensdarmes, R. Sestier-Carlin, J. Vendel and M. Bouchon dealing respectively with: 1) seismic assessment of existing nuclear facility: a case study position of the IRSN 2) static and dynamic evaluation of an existing nuclear facility reinforced concrete frame structure 3) experimental study of cracking of low-rise reinforced concrete shear walls 4) aeraulics study of crack networks on low-rise reinforced concrete walls subject to static cycling loading. The summaries are followed: 1) The Institute for Radioprotection and Nuclear Safety (IRSN) has the task of evaluating the seismic safety of existing building inventory in French nuclear facilities. Some of the existing structures are reinforced concrete frame buildings with masonry or reinforced concrete in-fill walls built during the 1960's, 70's and 80's following different building codes and seismic input data applicable at the time of construction. The studied building is a laboratory that was built in 1962. The building is composed of three different and independent blocks. The structure is a reinforced concrete frame with masonry in-fills and few stiff concrete elements. Moreover, the building contains an independent massive concrete cell. Structurally, the building has a number of irregularities. From the detailing standpoint, well known deficiencies of low-ductile reinforced concrete structures are evident especially, a lack of transverse reinforcement in the structural joints of the frame. A number of sensitivity studies were conducted using 2D and 3D linear models to evaluate seismic demand. Ambient vibration and regional earthquake records were used to check the soil nature and the existence or not of a possible site effect around the installation as well as to characterize the dynamic behavior of the building. 3D models revealed a

Planning Tool for Strategic Evaluation of Facility Plans - 13570

Energy Technology Data Exchange (ETDEWEB)

Magoulas, Virginia; Cercy, Michael [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Hall, Irin [Newport News Shipbuilding, 4101 Washington Ave., Newport News, VA 23607 (United States)

2013-07-01

Savannah River National Laboratory (SRNL) has developed a strategic planning tool for the evaluation of the utilization of its unique resources for processing and research and development of nuclear materials. The Planning Tool is a strategic level tool for assessing multiple missions that could be conducted utilizing the SRNL facilities and showcasing the plan. Traditional approaches using standard scheduling tools and laying out a strategy on paper tended to be labor intensive and offered either a limited or cluttered view for visualizing and communicating results. A tool that can assess the process throughput, duration, and utilization of the facility was needed. SRNL teamed with Newport News Shipbuilding (NNS), a division of Huntington Ingalls Industries, to create the next generation Planning Tool. The goal of this collaboration was to create a simulation based tool that allows for quick evaluation of strategies with respect to new or changing missions, and clearly communicates results to the decision makers. This tool has been built upon a mature modeling and simulation software previously developed by NNS. The Planning Tool provides a forum for capturing dependencies, constraints, activity flows, and variable factors. It is also a platform for quickly evaluating multiple mission scenarios, dynamically adding/updating scenarios, generating multiple views for evaluating/communicating results, and understanding where there are areas of risks and opportunities with respect to capacity. The Planning Tool that has been developed is useful in that it presents a clear visual plan for the missions at the Savannah River Site (SRS). It not only assists in communicating the plans to SRS corporate management, but also allows the area stakeholders a visual look at the future plans for SRS. The design of this tool makes it easily deployable to other facility and mission planning endeavors. (authors)

Planning Tool for Strategic Evaluation of Facility Plans - 13570

International Nuclear Information System (INIS)

Magoulas, Virginia; Cercy, Michael; Hall, Irin

2013-01-01

Savannah River National Laboratory (SRNL) has developed a strategic planning tool for the evaluation of the utilization of its unique resources for processing and research and development of nuclear materials. The Planning Tool is a strategic level tool for assessing multiple missions that could be conducted utilizing the SRNL facilities and showcasing the plan. Traditional approaches using standard scheduling tools and laying out a strategy on paper tended to be labor intensive and offered either a limited or cluttered view for visualizing and communicating results. A tool that can assess the process throughput, duration, and utilization of the facility was needed. SRNL teamed with Newport News Shipbuilding (NNS), a division of Huntington Ingalls Industries, to create the next generation Planning Tool. The goal of this collaboration was to create a simulation based tool that allows for quick evaluation of strategies with respect to new or changing missions, and clearly communicates results to the decision makers. This tool has been built upon a mature modeling and simulation software previously developed by NNS. The Planning Tool provides a forum for capturing dependencies, constraints, activity flows, and variable factors. It is also a platform for quickly evaluating multiple mission scenarios, dynamically adding/updating scenarios, generating multiple views for evaluating/communicating results, and understanding where there are areas of risks and opportunities with respect to capacity. The Planning Tool that has been developed is useful in that it presents a clear visual plan for the missions at the Savannah River Site (SRS). It not only assists in communicating the plans to SRS corporate management, but also allows the area stakeholders a visual look at the future plans for SRS. The design of this tool makes it easily deployable to other facility and mission planning endeavors. (authors)

International symposium on seismic evaluation of existing nuclear facilities. Book of invited and contributed papers

International Nuclear Information System (INIS)

2003-08-01

In the past decade, seismic evaluation of existing Nuclear Power Plants (NPPs) has been an issue in western countries (particularly for the east of North America and for older NPPs in Europe) as well as in eastern European countries where systematic reviews of NPPs were carried out. Several Member States have still on-going seismic upgrading programmes. Presently. projects of plant life extension create an additional interest in safety evaluation of existing NPPs. Seismic evaluation is also an issue for other nuclear facilities. In western countries. some older facilities (laboratories, research reactors, fuel plants...) have been designed without taking into account (or poorly taking into account) earthquake input, even on seismic sites. In eastern countries, the situation is not yet clearly evaluated. In several countries concerns are expressed regarding research reactors. Generally speaking, the seismic evaluation of these nuclear facilities is not so advanced as the evaluation of NPPs and presents a wider range of different situations. Those safety issues raised by the seismic evaluation of existing NPPs are addressed in an IAEA Safety Report 'Seismic Evaluation of Existing Nuclear Power Plants' (2003). Other nuclear facilities are, at least partly, covered by IAEA-TECDOC 1347 'Design of Nuclear Facilities other than NPPs in Relation to External Events, with a Special Emphasis on Earthquake' (2003) that supersedes the former TECDOC 348 'Earthquake Resistant Design of Nuclear Facilities with Limited Radioactive Inventory' (1985). Concurrently with the publishing of relevant documentation, the IAEA has organized this Symposium in order to foster the exchange of information on topical issues in seismic evaluation of existing nuclear facilities, with the aim of: consolidating an international consensus on the present status of these issues; promoting a homogeneous engineering approach of their resolution; identifying the needs for strengthening international co

International symposium on seismic evaluation of existing nuclear facilities. Book of invited and contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-08-01

In the past decade, seismic evaluation of existing Nuclear Power Plants (NPPs) has been an issue in western countries (particularly for the east of North America and for older NPPs in Europe) as well as in eastern European countries where systematic reviews of NPPs were carried out. Several Member States have still on-going seismic upgrading programmes. Presently. projects of plant life extension create an additional interest in safety evaluation of existing NPPs. Seismic evaluation is also an issue for other nuclear facilities. In western countries. some older facilities (laboratories, research reactors, fuel plants...) have been designed without taking into account (or poorly taking into account) earthquake input, even on seismic sites. In eastern countries, the situation is not yet clearly evaluated. In several countries concerns are expressed regarding research reactors. Generally speaking, the seismic evaluation of these nuclear facilities is not so advanced as the evaluation of NPPs and presents a wider range of different situations. Those safety issues raised by the seismic evaluation of existing NPPs are addressed in an IAEA Safety Report 'Seismic Evaluation of Existing Nuclear Power Plants' (2003). Other nuclear facilities are, at least partly, covered by IAEA-TECDOC 1347 'Design of Nuclear Facilities other than NPPs in Relation to External Events, with a Special Emphasis on Earthquake' (2003) that supersedes the former TECDOC 348 'Earthquake Resistant Design of Nuclear Facilities with Limited Radioactive Inventory' (1985). Concurrently with the publishing of relevant documentation, the IAEA has organized this Symposium in order to foster the exchange of information on topical issues in seismic evaluation of existing nuclear facilities, with the aim of: consolidating an international consensus on the present status of these issues; promoting a homogeneous engineering approach of their resolution; identifying the needs for strengthening international co

Evaluation and Selection of Renewable Energy Technologies for Highway Maintenance Facilities

Science.gov (United States)

Andrews, Taylor

The interest in renewable energy has been increasing in recent years as attempts to reduce energy costs as well the consumption of fossil fuels are becoming more common. Companies and organizations are recognizing the increasing reliance on limited fossil fuels' resources, and as competition and costs for these resources grow, alternative solutions are becoming more appealing. Many federally run buildings and associations also have the added pressure of meeting the mandates of federal energy policies that dictate specific savings or reductions. Federal highway maintenance facilities run by the Department of Transportation fall into this category. To help meet energy saving goals, an investigation into potential renewable energy technologies was completed for the Ohio Department of Transportation. This research examined several types of renewable energy technologies and the major factors that affect their performance and evaluated their potential for implementation at highway maintenance facilities. Facilities energy usage data were provided, and a facility survey and site visits were completed to enhance the evaluation of technologies and the suitability for specific projects. Findings and technology recommendations were presented in the form of selection matrices, which were designed to help make selections in future projects. The benefits of utilization of other tools such as analysis software and life cycle assessments were also highlighted. These selection tools were designed to be helpful guides when beginning the pursuit of a renewable energy technology for highway maintenance facilities, and can be applied to other similar building types and projects. This document further discusses the research strategies and findings as well as the recommendations that were made to the personnel overseeing Ohio's highway maintenance facilities.

Empirical evaluation of lung solubilities of airborne contamination at Harwell facilities

International Nuclear Information System (INIS)

Bull, R. K.; Wilson, G.

2011-01-01

Lung solubility is the key parameter in determining intakes and doses from inhalation of airborne contamination. However, information on lung solubility can be difficult to acquire, particularly for the historical exposures that are of relevance to lifetime-dose reconstruction. In this study, an empirical approach has been made in which over 200 dose assessments, mainly for Pu and Am, from the period 1986 to 2005 were re-evaluated and the solubility mix required for the best fit to the data was determined. The average of these solubility mixtures for any building or facility can be used as the default solubility for retrospective dose assessments for that facility. Results are presented for a radiochemistry facility, a materials development facility and a waste-storage/handling building at Harwell. The latter two areas are characterised by aerosols that are predominantly insoluble (type S), whereas the radiochemistry facility has a heterogeneous mixture of insoluble and soluble aerosols. The implications of these results for dose reconstruction are discussed in the paper. (authors)

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.

Engineering Evaluation/Cost Analysis for the 100-N Area Ancillary Facilities and Integration Plan

International Nuclear Information System (INIS)

Mukherjee, B.

1997-09-01

This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives for addressing final disposition of contaminated buildings and structures in the 100-N Area of the Hanford Site. The Hanford Site is located in southeastern Washington State and is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office (RL). In November 1989, the 100 Area of the Hanford Site (as well as the 200, 300, and 1100 Areas) was placed on the U.S. Environmental Protection Agency's National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980. The 100 Area NPL includes the 100-N Area, which is in various stages of the remediation process. It has been determined by RL that hazardous substances in the 100-N Area ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, RL, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the inactive contaminated ancillary facilities in the 100-N Area, the facilities residing in the buffer zone, and the Hanford Generating Plant (HGP) and the solid waste management units (SWMUs) inside HGP support facilities. The 105-N Reactor and 109-N Heat Exchange facilities are excluded from this EE/CA evaluation

Switch evaluation test system for the National Ignition Facility

International Nuclear Information System (INIS)

Savage, M.E.; Simpson, W.W.; Reynolds, F.D.

1997-01-01

Flashlamp pumped lasers use pulsed power switches to commute energy stored in capacitor banks to the flashlamps. The particular application in which the authors are interested is the National Ignition Facility (NIF), being designed by Lawrence Livermore National Laboratory, Los Alamos National Laboratory, and Sandia National Laboratories (SNL). To lower the total cost of these switches, SNL has a research program to evaluate large closing switches. The target value of the energy switched by a single device is 1.6 MJ, from a 6 mF, 24kV capacitor bank. The peak current is 500 kA. The lifetime of the NIF facility is 24,000 shots. There is no switch today proven at these parameters. Several short-lived switches (100's of shots) exist that can handle the voltage and current, but would require maintenance during the facility life. Other type devices, notably ignitrons, have published lifetimes in excess of 20,000 shots, but at lower currents and shorter pulse widths. The goal of the experiments at SNL is to test switches with the full NIF wave shape, and at the correct voltage. The SNL facility can provide over 500 kA at 24 kV charge voltage. the facility has 6.4 mF total capacitance, arranged in 25 sub-modules. the modular design makes the facility more flexible (for possible testing at lower current) and safer. For pulse shaping (the NIF wave shape is critically damped) there is an inductor and resistor for each of the 25 modules. Rather than one large inductor and resistor, this lowers the current in the pulse shaping components, and raises their value to those more easily attained with lumped inductors and resistors. The authors show the design of the facility, and show results from testing conducted thus far. They also show details of the testing plan for high current switches

Seismic evaluation of the LLNL plutonium facility (Building 332)

International Nuclear Information System (INIS)

Hall, W.J.; Sozen, M.A.

1982-03-01

The expected performance of the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (Building 332) subjected to earthquake ground motion has been evaluated. Anticipated behavior of the building, glove boxes, ventilation system and other systems critical for containment of plutonium is described for three severe postulated earthquake excitations. Based upon this evaluation, some damage to the building, glove boxes and ventilation system would be expected but no collapse of any structure is anticipated as a result of the postulated earthquake ground motions

Educational Facility Evaluations of Primary Schools in Rural Honduras: Departments of Cortes and Meambar.

Science.gov (United States)

Council of Educational Facility Planners, International, Scottsdale, AZ.

A team of 11 educational facility planners and architects from the United States and Canada conducted a facility evaluation of schools in the rural areas of Meambar and Cortes, Honduras. Team members were all part of the Council of Educational Facility Planners, International and traveled to Honduras under the auspices of a Christian mission…

Neutron transport calculation for Activation Evaluation for Decommissioning of PET cyclotron Facility

Science.gov (United States)

Nobuhara, Fumiyoshi; Kuroyanagi, Makoto; Masumoto, Kazuyoshi; Nakamura, Hajime; Toyoda, Akihiro; Takahashi, Katsuhiko

2017-09-01

In order to evaluate the state of activation in a cyclotron facility used for the radioisotope production of PET diagnostics, we measured the neutron flux by using gold foils and TLDs. Then, the spatial distribution of neutrons and induced activity inside the cyclotron vault were simulated with the Monte Calro calculation code for neutron transport and DCHAIN-SP for activation calculation. The calculated results are in good agreement with measured values within factor 3. Therefore, the adaption of the advanced evaluation procedure for activation level is proved to be important for the planning of decommissioning of these facilities.

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

Review Article : Utilization of Environmental Radiochemistry Techniques for Selection and Evaluation of Nuclear Facility Sites

International Nuclear Information System (INIS)

Atta, E.R.; Madbouly, A.M.; Zakaria, Kh.M.

2016-01-01

This research review puts necessary considerations on the available environmental radiochemistry techniques for selection and evaluation of a nuclear facility sites.The main bjective in site evaluation for nuclear facilities in terms of nuclear safety is to protect the site workers, the public and the environment from the effects of ionizing radiation release from nuclear facilities due to accidents. The extreme sensitivity and speed of radiochemical methods make their applications of considerable importance in several fields and they have found many uses. Information about the existed radioactivity in the different nuclear facilities is an essential requirement for their environmental assessment. It is necessary to estimate the various radioactivity levels in the environment through qualitative and quantitative analytical techniques and to assess the potential effects of the nuclear facility in the region by considering the characteristics of sites.The siting and site evaluation requirements are discussed. Emphasis was given to types of radiochemical techniques used for characterization of the site parameters which determine the potential hazards of the site on the facility and the facility on the site. Emphasis has been also given to the quantitative and qualitative analysis of naturally occurring radionuclides for monitoring and control .There are some techniques employed such as radioactive tracer technique, liquid scintillation technique, gamma spectrometry technique, neutron activation analysis technique, fluorimetric technique and isotope hydrology technique.

105-DR Large Sodium Fire Facility closure activities evaluation report

International Nuclear Information System (INIS)

Adler, J.G.

1996-01-01

This report evaluates the closure activities at the 105-DR Large Sodium Fire Facility. The closure activities discussed include: the closure activities for the structures, equipment, soil, and gravel scrubber; decontamination methods; materials made available for recycling or reuse; and waste management. The evaluation compares these activities to the regulatory requirements and closure plan requirements. The report concludes that the areas identified in the closure plan can be clean closed

Gamma irradiation facility: Evaluation of operational modes

International Nuclear Information System (INIS)

Adesanmi, C.A.; Ali, M.S.; Shonowo, O.A.; Akueche, E.C.; Sadare, O.O.; Mustapha, T.K.; Yusuf, U.; Inyanda, A.K.

2007-01-01

The multipurpose Gamma Irradiation Facility (GIF) at the Nuclear Technology Centre (NTC), Sheda Science and Technology Complex (SHETSCO), Abuja, Nigeria is designed as a semi-commercial plant with facilities for research and development (R and D). The design takes into account the different needs of the various research applications which require a wide dose range, a variety of techniques, different product sizes, shapes, mass, volume, densities and types. Programmable doses are used for food irradiation (0.04 - 10 kGy), biological seed mutation breeding and sterile insect technique (STI) (0.01- 5 kGy) sterilization of medical, pharmaceutical and cosmetic products and packages (up to 25 kGy) and cross-linking of polymers (up to 100 kGy). The six different modes of operations (sample elevator, stationary, swiveling, 2-path inner lane and 2-path outer lane and 4-path line) were evaluated. The dose range, mass range and range of irradiation time practicable were established and advantages for radiation processing of food and industrial products were enumerated for the six modes of operations for the first time

Thermionic system evaluated test (TSET) facility description

Science.gov (United States)

Fairchild, Jerry F.; Koonmen, James P.; Thome, Frank V.

1992-01-01

A consortium of US agencies are involved in the Thermionic System Evaluation Test (TSET) which is being supported by the Strategic Defense Initiative Organization (SDIO). The project is a ground test of an unfueled Soviet TOPAZ-II in-core thermionic space reactor powered by electrical heat. It is part of the United States' national thermionic space nuclear power program. It will be tested in Albuquerque, New Mexico at the New Mexico Engineering Research Institute complex by the Phillips Laboratoty, Sandia National Laboratories, Los Alamos National Laboratory, and the University of New Mexico. One of TSET's many objectives is to demonstrate that the US can operate and test a complete space nuclear power system, in the electrical heater configuration, at a low cost. Great efforts have been made to help reduce facility costs during the first phase of this project. These costs include structural, mechanical, and electrical modifications to the existing facility as well as the installation of additional emergency systems to mitigate the effects of utility power losses and alkali metal fires.

Evaluation of syngas production unit cost of bio-gasification facility using regression analysis techniques

Energy Technology Data Exchange (ETDEWEB)

Deng, Yangyang; Parajuli, Prem B.

2011-08-10

Evaluation of economic feasibility of a bio-gasification facility needs understanding of its unit cost under different production capacities. The objective of this study was to evaluate the unit cost of syngas production at capacities from 60 through 1800Nm 3/h using an economic model with three regression analysis techniques (simple regression, reciprocal regression, and log-log regression). The preliminary result of this study showed that reciprocal regression analysis technique had the best fit curve between per unit cost and production capacity, with sum of error squares (SES) lower than 0.001 and coefficient of determination of (R 2) 0.996. The regression analysis techniques determined the minimum unit cost of syngas production for micro-scale bio-gasification facilities of $0.052/Nm 3, under the capacity of 2,880 Nm 3/h. The results of this study suggest that to reduce cost, facilities should run at a high production capacity. In addition, the contribution of this technique could be the new categorical criterion to evaluate micro-scale bio-gasification facility from the perspective of economic analysis.

105-DR Large sodium fire facility soil sampling data evaluation report

International Nuclear Information System (INIS)

Adler, J.G.

1996-01-01

This report evaluates the soil sampling activities, soil sample analysis, and soil sample data associated with the closure activities at the 105-DR Large Sodium Fire Facility. The evaluation compares these activities to the regulatory requirements for meeting clean closure. The report concludes that there is no soil contamination from the waste treatment activities

User's guide for evaluating physical security capabilities of nuclear facilities by the EASI method

International Nuclear Information System (INIS)

Bennett, H.A.

1977-06-01

This handbook is a guide for evaluating physical security of nuclear facilities using the ''Estimate of Adversary Sequence Interruption (EASI)'' method and a hand-held programmable calculator. The handbook is intended for use by personnel at facilities where special nuclear materials are used, processed, or stored. It may also be used as a design aid for such facilities by potential licensees

Removal site evaluation report for the Isotope Facilities at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

This removal site evaluation (RmSE) report of the Isotope Facilities at Oak Ridge National Laboratory (ORNL) was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Isotopes Facility pose a substantial risk to human health or the environment and if remedial site evaluations (RSEs) or removal actions are required. The scope of the project included: (1) a review of historical evidence regarding operations and use of the facility; (2) interviews with facility personnel concerning current and past operating practices; (3) a site inspection; and (4) identification of hazard areas requiring maintenance, removal, or remedial actions. The results of RmSE indicate that no substantial risks exist from contaminants present in the Isotope Facilities because adequate controls and practices exist to protect human health and the environment. The recommended correction from the RmSE are being conducted as maintenance actions; accordingly, this RmSE is considered complete and terminated.

Removal site evaluation report for the Isotope Facilities at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-07-01

This removal site evaluation (RmSE) report of the Isotope Facilities at Oak Ridge National Laboratory (ORNL) was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Isotopes Facility pose a substantial risk to human health or the environment and if remedial site evaluations (RSEs) or removal actions are required. The scope of the project included: (1) a review of historical evidence regarding operations and use of the facility; (2) interviews with facility personnel concerning current and past operating practices; (3) a site inspection; and (4) identification of hazard areas requiring maintenance, removal, or remedial actions. The results of RmSE indicate that no substantial risks exist from contaminants present in the Isotope Facilities because adequate controls and practices exist to protect human health and the environment. The recommended correction from the RmSE are being conducted as maintenance actions; accordingly, this RmSE is considered complete and terminated

Evaluation of a Low-Cost Salmon Production Facility; 1988 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Hill, James M.; Olson, Todd

1989-05-01

This fiscal year 1988 study sponsored by the Bonneville Power Administration evaluates an existing, small-scale salmon production facility operated and maintained by the Clatsop County Economic Development Committee's Fisheries Project.

Progress towards developing consistent design and evaluation guidelines for DOE facilities subjected to natural phenomena hazards

International Nuclear Information System (INIS)

Kennedy, R.P.; Short, S.A.; McDonald, J.R.; McCann, M.W. Jr.; Reed, J.W.

1985-01-01

Probabilistic definitions of earthquake, wind and tornado natural phenomena hazards for many Department of Energy (DOE) facilities throughout the United States have been developed. In addition, definitions of the flood hazards which might affect these locations are currently being developed. The Department of Energy Natural Phenomena Hazards Panel is now preparing a document to provide guidance and criteria for DOE facility managers to assure that DOE facilities are adequately constructed to resist the effects of natural phenomena such as earthquake, strong wind and flood. The intent of this document is to provide instruction on how to utilize the hazard definitions to evaluate existing facilities and design new facilities in a manner such that the risk of adverse consequences is consistent with the cost, function, and danger to the public or environment of the facility. Potential effects on facilities of natural phenomena hazards are emphasized in this paper. The philosophy for mitigating these effects to be employed in the design and evaluation guidelines is also presented

Physical Sciences Facility Air Emission Control Equivalency Evaluation

Energy Technology Data Exchange (ETDEWEB)

Brown, David M.; Belew, Shan T.

2008-10-17

This document presents the adequacy evaluation for the application of technology standards during design, fabrication, installation and testing of radioactive air exhaust systems at the Physical Sciences Facility (PSF), located on the Horn Rapids Triangle north of the Pacific Northwest National Laboratory (PNNL) complex. The analysis specifically covers the exhaust portion of the heating, ventilation and air conditioning (HVAC) systems associated with emission units EP-3410-01-S, EP-3420-01-S and EP 3430-01-S.

Cold vacuum drying facility site evaluation report

International Nuclear Information System (INIS)

Diebel, J.A.

1996-01-01

In order to transport Multi-Canister Overpacks to the Canister Storage Building they must first undergo the Cold Vacuum Drying process. This puts the design, construction and start-up of the Cold Vacuum Drying facility on the critical path of the K Basin fuel removal schedule. This schedule is driven by a Tri-Party Agreement (TPA) milestone requiring all of the spent nuclear fuel to be removed from the K Basins by December, 1999. This site evaluation is an integral part of the Cold Vacuum Drying design process and must be completed expeditiously in order to stay on track for meeting the milestone

CMT scaling analysis and distortion evaluation in passive integral test facility

International Nuclear Information System (INIS)

Deng Chengcheng; Qin Benke; Wang Han; Chang Huajian

2013-01-01

Core makeup tank (CMT) is the crucial device of AP1000 passive core cooling system, and reasonable scaling analysis of CMT plays a key role in the design of passive integral test facilities. H2TS method was used to perform scaling analysis for both circulating mode and draining mode of CMT. And then, the similarity criteria for CMT important processes were applied in the CMT scaling design of the ACME (advanced core-cooling mechanism experiment) facility now being built in China. Furthermore, the scaling distortion results of CMT characteristic Ⅱ groups of ACME were calculated. At last, the reason of scaling distortion was analyzed and the distortion evaluation was conducted for ACME facility. The dominant processes of CMT circulating mode can be adequately simulated in the ACME facility, but the steam condensation process during CMT draining is not well preserved because the excessive CMT mass leads to more energy to be absorbed by cold metal. However, comprehensive analysis indicates that the ACME facility with high-pressure simulation scheme is able to properly represent CMT's important phenomena and processes of prototype nuclear plant. (authors)

Numerical Evaluation of a Light-Gas Gun Facility for Impact Test

Directory of Open Access Journals (Sweden)

C. Rahner

2014-01-01

Full Text Available Experimental tests which match the application conditions might be used to properly evaluate materials for specific applications. High velocity impacts can be simulated using light-gas gun facilities, which come in different types and complexities. In this work different setups for a one-stage light-gas gun facility have been numerically analyzed in order to evaluate their suitability for testing materials and composites used as armor protection. A maximal barrel length of 6 m and a maximal reservoir pressure of a standard industrial gas bottle (20 MPa were chosen as limitations. The numerical predictions show that it is not possible to accelerate the projectile directly to the desired velocity with nitrogen, helium, or hydrogen as propellant gas. When using a sabot corresponding to a higher bore diameter, the necessary velocity is achievable with helium and hydrogen gases.

Design, Evaluation and Test Technology Facility

Data.gov (United States)

Federal Laboratory Consortium — The mission of this facility, which is composed of numerous specialized facilities, is to provide capabilities to simulate a wide range of environments for component...

Performance Evaluation Facility for Fire Fighting Thermal Imager

International Nuclear Information System (INIS)

Kim, Sung Chan; Amon, Francine; Hamins, Anthony

2007-01-01

The present study investigates the characteristics of obscuring media inside an optical smoke cell, which is a bench-scale testing facility for the evaluation of thermal imaging cameras used by fire fighters. Light extinction coefficient and visibility through the smoke cell is characterized by the measured laser transmittance. The laser transmittance along the axial direction of the smoke cell is relatively uniform at upper and lower part for various air/fuel volume flow rate. Contrast level based image quality of visible CCD camera through the smoke cell is compared with that of thermal imaging camera. The optical smoke cell can be used as well-controlled and effective laboratory-scale test apparatus to evaluate the performance of thermal imaging camera for fire fighting application

performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Tavares, Renato L. A.; Filho, Josélio S. M., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear. Divisão de Normas e Segurança Física; Fontes, Gladson S.; Fiel, J.C.B., E-mail: gsfontes@hotmail.com, E-mail: fiel@ime.eb.br [Instituto Militar de Engenharia (SE-7/IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

2017-07-01

This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

International Nuclear Information System (INIS)

Tavares, Renato L. A.; Filho, Josélio S. M.; Fontes, Gladson S.; Fiel, J.C.B.

2017-01-01

This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

Application of dose evaluation of the MCNP code for interim spent fuel cask storage facility

International Nuclear Information System (INIS)

Kosako, Toshiso; Iimoto, Takeshi; Ishikawa, Satoshi; Tsuboi, Takafumi; Teramura, Masahiro; Okamura, Tomomi; Narumiya, Yoshiyuki

2007-01-01

The interim storage facility for spent fuel metallic cask is designed as a concrete building structure with air inlet and outlet for circulating the natural cooling. The feature of the interim storage facility is big capacity of spent fuel at several thousands MTU and restricted site usage. It is important to evaluate realistic dose rate in shielding design of the interim storage facility, therefore the three-dimensional continuous-energy Monte Carlo radiation transport code MCNP that exactly treating the complicated geometry was applied. The validation of dose evaluation for interim storage facility by MCNP code were performed by three kinds of neutron shielding benchmark experiments; cask shadow shielding experiment, duct streaming experiment and concrete deep penetration experiment. Dose rate distributions at each benchmark were measured and compared with the calculated results. The comparison showed a good consistency between calculation and experiment results. (author)

Procedure for Prioritization of Natural Phenomena Hazards Evaluations for Existing DOE Facilities

Energy Technology Data Exchange (ETDEWEB)

Conrads, T.J., Westinghouse Hanford

1996-05-07

This document describes the procedure to be used for the prioritization for natural phenomena hazards evaluations of existing DOE facilities in conformance with DOE Order 5480.28, `Natural Phenomena Hazards Mitigation.`

Use of the event tree method for evaluate the safety of radioactive facilities

International Nuclear Information System (INIS)

Hernandez S, A.; Cornejo D, N.; Callis F, E.

2006-01-01

The work shows the validity of the use of Trees of Events like a quantitative method appropriate to carry out evaluations of radiological safety. Its were took like base the evaluations of safety of five Radiotherapy Departments, carried out in the mark of the process of authorization of these facilities. The risk values were obtained by means of the combination of the probabilities of occurrence of the events with its consequences. The use of the method allowed to suggest improvements to the existent safety systems, as well as to confirm that the current regulator requirements for this type of facilities to lead to practices with acceptable risk levels. (Author)

A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

International Nuclear Information System (INIS)

Brumburgh, G.

1994-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

Removal site evaluation report on the Tower Shielding Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-09-01

This removal site evaluation report for the Tower Shielding Facility (TSF) at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Tower Shielding Facility pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and if remedial site evaluations or removal actions are, therefore, required. The scope of the project included a review of historical evidence regarding operations and use of the facility; interviews with facility personnel concerning current and past operating practices; a site inspection; and identification of hazard areas requiring maintenance, removal, or remedial actions. Based an the findings of this removal site evaluation, adequate efforts are currently being made at the TSF to contain and control existing contamination and hazardous substances on site in order to protect human health and the environment No conditions requiring maintenance or removal actions to mitigate imminent or potential threats to human health and the environment were identified during this evaluation. Given the current conditions and status of the buildings associated with the TSF, this removal site evaluation is considered complete and terminated according to the requirements for removal site evaluation termination

ESF [Exploratory Shaft Facility] impact evaluation report: Volume 1, Final report

International Nuclear Information System (INIS)

1985-08-01

This report assesses the impacts of integrating an Exploratory Shaft Facility (ESF) with a high-level nuclear waste repository in salt. A general repository subsurface design is described which complies with the Mine Safety and Health Administration regulations for gassy metal and non-metal mines. This design is combined with the ESF into a site-specific subsurface layout with associated shafts and surface facilities for each of seven sites. An evaluation to identify integration impacts is described for two specific ESF configurations (Cases 1 and 2) for each of the seven sites. These configurations are an ESF which uses two of the full size repository shafts, and an ESF with one 10-ft and one 22-ft diameter shaft. An evaluation of an ESF configuration (Case 3) with two 12-ft diameter shafts at three of the seven sites is also described. These sites are Deaf Smith, Davis Canyon, and Richton Dome. A fourth evaluation (Case 4) for the Deaf Smith site only, addresses a ''fast track'' subsurface development plan to allow waste emplacement by 1998. A fifth evaluation (Case 5), provides site-specific ES locations, for the three sites included in Case 3, which are supportive of a shaft siting study prepared by ONWI

Performance assessment studies for the long-term safety evaluation of radioactive waste disposal facility

International Nuclear Information System (INIS)

Bujoreanu, D.; Olteanu, M.; Bujoreanu, L.

2008-01-01

Especially during the last ten years, a part of Romanian research program 'Management of Radioactive Waste and Spent Fuel' was focused mainly on applicative research for the design of near-surface disposal facility, which intends to accommodate the low and intermediate radioactive waste generated from Cernavoda NPP. In this frame, our contribution was at the acquisition of technical data for the characterization of the future disposal facility. In the present, the project of the disposal facility, located on the Saligny site, near Cernavoda NPP, must be licensed. As regards to the safe disposal, the location of final disposal, the Saligny site, has been characterized through the five geological formations which contain potential routes for transport of radionuclide released from disposal facility, in the receiving zones(potential receiving zones), into liquid and gaseous phases. The technical characteristics of the disposal facility were adapted at the Romanian disposal concept using the reference data from IAEA technical report (IAEA,1999). Input parameters which characterized from physical and chemical point of view the disposal system, were partially taken from literature. The performance assessment studies, which follows the preliminary design development phases and the selection, describes how the source term is affected by the infiltration of water through the disposal facility, degradation process of engineering barriers (reflected in the distribution coefficient values) and solubility limit. The studies regard the evaluation of the source term, sensitivity and uncertainty analysis provide the information on 'how' and 'why' were evaluated, following: (i) radiological safety assessment of near-surface disposal facility on Saligny site; (ii) complexity standard assessment of the Engineering Barriers Systems (EBS); (iii) identification of the elements which must be elaborated for the increase of the disposal safety and the necessity for new technical data for

Weightless Environment Training Facility (WETF) materials coating evaluation, volume 1

Science.gov (United States)

1995-01-01

The Weightless Environment Training Facility Material Coating Evaluation project has included preparing, coating, testing, and evaluating 800 test panels of three differing substrates. Ten selected coating systems were evaluated in six separate exposure environments and subject to three tests for physical properties. Substrate materials were identified, the manner of surface preparation described, and exposure environments defined. Exposure environments included immersion exposure, cyclic exposure, and field exposure. Cyclic exposures, specifically QUV-Weatherometer and the KTA Envirotest were found to be the most agressive of the environments included in the study when all three evaluation criteria are considered. This was found to result primarily from chalking of the coatings under ultraviolet (UV) light exposure. Volumes 2 and 3 hold the 5 appendices to this report.

An Evaluation Model for Tailings Storage Facilities Using Improved Neural Networks and Fuzzy Mathematics

Directory of Open Access Journals (Sweden)

Sen Tian

2014-01-01

Full Text Available With the development of mine industry, tailings storage facility (TSF, as the important facility of mining, has attracted increasing attention for its safety problems. However, the problems of low accuracy and slow operation rate often occur in current TSF safety evaluation models. This paper establishes a reasonable TSF safety evaluation index system and puts forward a new TSF safety evaluation model by combining the theories for the analytic hierarchy process (AHP and improved back-propagation (BP neural network algorithm. The varying proportions of cross validation were calculated, demonstrating that this method has better evaluation performance with higher learning efficiency and faster convergence speed and avoids the oscillation in the training process in traditional BP neural network method and other primary neural network methods. The entire analysis shows the combination of the two methods increases the accuracy and reliability of the safety evaluation, and it can be well applied in the TSF safety evaluation.

A bicycle safety index for evaluating urban street facilities.

Science.gov (United States)

Asadi-Shekari, Zohreh; Moeinaddini, Mehdi; Zaly Shah, Muhammad

2015-01-01

The objectives of this research are to conceptualize the Bicycle Safety Index (BSI) that considers all parts of the street and to propose a universal guideline with microscale details. A point system method comparing existing safety facilities to a defined standard is proposed to estimate the BSI. Two streets in Singapore and Malaysia are chosen to examine this model. The majority of previous measurements to evaluate street conditions for cyclists usually cannot cover all parts of streets, including segments and intersections. Previous models also did not consider all safety indicators and cycling facilities at a microlevel in particular. This study introduces a new concept of a practical BSI to complete previous studies using its practical, easy-to-follow, point system-based outputs. This practical model can be used in different urban settings to estimate the level of safety for cycling and suggest some improvements based on the standards.

Multidisciplinary approach to evaluating welfare of veal calves in commercial facilities.

Science.gov (United States)

Stull, C L; McDonough, S P

1994-09-01

Due to pending legislation and public concerns, a multidisciplinary approach was designed to investigate the welfare of special-fed veal calves in commercial veal facilities. Concerns included housing conditions, dietary regimens, management practices, and behavioral aspects imposed on special-fed calves. Four categories of parameters including environment and housing, nutrition, health and stress, and behavior provided a broad base of evaluating veal systems. Observations and samples were collected on 550 Holstein bull calves located in 10 commercial veal facilities. Each facility was visited to collect data during wk 0 (week of arrival of the calves), 2, 4, 8, 12, and 16. Nine facilities used individual stalls 48 to 55 cm in width with tethers attached to the front of the stalls. One facility housed 30 calves in group pens after obtaining calves at 8 wk of age. Ammonia, carbon monoxide, and hydrogen sulfide gas did not exceed the permissible limit for humans in any facility. All facilities exceeded the 2-foot-candle recommendation for lighting. The average daily gain of calves was .85 kg during wk 0 to 8 and 1.18 kg during wk 8 to 16. Dietary iron levels decreased from 209 ppm at wk 0 to 32 ppm at wk 16. At 16 wk, 25% of calves were marginally anemic and 10% clinically anemic. Overall mortality was 4.2%. Stress indices such as plasma cortisol concentrations or neutrophil to lymphocyte ratios declined as calves approached market weight. In either pens or stalls, calves spent approximately 25 and 75% of time in standing and lying positions, respectively.(ABSTRACT TRUNCATED AT 250 WORDS)

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Facility effluent monitoring plan for 242-A Evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1993-03-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Methodology for worker neutron exposure evaluation in the PDCF facility design

International Nuclear Information System (INIS)

Scherpelz, R. I.; Traub, R. J.; Pryor, K. H.

2004-01-01

A project headed by Washington Group International is meant to design the Pit Disassembly and Conversion Facility (PDCF) to convert the plutonium pits from excessed nuclear weapons into plutonium oxide for ultimate disposition. Battelle staff are performing the shielding calculations that will determine appropriate shielding so that the facility workers will not exceed target exposure levels. The target exposure levels for workers in the facility are 5 mSv y -1 for the whole body and 100 mSv y -1 for the extremity, which presents a significant challenge to the designers of a facility that will process tons of radioactive material. The design effort depended on shielding calculations to determine appropriate thickness and composition for glove box walls, and concrete wall thicknesses for storage vaults. Pacific Northwest National Laboratory (PNNL) staff used ORIGEN-S and SOURCES to generate gamma and neutron source terms, and Monte Carlo (computer code for) neutron photon (transport) (MCNP-4C) to calculate the radiation transport in the facility. The shielding calculations were performed by a team of four scientists, so it was necessary to develop a consistent methodology. There was also a requirement for the study to be cost-effective, so efficient methods of evaluation were required. The calculations were subject to rigorous scrutiny by internal and external reviewers, so acceptability was a major feature of the methodology. Some of the issues addressed in the development of the methodology included selecting appropriate dose factors, developing a method for handling extremity doses, adopting an efficient method for evaluating effective dose equivalent in a non-uniform radiation field, modelling the reinforcing steel in concrete, and modularising the geometry descriptions for efficiency. The relative importance of the neutron dose equivalent compared with the gamma dose equivalent varied substantially depending on the specific shielding conditions and lessons were

Air-kerma evaluation at the maze entrance of HDR brachytherapy facilities

International Nuclear Information System (INIS)

Pujades, M C; Granero, D; Vijande, J; Ballester, F; Perez-Calatayud, J; Papagiannis, P; Siebert, F A

2014-01-01

In the absence of procedures for evaluating the design of brachytherapy (BT) facilities for radiation protection purposes, the methodology used for external beam radiotherapy facilities is often adapted. The purpose of this study is to adapt the NCRP 151 methodology for estimating the air-kerma rate at the door in BT facilities. Such methodology was checked against Monte Carlo (MC) techniques using the code Geant4. Five different facility designs were studied for 192 Ir and 60 Co HDR applications to account for several different bunker layouts. For the estimation of the lead thickness needed at the door, the use of transmission data for the real spectra at the door instead of the ones emitted by 192 Ir and 60 Co will reduce the lead thickness by a factor of five for 192 Ir and ten for 60 Co. This will significantly lighten the door and hence simplify construction and operating requirements for all bunkers. The adaptation proposed in this study to estimate the air-kerma rate at the door depends on the complexity of the maze: it provides good results for bunkers with a maze (i.e. similar to those used for linacs for which the NCRP 151 methodology was developed) but fails for less conventional designs. For those facilities, a specific Monte Carlo study is in order for reasons of safety and cost-effectiveness. (paper)

Air-kerma evaluation at the maze entrance of HDR brachytherapy facilities.

Science.gov (United States)

Pujades, M C; Granero, D; Vijande, J; Ballester, F; Perez-Calatayud, J; Papagiannis, P; Siebert, F A

2014-12-01

In the absence of procedures for evaluating the design of brachytherapy (BT) facilities for radiation protection purposes, the methodology used for external beam radiotherapy facilities is often adapted. The purpose of this study is to adapt the NCRP 151 methodology for estimating the air-kerma rate at the door in BT facilities. Such methodology was checked against Monte Carlo (MC) techniques using the code Geant4. Five different facility designs were studied for (192)Ir and (60)Co HDR applications to account for several different bunker layouts.For the estimation of the lead thickness needed at the door, the use of transmission data for the real spectra at the door instead of the ones emitted by (192)Ir and (60)Co will reduce the lead thickness by a factor of five for (192)Ir and ten for (60)Co. This will significantly lighten the door and hence simplify construction and operating requirements for all bunkers.The adaptation proposed in this study to estimate the air-kerma rate at the door depends on the complexity of the maze: it provides good results for bunkers with a maze (i.e. similar to those used for linacs for which the NCRP 151 methodology was developed) but fails for less conventional designs. For those facilities, a specific Monte Carlo study is in order for reasons of safety and cost-effectiveness.

Functional requirements for an Exercise Evaluation and Simulation Facility

International Nuclear Information System (INIS)

1983-04-01

The Exercise Evaluation and Simulation Facility (EESF) is a computer-based resource that will improve FEMA's capabilities for evaluating radiological emergency plans and preparedness around commercial nuclear sites. The EESF is being designed from the perspective of the organizations involved (i.e., FEMA Regional and National, and state and local response teams) and takes into account the evolution of radiological and other emergency preparedness activities. Like radiological emergency planning, EESF will evolve to suit FEMA (National and Regional) needs and interests and will be increasingly useful as a resource for radiological emergency planning and evaluation. Table ES-1 briefly describes seven functions for which EESF is currently being designed. They are listed in the approximate order in which they will be designed, developed, and implemented. The only exception is the data base function, which will be developed parallel with the other six functions and enhanced to support these functions, as well as be a source of information on sites, plans, exercises, and evaluations

Evaluation of mercury in the liquid waste processing facilities

Energy Technology Data Exchange (ETDEWEB)

Jain, Vijay [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Shah, Hasmukh [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Occhipinti, John E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Wilmarth, William R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Edwards, Richard E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-08-13

This report provides a summary of Phase I activities conducted to support an Integrated Evaluation of Mercury in Liquid Waste System (LWS) Processing Facilities. Phase I activities included a review and assessment of the liquid waste inventory and chemical processing behavior of mercury using a system by system review methodology approach. Gaps in understanding mercury behavior as well as action items from the structured reviews are being tracked. 64% of the gaps and actions have been resolved.

Evaluation of the CDTN's cementation facility using the results obtained in two different sizes: laboratory and facility

International Nuclear Information System (INIS)

Haucz, Maria Judite A.; Calabria, Jaqueline A. Almeida; Tello, Cledola Cassia O.; Candido, Francisco Donizete; Seles, Sandro Rogerio Novaes

2011-01-01

At CDTN R and D activities generate low-level radioactive wastes, among them the aqueous liquid ones, which need special attention due to their volumes. The usual treatment for these wastes is the volume reduction process using chemicals in order to change the radionuclides of the waste to an insoluble form. The resultant sludge is incorporated into cement in 200-liter drums using an in-line batch mixing system (CDTN Cementation Facility). The process parameters and solidified product quality are evaluated at the Cementation Laboratory (LABCIM), where tests are carried out to determine the viscosity, set time and density of the paste. In addition of the visual examination, compressive strength test and density are also established in the solidified product. In the cementation facility some pastes are also prepared for the immobilization of non-compactable waste, such as dump, scrap metal, wood, and other ones. This paper aims to present the study comparing the results of tests done in the pastes and products prepared in LABCIM and the ones obtained in CDTN's cementation facility, in order to check the efficiency of the cementation system. (author)

Evaluation of the CDTN cementation facility using the results obtained in two different sizes: laboratory and facility

International Nuclear Information System (INIS)

Haucz, Maria Judite A.; Calabria, Jaqueline A. Almeida; Tello, Cledola Cassia O.; Candido, Francisco Donizete; Seles, Sandro Rogerio Novaes

2011-01-01

At CDTN R and D activities generate low-level radioactive wastes, among them the aqueous liquid ones, which need special attention due to their volumes. The usual treatment for these wastes is the volume reduction process using chemicals in order to change the radionuclides of the waste to an insoluble form. The resultant sludge is incorporated into cement in 200-liter drums using an in-line batch mixing system (CDTN Cementation Facility). The process parameters and solidified product quality are evaluated at the Cementation Laboratory (LABCIM), where tests are carried out to determine the viscosity, set time and density of the paste. In addition of the visual examination, compressive strength test and density are also established in the solidified product. In the cementation facility some pastes are also prepared for the immobilization of non-compactable waste, such as dump, scrap metal, wood, and other ones. This paper aims to present the study comparing the results of tests done in the pastes and products prepared in LABCIM and the ones obtained in CDTN's cementation facility, in order to check the efficiency of the cementation system. (author)

Ground test facilities for evaluating nuclear thermal propulsion engines and fuel elements

International Nuclear Information System (INIS)

Allen, G.C.; Beck, D.F.; Harmon, C.D.; Shipers, L.R.

1992-01-01

Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program. 2 refs

Impacts of transportation on a test and evaluation facility for nuclear waste disposal: a systems analysis

International Nuclear Information System (INIS)

Varadarajan, R.V.; Peterson, R.W.; Joy, D.S.; Gibson, S.M.

1983-01-01

An essential element of the Test and Evaluation Facility (TEF) is a waste packaging facility capable of producing a small number Test and Evaluation Facility of packages consisting of several different waste forms. The study envisions three scenarios for such a packaging facility: (1) modify an existing hot cell facility such as the Engine Maintenance Assembly and Disassembly (EMAD) facility at the Nevada Test Site so that it can serve as a packaging facility for the TEF. This scenario is referred to as the EMAD Option. (2) Build a new generic packaging facility (GPF) at the site of the TEF. In other words, colocate the GPF and the TEF. This scenario is referred to as the GPF Option, and (3) utilize the EMAD facility in conjunction with a colocated GPF (of minimal size and scope) at the TEF. This scenario is referred to as the Split Option. The results of the system study clearly bring out the fact that transportation has a significant impact on the selection and siting of the waste packaging facility. Preliminary conclusions, subject to the assumptions of the study, include the following: (1) regardless of the waste form, the GPF option is preferable to the other two in minimizing both transportation costs and logistical problems, (2) for any given scenario and choice of waste forms, there exists a candidate TEF location for which the transportation costs are at a minimum compared to the other locations, (3) in spite of the increased transportation costs and logistical complexity, the study shows that the overall system costs favor modification of an existing hot cell facility for the particular case considered

Defense In-Depth Accident Analysis Evaluation of Tritium Facility Bldgs. 232-H, 233-H, and 234-H

International Nuclear Information System (INIS)

Blanchard, A.

1999-01-01

'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'

Defense In-Depth Accident Analysis Evaluation of Tritium Facility Bldgs. 232-H, 233-H, and 234-H

Energy Technology Data Exchange (ETDEWEB)

Blanchard, A.

1999-05-10

'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'

Evaluation of alternatives for the future of facilities at the Western New York Nuclear Service Center

International Nuclear Information System (INIS)

1978-08-01

Regulatory considerations are discussed. Alternatives for the continued operation or decommissioning of the state-licensed burial area, the low-level waste treatment facilities, and the NRC licensed burial area are evaluated. Radiological impact analyses were also performed for alternatives on other facilities

Economic evaluation of pharmacist-led medication reviews in residential aged care facilities.

Science.gov (United States)

Hasan, Syed Shahzad; Thiruchelvam, Kaeshaelya; Kow, Chia Siang; Ghori, Muhammad Usman; Babar, Zaheer-Ud-Din

2017-10-01

Medication reviews is a widely accepted approach known to have a substantial impact on patients' pharmacotherapy and safety. Numerous options to optimise pharmacotherapy in older people have been reported in literature and they include medication reviews, computerised decision support systems, management teams, and educational approaches. Pharmacist-led medication reviews are increasingly being conducted, aimed at attaining patient safety and medication optimisation. Cost effectiveness is an essential aspect of a medication review evaluation. Areas covered: A systematic searching of articles that examined the cost-effectiveness of medication reviews conducted in aged care facilities was performed using the relevant databases. Pharmacist-led medication reviews confer many benefits such as attainment of biomarker targets for improved clinical outcomes, and other clinical parameters, as well as depict concrete financial advantages in terms of decrement in total medication costs and associated cost savings. Expert commentary: The cost-effectiveness of medication reviews are more consequential than ever before. A critical evaluation of pharmacist-led medication reviews in residential aged care facilities from an economical aspect is crucial in determining if the time, effort, and direct and indirect costs involved in the review rationalise the significance of conducting medication reviews for older people in aged care facilities.

Occupational exposure assessment in a radioactive facility: a preliminary evaluation

International Nuclear Information System (INIS)

Alves, Alice dos Santos; Gerulis, Eduardo; Sanches, Matias P.; Carneiro, Janete C.G.G.

2013-01-01

The risk that a worker has found on the job is a function of the hazards present and his exposure level to those hazards. Exposure and risk assessment is therefore the heart of all occupational health and industrial hygiene programs involving a continuous process of information gathering. The use of a systematic method to characterize workplace exposures to chemical, physical and biological risks is a fundamental part of this process. This study aims to carry out a preliminary evaluation in a radioactive facility, identifying potential exposures and consequently the existing occupational hazards (risk/agent) in the workplace which the employee is subject. The study is based on proposal to carry out a basic characterization of the facility, which could be the first step in the investigation of occupational exposure. For this study was essential to know the workplace, potential risks and agents; workforce profile including assignment of tasks, sources of exposure processes, and control measures. The main tool used in this study was based on references, records, standards, procedures, interviews with the workers and with management. Since the basic characterization of the facility has been carried out, consequently the potential exposure to the agents of risks to workers has been identified. The study provided an overview of the perception of risk founded at facility studied. It is expected to contribute with the occupational health program resources for welfare of the worker. (author)

Occupational exposure assessment in a radioactive facility: a preliminary evaluation

Energy Technology Data Exchange (ETDEWEB)

Alves, Alice dos Santos; Gerulis, Eduardo; Sanches, Matias P.; Carneiro, Janete C.G.G., E-mail: alicesante@hotmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

The risk that a worker has found on the job is a function of the hazards present and his exposure level to those hazards. Exposure and risk assessment is therefore the heart of all occupational health and industrial hygiene programs involving a continuous process of information gathering. The use of a systematic method to characterize workplace exposures to chemical, physical and biological risks is a fundamental part of this process. This study aims to carry out a preliminary evaluation in a radioactive facility, identifying potential exposures and consequently the existing occupational hazards (risk/agent) in the workplace which the employee is subject. The study is based on proposal to carry out a basic characterization of the facility, which could be the first step in the investigation of occupational exposure. For this study was essential to know the workplace, potential risks and agents; workforce profile including assignment of tasks, sources of exposure processes, and control measures. The main tool used in this study was based on references, records, standards, procedures, interviews with the workers and with management. Since the basic characterization of the facility has been carried out, consequently the potential exposure to the agents of risks to workers has been identified. The study provided an overview of the perception of risk founded at facility studied. It is expected to contribute with the occupational health program resources for welfare of the worker. (author)

Annual evaluation of routine radiological survey/monitoring frequencies for the High Ranking Facilities Deactivating Project at Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-12-01

The Bethel Valley Watershed at the Oak Ridge National Laboratory (ORNL) has several Environmental Management (EM) facilities that are designated for deactivation and subsequent decontamination and decommissioning (D and D). The Surplus Facilities Program at ORNL provides surveillance and maintenance support for these facilities as deactivation objectives are completed to reduce the risks associated with radioactive material inventories, etc. The Bechtel Jacobs Company LLC Radiological Control (RADCON) Program has established requirements for radiological monitoring and surveying radiological conditions in these facilities. These requirements include an annual evaluation of routine radiation survey and monitoring frequencies. Radiological survey/monitoring frequencies were evaluated for two High Ranking Facilities Deactivation Project facilities, the Bulk Shielding Facility and Tower Shielding Facility. Considerable progress has been made toward accomplishing deactivation objectives, thus the routine radiological survey/monitoring frequencies are being reduced for 1999. This report identifies the survey/monitoring frequency adjustments and provides justification that the applicable RADCON Program requirements are also satisfied

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Nickels, J.M.; Geiger, J.L.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified. in. A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Structural evaluation of spent nuclear fuel storage facilities under aircraft crash impact. Numerical study on evaluation of sealing performance of metal cask subjected to impact force

International Nuclear Information System (INIS)

Namba, Kosuke; Shirai, Koji; Saegusa, Toshiari

2008-01-01

A lot of safety evaluations on the important nuclear facilities against the aircraft crash have been reported in other countries. But the condition and the evaluation method to define impact force of aircraft crash have not been described clearly in the reports. In Japan, public concern with the safety evaluation against aircraft crash is increasing. It is important to make clear the behavior of the storage facilities installing the metal casks on impact loading due to aircraft crash. In this study, concerning crash between commercial aircraft and storage facility, impact analysis using dynamic analysis code LS-DYNA has been executed. The results showed that the storage facility was not completely destroyed. But the rigid aircraft engine may penetrate into the storage facility with local failure. Thus, we assumed the engine hit a metal cask in the storage facility and evaluated sealing performance of the metal cask under the impact loading. If the engine with 90m/s crashed the storage facility having concrete wall of 85cm in thickness, the remaining velocity became 60m/s after penetration. We calculated impact force of the engine with 60m/s crashing into the metal cask. Concerning the metal cask loaded the impact force, impact analysis was executed. We assumed two directions of impact force. One is vertical load and another is horizontal load against the cask. The result showed that plastic strain was not generated on flanges of the 1st lid and the sealing performance of the cask was maintained in each impact case. (author)

Study on scenario evaluation methodology for decommissioning nuclear facilities using fuzzy logic

International Nuclear Information System (INIS)

Matsuhashi, Kazuya; Yanagihara, Satoshi

2015-01-01

Since there are many scenarios of the process from start to completion of a decommissioning project, it is important to study scenarios of decommissioning by evaluating such properties as safety, cost, and technology. An optimum scenario with the highest feasibility in accordance with the facility and environmental conditions should be selected on the basis of the results of the study. For analyzing a scenario of decommissioning, we prepared structured work packages by using the work breakdown structures (WBS) method together with qualitative evaluation of the technologies being applied to work packages located at the bottom (the third level) of the WBS. A calculation model was constructed to evaluate the feasibility of a scenario where fuzzy logic is applied to derive a score of technology performance and TOPSIS is applied for getting a feasibility grade of the scenario from technical performance scoring. As a case study, the model was applied to the debris removal scenario of Fukushima Daiichi Nuclear Power Plant to confirm its applicability. Two scenarios, underwater and in-air debris removal cases, were characterized by extracting the work packages with the lowest feasibility and by obtaining total average scores of the scenarios. It is confirmed that the methodology developed is useful for the scenario evaluation of decommissioning nuclear facilities. (author)

Facility effluent monitoring plan for the fast flux test facility

International Nuclear Information System (INIS)

Nickels, J.M.; Dahl, N.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in US Department of Energy Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A Facility Effluent Monitoring Plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

Facility for the evaluation of space communications and related systems

Science.gov (United States)

Kerczewski, Robert J.; Svoboda, James S.; Kachmar, Brian A.

1995-01-01

NASA Lewis Research Center's Communications Projects Branch has developed a facility for the evaluation of space communications systems and related types of systems, called the Advanced Space Communications (ASC) Laboratory. The ASC Lab includes instrumentation, testbed hardware, and experiment control and monitor software for the evaluation of components, subsystems, systems, and networks. The ASC lab has capabilities to perform radiofrequency (RF), microwave, and millimeter-wave characterizations as well as measurements using low, medium, or high data rate digital signals. In addition to laboratory measurements, the ASC Lab also includes integrated satellite ground terminals allowing experimentation and measurements accessing operational satellites through real space links.

Spent unreprocessed fuel (SURF) facility evaluation plan of the alternative storage concepts

International Nuclear Information System (INIS)

Berry, S.M.

1978-01-01

Concepts were evaluated for the storage of unreprocessed spent fuel in a retrievable surface storage facility. This document provides a systematic format for making a concept selection from the seven alternative concepts presented in RHO-LD-2. Results of the evaluation was that the Drywell concept was rated highest with the Water Basin Concept and the Sealed Storage Cask concept with multiple canisters of SURF coming in a close second and third

Materials evaluation for a transuranic processing facility

International Nuclear Information System (INIS)

Barker, S.A.; Schwenk, E.B.; Divine, J.R.

1990-11-01

The Westinghouse Hanford Company, with the assistance of the Pacific Northwest Laboratory, is developing a transuranium extraction process for preheating double-shell tank wastes at the Hanford Site to reduce the volume of transuranic waste being sent to a repository. The bench- scale transuranium extraction process development is reaching a stage where a pilot plant design has begun for the construction of a facility in the existing B Plant. Because of the potential corrosivity of neutralized cladding removal waste process streams, existing embedded piping alloys in B Plant are being evaluated and ''new'' alloys are being selected for the full-scale plant screening corrosion tests. Once the waste is acidified with HNO 3 , some of the process streams that are high in F - and low in Al and zr can produce corrosion rates exceeding 30,000 mil/yr in austenitic alloys. Initial results results are reported concerning the applicability of existing plant materials to withstand expected process solutions and conditions to help determine the feasibility of locating the plant at the selected facility. In addition, process changes are presented that should make the process solutions less corrosive to the existing materials. Experimental work confirms that Hastelloy B is unsatisfactory for the expected process solutions; type 304L, 347 and 309S stainless steels are satisfactory for service at room temperature and 60 degrees C, if process stream complexing is performed. Inconel 625 was satisfactory for all solutions. 17 refs., 5 figs., 8 tabs

Central Facilities Area Sewage Lagoon Evaluation

Energy Technology Data Exchange (ETDEWEB)

Giesbrecht, Alan [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

The Central Facilities Area (CFA) located in Butte County, Idaho at Idaho National Laboratory (INL) has an existing wastewater system to collect and treat sanitary wastewater and non contact cooling water from the facility. The existing treatment facility consists of three cells: Cell 1 has a surface area of 1.7 acres, Cell 2 has a surface area of 10.3 acres, and Cell 3 has a surface area of 0.5 acres. If flows exceed the evaporative capacity of the cells, wastewater is discharged to a 73.5 acre land application site that utilizes a center pivot irrigation sprinkler system. The purpose of this current study is to update the analysis and conclusions of the December 2013 study. In this current study, the new seepage rate and influent flow rate data have been used to update the calculations, model, and analysis.

FOAM FORMATION IN THE SALTSTONE PRODUCTION FACILITY: EVALUATION OF SOURCES AND MITIGATION

Energy Technology Data Exchange (ETDEWEB)

Cozzi, A.

2011-01-18

The Saltstone Production Facility receives waste from Tank 50H for treatment. Influents into Tank 50H include the Effluent Treatment Project waste concentrate, H-Canyon low activity waste and General Purpose Evaporator bottoms, Modular Caustic Side Solvent Extraction Unit decontaminated salt solution, and salt solution from the Deliquification, Dissolution and Adjust campaign. Using the Waste Characterization System (WCS), this study tracks the relative amounts of each influent into Tank 50H, as well as the total content of Tank 50H, in an attempt to identify the source of foaming observed in the Saltstone Production Facility hopper. Saltstone has been using antifoam as part of routine processing with the restart of the facility in December 2006. It was determined that the maximum admix usage in the Saltstone Production Facility, both antifoam and set retarder, corresponded with the maximum concentration of H-Canyon low activity waste in Tank 50H. This paper also evaluates archived salt solutions from Waste Acceptance Criteria analysis for propensity to foam and the antifoam dosage required to mitigate foaming. It was determined that Effluent Treatment Project contributed to the expansion factor (foam formation) and General Purpose Evaporator contributed to foaminess (persistence). It was also determined that undissolved solids contribute to foam persistence. It was shown that additions of Dow Corning Q2-1383a antifoam reduced both the expansion factor and foaminess of salt solutions. The evaluation of foaming in the grout hopper during the transition from water to salt solution indicated that higher water-to-premix ratios tended to produce increased foaming. It was also shown that additions of Dow Corning Q2-1383a antifoam reduced foam formation and persistence.

Evaluation of a high-level waste radiological maintenance facility

International Nuclear Information System (INIS)

Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation''s first and world''s largest high level waste vitrification facility. DWPF began, operations in March 1996 to process radioactive waste, consisting of a matrixed predominantly 137 Cs precipitate and a predominately 90 Sr and alpha emitting sludge, into boro-silicate glass for long term storage. Presently, DWPF is processing only sludge waste and is preparing to process a combination of sludge and precipitate waste. During precipitate operations, canister dose rates are expected to exceed 10 Sv hr -1 (1000 rem hr -1 ). In sludge-only operations, canister contact gamma dose rates are approximately 15 mSv hr -1 (1500 mrem hr -1 ). Transferable contamination levels have been greater than 10 mSv hr -1 (100 cm 2 ) -1 for beta-gamma emitters and into the millions of Bq (100 cm 2 ) -1 for the alpha emitting radionuclides. This paper presents an evaluation of the radiological maintenance areas and their ability to support radiological work

Evaluation of the ORNL area for future waste burial facilities

International Nuclear Information System (INIS)

Lomenick, T.F.; Byerly, D.W.; Gonzales, S.

1983-10-01

Additional waste-burial facilities will be needed at ORNL within this decade. In order to find environmentally acceptable sites, the ORNL area must be systematically evaluated. This document represents the first step in that selection process. Geologic and hydrologic data from the literature and minor field investigations are used to identify more favorable sites for Solid Waste Storage Area (SWSA) 7. Also underway at this time is a companion study to locate a Central Waste Storage Area which could be used in the future to accommodate wastes generated by the X-10, Y-12, and K-25 facilities. From the several watershed options available, the Whiteoak Creek drainage basin is selected as the most promising hydrologic regime. This area contains all past and present waste-disposal facilities and is thus already well monitored. The seven bedrock units within the ORNL area are evaluated as potential burial media. Shales of the Conasauga Group, which are currently used for waste burial in the Whiteoak Creek drainage basin, and the Knox Group are considered the leading candidates. Although the residuum derived from and overlying the Knox dolomite has many favorable characteristics and may be regarded as having a high potential for burial of low-level wastes, at the present it is unproven. Therefore, the Conasauga shales are considered a preferable option for SWSA 7 within the ORNL area. Since the Conasauga interval is currently used for waste burial, it is better understood. One tract in Melton Valley that is underlain by Conasauga shales is nominated for detailed site-characterization studies, and several other tracts are recommended for future exploratory drilling. Exploration is also suggested for a tract in the upper Whiteoak Creek basin where Knox residuum is the shallow subsurface material

Source term model evaluations for the low-level waste facility performance assessment

Energy Technology Data Exchange (ETDEWEB)

Yim, M.S.; Su, S.I. [North Carolina State Univ., Raleigh, NC (United States)

1995-12-31

The estimation of release of radionuclides from various waste forms to the bottom boundary of the waste disposal facility (source term) is one of the most important aspects of LLW facility performance assessment. In this work, several currently used source term models are comparatively evaluated for the release of carbon-14 based on a test case problem. The models compared include PRESTO-EPA-CPG, IMPACTS, DUST and NEFTRAN-II. Major differences in assumptions and approaches between the models are described and key parameters are identified through sensitivity analysis. The source term results from different models are compared and other concerns or suggestions are discussed.

Exposure dose evaluation of worker at radioactive waste incineration facility on KAERI

International Nuclear Information System (INIS)

Park, Sang Kyu; Jeon, Jong Seon; Kim, Youn Hwa; Lee, Jae Min; Lee, Gi Won

2011-01-01

An incineration treatment of inflammable radioactive wastes leads to have a reduction effect of disposal cost and also to contribute an enhancement of safety at a disposal site by taking the advantage of stabilization of the wastes which is accomplished by converting organic materials into inorganic materials. As it was required for an incineration technology, KAERI (Korea Atomic Energy Research Institute) has developed a pilot incineration process and then constructed a demonstration incineration facility having based on the operating experiences of the pilot process. In this study, worker exposure doses were evaluated to confirm safety of workers before the demonstration incineration facility will commence a commercial. (author)

Generalized economic model for evaluating disposal costs at a low-level waste disposal facility

International Nuclear Information System (INIS)

Baird, R.D.; Rogers, V.C.

1985-01-01

An economic model is developed which can be used to evaluate cash flows associated with the development, operations, closure, and long-term maintenance of a proposed Low-Level Radioactive Waste disposal facility and to determine the unit disposal charges and unit surcharges which might result. The model includes the effects of nominal interest rate (rate of return on investment, or cost of capital), inflation rate, waste volume growth rate, site capacity, duration of various phases of the facility history, and the cash flows associated with each phase. The model uses standard discounted cash flow techniques on an after-tax basis to determine that unit disposal charge which is necessary to cover all costs and expenses and to generate an adequate rate of return on investment. It separately considers cash flows associated with post-operational activities to determine the required unit surcharge. The model is applied to three reference facilities to determine the respective unit disposal charges and unit surcharges, with various values of parameters. The sensitivity of the model results are evaluated for the unit disposal charge

Evaluation of engineered barrier materials for surface disposal facilities. Appendix 2: Brazil

International Nuclear Information System (INIS)

Endo, L.S.

2001-01-01

Full text: In practice, those nuclear installations that generate most wastes in Brazil often have interim storage facilities at the same site. They can also accommodate wastes from small users that have no suitable place to manage their wastes. The forecast at the time of the CRP for Brazilian waste generation due to all nuclear and radioactive activities by the year 2010 is to be about 5000 m 3 , not including the waste of 3500 m 3 from Goiania accident. With the impact of the accident on the public opinion, the quest for a safe disposal facility became more urgent, especially the siting and licensing a disposal facility which could receive the Goiania waste. Although the construction of a national repository was a matter of future decision at the time of the CRP, research programmes were being developed and carried out by the research institutes of the Brazilian National Commission of Nuclear Energy. The R and D programmes were primarily intended to establish required technical capability in dealing with the subject especially in terms of issues related to the evaluation of disposal facility performance and lifetime. Some activities of the programmes were within the scope of the CRP, namely: study of diffusion through cementitious materials; degradation of concrete due to chemical corrosion and microbiological attack; evaluation of additives for the improvement of structural concrete and cemented wasteform quality. In the work relating to the improvement of wasteforms and concrete, silica-fume was being evaluated as an admixture in the cementation process. Ion-exchange resins, a typical power reactor waste, and simulated liquid waste from fission production were used as reference wastes. The performance of the produced wasteforms was evaluated by measuring four properties of interest: setting time; heat developed during hydration process, compressive strength, and leachability. Results showed that the addition of silica-fume increased the compressive strength

Facility effluent monitoring plan for 242-A evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1995-02-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

Removal site evaluation report on the bulk shielding facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-09-01

This removal site evaluation report on the Bulk Shielding Facility (BSF) at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around BSF buildings pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and whether remedial site evaluations or removal actions are, therefore, required. A removal site evaluation was conducted at nine areas associated with the BSF. The scope of each evaluation included (1) a search for, and review of, readily available historical records regarding operations and use of the facility (including hazardous substance usage and existing contamination); (2) interviews with facility personnel concerning current and past practices; and (3) a brief walk-through to visually inspect the facility and identify existing hazard areas requiring maintenance actions or remedial evaluation. The results of the removal site evaluation indicate that no substantial risks exist from contaminants present because adequate efforts are being made to contain and control existing contamination and hazardous substances and to protect human health and the environment. At Building 3004, deteriorated and peeling exterior paint has a direct pathway to the storm water drainage system and can potentially impact local surface water during periods of storm water runoff. The paint is assumed to be lead based, thus posing a potential problem. The paint should be sampled and analyzed to determine its lead content and to assess whether a hazard exists. If so, a maintenance action will be necessary to prevent further deterioration and dislodging of the paint. In addition, if the paint contains lead, then a remedial site evaluation should be conducted to determine whether lead from fallen chips has impacted soils in the immediate area of the building

DETERMINATION OF IMPORTANCE EVALUATION FOR THE SURFACE EXPLORATORY STUDIES FACILITY

Energy Technology Data Exchange (ETDEWEB)

C.J. Byrne

2000-07-25

This DIE applies to the surface facilities component of the Yucca Mountain Site Characterization Project (W) ESF. The ESF complex-including surface and subsurface accommodations--encompasses an area that is approximately six miles wide and nine miles long (approximately 30,000 acres total) (United States Department of Energy [DOE] 1997, p. 9.04). It is located on federally withdrawn lands, near the southwest border of the Nevada Test Site (NTS) in southern Nevada (DOE 1997, p. 9.04). Site characterization activities are conducted within the subsurface ESF to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. Most ESF surface facilities are located within the Conceptual Controlled Area Boundary (CCAB) (DOE 1997, p. 9.04), with the exception of the southeastern most portions of the H-Road and the Water Supply System. Various SBT activities are also conducted throughout the Yucca Mountain region as a part of the overall site-characterization effort. In general, the DIE for SBT Activities (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 1998a) evaluates activities associated with SBT. Potential test-to-test interference and waste isolation impacts associated with SBT activities are also evaluated in CRWMS M&O (1998a).

DETERMINATION OF IMPORTANCE EVALUATION FOR THE SURFACE EXPLORATORY STUDIES FACILITY

International Nuclear Information System (INIS)

C.J. Byrne

2000-01-01

This DIE applies to the surface facilities component of the Yucca Mountain Site Characterization Project (W) ESF. The ESF complex-including surface and subsurface accommodations--encompasses an area that is approximately six miles wide and nine miles long (approximately 30,000 acres total) (United States Department of Energy [DOE] 1997, p. 9.04). It is located on federally withdrawn lands, near the southwest border of the Nevada Test Site (NTS) in southern Nevada (DOE 1997, p. 9.04). Site characterization activities are conducted within the subsurface ESF to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. Most ESF surface facilities are located within the Conceptual Controlled Area Boundary (CCAB) (DOE 1997, p. 9.04), with the exception of the southeastern most portions of the H-Road and the Water Supply System. Various SBT activities are also conducted throughout the Yucca Mountain region as a part of the overall site-characterization effort. In general, the DIE for SBT Activities (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M andO] 1998a) evaluates activities associated with SBT. Potential test-to-test interference and waste isolation impacts associated with SBT activities are also evaluated in CRWMS M andO (1998a)

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

International Nuclear Information System (INIS)

1993-11-01

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24

Engineering evaluation cost analysis for the 100-B/C area ancillary facilities at the 108-F Building

International Nuclear Information System (INIS)

1996-10-01

In 1995, the US Department of Energy (DOE), Richland Operations Office (RL) conducted a removal site evaluation of selected facilities in the 100 Area of the Hanford Site in accordance with CERCLA and 40 Code of Federal Regulations (CFR) 300.410. The scope of the evaluation included the aboveground portions of the 108-F Biology Laboratory in the 100-F Area and all inactive ancillary buildings and structures in the 100-B/C Area, excluding the reactor building and the river outfall. Based on the evaluation, RL determined that hazardous substances in the 108-F Biology Laboratory and five of the 100-B/C Area facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. This determination was documented in an engineering evaluation/cost analysis (EE/CA) approval memorandum. The EE/CA approval memorandum is the basis on which to proceed with the performance of an EE/CA to determine the appropriate removal action. This report presents the results of the EE/CA for removal alternatives for final disposition of these six facilities. The EE/CA was conducted pursuant to the requirements of CERCLA and 40 CFR 300.415 and is intended to aid RL and the EPA in selecting a preferred removal action

Methodology to evaluate the site standard seismic motion to a nuclear facility

International Nuclear Information System (INIS)

Soares, W.A.

1983-01-01

For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

Calculation of parameters for inspection planning and evaluation: mixed-oxide fuel fabrication facilities

International Nuclear Information System (INIS)

Reardon, P.T.; Mullen, M.F.

1982-08-01

As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities for mixed-oxide fuel fabrication facilities. There were four distinct efforts involved in this task. These were as follows: show the effect on a material balance verification of using two variables measurement methods in some strata; perform additional calculations for the reference facility described in STR-89; modify the INSPECT computer programs to be used as an after-inspection analysis tool, as well as a preinspection planning tool; provide written comments and explantations of text and graphs of the first draft of STR-89, Safeguards Considerations for Mixed-Oxide Fuel Element Fabrication Facilities, by W. Bahm, T. Shea, and D. Tolchenkov, System Studies Section, IAEA

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

International Nuclear Information System (INIS)

Gates, R.; Glukhov, A.; Markowski, F.

1996-06-01

This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

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.

Facility effluent monitoring plan for the 2724-W Protective Equipment Decontamination Facility

International Nuclear Information System (INIS)

Nickels, J.M.; Lavey, G.H.

1992-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

A probabilistic risk assessment of the LLNL Plutonium Facility's evaluation basis fire operational accident. Revision 1

International Nuclear Information System (INIS)

Brumburgh, G.P.

1995-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

Introduction to the nuclear criticality safety evaluation of facility X-705, Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

Sheaffer, M.K.; Keeton, S.C.

1993-01-01

This report is the first in a series of documents that will evaluate nuclear criticality safety in the Decontamination and Recovery Facility, X-705, Portsmouth Gaseous Diffusion Plant. It provides an overview of the facility, categorizes its functions for future analysis, reviews existing NCS documentation, and explains the follow-on effort planned for X-705. A detailed breakdown of systems, subsystems, and operational areas is presented and cross-referenced to existing NCS documentation

Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

International Nuclear Information System (INIS)

Goodin, S.

2002-01-01

This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M andO 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M andO 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M andO 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the

Process Evaluation of Communitisation Programme in Public Sector Health Facilities, Mokokchung District, Nagaland, 2015.

Science.gov (United States)

Tushi, Aonungdok; Kaur, Prabhdeep

2017-01-01

Public sector health facilities were poorly managed due to a history of conflict in Nagaland, India. Government of Nagaland introduced "Nagaland Communitisation of Public Institutions and Services Act" in 2002. Main objectives of the evaluation were to review the functioning of Health Center Managing Committees (HCMCs), deliver health services in the institutions managed by HCMC, identify strengths as well as challenges perceived by HCMC members in the rural areas of Mokokchung district, Nagaland. The evaluation was made using input, process and output indicators. A doctor, the HCMC Chairman and one member from each of the three community health centers (CHC) and four primary health centers (PHC) were surveyed using a semi-structured questionnaire and an in-depth interview guide. Proportions for quantitative data were computed and key themes from the same were identified. Overall; the infrastructure, equipment and outpatient/inpatient service availability was satisfactory. There was a lack of funds and shortage of doctors, drugs as well as laboratory facilities. HCMCs were in place and carried out administrative activities. HCMCs felt ownership, mobilized community contributions and managed human resources. HCMC members had inadequate funds for their transport and training. They faced challenges in service delivery due to political interference and lack of adequate human, material, financial resources. Communitisation program was operational in the district. HCMC members felt the ownership of health facilities. Administrative, political support and adequate funds from the government are needed for effective functioning of HCMCs and optimal service delivery in public sector facilities.

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)

Shielding Design and Radiation Shielding Evaluation for LSDS System Facility

International Nuclear Information System (INIS)

Kim, Younggook; Kim, Jeongdong; Lee, Yongdeok

2015-01-01

As the system characteristics, the target in the spectrometer emits approximately 1012 neutrons/s. To efficiently shield the neutron, the shielding door designs are proposed for the LSDS system through a comparison of the direct shield and maze designs. Hence, to guarantee the radiation safety for the facility, the door design is a compulsory course of the development of the LSDS system. To improve the shielding rates, 250x250 covering structure was added as a subsidiary around the spectrometer. In this study, the evaluations of the suggested shielding designs were conducted using MCNP code. The suggested door design and covering structures can shield the neutron efficiently, thus all evaluations of all conditions are satisfied within the public dose limits. From the Monte Carlo code simulation, Resin(Indoor type) and Tungsten(Outdoor type) were selected as the shielding door materials. From a comparative evaluation of the door thickness, In and Out door thickness was selected 50 cm

FLUX SENSOR EVALUATIONS AT THE ATR CRITICAL FACILITY

International Nuclear Information System (INIS)

Unruh, Troy; Rempe, Joy; Nigg, David; Imel, George; Harris, Jason; Bonebrake, Eric

2010-01-01

The Advanced Test Reactor (ATR) and the ATR Critical (ATRC) facilities lack real-time methods for detecting thermal neutron flux and fission reaction rates for irradiation capsules. Direct measurements of the actual power deposited into a test are now possible without resorting to complicated correction factors. In addition, it is possible to directly measure minor actinide fission reaction rates and to provide time-dependent monitoring of the fission reaction rate or fast/thermal flux during transient testing. A joint Idaho State University/Idaho National Laboratory ATR National Scientific User Facility (ATR NSUF) project was recently initiated to evaluate new real-time state-of-the-art in-pile flux detection sensors. Initially, the project is comparing the accuracy, response time, and long duration performance of French Atomic Energy Commission (CEA)-developed miniature fission chambers, specialized self-powered neutron detectors (SPNDs) by the Argentinean National Energy Commission (CNEA), specially developed commercial SPNDs, and back-to-back fission (BTB) chambers developed by Argonne National Laboratory (ANL). As discussed in this paper, specialized fixturing and software was developed by INL to facilitate these joint ISU/INL evaluations. Calculations were performed by ISU to assess the performance of and reduce uncertainties in flux detection sensors and compare data obtained from these sensors with existing integral methods employed at the ATRC. Ultimately, project results will be used to select the detector that can provide the best online regional ATRC power measurement. It is anticipated that project results may offer the potential to increase the ATRC's current power limit and its ability to perform low-level irradiation experiments. In addition, results from this effort will provide insights about the viability of using these detectors in the ATR. Hence, this effort complements current activities to improve ATR software tools, computational protocols

F/H Effluent Treatment Facility filtration upgrade alternative evaluations overview

Energy Technology Data Exchange (ETDEWEB)

Miles, W.C. Jr.; Poirier, M.R.; Brown, D.F.

1992-01-01

The F/H Effluent Treatment Facility (ETF) at the Savannah River Site (SRS) was designed to treat process wastewater from the 200-F/H Production Facilities (routine wastewater) as well as intermittent flows from the F/H Retention Basins and F/H Cooling Water Basins (nonroutine wastewater). Since start-up of the ETF at SRS in 1988, the treatment process has experienced difficulties processing routine and nonroutine wastewater. Studies have identified high bacteria and bacterial decomposition products in the wastewater as the cause for excessive fouling of the filtration system. In order to meet Waste Management requirements for the treatment of processed wastewater, an upgrade of the ETF filtration system is being developed. This upgrade must be able to process the nonroutine wastewater at design capacity. As a result, a study of alternative filter technologies was conducted utilizing simulated wastewater. The simulated wastewater tests have been completed. Three filter technologies, centrifugal polymeric ultrafilters, tubular polymeric ultrafilters, and backwashable cartridge filters have been selected for further evaluation utilizing actual ETF wastewater.

F/H Effluent Treatment Facility filtration upgrade alternative evaluations overview

Energy Technology Data Exchange (ETDEWEB)

Miles, W.C. Jr.; Poirier, M.R.; Brown, D.F.

1992-07-01

The F/H Effluent Treatment Facility (ETF) at the Savannah River Site (SRS) was designed to treat process wastewater from the 200-F/H Production Facilities (routine wastewater) as well as intermittent flows from the F/H Retention Basins and F/H Cooling Water Basins (nonroutine wastewater). Since start-up of the ETF at SRS in 1988, the treatment process has experienced difficulties processing routine and nonroutine wastewater. Studies have identified high bacteria and bacterial decomposition products in the wastewater as the cause for excessive fouling of the filtration system. In order to meet Waste Management requirements for the treatment of processed wastewater, an upgrade of the ETF filtration system is being developed. This upgrade must be able to process the nonroutine wastewater at design capacity. As a result, a study of alternative filter technologies was conducted utilizing simulated wastewater. The simulated wastewater tests have been completed. Three filter technologies, centrifugal polymeric ultrafilters, tubular polymeric ultrafilters, and backwashable cartridge filters have been selected for further evaluation utilizing actual ETF wastewater.

F/H effluent treatment facility filtration upgrade alternative evaluations overview

International Nuclear Information System (INIS)

Miles, W.C. Jr.; Poirier, M.R.; Brown, D.F.

1992-01-01

The F/H Effluent Treatment Facility (ETF) at the Savannah River Site (SRS) was designed to treat process wastewater from the 200-F/H Production Facilities (routine wastewater) as well as intermittent flows from the F/H Retention Basins and F/H Cooling Water Basins (nonroutine wastewater). Since start-up of the ETF at SRS in 1988, the treatment process has experienced difficulties processing routine and nonroutine wastewater. Studies have identified high bacteria and bacterial decomposition products in the wastewater as the cause for excessive fouling of the filtration system. In order to meet Waste Management requirements for the treatment of processed wastewater, an upgrade of the ETF filtration system is being developed. This upgrade must be able to process the nonroutine wastewater at design capacity. As a result, a study of alternative filter technologies was conducted utilizing simulated wastewater. The simulated wastewater tests have been completed. Three filter technologies, centrifugal polymeric ultrafilters, tubular polymeric ultrafilters, and backwashable cartridge filters have been selected for further evaluation utilizing actual ETF wastewater. (author)

Evaluation of the Nuclear Medicine facilities in Minas Gerais state: quality control program of equipment

International Nuclear Information System (INIS)

Kubo, Tadeu Takao Almodovar; Biancardi, Rodrigo; Rocha, Adriana Marcia Guimaraes; Ferreira, Denia Romao; Silva, Franciele Aquiles Anjos; Assuncao, Jonathan Buenos Aires; Alves, Ederson Henrique; Almeida, Ana Flavia Batista; Alves, Nathalia Fernandes; Xavier, Faber Henrique Zacarias; Gontijo, Rodrigo Modesto Gadelha; Mamede, Marcelo; Universidade Federal de Minas Gerais

2017-01-01

With the reformulation of the CNEN-NN-3.05 standard in December 2013, Brazil's Nuclear Medicine (NMS) services have to perform a greater number of quality controls for SPECT and PET equipment. However, little is known about the reality of the quality control programs of these services regarding the application of the new standard. Thus, in this context, the objective of the present study was to evaluate the quality control program of MNSs in the state of Minas Gerais. All NMSs in the state of Minas Gerais were invited to participate in the project. Of these, 34.48% (20 facilities) agreed to participate in the project, 50.00% (29 facilities) did not respond to the invitation and 15.52%(9 facilities) declined their participation. Thus, as of November 2015, 20 SPECT and 2 PET/CT equipment were evaluated for the performance of the quality control tests recommended by the new CNEN standard. The phantoms required for the evaluation came from the Laboratory of Dosimetry and Quality Control of UFMG. Even with the deadlines set by CNEN for the implementation of the quality control program in the NMSs, more than 50% of the evaluated services did not implement the quality controls, and the absence of specific phantoms is the main reason for the failure. Among the problems found in the installations, the most critical were: collimators with no conditions of use in the clinical routine, linearity problems of the evaluated image and values of image uniformity superior to the limits of acceptance. Problems in the uniformity and linearity of the image found directly impacted the performance of other tests, such as spatial resolution, SPECT performance, among others. In a general way, the NMSs in the state of Minas Gerais evaluated with the present study are in clinical feasible conditions. (author)

Evaluation of cold testing for Tokai Vitrification Facility

International Nuclear Information System (INIS)

Yoshioka, Masahiro; Inada, Eiichi

1994-01-01

The cold testing of the Tokai Vitrification Facility (TVF) was completed at the end of March, 1994 through the tests of nearly two years since May in 1992. The cold testing was carried out in order to evaluate the process equipment, product quality control, remote maintenance capability. The test results shown that TVF has enough performance with safety to treat the liquid waste in each process, and to control the product quality. For the remote maintenance of process equipment in the vitrification cell, the remote maintenance capability was confirmed for all remote equipment in the cell. The improvements were taken for some equipment with problem from the point of the operability and maintenance. It was confirmed by these test results that the TVF can go forward to the hot test operation using actual waste. (author)

Evaluating physical protection systems of licensed nuclear facilities using systems engineered inspection guidance

International Nuclear Information System (INIS)

Bradley, R.T.; Olson, A.W.; Rogue, F.; Scala, S.; Richard, E.W.

1980-01-01

The Lawrence Livermore National Laboratory (LLNL) and the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) have applied a systems engineering approach to provide the NRC Office of Inspection and Enforcement (IE) with improved methods and guidance for evaluating the physical protection systems of licensed nuclear facilities

340 Facility compliance assessment

International Nuclear Information System (INIS)

English, S.L.

1993-10-01

This study provides an environmental compliance evaluation of the RLWS and the RPS systems of the 340 Facility. The emphasis of the evaluation centers on compliance with WAC requirements for hazardous and mixed waste facilities, federal regulations, and Westinghouse Hanford Company (WHC) requirements pertinent to the operation of the 340 Facility. The 340 Facility is not covered under either an interim status Part A permit or a RCRA Part B permit. The detailed discussion of compliance deficiencies are summarized in Section 2.0. This includes items of significance that require action to ensure facility compliance with WAC, federal regulations, and WHC requirements. Outstanding issues exist for radioactive airborne effluent sampling and monitoring, radioactive liquid effluent sampling and monitoring, non-radioactive liquid effluent sampling and monitoring, less than 90 day waste storage tanks, and requirements for a permitted facility

Evaluation of mercury in liquid waste processing facilities - Phase I report

Energy Technology Data Exchange (ETDEWEB)

Jain, V. [Savannah River Site (SRS), Aiken, SC (United States); Occhipinti, J. E. [Savannah River Site (SRS), Aiken, SC (United States); Shah, H. [Savannah River Site (SRS), Aiken, SC (United States); Wilmarth, W. R. [Savannah River Site (SRS), Aiken, SC (United States); Edwards, R. E. [Savannah River Site (SRS), Aiken, SC (United States)

2015-07-01

This report provides a summary of Phase I activities conducted to support an Integrated Evaluation of Mercury in Liquid Waste System (LWS) Processing Facilities. Phase I activities included a review and assessment of the liquid waste inventory and chemical processing behavior of mercury using a system by system review methodology approach. Gaps in understanding mercury behavior as well as action items from the structured reviews are being tracked. 64% of the gaps and actions have been resolved.

Evaluation of Mercury in Liquid Waste Processing Facilities - Phase I Report

Energy Technology Data Exchange (ETDEWEB)

Jain, V. [Savannah River Site (SRS), Aiken, SC (United States); Occhipinti, J. [Savannah River Site (SRS), Aiken, SC (United States); Shah, H. [Savannah River Site (SRS), Aiken, SC (United States); Wilmarth, B. [Savannah River Site (SRS), Aiken, SC (United States); Edwards, R. [Savannah River Site (SRS), Aiken, SC (United States)

2015-07-01

This report provides a summary of Phase I activities conducted to support an Integrated Evaluation of Mercury in Liquid Waste System (LWS) Processing Facilities. Phase I activities included a review and assessment of the liquid waste inventory and chemical processing behavior of mercury using a system by system review methodology approach. Gaps in understanding mercury behavior as well as action items from the structured reviews are being tracked. 64% of the gaps and actions have been resolved.

Process evaluation of communitisation programme in public sector health facilities, Mokokchung district, Nagaland, 2015

Directory of Open Access Journals (Sweden)

Aonungdok Tushi

2017-01-01

Full Text Available Background: Public sector health facilities were poorly managed due to a history of conflict in Nagaland, India. Government of Nagaland introduced “Nagaland Communitisation of Public Institutions and Services Act” in 2002. Main objectives of the evaluation were to review the functioning of Health Center Managing Committees (HCMCs, deliver health services in the institutions managed by HCMC, identify strengths as well as challenges perceived by HCMC members in the rural areas of Mokokchung district, Nagaland. Materials and Methods: The evaluation was made using input, process and output indicators. A doctor, the HCMC Chairman and one member from each of the three community health centers (CHC and four primary health centers (PHC were surveyed using a semi-structured questionnaire and an in-depth interview guide. Proportions for quantitative data were computed and key themes from the same were identified. Results: Overall; the infrastructure, equipment and outpatient/inpatient service availability was satisfactory. There was a lack of funds and shortage of doctors, drugs as well as laboratory facilities. HCMCs were in place and carried out administrative activities. HCMCs felt ownership, mobilized community contributions and managed human resources. HCMC members had inadequate funds for their transport and training. They faced challenges in service delivery due to political interference and lack of adequate human, material, financial resources. Conclusions: Communitisation program was operational in the district. HCMC members felt the ownership of health facilities. Administrative, political support and adequate funds from the government are needed for effective functioning of HCMCs and optimal service delivery in public sector facilities.

Methodology to evaluate the site standard seismic motion for a nuclear facility

International Nuclear Information System (INIS)

Soares, W.A.

1983-03-01

An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt

Facilities Programming.

Science.gov (United States)

Bullis, Robert V.

1992-01-01

A procedure for physical facilities management written 17 years ago is still worth following today. Each of the steps outlined for planning, organizing, directing, controlling, and evaluating must be accomplished if school facilities are to be properly planned and constructed. However, lessons have been learned about energy consumption and proper…

Evaluation of {sup 18}F radioactive concentration in exhaust at cyclotron facility at Chosun University

Energy Technology Data Exchange (ETDEWEB)

Jeong, Cheol Ki; Jang, Han; Lee, Goung Jin [Dept. of Nuclear Engineering, Chsoun University, Gwangju (Korea, Republic of)

2016-11-15

the recent prevalence of PET examinations in Korea has led to an increase in the number of cyclotrons. the medical isotope 18F produced in most cyclotron facilities currently operating in Korea is emitted into the environment during the production of [{sup 18}F]FdG, a cancerdiagnosis reagent. the amount of [{sup 18}F]FdG synthesized determines the radioactive concentration of {sup 18}F in the exhaust. at some facilities, this amount temporarily exceeds the emission limit. In this study, we evaluated the {sup 18}F radioactivity concentration in the exhaust from the cyclotron facility at chosun university. the {sup 18}F radioactivity concentration was measured using an air sampler and a hPGe semiconductor detector. the measurements showed that the radioactive concentration of {sup 18}F in the exhaust at the cyclotron facility at Chosun university was the highest during [{sup 18}F]FdG synthesis but remained under the legal limit of 2,000 Bq m{sup -3}.

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

Energy Technology Data Exchange (ETDEWEB)

Dwyer, P.A.

1991-10-01

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

International Nuclear Information System (INIS)

Dwyer, P.A.

1991-10-01

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material

Evaluation of effectiveness of physical protection systems at nuclear facilities in the Slovak Republic

International Nuclear Information System (INIS)

Stefulova, A.

2001-01-01

This paper contains a short presentation of the state supervision in approach to the evaluation of physical protection systems at the nuclear facilities as one kind of measure used to prevent combat illicit trafficking of nuclear and other radioactive materials in the Slovak Republic. (author)

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs.

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

International Nuclear Information System (INIS)

1998-09-01

This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs

An evaluation on the scenarios of work trajectory during installation of dismantling equipment for decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Kang, ShinYoung; Choi, JongWon; Jeong, SeongYoung; Ahn, SangMyeon; Lee, JungJun

2016-01-01

Highlights: • An evaluation on the scenarios of work trajectory. • An evaluation using the virtual decommissioning environments. • An evaluation on work movement under radiation environments. - Abstract: This study is intended to suggest an ergonomic evaluation on the working postural comfort. This study issued for the first time a methodology in view of combination between visual field and comfort. Especially, the ergonomic evaluation using the virtual decommissioning environments is user-friendly because setup of physical mock-up environments is difficult. This study verified the front and standing postures are best working postures during movement under radiation environments of nuclear facilities. It is expected that this methodology will make it possible to establish the ergonomic plan for decommissioning of nuclear facilities and safety of decommissioning will be improved and also decommissioning costs also can be reduced.

Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

International Nuclear Information System (INIS)

C.J. Byrne

2001-01-01

This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M and O 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M and O 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M and O 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the

Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

Energy Technology Data Exchange (ETDEWEB)

C.J. Byrne

2001-02-20

This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M&O 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M&O 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M&O 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the individual

[Design of a supervision model for administration of the Child Development Evaluation Test at primary care facilities in Mexico].

Science.gov (United States)

Villasís-Keever, Miguel Ángel; Rizzoli-Córdoba, Antonio; Delgado-Ginebra, Ismael; Mares-Serratos, Blanca Berenice; Martell-Valdez, Liliana; Sánchez-Velázquez, Olivia; Reyes-Morales, Hortensia; O'Shea-Cuevas, Gabriel; Aceves-Villagrán, Daniel; Carrasco-Mendoza, Joaquín; Antillón-Ocampo, Fátima Adriana; Villagrán-Muñoz, Víctor Manuel; Halley-Castillo, Elizabeth; Baqueiro-Hernández, César Iván; Pizarro-Castellanos, Mariel; Martain-Pérez, Itzamara Jacqueline; Palma-Tavera, Josuha Alexander; Vargas-López, Guillermo; Muñoz-Hernández, Onofre

The Child Development Evaluation (CDE) test designed and validated in Mexico has been used as a screening tool for developmental problems in primary care facilities across Mexico. Heterogeneous results were found among those states where these were applied, despite using the same standardized training model for application. The objective was to evaluate a supervision model for quality of application of the CDE test at primary care facilities. A study was carried out in primary care facilities from three Mexican states to evaluate concordance of the results between supervisor and primary care personnel who administered the test using two different methods: direct observation (shadow study) or reapplication of the CDE test (consistency study). There were 380 shadow studies applied to 51 psychologists. General concordance of the shadow study was 86.1% according to the supervisor: green 94.5%, yellow 73.2% and red 80.0%. There were 302 re-test evaluations with a concordance of 88.1% (n=266): green 96.8%, yellow 71.7% and red 81.8%. There were no differences between CDE test subgroups by age. Both shadow and re-test study were adequate for the evaluation of the quality of the administration of the CDE Test and may be useful as a model of supervision in primary care facilities. The decision of which test to use relies on the availability of supervisors. Copyright © 2015 Hospital Infantil de México Federico Gómez. Publicado por Masson Doyma México S.A. All rights reserved.

Structural Shielding Design and Evaluation for Megavoltage X- and Gamma-Ray Radiotherapy Facilities.

Science.gov (United States)

Glasgow, Glenn P

2006-09-01

Structural Shielding Design and Evaluation for Megavoltage X- and Gamma-Ray Radiotherapy Facilities NCRP Report No. 151, 2005, 246 pp. (Hardcover $100). National Council on Radiation Protection and Measurements, 7910 Woodmont Avenue, Suite 400, Bethesda, MD 20814-3095. ISBN-10 0-0929600-87-8; http://www.NCRPonline.org. © 2006 American Association of Physicists in Medicine.

Seismic analysis, evaluation and upgrade design for a nuclear facility exhaust stack building

International Nuclear Information System (INIS)

Malik, L.E.; Kabir, A.F.

1991-01-01

This paper reports on an exhaust stack building of a nuclear reactor facility with complex structural configuration that has been analyzed and evaluated for seismic forces. This building was built in the 1950's and had not been designed to resist seismic forces. A very rigorous analysis and evaluation program was implemented to minimize the costly retrofits required to upgrade the building to resist high seismic forces. The seismic evaluations were performed for the building in its as-is configuration, and as modified for several upgrade schemes. Soil-structure-interaction, base mat flexibility and the influence of the nearby reactor building have been considered in the seismic analyses. The rigorous analyses and evaluation enabled limited upgrades to qualify the stack building for the seismic forces

Evaluation of the improvement suggestion system in a nuclear facility

International Nuclear Information System (INIS)

Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida

2017-01-01

This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

Evaluation of the improvement suggestion system in a nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida, E-mail: joaocarnaval@inb.gov.br, E-mail: geice@inb.gov.br [Industrias Nucleares do Brasil S.A (INB), Resende, RJ (Brazil)

2017-11-01

This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

Evaluation of methods for seismic analysis of nuclear fuel reprocessing and fabrication facilities

International Nuclear Information System (INIS)

Arthur, D.F.; Dong, R.G.; Murray, R.C.; Nelson, T.A.; Smith, P.D.; Wight, L.H.

1978-01-01

Methods of seismic analysis for critical structures and equipment in nuclear fuel reprocessing plants (NFRPs) and mixed oxide fuel fabrication plants (MOFFPs) are evaluated. The purpose of this series of reports is to provide the NRC with a technical basis for assessing seismic analysis methods and for writing regulatory guides in which methods ensuring the safe design of nuclear fuel cycle facilities are recommended. The present report evaluates methods of analyzing buried pipes and wells, sloshing effects in large pools, earth dams, multiply supported equipment, pile foundations, and soil-structure interactions

A facility for long term evaluation and quality assurance of LHCb Vertex Detector modules

CERN Document Server

Marinho, F; Dimattia, R; Doherty, F; Dumps, R; Gersabeck, M; Melone, J; Parkes, C; Saavedra, A; Tobin, M

2007-01-01

This note describes the facility developed for long term evaluation and quality assurance of the LHCb Vertex Detector modules, known as the 'Glasgow Burn-in System'. This facility was developed to ensure that the modules conform to stringent quality levels. The system was able to uncover any weaknesses that could be introduced during the manufacturing and assembly of the components or during the transport of the modules to CERN. The system consisted of: a high resolution microscope for visual inspections; and a burn-in system to operate cooled modules in vacuum. The main components of the burn-in system were a vacuum system, a cooling system and a DAQ system.

Evaluation of Island and Nearshore Confined Disposal Facility Alternatives, Pascagoula River Harbor Dredged Material Management Plan

National Research Council Canada - National Science Library

Bunch, Barry

2003-01-01

...) for the Federal navigation project at Pascagoula, MS. The studies focused on evaluating an option under consideration for the placement of dredged material in an island confined disposal facility (CDF...

Evaluation on applicability of construction methods and construction quality of low-diffusion layer of cavern type radioactive waste disposal facility

International Nuclear Information System (INIS)

Takechi, Shin-ichi; Yokozeki, Kosuke; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

2014-01-01

A performance verification experiment of cavern type radioactive waste disposal facility with a real scale construction is being conducted to evaluate the applicability of proposed construction methods and construction quality of the facility. In this paper, we confirmed that the low-diffusion layer, which is one of the cementitious materials based members, could be filled with mortar from end to end of the member; cracks of low-diffusion layer would not affect the long-term safety evaluation of the facility. And also we figured out the relationship between the material strength and the accumulated temperature, relationship between diffusion coefficient and porosity of low-diffusion layer. (author)

Evaluating malaria case management at public health facilities in two provinces in Angola.

Science.gov (United States)

Plucinski, Mateusz M; Ferreira, Manzambi; Ferreira, Carolina Miguel; Burns, Jordan; Gaparayi, Patrick; João, Lubaki; da Costa, Olinda; Gill, Parambir; Samutondo, Claudete; Quivinja, Joltim; Mbounga, Eliane; de León, Gabriel Ponce; Halsey, Eric S; Dimbu, Pedro Rafael; Fortes, Filomeno

2017-05-03

Malaria accounts for the largest portion of healthcare demand in Angola. A pillar of malaria control in Angola is the appropriate management of malaria illness, including testing of suspect cases with rapid diagnostic tests (RDTs) and treatment of confirmed cases with artemisinin-based combination therapy (ACT). Periodic systematic evaluations of malaria case management are recommended to measure health facility readiness and adherence to national case management guidelines. Cross-sectional health facility surveys were performed in low-transmission Huambo and high-transmission Uíge Provinces in early 2016. In each province, 45 health facilities were randomly selected from among all public health facilities stratified by level of care. Survey teams performed inventories of malaria commodities and conducted exit interviews and re-examinations, including RDT testing, of a random selection of all patients completing outpatient consultations. Key health facility readiness and case management indicators were calculated adjusting for the cluster sampling design and utilization. Availability of RDTs or microscopy on the day of the survey was 71% (54-83) in Huambo and 85% (67-94) in Uíge. At least one unit dose pack of one formulation of an ACT (usually artemether-lumefantrine) was available in 83% (66-92) of health facilities in Huambo and 79% (61-90) of health facilities in Uíge. Testing rates of suspect malaria cases in Huambo were 30% (23-38) versus 69% (53-81) in Uíge. Overall, 28% (13-49) of patients with uncomplicated malaria, as determined during the re-examination, were appropriately treated with an ACT with the correct dose in Huambo, compared to 60% (42-75) in Uíge. Incorrect case management of suspect malaria cases was associated with lack of healthcare worker training in Huambo and ACT stock-outs in Uíge. The results reveal important differences between provinces. Despite similar availability of testing and ACT, testing and treatment rates were lower in

Armament Technology Facility (ATF)

Data.gov (United States)

Federal Laboratory Consortium — The Armament Technology Facility is a 52,000 square foot, secure and environmentally-safe, integrated small arms and cannon caliber design and evaluation facility....

A Facile Approach to Evaluate Thermal Insulation Performance of Paper Cups

Directory of Open Access Journals (Sweden)

Yudi Kuang

2015-01-01

Full Text Available Paper cups are ubiquitous in daily life for serving water, soup, coffee, tea, and milk due to their convenience, biodegradability, recyclability, and sustainability. The thermal insulation performance of paper cups is of significance because they are used to supply hot food or drinks. Using an effective thermal conductivity to accurately evaluate the thermal insulation performance of paper cups is complex due to the inclusion of complicated components and a multilayer structure. Moreover, an effective thermal conductivity is unsuitable for evaluating thermal insulation performance of paper cups in the case of fluctuating temperature. In this work, we propose a facile approach to precisely analyze the thermal insulation performance of paper cups in a particular range of temperature by using an evaluation model based on the MISO (Multiple-Input Single-Output technical theory, which includes a characterization parameter (temperature factor and a measurement apparatus. A series of experiments was conducted according to this evaluation model, and the results show that this evaluation model enables accurate characterization of the thermal insulation performance of paper cups and provides an efficient theoretical basis for selecting paper materials for paper cups.

Dosimetric evaluation of semiconductor detectors for application in neutron dosimetry and microdosimetry in nuclear reactor and radiosurgical facilities

International Nuclear Information System (INIS)

Cardenas, Jose Patricio Nahuel

2010-01-01

The main objective of this research is the dosimetric evaluation of semiconductor components (surface barrier detectors and PIN photodiodes) for applications in dose equivalent measurements on low dose fields (fast and thermal fluxes) using an AmBe neutron source, the IEA-R1 reactor neutrongraphy facility (epithermal and thermal fluxes) and the Critical Unit facility IPEN/MB-01 (fast fluxes). As moderator compound to fast neutrons flux from the AmBe source was used paraffin and boron and polyethylene as converter for thermal and fast neutrons measurements. The resulting fluxes were used to the irradiation of semiconductor components (SSB - Surface Barrier Detector and PIN photodiodes). A mixed converter made of a borated polyethylene foil (Kodak) was also used. Monte Carlo simulation methodology was employed to evaluate analytically the optimal paraffin thickness. The obtained results were similar to the experimental data and allowed the evaluation of emerging neutron flux from moderator, as well as the fast neutron flux reaching the polyethylene covering the semiconductor sensitive surface. Gamma radiation levels were evaluated covering the whole detector with cadmium foil 1 mm thick, allowing thermal neutrons blockage and gamma radiation measurements. The IPEN/MB-01 facility was employed to evaluate the detector response for high neutron flux. The results were in good agreement with other studies published. Using the obtained spectra an approach to dose equivalent calculation was established. (author)

Evaluation of RayXpert® for shielding design of medical facilities

Science.gov (United States)

Derreumaux, Sylvie; Vecchiola, Sophie; Geoffray, Thomas; Etard, Cécile

2017-09-01

In a context of growing demands for expert evaluation concerning medical, industrial and research facilities, the French Institute for radiation protection and nuclear safety (IRSN) considered necessary to acquire new software for efficient dimensioning calculations. The selected software is RayXpert®. Before using this software in routine, exposure and transmission calculations for some basic configurations were validated. The validation was performed by the calculation of gamma dose constants and tenth value layers (TVL) for usual shielding materials and for radioisotopes most used in therapy (Ir-192, Co-60 and I-131). Calculated values were compared with results obtained using MCNPX as a reference code and with published values. The impact of different calculation parameters, such as the source emission rays considered for calculation and the use of biasing techniques, was evaluated.

Preliminary safety evaluation of a commercial-scale krypton-85 encapsulation facility

International Nuclear Information System (INIS)

Christensen, A.B.; Tanner, J.E.; Knecht, D.A.

1980-09-01

This report demonstrates that a commercial-scale facility for encapsulating krypton-85 in zeolite-5A or glass at a 2000 MTHM per year nuclear fuel reprocessing plant can be designed to contain fragments and the 340 to 850 kCi krypton-85 inventory from an assumed catastrophic failure of the high pressure vessel. The vessel failure was assumed as a worst case and was not based on a detailed design evaluation or operating experience. The process design is based on existing commercial hot isostatic pressing technology operated at up to 40 times the scale required for krypton encapsulation. From the calculated process gas inventory in the pressure vessel and vessel design, the explosive energy of 8.4 kg TNT and vessel plug and fragment velocities were calculated. The facility Containment Cell housing the high pressure vessel was designed to contain the gases, fragments, and the shock wave energy calculated for vessel failure. The Access Cell located directly above the Containment Cell was designed to be a tertiary confinement of krypton-85, should the access hatch be breached

Facility effluent monitoring plan for the tank farm facility

Energy Technology Data Exchange (ETDEWEB)

Crummel, G.M.

1998-05-18

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

International Nuclear Information System (INIS)

Baumann, B.L.; Haffner, D.R.; Miller, R.L.; Scotti, K.S.

1986-06-01

This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

Development of a standardized transfusion ratio as a metric for evaluating dialysis facility anemia management practices.

Science.gov (United States)

Liu, Jiannong; Li, Suying; Gilbertson, David T; Monda, Keri L; Bradbury, Brian D; Collins, Allan J

2014-10-01

Because transfusion avoidance has been the cornerstone of anemia treatment for patients with kidney disease, direct measurement of red blood cell transfusion use to assess dialysis facility anemia management performance is reasonable. We aimed to explore methods for estimating facility-level standardized transfusion ratios (STfRs) to assess provider anemia treatment practices. Retrospective cohort study. Point prevalent US hemodialysis patients on January 1, 2009, with Medicare as primary payer and dialysis duration of 90 days or longer were included (n = 223,901). All dialysis facilities with eligible patients were included (n = 5,345). Dialysis facility assignment. Receiving a red blood cell transfusion in the inpatient or outpatient setting. We evaluated 3 approaches for estimating STfR: ratio of observed to expected numbers of transfusions (STfR(obs)), a Bayesian approach (STfR(Bayes)), and a modified version of the Bayesian approach (STfR(modBayes)). The overall national transfusion rate in 2009 was 23.2 per 100 patient-years. Our model for predicting the expected number of transfusions performed well. For large facilities, all 3 STfRs worked well. However, for small facilities, while the STfR(modBayes) worked well, STfR(obs) values demonstrated instability and the STfR(Bayes) may produce more bias. Administration of transfusions to dialysis patients reflects medical practice both within and outside the dialysis unit. Some transfusions may be deemed unavoidable and transfusion practices are subject to considerable regional variation. Development of an STfR metric is feasible and reasonable for assessing anemia treatment at dialysis facilities. The STfR(obs) is simple to calculate and works well for larger dialysis facilities. The STfR(modBayes) is more analytically complex, but facilitates comparisons across all dialysis facilities, including small facilities. Copyright © 2014 National Kidney Foundation, Inc. Published by Elsevier Inc. All rights reserved.

Ouellette Thermal Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The Thermal Test Facility is a joint Army/Navy state-of-the-art facility (8,100 ft2) that was designed to:Evaluate and characterize the effect of flame and thermal...

Evaluation of renewable energy alternatives for highway maintenance facilities.

Science.gov (United States)

2013-12-01

A considerable annual energy budget is used for heating, lighting, cooling and operating ODOT : maintenance facilities. Such facilities contain vehicle repair and garage bays, which are large open : spaces with high heating demand in winter. The main...

Radiological assessment of the PET facility

International Nuclear Information System (INIS)

Discacciatti, Adrian; Cruzate, Juan A.; Bomben, Ana M.; Carelli, Jorge; Namias, Mario

2008-01-01

The radiological assessment of a Positron Emission Tomography (PET) facility consists of the evaluation of the annual effective dose to workers exposed occupationally and to members of the public. This evaluation takes into account the radionuclide involved, the characteristics of the facility, the working procedure and the expected number of patients per year. This paper details the methodology used by the Nuclear Regulatory Authority (in Spanish ARN) to independently assess the design of PET facilities considering only radioprotection aspects. The results of the evaluation are compared with the design requirements established in the ARN regulations to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. As an example of the above mentioned methodology, this paper presents the assessment of a PET facility located in Buenos Aires called Fundacion Centro Diagnostico Nuclear (FCDN). (author)

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

ESF [Exploratory Shaft Facility] impact evaluation report: Volume 2: Final report

International Nuclear Information System (INIS)

1985-08-01

This report assesses the impacts of integrating an Exploratory Shaft Facility (ESF) with a high-level nuclear waste repository in salt. An evaluation to identify integration impacts is described for two specific ESF configurations (Cases 1 and 2) for each of the seven sites. These configurations are an ESF which uses two of the full size repository shafts, and an ESF with one 10-ft and one 22-ft diameter shaft. An evaluation of an ESF configuration (Case 3) with two 12-ft diameter shafts at three of the seven sites is also described. These sites are Deaf Smith, Davis Canyon, and Richton Dome. A fourth evaluation (Case 4) for the Deaf Smith site only, addresses a ''fast track'' subsurface development plan to allow waste emplacement by 1998. A fifth evaluation (Case 5), provides site-specific ES locations, for the three sites included in Case 3, which are supportive of a shaft siting study prepared by ONWI. The report presents development schedules depicting construction activities and time frames commencing with receipt of the repository Construction Authorization and proceeding to initiation of emplacement operations. These schedules are site specific and are presented for each of the five cases

DETERMINATION OF IMPORTANCE EVALUATION FOR THE SUBSURFACE EXPLORATORY STUDIES FACILITY

International Nuclear Information System (INIS)

Clark, W.J.

1999-01-01

This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), the Enhanced Characterization of the Repository Block (ECRB) East-West Cross Drift Starter Tunnel (to approximate ECRB Station 0+26 m), and ancillary test and operation support areas in the TS Loop. This evaluation applies to the construction, operation, and maintenance of these excavations. A more detailed description of these items is provided in Section 6.0. Testing activities are not evaluated in this DIE. Certain construction activities with respect to testing activities are evaluated; but the testing activities themselves are not evaluated. The DIE for ESF Subsurface Testing Activities (BAJ3000000-01717-2200-000111) (CRWMS M and O 1998a) evaluates Subsurface ESF Testing activities. The construction, operation, and maintenance of the TS Loop niches and alcove slot cuts is evaluated herein and is also discussed in CRWMS M and O 1998a. The construction, operation, and maintenance of the Busted Butte subsurface test area in support of the Unsaturated Zone (UZ) Transport Test is evaluated in CRWMS M and O 1998a. Potential test-to-test interference and the waste isolation impacts of testing activities are evaluated in the ESF Subsurface Testing Activities DIE and other applicable evaluation(s) for the Job Package (JP), Test Planning Package (TPP), and/or Field Work Package (FWP). The objectives of this DIE are to determine whether the Subsurface ESF TS Loop and associated excavations, including activities associated with their construction and operation, potentially impact site characterization testing or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified. The validity and veracity of the individual tests, including data collection, are the

DETERMINATION OF IMPORTANCE EVALUATION FOR THE SUBSURFACE EXPORATORY STUDIES FACILITY

Energy Technology Data Exchange (ETDEWEB)

W.J. Clark

1999-06-28

This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), the Enhanced Characterization of the Repository Block (ECRB) East-West Cross Drift Starter Tunnel (to approximate ECRB Station 0+26 m), and ancillary test and operation support areas in the TS Loop. This evaluation applies to the construction, operation, and maintenance of these excavations. A more detailed description of these items is provided in Section 6.0. Testing activities are not evaluated in this DIE. Certain construction activities with respect to testing activities are evaluated; but the testing activities themselves are not evaluated. The DIE for ESF Subsurface Testing Activities (BAJ3000000-01717-2200-00011 Rev 01) (CRWMS M&O 1998a) evaluates Subsurface ESF Testing activities. The construction, operation, and maintenance of the TS Loop niches and alcove slot cuts is evaluated herein and is also discussed in CRWMS M&O 1998a. The construction, operation, and maintenance of the Busted Butte subsurface test area in support of the Unsaturated Zone (UZ) Transport Test is evaluated in CRWMS M&O 1998a. Potential test-to-test interference and the waste isolation impacts of testing activities are evaluated in the ESF Subsurface Testing Activities DIE and other applicable evaluation(s) for the Job Package (JP), Test Planning Package (TPP), and/or Field Work Package (FWP). The objectives of this DIE are to determine whether the Subsurface ESF TS Loop and associated excavations, including activities associated with their construction and operation, potentially impact site characterization testing or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified. The validity and veracity of the individual tests, including data collection, are the responsibility

Process evaluation of the RaDIANT community study: a dialysis facility-level intervention to increase referral for kidney transplantation.

Science.gov (United States)

Hamoda, Reem E; Gander, Jennifer C; McPherson, Laura J; Arriola, Kimberly J; Cobb, Loren; Pastan, Stephen O; Plantinga, Laura; Browne, Teri; Hartmann, Erica; Mulloy, Laura; Zayas, Carlos; Krisher, Jenna; Patzer, Rachel E

2018-01-15

The Reducing Disparities in Access to kidNey Transplantation Community Study (RaDIANT) was an End-Stage Renal Disease (ESRD) Network 6-developed, dialysis facility-level randomized trial testing the effectiveness of a 1-year multicomponent education and quality improvement intervention in increasing referral for kidney transplant evaluation among selected Georgia dialysis facilities. To assess implementation of the RaDIANT intervention, we conducted a process evaluation at the conclusion of the intervention period (January-December 2014). We administered a 20-item survey to the staff involved with transplant education in 67 dialysis facilities randomized to participate in intervention activities. Survey items assessed facility participation in the intervention (fidelity and reach), helpfulness and willingness to continue intervention activities (sustainability), suggestions for improving intervention components (sustainability), and factors that may have influenced participation and study outcomes (context). We defined high fidelity to the intervention as completing 11 or more activities, and high participation in an activity as having at least 75% participation across intervention facilities. Staff from 65 of the 67 dialysis facilities completed the questionnaire, and more than half (50.8%) reported high adherence (fidelity) to RaDIANT intervention requirements. Nearly two-thirds (63.1%) of facilities reported that RaDIANT intervention activities were helpful or very helpful, with 90.8% of facilities willing to continue at least one intervention component beyond the study period. Intervention components with high participation emphasized staff and patient-level education, including in-service staff orientations, patient and family education programs, and patient educational materials. Suggested improvements for intervention activities emphasized addressing financial barriers to transplantation, with financial education materials perceived as most helpful among Ra

Tracking implementation and (un)intended consequences: a process evaluation of an innovative peripheral health facility financing mechanism in Kenya.

Science.gov (United States)

Waweru, Evelyn; Goodman, Catherine; Kedenge, Sarah; Tsofa, Benjamin; Molyneux, Sassy

2016-03-01

In many African countries, user fees have failed to achieve intended access and quality of care improvements. Subsequent user fee reduction or elimination policies have often been poorly planned, without alternative sources of income for facilities. We describe early implementation of an innovative national health financing intervention in Kenya; the health sector services fund (HSSF). In HSSF, central funds are credited directly into a facility's bank account quarterly, and facility funds are managed by health facility management committees (HFMCs) including community representatives. HSSF is therefore a finance mechanism with potential to increase access to funds for peripheral facilities, support user fee reduction and improve equity in access. We conducted a process evaluation of HSSF implementation based on a theory of change underpinning the intervention. Methods included interviews at national, district and facility levels, facility record reviews, a structured exit survey and a document review. We found impressive achievements: HSSF funds were reaching facilities; funds were being overseen and used in a way that strengthened transparency and community involvement; and health workers' motivation and patient satisfaction improved. Challenges or unintended outcomes included: complex and centralized accounting requirements undermining efficiency; interactions between HSSF and user fees leading to difficulties in accessing crucial user fee funds; and some relationship problems between key players. Although user fees charged had not increased, national reduction policies were still not being adhered to. Finance mechanisms can have a strong positive impact on peripheral facilities, and HFMCs can play a valuable role in managing facilities. Although fiduciary oversight is essential, mechanisms should allow for local decision-making and ensure that unmanageable paperwork is avoided. There are also limits to what can be achieved with relatively small funds in

Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities

International Nuclear Information System (INIS)

Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

1994-02-01

This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km 2 Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included

Preliminary safety evaluation of a commercial-scale krypton-85 encapsulation facility

International Nuclear Information System (INIS)

Christensen, A.B.; Tanner, J.E.; Knecht, D.A.

1980-01-01

This paper demonstrates that a commercial-scale facility for encapsulating krypton-85 in zeolite-5A or glass at a 2000 MTHM per year nuclear fuel reprocessing plant can be designed to contain fragments and the 340 to 850 kCi krypton-85 inventory from an assumed catastrophic failure of the high pressure vessel. The vessel failure was assumed as a worst case and was not based on a detailed design evaluation or operating experience. The process design is based on existing commercial hot isostatic pressing technology operated at up to 40 times the scale required for krypton encapsulation. From the calculated process gas inventory in the pressure vessel and vessel design, the maximum explosive energy of 8.4 kg TNT and resulting vessel plug and fragment velocities were calculated. The facility Containment Cell housing the high pressure vessel was designed to contain the gases, fragments, and the shock wave energy calculated for a hypothetical vessel failure. The Access Cell located directly above the Containment Cell was designed to be a tertiary confinement of krypton-85, should the access hatch be breached. 3 figures, 2 tables

Source term evaluation for accident transients in the experimental fusion facility ITER

Energy Technology Data Exchange (ETDEWEB)

Virot, F.; Barrachin, M.; Cousin, F. [IRSN, BP3-13115, Saint Paul lez Durance (France)

2015-03-15

We have studied the transport and chemical speciation of radio-toxic and toxic species for an event of water ingress in the vacuum vessel of experimental fusion facility ITER with the ASTEC code. In particular our evaluation takes into account an assessed thermodynamic data for the beryllium gaseous species. This study shows that deposited beryllium dusts of atomic Be and Be(OH){sub 2} are formed. It also shows that Be(OT){sub 2} could exist in some conditions in the drain tank. (authors)

VISA: a method for evaluating the performance of integrated safeguards systems at nuclear facilities

International Nuclear Information System (INIS)

Donnelly, H.; Fullwood, R.; Glancy, J.

1977-06-01

This is the second volume of a two volume report on the VISA method for evaluating safeguards at fixed-site facilities. This volume contains appendices that support the description of the VISA concept and the initial working version of the method, VISA-1, presented in Volume I. The information is separated into four appendices, each describing details of one of the four analysis modules that comprise the analysis sections of the method. The first appendix discusses Path Analysis methodology, applies it to a Model Fuel Facility, and describes the computer codes that are being used. Introductory material on Path Analysis given in Chapter 3.2.1 and Chapter 4.2.1 of Volume I. The second appendix deals with Detection Analysis, specifically the schemes used in VISA-1 for classifying adversaries and the methods proposed for evaluating individual detection mechanisms in order to build the data base required for detection analysis. Examples of evaluations on identity-access systems, SNM portal monitors, and intrusion devices are provided. The third appendix describes the Containment Analysis overt-segment path ranking, the Monte Carlo engagement model, the network simulation code, the delay mechanism data base, and the results of a sensitivity analysis. The last appendix presents general equations used in Interruption Analysis for combining covert-overt segments and compares them with equations given in Volume I, Chapter 3

An evaluation of systematic tuberculosis screening at private facilities in Karachi, Pakistan.

Directory of Open Access Journals (Sweden)

Jacob Creswell

Full Text Available BACKGROUND: In Pakistan, like many Asian countries, a large proportion of healthcare is provided through the private sector. We evaluated a systematic screening strategy to identify people with tuberculosis in private facilities in Karachi and assessed the approaches' ability to diagnose patients earlier in their disease progression. METHODS AND FINDINGS: Lay workers at 89 private clinics and a large hospital outpatient department screened all attendees for tuberculosis using a mobile phone-based questionnaire during one year. The number needed to screen to detect a case of tuberculosis was calculated. To evaluate early diagnosis, we tested for differences in cough duration and smear grading by screening facility. 529,447 people were screened, 1,010 smear-positive tuberculosis cases were detected and 942 (93.3% started treatment, representing 58.7% of all smear-positive cases notified in the intervention area. The number needed to screen to detect a smear-positive case was 124 (prevalence 806/100,000 at the hospital and 763 (prevalence 131/100,000 at the clinics; however, ten times the number of individuals were screened in clinics. People with smear-positive TB detected at the hospital were less likely to report cough lasting 2-3 weeks (RR 0.66 95%CI [0.49-0.90] and more likely to report cough duration >3 weeks (RR 1.10 95%CI [1.03-1.18]. Smear-positive cases at the clinics were less likely to have a +3 grade (RR 0.76 95%CI [0.63-0.92] and more likely to have +1 smear grade (RR 1.24 95%CI [1.02-1.51]. CONCLUSIONS: Tuberculosis screening at private facilities is acceptable and can yield large numbers of previously undiagnosed cases. Screening at general practitioner clinics may find cases earlier than at hospitals although more people must be screened to identify a case of tuberculosis. Limitations include lack of culture testing, therefore underestimating true TB prevalence. Using more sensitive and specific screening and diagnostic tests such

An evaluation of systematic tuberculosis screening at private facilities in Karachi, Pakistan.

Science.gov (United States)

Creswell, Jacob; Khowaja, Saira; Codlin, Andrew; Hashmi, Rabia; Rasheed, Erum; Khan, Mubashir; Durab, Irfan; Mergenthaler, Christina; Hussain, Owais; Khan, Faisal; Khan, Aamir J

2014-01-01

In Pakistan, like many Asian countries, a large proportion of healthcare is provided through the private sector. We evaluated a systematic screening strategy to identify people with tuberculosis in private facilities in Karachi and assessed the approaches' ability to diagnose patients earlier in their disease progression. Lay workers at 89 private clinics and a large hospital outpatient department screened all attendees for tuberculosis using a mobile phone-based questionnaire during one year. The number needed to screen to detect a case of tuberculosis was calculated. To evaluate early diagnosis, we tested for differences in cough duration and smear grading by screening facility. 529,447 people were screened, 1,010 smear-positive tuberculosis cases were detected and 942 (93.3%) started treatment, representing 58.7% of all smear-positive cases notified in the intervention area. The number needed to screen to detect a smear-positive case was 124 (prevalence 806/100,000) at the hospital and 763 (prevalence 131/100,000) at the clinics; however, ten times the number of individuals were screened in clinics. People with smear-positive TB detected at the hospital were less likely to report cough lasting 2-3 weeks (RR 0.66 95%CI [0.49-0.90]) and more likely to report cough duration >3 weeks (RR 1.10 95%CI [1.03-1.18]). Smear-positive cases at the clinics were less likely to have a +3 grade (RR 0.76 95%CI [0.63-0.92]) and more likely to have +1 smear grade (RR 1.24 95%CI [1.02-1.51]). Tuberculosis screening at private facilities is acceptable and can yield large numbers of previously undiagnosed cases. Screening at general practitioner clinics may find cases earlier than at hospitals although more people must be screened to identify a case of tuberculosis. Limitations include lack of culture testing, therefore underestimating true TB prevalence. Using more sensitive and specific screening and diagnostic tests such as chest x-ray and Xpert MTB/RIF may improve results.

Evaluation of replacement tritium facility (RTF) compliance with DOE safety goals using probabilistic consequence assessment methodology

International Nuclear Information System (INIS)

O'Kula, K.R.; East, J.M.; Moore, M.L.

1993-01-01

The Savannah River Site (SRS), operated by the Westinghouse Savannah River Company (WSRC) for the US Department of Energy (DOE), is a major center for the processing of nuclear materials for national defense, deep-space exploration, and medical treatment applications in the United States. As an integral part of the DOE's effort to modernize facilities, implement improved handling and processing technology, and reduce operational risk to the general public and onsite workers, transition of tritium processing at SRS from the Consolidated Tritium Facility to the Replacement Tritium Facility (RTF) began in 1993. To ensure that operation of new DOE facilities such as RTF present minimum involuntary and voluntary risks to the neighboring public and workers, indices of risk have been established to serve as target levels or safety goals of performance for assessing nuclear safety. These goals are discussed from a historical perspective in the initial part of this paper. Secondly, methodologies to quantify risk indices are briefly described. Lastly, accident, abnormal event, and normal operation source terms from RTF are evaluated for consequence assessment purposes relative to the safety targets

Design Evaluation of a Piping System in the SELFA Sodium Test Facility

Energy Technology Data Exchange (ETDEWEB)

Son, Seok-Kwon; Jo, Young-Chul; Lee, Hyeong-Yeon; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

In this study, design evaluations on the SELFA piping system has been conducted according to the ASME B31.1 and RCC-MRx RD-3600. The conservatism of the two codes was quantified based on the evaluation results. It was shown that B31.1 was more conservative for the sustained loads while less conservative for thermal expansion loads when compare with those of RD-3600. However, all the evaluation results according to the two codes were within the code allowables. There are two main piping systems in the SELFA test loop. In this study, the integrity of the SELFA piping system has been evaluated according to the two design-by-rule (DBR) codes of ASME B31.1 and RCC-MRx RD-3600. B31.1 is an industry design code for power piping while RD-3600 is a class 3 nuclear DBR code. The conservatism of the two codes was quantified based on the evaluation results as per the two DBR codes. The sodium test facility of the SELFA is under construction at KAERI for the investigation of thermo-hydraulic behavior of finned-tube sodium-to-air heat exchanger.

Probabilistic safety assessment for food irradiation facility

International Nuclear Information System (INIS)

Solanki, R.B.; Prasad, M.; Sonawane, A.U.; Gupta, S.K.

2012-01-01

Highlights: ► Different considerations are required in PSA for Non-Reactor Nuclear Facilities. ► We carried out PSA for food irradiation facility as a part of safety evaluation. ► The results indicate that the fatal exposure risk is below the ‘acceptable risk’. ► Adequate operator training and observing good safety culture would reduce the risk. - Abstract: Probabilistic safety assessment (PSA) is widely used for safety evaluation of Nuclear Power Plants (NPPs) worldwide. The approaches and methodologies are matured and general consensus exists on using these approaches in PSA applications. However, PSA applications for safety evaluation for non-reactor facilities are limited. Due to differences in the processes in nuclear reactor facilities and non-reactor facilities, the considerations are different in application of PSA to these facilities. The food irradiation facilities utilize gamma irradiation sources, X-ray machines and electron accelerators for the purpose of radiation processing of variety of food items. This is categorized as Non-Reactor Nuclear Facility. In this paper, the application of PSA to safety evaluation of food irradiation facility is presented considering the ‘fatality due to radiation overexposure’ as a risk measure. The results indicate that the frequency of the fatal exposure is below the numerical acceptance guidance for the risk to the individual. Further, it is found that the overall risk to the over exposure can be reduced by providing the adequate operator training and observing good safety culture.

Earthquake damage to underground facilities

International Nuclear Information System (INIS)

Pratt, H.R.; Stephenson, D.E.; Zandt, G.; Bouchon, M.; Hustrulid, W.A.

1980-01-01

In order to assess the seismic risk for an underground facility, a data base was established and analyzed to evaluate the potential for seismic disturbance. Substantial damage to underground facilities is usually the result of displacements primarily along pre-existing faults and fractures, or at the surface entrance to these facilities. Evidence of this comes from both earthquakes and large explosions. Therefore, the displacement due to earthquakes as a function of depth is important in the evaluation of the hazard to underground facilities. To evaluate potential displacements due to seismic effects of block motions along pre-existing or induced fractures, the displacement fields surrounding two types of faults were investigated. Analytical models were used to determine relative displacements of shafts and near-surface displacement of large rock masses. Numerical methods were used to determine the displacement fields associated with pure strike-slip and vertical normal faults. Results are presented as displacements for various fault lengths as a function of depth and distance. This provides input to determine potential displacements in terms of depth and distance for underground facilities, important for assessing potential sites and design parameters

Evaluation of rubber seal products for gamma facilities

International Nuclear Information System (INIS)

Sobhy, M.S.; Shafy, M.A.; Shahin, F.

2005-01-01

Ageing behavior by employing the prolonged exposures of high-energy radiation such as gamma-rays on the physicomechanical properties of some rubber seal products are studied. The proposed binary-rubber blends, SBR/NBR, EPDM/NBR and EPDM/EPM. have overcome their problem of inhomogeneity and incompatibility between the two rubber phases. Such enhancements are acquired by either the replacement of part of NBR by SBR during mastication, or the incorporation of maleic anhydride. Results show that the EPDM/EPM rubber blend has possessed the radiation resistance property towards the deterioration due to higher gamma-irradiation dose. The SEM images have c early observed the role of the used antioxidant, where a thin film is usually produced, degraded; with the appearance of surface cracks, and repaired with further gamma-irradiation up to high doses. Such enhancement is necessary for the definition of the requirements to be put on rubber seal materials. Finally, these products ought to assure the quality control in production and evaluate their application suitability that may employ in the pneumatic system in gamma facility

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

Energy Technology Data Exchange (ETDEWEB)

West, K.A.

1988-11-01

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

International Nuclear Information System (INIS)

West, K.A.

1988-11-01

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs

Development of simplified decommissioning cost estimation code for nuclear facilities

International Nuclear Information System (INIS)

Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu

2010-01-01

The simplified decommissioning cost estimation code for nuclear facilities (DECOST code) was developed in consideration of features and structures of nuclear facilities and similarity of dismantling methods. The DECOST code could calculate 8 evaluation items of decommissioning cost. Actual dismantling in the Japan Atomic Energy Agency (JAEA) was evaluated; unit conversion factors used to calculate the manpower of dismantling activities were evaluated. Consequently, unit conversion factors of general components could be classified into three kinds. Weights of components and structures of the facility were necessary for calculation of manpower. Methods for evaluating weights of components and structures of the facility were studied. Consequently, the weight of components in the facility was proportional to the weight of structures of the facility. The weight of structures of the facility was proportional to the total area of floors in the facility. Decommissioning costs of 7 nuclear facilities in the JAEA were calculated by using the DECOST code. To verify the calculated results, the calculated manpower was compared with the manpower gained from actual dismantling. Consequently, the calculated manpower and actual manpower were almost equal. The outline of the DECOST code, evaluation results of unit conversion factors, the evaluation method of the weights of components and structures of the facility are described in this report. (author)

Evaluation of the impact and the releases of operating nuclear facilities

International Nuclear Information System (INIS)

2005-01-01

The monitoring of nuclear installations releases, the associated impacts evaluation and the radiation monitoring of the environment are of an increase interest since the last ten years. Theses two days, organized by the environment section of the SFRP (French Society of Radiation Protection), aim to discuss the following topics: the development of the methods to improve radioactive elements and toxic substances releases in the environment; the structure of the environment control and the objectives of this control; the association of the local actors to the releases monitoring and to the environment control; the perspectives of evolution in matter of nuclear facilities releases management. (A.L.B.)

ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

International Nuclear Information System (INIS)

Phillips, Ann Marie; Meservey, Richard H.

2003-01-01

Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

An Evaluation of Facility Maintenance and Repair Strategies of Select Companies

National Research Council Canada - National Science Library

Sharp, Christopher

2002-01-01

...) with the benefits derived from those facilities. This thesis documents how a selection of companies implemented that balance by determining their facilities requirements based on their chosen facility condition level and how they then allocated funds...

Post-Occupancy Evaluation of a Mental Healthcare Facility Based on Staff Perceptions of Design Innovations.

Science.gov (United States)

Kalantari, Saleh; Snell, Robin

2017-07-01

This study was a post-occupancy evaluation (POE) to examine the effectiveness of three specific design innovations in a mental healthcare facility. In addition to collecting data about the impact of these specific designs, the study provides a model for the broader implementation of POE approaches in the mental healthcare context. POEs in general healthcare settings have been shown to lead to better work environments and better outcomes for patients. Despite growing evidence of the value provided by POE studies, the industry has been somewhat slow to adopt their regular use, in part due to unfamiliarity with the POE process. This is particularly true in mental healthcare contexts, where POE studies remain virtually nonexistent. In-depth interviews and a widely distributed, anonymous survey were used to collect hospital staff perceptions and feedback regarding the impact of specific design features. The hospital staff were quite enthusiastic about two of the design innovations studied here (a new wayfinding strategy and the use of vibrant colors in specific areas of the facility). The third innovation, open-style communication centers, elicited more mixed evaluations. The results include extensive hypothesis testing about the effects of each innovation as well as narrative discussions of their pros and cons. The study generated new knowledge about three specific mental healthcare design innovations and provides a model for the practical implementation of a POE approach in mental healthcare contexts. The results are particularly relevant for designers who are considering innovative strategies in future mental healthcare facilities.

HUMAN MACHINE INTERFACE (HMI) EVALUATION OF ROOMS TA-50-1-60/60A AT THE RADIOACTIVE LIQUID WASTE TREATMENT FACILITY (RLWTF)

Energy Technology Data Exchange (ETDEWEB)

Gilmore, Walter E. [Los Alamos National Laboratory; Stender, Kerith K. [Los Alamos National Laboratory

2012-08-29

This effort addressed an evaluation of human machine interfaces (HMIs) in Room TA-50-1-60/60A of the Radioactive Liquid Waste Treatment Facility (RLWTF). The evaluation was performed in accordance with guidance outlined in DOE-STD-3009, DOE Standard Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, 2006 [DOE 2006]. Specifically, Chapter 13 of DOE 2006 highlights the 10 CFR 830, Nuclear Safety Management, 2012, [CFR 2012] and DOE G 421.1-2 [DOE 2001a] requirements as they relate to the human factors process and, in this case, the safety of the RLWTF. The RLWTF is a Hazard Category 3 facility and, consequently, does not have safety-class (SSCs). However, safety-significant SSCs are identified. The transuranic (TRU) wastewater tanks and associated piping are the only safety-significant SSCs in Rooms TA-50-1-60/60A [LANL 2010]. Hence, the human factors evaluation described herein is only applicable to this particular assemblage of tanks and piping.

Evaluation of separation distance from the temporary storage facility for decontamination waste to ensure public radiological safety after Fukushima nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Kim, Min Jung; Go, A Ra; Kim, Kwang Pyo [Kyung Hee University, Yongin (Korea, Republic of)

2016-09-15

The object of this study was to evaluate the separation distance from a temporary storage facility satisfying the dose criteria. The calculation of ambient dose rates took into account cover soil thickness, facility size, and facility type by using MCNPX code. Shielding effects of cover soil were 68.9%, 96.9% and 99.7% at 10 cm, 30 cm and 50 cm respectively. The on-ground type of storage facility had the highest ambient dose rate, followed by the semi-ground type and the underground type. The ambient dose rate did not vary with facility size (except 5 × 5 × 2 m size) due to the self-shielding of decontamination waste in temporary storage. The separation distances without cover soil for a 50 × 50 × 2 m size facility were evaluated as 14 m (minimum radioactivity concentration), 33 m (most probably radioactivity concentration), and 57 m (maximum radioactivity concentration) for on-ground storage type, 9 m, 24 m, and 45 m for semi-underground storage type, and 6 m, 16 m, and 31 m for underground storage type.

Auditing radiation sterilization facilities

Science.gov (United States)

Beck, Jeffrey A.

The diversity of radiation sterilization systems available today places renewed emphasis on the need for thorough Quality Assurance audits of these facilities. Evaluating compliance with Good Manufacturing Practices is an obvious requirement, but an effective audit must also evaluate installation and performance qualification programs (validation_, and process control and monitoring procedures in detail. The present paper describes general standards that radiation sterilization operations should meet in each of these key areas, and provides basic guidance for conducting QA audits of these facilities.

Evaluation of the 183-D Water Filtration Facility for Bat Roosts and Development of a Mitigation Strategy, 100-D Area, Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Lindsey, C. T.; Gano, K. A.; Lucas, J. G.

2011-03-07

The 183-D Water Filtration Facility is located in the 100-D Area of the Hanford Site, north of Richland, Washington. It was used to provide filtered water for cooling the 105-D Reactor and supplying fire-protection and drinking water for all facilities in the 100-D Area. The facility has been inactive since the 1980s and is now scheduled for demolition. Therefore, an evaluation was conducted to determine if any part of the facility was being used as roosting habitat by bats.

Safety evaluation of the NSRR facility relevant to the modification for improved pulse operation and preirradiated fuel experiments

International Nuclear Information System (INIS)

Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; Katagiri, Hiroshi; Kobayashi, Hideo

1988-11-01

The Nuclear Safety Research Reactor (NSRR) is a pulse reactor for the inpile experiments to study the fuel behavior under reactivity initiated accident conditions. The present operation modes of the NSRR consist of the steady state operation up to 300 kW and the natural pulse operation in which a sharp pulsed power is generated from substantially zero power level. In addition to these, two new modes of shaped pulse operation and combined pulse operation will be conducted in the near future as the improved pulse operations. A transient power up to 10 MW will be generated in the shaped pulse operation, and a combination of a transient power up to 10 MW and a sharp pulsed power will be generated in the combined pulse operation. Furthermore, preirradiated fuel rods will be employed in the future experiments whereas the present experiments are confined to the test specimens of unirradiated fuel rods. To provide for these programs, the fundamental design works relevant to the modification of the reactor facility including the reactor instrumentation and control systems and experimental provision were developed. The reactor safety evaluation is prerequisite for confirming the propriety of the fundamental design of the reactor facility from the safety point of view. The safety evaluation was therefore conducted postulating such events that would bring about abnormal conditions in the reactor facility. As a result of the safety evaluation, it has been confirmed as to the NSRR facility after modification that the anticipated transients, the postulated accidents, the major accident and the hypothetical accident do not result respectively in any serious safety problem and that the fundamental design principles and the reactor siting are adequate and acceptable. (author)

On The Issue Of The Nature And Evaluation Of The Equipment And Facilities During The Accreditation Of Schools Of Higher Education

OpenAIRE

Ivan Zhelev

2012-01-01

The provision of high quality education in higher schools is connected with the need for skilled and habilitated academic staff and the existence of modern equipment and facilities. In the article there are examined some theoretical and applied aspects of the equipment and facilities of the higher schools and on that basis there is outlined a methodical approach for their evaluation during accreditation. There are clarifie d the nature, elements and scope of the term „equipment and facilities...

Evaluating Commercial and Private Cloud Services for Facility-Scale Geodetic Data Access, Analysis, and Services

Science.gov (United States)

Meertens, C. M.; Boler, F. M.; Ertz, D. J.; Mencin, D.; Phillips, D.; Baker, S.

2017-12-01

UNAVCO, in its role as a NSF facility for geodetic infrastructure and data, has succeeded for over two decades using on-premises infrastructure, and while the promise of cloud-based infrastructure is well-established, significant questions about suitability of such infrastructure for facility-scale services remain. Primarily through the GeoSciCloud award from NSF EarthCube, UNAVCO is investigating the costs, advantages, and disadvantages of providing its geodetic data and services in the cloud versus using UNAVCO's on-premises infrastructure. (IRIS is a collaborator on the project and is performing its own suite of investigations). In contrast to the 2-3 year time scale for the research cycle, the time scale of operation and planning for NSF facilities is for a minimum of five years and for some services extends to a decade or more. Planning for on-premises infrastructure is deliberate, and migrations typically take months to years to fully implement. Migrations to a cloud environment can only go forward with similar deliberate planning and understanding of all costs and benefits. The EarthCube GeoSciCloud project is intended to address the uncertainties of facility-level operations in the cloud. Investigations are being performed in a commercial cloud environment (Amazon AWS) during the first year of the project and in a private cloud environment (NSF XSEDE resource at the Texas Advanced Computing Center) during the second year. These investigations are expected to illuminate the potential as well as the limitations of running facility scale production services in the cloud. The work includes running parallel equivalent cloud-based services to on premises services and includes: data serving via ftp from a large data store, operation of a metadata database, production scale processing of multiple months of geodetic data, web services delivery of quality checked data and products, large-scale compute services for event post-processing, and serving real time data

Facility effluent monitoring

Energy Technology Data Exchange (ETDEWEB)

Gleckler, B.P.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

Risk management study for the Hanford Site facilities: Risk reduction cost comparison for the retired Hanford Site facilities. Volume 4

Energy Technology Data Exchange (ETDEWEB)

Coles, G.A.; Egge, R.G.; Senger, E.; Shultz, M.W.; Taylor, W.E.

1994-02-01

This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km{sup 2} Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This cost-comparison evaluation (1) determines relative costs for reducing risk to acceptable levels; (2) compares the cost of reducing risk using different risk-reduction options; and (3) compares the cost of reducing risks at different facilities. The result is an identification of the cost effective risk-reduction measures. Supporting information required to develop costs of the various risk-reduction options also is included.

Facility Effluent Monitoring Plan for the uranium trioxide facility

International Nuclear Information System (INIS)

Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Addressing social aspects associated with wastewater treatment facilities

International Nuclear Information System (INIS)

Padilla-Rivera, Alejandro; Morgan-Sagastume, Juan Manuel; Noyola, Adalberto; Güereca, Leonor Patricia

2016-01-01

In wastewater treatment facilities (WWTF), technical and financial aspects have been considered a priority, while other issues, such as social aspects, have not been evaluated seriously and there is not an accepted methodology for assessing it. In this work, a methodology focused on social concerns related to WWTF is presented. The methodology proposes the use of 25 indicators as a framework for measuring social performance to evaluate the progress in moving towards sustainability. The methodology was applied to test its applicability and effectiveness in two WWTF in Mexico (urban and rural). This evaluation helped define the key elements, stakeholders and barriers in the facilities. In this context, the urban facility showed a better overall performance, a result that may be explained mainly by the better socioeconomic context of the urban municipality. Finally, the evaluation of social aspects using the semi-qualitative approach proposed in this work allows for a comparison between different facilities and for the identification of strengths and weakness, and it provides an alternative tool for achieving and improving wastewater management. - Highlights: • The methodology proposes 25 indicators as a framework for measuring social performance in wastewater treatment facilities. • The evaluation helped to define the key elements, stakeholders and barriers in the wastewater treatment facilities. • The evaluation of social aspects allows the identification of strengths and weakness for improving wastewater management. • It provides a social profile of the facility that highlights the best and worst performances.

Addressing social aspects associated with wastewater treatment facilities

Energy Technology Data Exchange (ETDEWEB)

Padilla-Rivera, Alejandro; Morgan-Sagastume, Juan Manuel; Noyola, Adalberto; Güereca, Leonor Patricia, E-mail: lguerecah@iingen.unam.mx

2016-02-15

In wastewater treatment facilities (WWTF), technical and financial aspects have been considered a priority, while other issues, such as social aspects, have not been evaluated seriously and there is not an accepted methodology for assessing it. In this work, a methodology focused on social concerns related to WWTF is presented. The methodology proposes the use of 25 indicators as a framework for measuring social performance to evaluate the progress in moving towards sustainability. The methodology was applied to test its applicability and effectiveness in two WWTF in Mexico (urban and rural). This evaluation helped define the key elements, stakeholders and barriers in the facilities. In this context, the urban facility showed a better overall performance, a result that may be explained mainly by the better socioeconomic context of the urban municipality. Finally, the evaluation of social aspects using the semi-qualitative approach proposed in this work allows for a comparison between different facilities and for the identification of strengths and weakness, and it provides an alternative tool for achieving and improving wastewater management. - Highlights: • The methodology proposes 25 indicators as a framework for measuring social performance in wastewater treatment facilities. • The evaluation helped to define the key elements, stakeholders and barriers in the wastewater treatment facilities. • The evaluation of social aspects allows the identification of strengths and weakness for improving wastewater management. • It provides a social profile of the facility that highlights the best and worst performances.

Experimental performance evaluation of two stack sampling systems in a plutonium facility

International Nuclear Information System (INIS)

Glissmeyer, J.A.

1992-04-01

The evaluation of two routine stack sampling systems at the Z-Plant plutonium facility operated by Rockwell International for USERDA is part of a larger study, sponsored by Rockwell and conducted by Battelle, Pacific Northwest Laboratories, of gaseous effluent sampling systems. The gaseous effluent sampling systems evaluated are located at the main plant ventilation stack (291-Z-1) and at a vessel vent stack (296-Z-3). A preliminary report, which was a paper study issued in April 1976, identified many deficiencies in the existing sampling systems and made recommendations for corrective action. The objectives of this experimental evaluation of those sampling systems were as follows: Characterize the radioactive aerosols in the stack effluents; Develop a tracer aerosol technique for validating particulate effluent sampling system performance; Evaluate the performance of the existing routine sampling systems and their compliance with the sponsor's criteria; and Recommend corrective action where required. The tracer aerosol approach to sampler evaluation was chosen because the low concentrations of radioactive particulates in the effluents would otherwise require much longer sampling times and thus more time to complete this evaluation. The following report describes the sampling systems that are the subject of this study and then details the experiments performed. The results are then presented and discussed. Much of the raw and finished data are included in the appendices

Evaluation of a prototype air transport system for use in a crate handling and size reduction facility

International Nuclear Information System (INIS)

Kennedy, S.T.

1987-09-01

This paper describes the design features and evaluation, under simulated active conditions, of a purpose designed remotely operated air transporter system. The paper concludes by recommending that an air transporter, based on this concept, is considered for the alpha active facility. (author)

Preliminary geotechnical evaluation of deep borehole facilities for nuclear waste disposal in shales

International Nuclear Information System (INIS)

Nataraj, M.S.; New Orleans Univ., LA

1991-01-01

This study is concerned with a preliminary engineering evaluation of borehole facilities for nuclear waste disposal in shales. Some of the geotechnical properties of Pierre, Rhinestreet, and typical illite shale have been collected. The influence of a few geotechnical properties on strength and deformation of host material is briefly examined. It appears that Pierre shale is very unstable and requires support to prevent collapse. Typical illite shale is more stable than Rhinestreet shale, although it undergoes relatively more deformation. 16 refs., 5 figs., 3 tabs

Groundwater screening evaluation/monitoring plan: 200 Area Treated Effluent Disposal Facility (Project W-049H). Revision 1

International Nuclear Information System (INIS)

Barnett, D.B.; Davis, J.D.; Collard, L.B.; Freeman, P.B.; Chou, C.J.

1995-05-01

This report consists of the groundwater screening evaluation required by Section S.8 of the State Waste Discharge Permit for the 200 Area TEDF. Chapter 1.0 describes the purpose of the groundwater monitoring plan. The information in Chapter 2.0 establishes a water quality baseline for the facility and is the groundwater screening evaluation. The following information is included in Chapter 2.0: Facility description;Well locations, construction, and development data; Geologic and hydrologic description of the site and affected area; Ambient groundwater quality and current use; Water balance information; Hydrologic parameters; Potentiometric map, hydraulic gradients, and flow velocities; Results of infiltration and hydraulic tests; Groundwater and soils chemistry sampling and analysis data; Statistical evaluation of groundwater background data; and Projected effects of facility operation on groundwater flow and water quality. Chapter 3.0 defines, based on the information in Chapter 2.0, how effects of the TEDF on the environment will be evaluated and how compliance with groundwater quality standards will be documented in accordance with the terms and conditions of the permit. Chapter 3.0 contains the following information: Media to be monitored; Wells proposed as the point of compliance in the uppermost aquifer; Basis for monitoring well network and evidence of monitoring adequacy; Contingency planning approach for vadose zone monitoring wells; Which field parameters will be measured and how measurements will be made; Specification of constituents to be sampled and analyzed; and Specification of the sampling and analysis procedures that will be used. Chapter 4.0 provides information on how the monitoring results will be reported and the proposed frequency of monitoring and reporting. Chapter 5.0 lists all the references cited in this monitoring plan. These references should be consulted for additional or more detailed information

Study of physical resistance of the disposal facility for accidental artificial event in LLW disposal facility

International Nuclear Information System (INIS)

Ogawa, Suihei; Irie, Masaaki; Uchida, Masahiro

2013-11-01

This report refer to results of examine what follows for structural stability evaluation for the LLW disposal facility in depth over general human activity in underground. Study of physically resistance on the facility for accidental artificial event, namely tunneling an operation facing the disposal facility in future. Physically resistance to excavation of tunneling etc. in disposal facility is studied based on supposing of Tunnel Boring Machine as an excavator, paying attention to reinforcement bar in concrete and steel plate of waste package, as feature of strength in these material differs from rock strength. And it is examined not only resistibility on excavation but also about hard situations of excavation in tunneling works, and namely give thorough consideration to critical quantity of cutting to reinforcement bar and steel plate that could keep resistibility on excavation based on tunneling velocity and limits time furthermore. It requests necessity of evaluation in consider with metal corrosion that status alteration on disposal facility is considered with on timescale. Period of keep on the physically resistance is estimated by velocity of metal corrosion consequently. The physically resistance is kept until metal corrosion reach remaining its material, giving a limits of the physically resistance on inside of facility. Main point of physically resistance in the report will be made the good use of a practice to physically resistance evaluation of in safety assessment. (author)

Hanford Surplus Facilities Program plan

International Nuclear Information System (INIS)

Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

1989-09-01

The Hanford Surplus Facilities Program is responsible for the safe and cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The management of these facilities requires a surveillance and maintenance program to keep them in a safe condition and development of a plan for ultimate disposition. Criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy-Richland Operations Office, Defense Facilities Decommissioning Program Office, and are consistent with the Westinghouse Hanford Company commitment to decommission the Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities to the end of disposition

Stockbridge Antenna Measurement and Research Facility

Data.gov (United States)

Federal Laboratory Consortium — The Stockbridge Antenna Measurement Facility is located 23 miles southwest of AFRL¹s Rome Research Site. This unique measurement facility is designed to evaluate the...

Evaluation of a prototype air transport system for use in a crate handling and size reduction facility

International Nuclear Information System (INIS)

Kennedy, S.T.

1987-01-01

This paper describes in detail the design features and evaluation, under simulated active conditions, of a purpose designed remotely operated air transporter system. The paper concludes by recommending that an air transporter, based on this concept, is considered for the alpha active facility. (author)

Precision Clock Evaluation Facility

Data.gov (United States)

Federal Laboratory Consortium — FUNCTION: Tests and evaluates high-precision atomic clocks for spacecraft, ground, and mobile applications. Supports performance evaluation, environmental testing,...

Evaluation of the 12-hour shift schedule at the Fast Flux Test Facility

International Nuclear Information System (INIS)

Lewis, P.M.; Swaim, D.J.; Rosa, R.R.; Colligan, M.J.; Booth, R.J.; Swint, M.J.

1986-09-01

The objective of this report are to evaluate the effect of the change to the 12-hour/day schedule on operational performance and safety of FFTF; to evaluate the degree to which the change to the 12-hour/day schedule has met its objectives; and to gather information that may be useful to FFTF management and the US Department of Energy (DOE) in evaluating 8- and 12-hour shift schedules at other facilities. The principal conclusion of this report is that the 12-hour/day shift schedule is a reasonable alternative to an 8-hour/day schedule at FFTF. As a result of the scedule change, it seems clear that plant performance improved in two ways. The operator error rate in keeping the Technical Specification Compliance Logs was already very low on the 8-hour shift. On the 12-hour shift, the rate was even lower. Also, the operator interface with craft personnel resulted in an increase in the productivity of the craft personnel

Progress towards developing consistent design and evaluation guidelines for US Department of Energy facilities subjected to natural phenomena

International Nuclear Information System (INIS)

Murray, R.C.

1987-01-01

Probabilistic definitions of earthquake, wind, and tornado hazards for many DOE facilities throughout the United States have been developed. In addition, definitions of the flood hazards which might affect these locations are currently being developed. We have prepared a document to provide guidance and criteria for DOE facility managers to assure that DOE facilities are adequately constructed to resist the effects of natural phenomena such as earthquake, strong wind, and flood. The intent of this document is to provide instruction on how to utilize the hazard definitions to evaluate existing facilities and design new facilities in a manner such that the risk of adverse consequences is consistent with the cost, function, and danger to the public or environment. A conference and six mini-courses were organized on natural phenomena hazards mitigation. This provided a mechanism for technology transfer to the DOE community. Complementary manuals have also been developed for 1) suspended ceiling systems and recommendations for bracing them, 2) practical equipment seismic upgrade and strengthening guidelines, and 3) suggested structural details for wind design. These manuals are intended to provide input and guidance for ongoing site safety programs. (orig./HP)

Progress towards developing consistent design and evaluation guidelines for US Department of Energy facilities subjected to natural phenomena

International Nuclear Information System (INIS)

Murray, R.C.

1987-01-01

Probabilistic definitions of earthquake, wind, and tornado hazards for many Department of Energy (DOE) facilities throughout the United States have been developed. In addition, definitions of the flood hazards which might affect these locations are currently being developed. The authors have prepared a document to provide guidance and criteria for DOE facility managers to assure that DOE facilities are adequately constructed to resist the effects of natural phenomena such as earthquake, strong wind, and flood. The intent of this document is to provide instruction on how to utilize the hazard definitions to evaluate existing facilities and design new facilities in a manner such that the risk of adverse consequences is consistent with the cost, function, and danger to the public or environment. A conference and six mini-courses were organized on natural phenomena hazards mitigation. This provided a mechanism for technology transfer to the DOE community. Complementary manuals have also been developed for 1) suspended ceiling systems and recommendations for bracing them, 2) practical equipment seismic upgrade and strengthening guidelines, and 3) suggested structural details for wind design. These manuals are intended to provide input and guidance for ongoing site safety programs

303-K Storage Facility: Report on FY98 closure activities

International Nuclear Information System (INIS)

Adler, J.G.

1998-01-01

This report summarizes and evaluates the decontamination activities, sampling activities, and sample analysis performed in support of the closure of the 303-K Storage Facility. The evaluation is based on the validated data included in the data validation package (98-EAP-346) for the 303-K Storage Facility. The results of this evaluation will be used for assessing contamination for the purpose of closing the 303-K Storage Facility as described in the 303-K Storage Facility Closure Plan, DOE/RL-90-04. The closure strategy for the 303-K Storage Facility is to decontaminate the interior of the north half of the 303-K Building to remove known or suspected dangerous waste contamination, to sample the interior concrete and exterior soils for the constituents of concern, and then to perform data analysis, with an evaluation to determine if the closure activities and data meet the closure criteria. The closure criteria for the 303-K Storage Facility is that the concentrations of constituents of concern are not present above the cleanup levels. Based on the evaluation of the decontamination activities, sampling activities, and sample data, determination has been made that the soils at the 303-K Storage Facility meet the cleanup performance standards (WMH 1997) and can be clean closed. The evaluation determined that the 303-K Building cannot be clean closed without additional closure activities. An additional evaluation will be needed to determine the specific activities required to clean close the 303-K Storage Facility. The radiological contamination at the 303-K Storage Facility is not addressed by the closure strategy

EVALUATION OF ECONOMIC EFFICIENCY PERTAINING TO USAGE OF AUTOMOTIVE TRANSPORT FACILITIES WHILE EXECUTING INTERNATIONAL CARGO TRANSPORTATION

Directory of Open Access Journals (Sweden)

R. B. Ivut

2010-01-01

Full Text Available The paper presents a methodology for evaluation of economic efficiency pertaining to usage of automotive transport facilities while executing international cargo transportation on the basis of average internal norm calculation of automotive operational profitability of a specific model under conditions which are typical for the given market by an average carrier.

Performance evaluation of the Solar Building Test Facility

Science.gov (United States)

Jensen, R. N.

1981-01-01

The general performance of the NASA Solar Building Test Facility (SBTF) and its subsystems and components over a four year operational period is discussed, and data are provided for a typical one year period. The facility consists of a 4645 sq office building modified to accept solar heated water for operation of an absorption air conditioner and a baseboard heating system. An adjoining 1176 sq solar flat plate collector field with a 114 cu tank provides the solar heated water. The solar system provided 57 percent of the energy required for heating and cooling on an annual basis. The average efficiency of the solar collectors was 26 percent over a one year period.

Analysis of factors related to man-induced hazard for nuclear facilities

International Nuclear Information System (INIS)

Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young

2003-03-01

This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out

Analysis of factors related to man-induced hazard for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young [Seoul National Univ. of Technology, Seoul (Korea, Republic of)

2003-03-15

This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out.

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Facility effluent monitoring plan for the plutonium uranium extraction facility

Energy Technology Data Exchange (ETDEWEB)

Wiegand, D.L.

1994-09-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Facility effluent monitoring plan for the plutonium uranium extraction facility

International Nuclear Information System (INIS)

Wiegand, D.L.

1994-09-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

International Nuclear Information System (INIS)

Greager, E.M.

1997-01-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years

Facility effluent monitoring plan for the plutonium-uranium extraction facility

Energy Technology Data Exchange (ETDEWEB)

Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, NM (United States)

1993-12-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

Energy Technology Data Exchange (ETDEWEB)

Ramirez, Amanda Ann

2008-09-01

The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

Microcomputer simulation model for facility performance assessment: a case study of nuclear spent fuel handling facility operations

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.; Otis, P.T.

1985-10-01

A microcomputer based simulation model was recently developed at the Pacific Northwest Laboratory (PNL) to assist in the evaluation of design alternatives for a proposed facility to receive, consolidate and store nuclear spent fuel from US commercial power plants. Previous performance assessments were limited to deterministic calculations and Gantt chart representations of the facility operations. To insure that the design of the facility will be adequate to meet the specified throughput requirements, the simulation model was used to analyze such factors as material flow, equipment capability and the interface between the MRS facility and the nuclear waste transportation system. The simulation analysis model was based on commercially available software and application programs designed to represent the MRS waste handling facility operations. The results of the evaluation were used by the design review team at PNL to identify areas where design modifications should be considered. 4 figs

Facility effluent monitoring plan for the tank farms facilities

Energy Technology Data Exchange (ETDEWEB)

Bachand, D.D.; Crummel, G.M.

1995-05-01

A facility effluent monitoring plan is required by the US Department of Energy for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using specific guidelines. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

Fuel conditioning facility material accountancy

International Nuclear Information System (INIS)

Yacout, A.M.; Bucher, R.G.; Orechwa, Y.

1995-01-01

The operation of the Fuel conditioning Facility (FCF) is based on the electrometallurgical processing of spent metallic reactor fuel. It differs significantly, therefore, from traditional PUREX process facilities in both processing technology and safeguards implications. For example, the fissile material is processed in FCF only in batches and is transferred within the facility only as solid, well-characterized items; there are no liquid steams containing fissile material within the facility, nor entering or leaving the facility. The analysis of a single batch lends itself also to an analytical relationship between the safeguards criteria, such as alarm limit, detection probability, and maximum significant amount of fissile material, and the accounting system's performance, as it is reflected in the variance associated with the estimate of the inventory difference. This relation, together with the sensitivity of the inventory difference to the uncertainties in the measurements, allows a thorough evaluation of the power of the accounting system. The system for the accountancy of the fissile material in the FCF has two main components: a system to gather and store information during the operation of the facility, and a system to interpret this information with regard to meeting safeguards criteria. These are described and the precision of the inventory closure over one batch evaluated

The Upgrade Programme for the Structural Biology beamlines at the European Synchrotron Radiation Facility - High throughput sample evaluation and automation

Science.gov (United States)

Theveneau, P.; Baker, R.; Barrett, R.; Beteva, A.; Bowler, M. W.; Carpentier, P.; Caserotto, H.; de Sanctis, D.; Dobias, F.; Flot, D.; Guijarro, M.; Giraud, T.; Lentini, M.; Leonard, G. A.; Mattenet, M.; McCarthy, A. A.; McSweeney, S. M.; Morawe, C.; Nanao, M.; Nurizzo, D.; Ohlsson, S.; Pernot, P.; Popov, A. N.; Round, A.; Royant, A.; Schmid, W.; Snigirev, A.; Surr, J.; Mueller-Dieckmann, C.

2013-03-01

Automation and advances in technology are the key elements in addressing the steadily increasing complexity of Macromolecular Crystallography (MX) experiments. Much of this complexity is due to the inter-and intra-crystal heterogeneity in diffraction quality often observed for crystals of multi-component macromolecular assemblies or membrane proteins. Such heterogeneity makes high-throughput sample evaluation an important and necessary tool for increasing the chances of a successful structure determination. The introduction at the ESRF of automatic sample changers in 2005 dramatically increased the number of samples that were tested for diffraction quality. This "first generation" of automation, coupled with advances in software aimed at optimising data collection strategies in MX, resulted in a three-fold increase in the number of crystal structures elucidated per year using data collected at the ESRF. In addition, sample evaluation can be further complemented using small angle scattering experiments on the newly constructed bioSAXS facility on BM29 and the micro-spectroscopy facility (ID29S). The construction of a second generation of automated facilities on the MASSIF (Massively Automated Sample Screening Integrated Facility) beam lines will build on these advances and should provide a paradigm shift in how MX experiments are carried out which will benefit the entire Structural Biology community.

Evaluating the Effects of Air Pollution from a Plastic Recycling Facility on the Health of Nearby Residents.

Science.gov (United States)

Xin, Zhao; Tsuda, Toshihide; Doi, Hiroyuki

2017-06-01

We evaluated how exposure to airborne volatile organic compounds emitted from a plastic recycling facility affected nearby residents, in a cross-sectional study. Individuals>10 years old were randomly sampled from 50 households at five sites and given questionnaires to complete. We categorized the subjects by distance from the recycling facility and used this as a proxy measure for pollutant exposure. We sought to improve on a preceding study by generating new findings, improving methods for questionnaire distribution and collection, and refining site selection. We calculated the odds of residents living 500 or 900 m away from the facility reporting mucocutaneous and respiratory symptoms using a reference group of residents 2,800 m away. Self-reported nasal congestion (odds ratio=3.0, 95% confidence interval=1.02-8.8), eczema (5.1, 1.1-22.9), and sore throat (3.9, 1.1-14.1) were significantly higher among residents 500 m from the facility. Those 900 m away were also considerably more likely to report experiencing eczema (4.6, 1.4-14.9). Air pollution was found responsible for significantly increased reports of mucocutaneous and respiratory symptoms among nearby residents. Our findings confirm the effects of pollutants emitted from recycling facilities on residents' health and clarify that study design differences did not affect the results.

Seismic evaluation of existing nuclear power plants and other facilities V. 1. Proceedings of the technical committee meeting. Working material

International Nuclear Information System (INIS)

2002-01-01

The objectives of this Tcm are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. Today the nuclear industry relies much more on existing facilities than on the design of new ones. Nevertheless it appears that safety evaluation against external hazards is not a decreasing activity. The reason being that maintaining an acceptable level of nuclear safety requires periodic re-assessments of facilities, either because of modifications of the environment due to human activity or because of new data or new approaches in the assessment of natural hazards. In this regard, seismic re-evaluation has increasingly become a key issue for several existing nuclear facilities, including not only nuclear power plants but also other plants of the fuel cycle, as well as research reactors or laboratories. The IAEA has already supported development of engineering practices in this field by managing a Co-ordinated Research Programme, launched in 1992, on a Benchmark Study for the seismic analysis and testing of WWER 1000 type NPPs. It is now proposed to investigate other aspects of this issue. Many of these facilities were built according to older standards which did not take into account seismic hazard. Consequently, the seismic re-evaluation of existing facilities is a real challenge for earthquake engineers. In most of the cases, it is impossible to re-evaluate according to the up to date standards because entering these standards implies that some design rules are met, what is generally not the case for older facilities. In the best cases some rules exist for non nuclear buildings. In order to achieve a consensus on this matter, the IAEA intends to edit a Safety Report on 'Seismic Evaluation of existing NPPs'. The TCM will offer the opportunity to review the draft of

An evaluation related to the effect of strategic facility management on choice of medical tourism destination

Directory of Open Access Journals (Sweden)

Tarcan Ertugrul

2015-01-01

Full Text Available This study based on literature review aims to evaluate and emphasize the affect of the strategic facility management (SFM on choice of medical tourism destination. Medical Tourism, which ranges from the health care services involving a cure to the wellness services involving no specific health trouble to pleasure and amusement services, is one of the most growing sectors in the world. Cost and quality of medical services are among the main reasons for the choice of destination. Strategic facility management has a positive correlation on the levels of quality, cost and customer satisfaction. Thus medical tourism and destination managers should take into account of the potential advantages of value creation offered through SFM in order to be chosen by customers (stakeholders.

Seismic design evaluation guidelines for buried piping for the DOE HLW Facilities

International Nuclear Information System (INIS)

Lin, Chi-Wen; Antaki, G.; Bandyopadhyay, K.; Bush, S.H.; Costantino, C.; Kennedy, R.

1995-01-01

This paper presents the seismic design and evaluation guidelines for underground piping for the Department of Energy (DOE) High-Level-Waste (HLW) Facilities. The underground piping includes both single and double containment steel pipes and concrete pipes with steel lining, with particular emphasis on the double containment piping. The design and evaluation guidelines presented in this paper follow the generally accepted beam-on-elastic-foundation analysis principle and the inertial response calculation method, respectively, for piping directly in contact with the soil or contained in a jacket. A standard analysis procedure is described along with the discussion of factors deemed to be significant for the design of the underground piping. The following key considerations are addressed: the design feature and safety requirements for the inner (core) pipe and the outer pipe; the effect of soil strain and wave passage; assimilation of the necessary seismic and soil data; inertial response calculation for the inner pipe; determination of support anchor movement loads; combination of design loads; and code comparison. Specifications and justifications of the key parameters used, stress components to be calculated and the allowable stress and strain limits for code evaluation are presented

Evaluation of juvenile salmonid bypass facilities and passage at water diversions on the lower Umatilla River. Final report

International Nuclear Information System (INIS)

Cameron, W.A.; Knapp, S.M.; Carmichael, R.W.

1997-07-01

Outdated juvenile and adult fish passage facilities were recently reconstructed at the five major irrigation dams on the lower Umatilla River, Oregon to meet National marine Fisheries Service (NMFS) design standards. Changes in design at juvenile fish bypass facilities included reduced mesh size on the rotating drum screens, larger screening area, a more oblique orientation of the drum screens to canal flow, improved screen seals, replacement of bypass portals with vertical slot bypass channels, and increased bypass pipe diameters. Weir-and-pool adult fish ladders and jump pools were replaced with vertical-slot ladders. From 1991--1995, they investigated injury and travel rate of juvenile fish moving through the facilities, and efficiency of screens in preventing fish entry into the canals. Water velocities in front of canal screens, at bypass channel entrances, and at ladder diffusers were measured to assess adherence to NMFS criteria and identify hydraulic patterns. Biological evaluations were conducted by releasing and recapturing marked yearling summer steelhead (Oncorhynchus mykiss), yearling spring chinook salmon (O. tshawytscha), and subyearling fall chinook salmon (O. tshawytscha) in varying locations within the fish passage facilities

Engineering Evaluation/Cost Analysis for Power Burst Facility (PER-620) Final End State and PBF Vessel Disposal

Energy Technology Data Exchange (ETDEWEB)

B. C. Culp

2007-05-01

Preparation of this engineering evaluation/cost analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, (DOE and EPA 1995) which establishes the Comprehensive Environmental, Response, Compensation, and Liability Act non-time critical removal action process as an approach for decommissioning. The scope of this engineering evaluation/cost analysis is to evaluate alternatives and recommend a preferred alternative for the final end state of the PBF and the final disposal location for the PBF vessel.

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontage, S.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

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

Evaluating the effectiveness of training for nuclear facility personnel. Proceedings of the specialists' meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

One of the essential requirements for safe and reliable nuclear power plant operation and maintenance is the availability of competent personnel. The systematic approach to training (SAT) is recognized world-wide as the international best practice for attaining and maintaining the qualification and competence of nuclear power plant personnel. Many countries have applied and are now implementing or enhancing the use of SAT in their training systems, as demonstrated by the results of the IAEA World Survey on Nuclear Power Plant Personnel Training published in the beginning of 1999. Among the major challenges of human resource professionals is the need to measure the effectiveness of their training programs. Most training programs in the nuclear industry are effective because they are meeting legitimate needs and are conducted by competent, professional staff. Unfortunately, the extent of the impact of teaming is usually unknown or vague at best. Measurement and evaluation processes and procedures are usually inadequate or need further development and refinement. The IAEA has already been addressing the NPP personnel teaming problem during the last several years. Nevertheless, the scope of the problem is widening and new solutions are being developed. Therefore, the IAEA has decided to invite teaming professionals to a Specialists' Meeting to learn about and discuss NPP personnel training trends. The topic of this meeting, evaluating the effectiveness of training for nuclear facility personnel, was selected by the IAEA International Working Group on Training and Qualification of Nuclear Power Plant Personnel. A Specialists' Meeting on Evaluating the Effectiveness of Training for Nuclear Facility Personnel, organized in co-operation with EXITECH Corporation, the US DOE was attended by participants from 12 countries presenting 21 papers.

Evaluating the effectiveness of training for nuclear facility personnel. Proceedings of the specialists' meeting

International Nuclear Information System (INIS)

2003-01-01

One of the essential requirements for safe and reliable nuclear power plant operation and maintenance is the availability of competent personnel. The systematic approach to training (SAT) is recognized world-wide as the international best practice for attaining and maintaining the qualification and competence of nuclear power plant personnel. Many countries have applied and are now implementing or enhancing the use of SAT in their training systems, as demonstrated by the results of the IAEA World Survey on Nuclear Power Plant Personnel Training published in the beginning of 1999. Among the major challenges of human resource professionals is the need to measure the effectiveness of their training programs. Most training programs in the nuclear industry are effective because they are meeting legitimate needs and are conducted by competent, professional staff. Unfortunately, the extent of the impact of teaming is usually unknown or vague at best. Measurement and evaluation processes and procedures are usually inadequate or need further development and refinement. The IAEA has already been addressing the NPP personnel teaming problem during the last several years. Nevertheless, the scope of the problem is widening and new solutions are being developed. Therefore, the IAEA has decided to invite teaming professionals to a Specialists' Meeting to learn about and discuss NPP personnel training trends. The topic of this meeting, evaluating the effectiveness of training for nuclear facility personnel, was selected by the IAEA International Working Group on Training and Qualification of Nuclear Power Plant Personnel. A Specialists' Meeting on Evaluating the Effectiveness of Training for Nuclear Facility Personnel, organized in co-operation with EXITECH Corporation, the US DOE was attended by participants from 12 countries presenting 21 papers

33-GVA interrupter test facility

International Nuclear Information System (INIS)

Parsons, W.M.; Honig, E.M.; Warren, R.W.

1979-01-01

The use of commercial ac circuit breakers for dc switching operations requires that they be evaluated to determine their dc limitations. Two 2.4-GVA facilities have been constructed and used for this purpose at LASL during the last several years. In response to the increased demand on switching technology, a 33-GVA facility has been constructed. Novel features incorporated into this facility include (1) separate capacitive and cryogenic inductive energy storage systems, (2) fiber-optic controls and optically-coupled data links, and (3) digital data acquisition systems. Facility details and planned tests on an experimental rod-array vacuum interrupter are presented

Evaluation of environmental change and its effects on the radiological performance of a hypothetical shallow engineered disposal facility at Elstow, Bedfordshire

International Nuclear Information System (INIS)

1988-03-01

The results of a project designed to evaluate aspects of a hypothetical facility for disposal of radioactive wastes at Elstow, Bedfordshire, are described. The project included modelling of environmental change using the TIME2 code, groundwater flow modelling, biosphere modelling and risk analysis using the SYVAC A/C code. The aims of the work were to demonstrate use of TIME2, investigate the evolution of the facility's environment and to evaluate the influence of environmental change on estimates of radiological risk. Risk analysis of several time-independent environmental system states, using data obtained from the other tasks, indicated that environmental changes significantly influence estimates of radiological risk. (author)

Design of a cryogenic test facility for evaluating the performance of interferometric components of the SPICA/SAFARI instrument

Science.gov (United States)

Veenendaal, Ian T.; Naylor, David A.; Gom, Brad G.

2014-08-01

The Japanese SPace Infrared telescope for Cosmology and Astrophysics (SPICA), a 3 m class telescope cooled to ~ 6 K, will provide extremely low thermal background far-infrared observations. An imaging Fourier transform spectrometer (SAFARI) is being developed to exploit the low background provided by SPICA. Evaluating the performance of the interferometer translation stage and key optical components requires a cryogenic test facility. In this paper we discuss the design challenges of a pulse tube cooled cryogenic test facility that is under development for this purpose. We present the design of the cryostat and preliminary results from component characterization and external optical metrology.

Air quality impacts due to construction of LWR waste management facilities

International Nuclear Information System (INIS)

1977-06-01

Air quality impacts of construction activities and induced housing growth as a result of construction activities were evaluated for four possible facilities in the LWR fuel cycle: a fuel reprocessing facility, fuel storage facility, fuel fabrication plant, and a nuclear power plant. Since the fuel reprocessing facility would require the largest labor force, the impacts of construction of that facility were evaluated in detail

Using virtual reality in the training of security staff and evaluation of physical protection barriers in nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Augusto, Silas C.; Mol, Antonio C.A.; Mol, Pedro C.; Sales, Douglas S. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil)], e-mail: silas@ien.gov.br, e-mail: mol@ien.gov.br, e-mail: pedro98@gmail.com, e-mail: dsales@ien.gov.br

2009-07-01

The physical security of facilities containing radioactive objects, an already important matter, now has a new aggravating factor: the existence of groups intending to obtain radioactive materials for the purpose of intentionally induce radioactive contamination incidents, as for example the explosion of dirty bombs in populated regions, damaging both people and environment. In this context, the physical security of such facilities must be reinforced so to reduce the possibilities of such incidents. This paper presents a adapted game engine used as a virtual reality system, enabling the modeling and simulation of scenarios of nuclear facilities containing radioactive objects. In these scenarios, the physical protection barriers, as fences and walls, are simulated along with vigilance screens. Using a computer network, several users can participate simultaneously in the simulation, being represented by avatars. Users can play the roles of both invaders and security staff. The invaders have as objective to surpass the facility's physical protection barriers to steal radioactive objects and flee. The security staff have as objective to prevent and stop the theft of radioactive objects from the facility. The system can be used to analysis simulated scenarios and train vigilance/security staff. A test scenario was already developed and used, and the preliminary tests had satisfactory results, as they enabled the evaluation of the physical protection barriers of the virtual facility, and the training of those who participated in the simulations in the functions of a security staff. (author)

Using virtual reality in the training of security staff and evaluation of physical protection barriers in nuclear facilities

International Nuclear Information System (INIS)

Augusto, Silas C.; Mol, Antonio C.A.; Mol, Pedro C.; Sales, Douglas S.

2009-01-01

The physical security of facilities containing radioactive objects, an already important matter, now has a new aggravating factor: the existence of groups intending to obtain radioactive materials for the purpose of intentionally induce radioactive contamination incidents, as for example the explosion of dirty bombs in populated regions, damaging both people and environment. In this context, the physical security of such facilities must be reinforced so to reduce the possibilities of such incidents. This paper presents a adapted game engine used as a virtual reality system, enabling the modeling and simulation of scenarios of nuclear facilities containing radioactive objects. In these scenarios, the physical protection barriers, as fences and walls, are simulated along with vigilance screens. Using a computer network, several users can participate simultaneously in the simulation, being represented by avatars. Users can play the roles of both invaders and security staff. The invaders have as objective to surpass the facility's physical protection barriers to steal radioactive objects and flee. The security staff have as objective to prevent and stop the theft of radioactive objects from the facility. The system can be used to analysis simulated scenarios and train vigilance/security staff. A test scenario was already developed and used, and the preliminary tests had satisfactory results, as they enabled the evaluation of the physical protection barriers of the virtual facility, and the training of those who participated in the simulations in the functions of a security staff. (author)

Indonesia - Green Prosperity - Grant Facility

Data.gov (United States)

Millennium Challenge Corporation — The evaluation is designed to assess the design and operations of the GP Facility, which consists of Activities 2-3 of the GP Project. It is a performance evaluation...

Evaluation of protection factor of respiratory protective equipment using indigenously developed protection factor test facility

International Nuclear Information System (INIS)

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

2018-01-01

Assigned protection factor (APF) is an indicator representing effectiveness of a respirator and it provides workplace level of respiratory protection for workers in providing protection against exposure to airborne contaminants Occupational Safety and Health Administration (OSHA) specifies 'Respirator APF' and 'Maximum Use Concentration' (MUC - a term derived using APF) shall be an integral part of Respirator Protection Standard. MUC establishes the maximum airborne concentration of a contaminant in which a respirator with a given APF may be used. The use of particulate respirators such as half face mask, full face mask and powered air purifying respirators is essential for radioactive jobs in nuclear facilities to prevent any intake of radionuclide. With this impetus, the Protection Factor Test Facility (PFTF) for testing and evaluation of respiratory protective equipment meeting relevant applicable standards was designed, fabricated and installed in Respiratory Protective Equipment Laboratory of Health Physics Division

Beneficial Re-use of Decommissioned Former Nuclear Facilities

International Nuclear Information System (INIS)

Boing, L.E.

1997-01-01

With the decision to decommission a nuclear facility, it is necessary to evaluate whether to fully demolish a facility or to re-use the facility in some capacity. This evaluation is often primarily driven by both the past mission of the site and the facility and the site's perceived future mission. In the case where the facility to be decommissioned is located within a large research or industrial complex and represents a significant resource to the site's future mission, it may be a perfect candidate to be re-used in some fashion. However, if the site is a rather remote older facility with little chance of being modified to today's standards for its re-use, the chances for its re-use will be substantially reduced. In this presentation, some specific cases of former nuclear facilities being decommissioned and re-used will be reviewed and some factors required to be considered in making this decision will be reviewed

Results of the application of the Risk Evaluation System in Radiotherapy (RESRA) in radiotherapy facilities in Mexico

International Nuclear Information System (INIS)

Paz G, A.; Godinez S, V.

2013-10-01

The present work describes the main results of the risk evaluation for some radiotherapy treatments with lineal accelerators, cobalt 60, brachytherapy of high dose rate and brachytherapy of low dose rate that are realize in Mexico. These evaluations were carried out applying the risk matrices method with the tool computer risk evaluation system in radiotherapy, accessible for the national users through internet, and developed by the Comision Nacional de Seguridad Nuclear y Salvaguardias in Mexico, in cooperation with the Forum of Ibero-American regulators. The used methodology is based on the risk matrices method that is a mathematical tool for the risk evaluation, and it was centered in the evaluation from the risk to which are exposed the patients, the occupational exposed personnel and people in general, by the mechanical faults of the treatment equipment s, bad calibrations, human errors, or any other event initiator of accidents. The events initiators of accidents are defined as those undesirable events that can produce and administration of an excessive dose or a sub-dose of the prescribed dose by the doctor, to the planned objective volume, or undesirable dose to the patient's regions or dose to occupational exposed personnel or people in general. The barriers are the actions and systems as mechanical switches, interlocks or alarms, dedicated to avoid that these accidents take place. The evaluation analysis of the risk developed by the members of the Forum for radiotherapy facilities together with the software RESRA has demonstrated to be useful in the prevention of many possible accidents that have happened in the past in other facilities and can avoid many others in the future. (Author)

Facility effluent monitoring plan for the 300 Area Fuels Fabrication Facility

International Nuclear Information System (INIS)

Nickels, J.M.; Brendel, D.F.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring system by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The Fuel Fabrication Facility in the Hanford 300 Area supported the production reactors from the 1940's until they were shut down in 1987. Prior to 1987 the Fuel Fabrication Facility released both airborne and liquid radioactive effluents. In January 1987 the emission of airborne radioactive effluents ceased with the shutdown of the fuels facility. The release of liquid radioactive effluents have continued although decreasing significantly from 1987 to 1990

Evaluation of environmental-control technologies for commercial nuclear fuel-conversion (UF6) facilities

International Nuclear Information System (INIS)

Perkins, B.L.

1982-10-01

At present in the United States, there are two commercial conversion facilities. These facilities process uranium concentrate into UF 6 for shipment to the enrichment facilities. One conversion facility uses a dry hydrofluor process, whereas the other facility uses a process known as the wet solvent extraction-fluorination process. Because of the different processes used in the two plants, waste characteristics, quantities, and treatment practices differ at each facility. Wastes and effluent streams contain impurities found in the concentrate (such as uranium daughters, vanadium, molybdenum, selenium, arsenic, and ammonia) and process chemicals used in the circuit (including fluorine, nitrogen, and hydrogen), as well as small quantities of uranium. Studies of suitable disposal options for the solid wastes and sludges generated at the facilities and the long-term effects of emissions to the ambient environment are needed. 30 figures, 34 tables

Transonic Experimental Research Facility

Data.gov (United States)

Federal Laboratory Consortium — The Transonic Experimental Research Facility evaluates aerodynamics and fluid dynamics of projectiles, smart munitions systems, and sub-munitions dispensing systems;...

The Upgrade Programme for the Structural Biology beamlines at the European Synchrotron Radiation Facility – High throughput sample evaluation and automation

International Nuclear Information System (INIS)

Theveneau, P; Baker, R; Barrett, R; Beteva, A; Bowler, M W; Carpentier, P; Caserotto, H; Sanctis, D de; Dobias, F; Flot, D; Guijarro, M; Giraud, T; Lentini, M; Leonard, G A; Mattenet, M; McSweeney, S M; Morawe, C; Nurizzo, D; McCarthy, A A; Nanao, M

2013-01-01

Automation and advances in technology are the key elements in addressing the steadily increasing complexity of Macromolecular Crystallography (MX) experiments. Much of this complexity is due to the inter-and intra-crystal heterogeneity in diffraction quality often observed for crystals of multi-component macromolecular assemblies or membrane proteins. Such heterogeneity makes high-throughput sample evaluation an important and necessary tool for increasing the chances of a successful structure determination. The introduction at the ESRF of automatic sample changers in 2005 dramatically increased the number of samples that were tested for diffraction quality. This 'first generation' of automation, coupled with advances in software aimed at optimising data collection strategies in MX, resulted in a three-fold increase in the number of crystal structures elucidated per year using data collected at the ESRF. In addition, sample evaluation can be further complemented using small angle scattering experiments on the newly constructed bioSAXS facility on BM29 and the micro-spectroscopy facility (ID29S). The construction of a second generation of automated facilities on the MASSIF (Massively Automated Sample Screening Integrated Facility) beam lines will build on these advances and should provide a paradigm shift in how MX experiments are carried out which will benefit the entire Structural Biology community.

Evaluation of environmental control technologies for commercial uranium nuclear fuel fabrication facilities

International Nuclear Information System (INIS)

Perkins, B.L.

1983-01-01

At present in the United States, there are seven commercial light-water reactor uranium fuel fabrication facilities. Effluent wastes from these facilities include uranium, nitrogen, fluorine, and organic-containing compounds. These effluents may be either discharged to the ambient environment, treated and recycled internally, stored or disposed of on-site, sent off-site for treatment and/or recovery, or sent off-site for disposal (including disposal in low-level waste burial sites). Quantities of waste generated and treatment techniques vary greatly depending on the facility and circuits used internally at the facility, though in general all the fluorine entering the facility as UF 6 is discharged as waste. Further studies to determine techniques and procedures that might minimize dose (ALARA) and to give data on possible long-term effects of effluent discharge and waste disposal are needed

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

International Nuclear Information System (INIS)

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C.

1995-01-01

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

Energy Technology Data Exchange (ETDEWEB)

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C. [Oak Ridge National Lab., TN (United States). Technical Programs and Services; Brock, W.R.; Denton, D.R. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

1995-12-31

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation.

Lustre Distributed Name Space (DNE) Evaluation at the Oak Ridge Leadership Computing Facility (OLCF)

Energy Technology Data Exchange (ETDEWEB)

Simmons, James S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Center for Computational Sciences; Leverman, Dustin B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Center for Computational Sciences; Hanley, Jesse A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Center for Computational Sciences; Oral, Sarp [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Center for Computational Sciences

2016-08-22

This document describes the Lustre Distributed Name Space (DNE) evaluation carried at the Oak Ridge Leadership Computing Facility (OLCF) between 2014 and 2015. DNE is a development project funded by the OpenSFS, to improve Lustre metadata performance and scalability. The development effort has been split into two parts, the first part (DNE P1) providing support for remote directories over remote Lustre Metadata Server (MDS) nodes and Metadata Target (MDT) devices, while the second phase (DNE P2) addressed split directories over multiple remote MDS nodes and MDT devices. The OLCF have been actively evaluating the performance, reliability, and the functionality of both DNE phases. For these tests, internal OLCF testbed were used. Results are promising and OLCF is planning on a full DNE deployment by mid-2016 timeframe on production systems.

Evaluation of energy response of neutron rem monitor applied to high-energy accelerator facilities

Energy Technology Data Exchange (ETDEWEB)

Nakane, Yoshihiro; Harada, Yasunori; Sakamoto, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2003-03-01

A neutron rem monitor was newly developed for applying to the high-intensity proton accelerator facility (J-PARC) that is under construction as a joint project between the Japan Atomic Energy Research Institute and the High Energy Accelerator Research Organization. To measure the dose rate accurately for wide energy range of neutrons from thermal to high-energy region, the neutron rem monitor was fabricated by adding a lead breeder layer to a conventional neutron rem monitor. The energy response of the monitor was evaluated by using neutron transport calculations for the energy range from thermal to 150 MeV. For verifying the results, the response was measured at neutron fields for the energy range from thermal to 65 MeV. The comparisons between the energy response and dose conversion coefficients show that the newly developed neutron rem monitor has a good performance in energy response up to 150 MeV, suggesting that the present study offered prospects of a practical fabrication of the rem monitor applicable to the high intensity proton accelerator facility. (author)

Research on consequence analysis method for probabilistic safety assessment of nuclear fuel facilities (5). Evaluation method and trial evaluation of criticality accident

International Nuclear Information System (INIS)

Yamane, Yuichi; Abe, Hitoshi; Nakajima, Ken; Hayashi, Yoshiaki; Arisawa, Jun; Hayami, Satoru

2010-01-01

A special committee of 'Research on the analysis methods for accident consequence of nuclear fuel facilities (NFFs)' was organized by the Atomic Energy Society of Japan (AESJ) under the entrustment of Japan Atomic Energy Agency (JAEA). The committee aims to research on the state-of-the-art consequence analysis method for the Probabilistic Safety Assessment (PSA) of NFFs, such as fuel reprocessing and fuel fabrication facilities. The objectives of this research are to obtain information useful for establishing quantitative performance objectives and to demonstrate risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NFFs. The research activities of the committee were mainly focused on the consequence analysis method for postulated accidents with potentially large consequences in NFFs, e.g., events of criticality, spill of molten glass, hydrogen explosion, boiling of radioactive solution and fire (including the rapid decomposition of TBP complexes), resulting in the release of radioactive materials to the environment. The results of the research were summarized in a series of six reports, which consist of a review report and five technical ones. In this report, the evaluation methods of criticality accident, such as simplified methods, one-point reactor kinetics codes and quasi-static method, were investigated and their features were summarized to provide information useful for the safety evaluation of NFFs. In addition, several trial evaluations were performed for a hypothetical scenario of criticality accident using the investigated methods, and their results were compared. The release fraction of volatile fission products in a criticality accident was also investigated. (author)

Methodology for analyzing risk at nuclear facilities

International Nuclear Information System (INIS)

Yoo, Hosik; Lee, Nayoung; Ham, Taekyu; Seo, Janghoon

2015-01-01

Highlights: • A new methodology for evaluating the risk at nuclear facilities was developed. • Five measures reflecting all factors that should be concerned to assess risk were developed. • The attributes on NMAC and nuclear security culture are included as attributes for analyzing. • The newly developed methodology can be used to evaluate risk of both existing facility and future nuclear system. - Abstract: A methodology for evaluating risks at nuclear facilities is developed in this work. A series of measures is drawn from the analysis of factors that determine risks. Five measures are created to evaluate risks at nuclear facilities. These include the legal and institutional framework, material control, physical protection system effectiveness, human resources, and consequences. Evaluation attributes are developed for each measure and specific values are given in order to calculate the risk value quantitatively. Questionnaires are drawn up on whether or not a state has properly established a legal and regulatory framework (based on international standards). These questionnaires can be a useful measure for comparing the status of the physical protection regime between two countries. Analyzing an insider threat is not an easy task and no methodology has been developed for this purpose. In this study, attributes that could quantitatively evaluate an insider threat, in the case of an unauthorized removal of nuclear materials, are developed by adopting the Nuclear Material Accounting & Control (NMAC) system. The effectiveness of a physical protection system, P(E), could be analyzed by calculating the probability of interruption, P(I), and the probability of neutralization, P(N). In this study, the Tool for Evaluating Security System (TESS) code developed by KINAC is used to calculate P(I) and P(N). Consequence is an important measure used to analyze risks at nuclear facilities. This measure comprises radiological, economic, and social damage. Social and

Facility to evaluate street lightning solutionsin a realistic urban setting

DEFF Research Database (Denmark)

Andersen, Jakob Munkgaard; Thorseth, Anders; Dam-Hansen, Carsten

2015-01-01

This paper describes a new large scale outdoor testing facility for street lighting solutions, that has been establish in Denmark for both research and demonstration purposes. The facility is fitted with lamp posts with an array of sensors and connections to allow for monitoring and control...... of lighting solutions under test. Initial data suggests a 75% reduction in energy usage from use of LED luminaries combined with traffic monitoring systems could be achievable....

Evaluating and optimizing horticultural regimes in space plant growth facilities

Science.gov (United States)

Berkovich, Y.; Chetirkin, R.; Wheeler, R.; Sager, J.

In designing innovative Space Plant Growth Facilities (SPGF) for long duration space f ightl various limitations must be addressed including onboard resources: volume, energy consumption, heat transfer and crew labor expenditure. The required accuracy in evaluating onboard resources by using the equivalent mass methodology and applying it to the design of such facilities is not precise. This is due to the uncertainty of the structure and not completely understanding of the properties of all associated hardware, including the technology in these systems. We present a simple criteria of optimization for horticultural regimes in SPGF: Qmax = max [M · (EBI) 2 / (V · E · T) ], where M is the crop harvest in terms of total dry biomass in the plant growth system; EBI is the edible biomass index (harvest index), V is a volume occupied by the crop; E is the crop light energy supply during growth; T is the crop growth duration. The criterion reflects directly on the consumption of onboard resources for crop production. We analyzed the efficiency of plant crops and the environmental parameters by examining the criteria for 15 salad and 12 wheat crops from the data in the ALS database at Kennedy Space Center. Some following conclusion have been established: 1. The technology involved in growing salad crops on a cylindrical type surface provides a more meaningful Q-criterion; 2. Wheat crops were less efficient than leafy greens (salad crops) when examining resource utilization; 3. By increasing light intensity of the crop the efficiency of the resource utilization could decrease. Using the existing databases and Q-criteria we have found that the criteria can be used in optimizing design and horticultural regimes in the SPGF.

Grande Ronde Endemic Spring Chinook Salmon Supplementation Program: Facility Operation and Maintenance and Monitoring and Evaluation, 2000 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Boe, Stephen J.; Lofy, Peter T. (Confederated Tribes of the Umatilla Indian Reservation, Pendleton, OR)

2003-03-01

This is the third annual report of a multi-year project to operate adult collection and juvenile acclimation facilities on Catherine Creek and the upper Grande Ronde River for Snake River spring chinook salmon. These two streams have historically supported populations that provided significant tribal and non-tribal fisheries. Supplementation using conventional and captive broodstock techniques is being used to restore fisheries in these streams. Statement of Work Objectives for 2000: (1) Participate in implementation of the comprehensive multiyear operations plan for the Grande Ronde Endemic Spring Chinook Supplementation Program (GRESCP). (2) Plan for recovery of endemic summer steelhead populations in Catherine Creek and the upper Grande Ronde River. (3) Ensure proper construction and trial operation of semi-permanent adult and juvenile facilities for use in 2000. (4) Collect summer steelhead. (5) Collect adult endemic spring chinook salmon broodstock. (6) Acclimate juvenile spring chinook salmon prior to release into the upper Grande Ronde River and Catherine Creek. (7) Document accomplishments and needs to permitters, comanagers, and funding agency. (8) Communicate project results to the scientific community. (9) Plan detailed GRESCP Monitoring and Evaluation for future years. (10) Monitor adult population abundance and characteristics of Grande Ronde River spring chinook salmon populations and incidentally-caught summer steelhead and bull trout. (11) Monitor condition, movement, and mortality of spring chinook salmon acclimated at remote facilities. (12) Monitor water quality at facilities. (13) Participate in Monitoring & Evaluation of the captive brood component of the Program to document contribution to the Program.

Universal Drive Train Facility

Data.gov (United States)

Federal Laboratory Consortium — This vehicle drive train research facility is capable of evaluating helicopter and ground vehicle power transmission technologies in a system level environment. The...

Methods for developing seismic and extreme wind-hazard models for evaluating critical structures and equipment at US Department of Energy facilities and commercial plutonium facilities in the United States

International Nuclear Information System (INIS)

Coats, D.W.; Murray, R.C.; Bernreuter, D.L.

1981-01-01

Lawrence Livermore National Laboratory (LLNL) is developing seismic and wind hazard models for the US Department of Energy (DOE). The work is part of a three-phase effort to establish building design criteria developed with a uniform methodology for seismic and wind hazards at the various DOE sites throughout the United States. In Phase 1, LLNL gathered information on the sites and their critical facilities, including nuclear reactors, fuel-reprocessing plants, high-level waste storage and treatment facilities, and special nuclear material facilities. Phase 2 - development of seismic and wind hazard models - is discussed in this paper, which summarizes the methodologies used by seismic and extreme-wind experts and gives sample hazard curves for the first sites to be modeled. These hazard models express the annual probability that the site will experience an earthquake (or windspeed) greater than some specified magnitude. In the final phase, the DOE will use the hazards models and LLNL-recommended uniform design criteria to evaluate critical facilities. The methodology presented in this paper also was used for a related LLNL study - involving the seismic assessment of six commercial plutonium fabrication plants licensed by the US Nuclear Regulatory Commission (NRC). Details and results of this reassessment are documented in reference

Radiation shielding and dose rate evaluation at the interim storage facility for spent fuel from Cernavoda NPP

International Nuclear Information System (INIS)

Stanciu, Marcela; Mateescu, Silvia; Pantazi, Doina; Penescu, Maria

2000-01-01

At present studies necessary to license the Interim Storage Facility for the Spent Fuel (CANDU type) from Cernavoda NPP are developed in our country.The spent fuel from Cernavoda NPP is discharged into Spent Fuel Bay in Service Building of the plant, where it remains several years for cooling. After this period, the bundles of spent fuel are to be transferred to the Interim Storage Facility.The dry interim storage solution seems to be the most appropriate variant for Cernavoda NPP.The design of the Spent Fuel Interim Storage Facility must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility achievement. In this paper we intend to present the calculation of radiation shielding at the spent fuel interim storage facility for two technical solutions: - Concrete Monolithic Module and Concrete Storage Cask. In order to quantify the fuel composition after irradiation, the isotope generation and depletion code ORIGEN 2.1 has been used, taking into account a cooling time of 7 years and 9 years, respectively, for these two variants. The shielding calculations have been performed using the computer codes QAD-5K and MICROSHIELD-4. The evaluations refer only to gamma radiation because the resulting neutron source (from (α,n) reactions and spontaneous fission) is insignificant as compared to the gamma source. The final results consist in the minimum thickness of the shielding and the corresponding external dose rates, ensuring a design average dose rate based on national and international regulations. (authors)

Survey of computer codes applicable to waste facility performance evaluations

International Nuclear Information System (INIS)

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

1988-01-01

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

Engine Test Facility (ETF)

Data.gov (United States)

Federal Laboratory Consortium — The Air Force Arnold Engineering Development Center's Engine Test Facility (ETF) test cells are used for development and evaluation testing of propulsion systems for...

Safety evaluation of the loss of fluid test facility project No. 394

International Nuclear Information System (INIS)

1975-05-01

Assessment of the safety of the LOFT facility and subsequent recommendations have been based on a comparison of the LOFT facility to requirements for commercial power reactors. In this comparison, the many unique features of the LOFT facility were considered including the low power level, the limited operational use as a test reactor, and the remoteness of the site. Based on this assessment, it is concluded, that while the likelihood of an accidental release of fission products may be greater than for a commercial power reactor, the consequences of such a release are reduced by the lower fission product inventory, the remoteness of the site and the capability of evacuating the Idaho National Engineering Laboratory (INEL) and adjacent areas. There is reasonable assurance that the public health and safety will not be endangered due to operation of this facility, specifically: The INEL site is acceptable with respect to location, land use, population distribution, controlled access, hydrology, meteorology, geology and seismology. Sufficient engineered safety features have been included to assure that the potential offsite doses are well within 10 CFR Part 100 guidelines. The LOFT facility has been designed in general accordance with standards, guides and codes which are comparable to those applied to commercial power reactors and any exceptions to these have been based on the unique features of the LOFT facility. Certain matters including the final safety analyses based on detailed component designs, Technical Specifications, LOCE controls and detailed program plan have not been reviewed but we assume will properly be resolved by ERDA, which has the ultimate responsibility for the safety of this facility. Changes to the facility design or program plan such as removal of the fueled Mobile Test Assembly or blowdowns to the containment vessel also will require additional analyses and review. (U.S.)

Safety guide data on radiation shielding in a reprocessing facility

International Nuclear Information System (INIS)

Sekiguchi, Noboru; Naito, Yoshitaka

1986-04-01

In a reprocessing facility, various radiation sources are handled and have many geometrical conditions. To aim drawing up a safety guidebook on radiation shielding in order to evaluate shielding safety in a reprocessing facility with high reliability and reasonableness, JAERI trusted investigation on safety evaluation techniques of radiation shielding in a reprocessing facility to Nuclear Safety Research Association. This report is the collection of investigation results, and describes concept of shielding safety design principle, radiation sources in reprocessing facility and estimation of its strength, techniques of shielding calculations, and definite examples of shielding calculation in reprocessing facility. (author)

EVA Training and Development Facilities

Science.gov (United States)

Cupples, Scott

2016-01-01

Overview: Vast majority of US EVA (ExtraVehicular Activity) training and EVA hardware development occurs at JSC; EVA training facilities used to develop and refine procedures and improve skills; EVA hardware development facilities test hardware to evaluate performance and certify requirement compliance; Environmental chambers enable testing of hardware from as large as suits to as small as individual components in thermal vacuum conditions.

Laser Guidance Analysis Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility, which provides for real time, closed loop evaluation of semi-active laser guidance hardware, has and continues to be instrumental in the development...

Evaluation of skyshine dose due to gamma-rays from a cobalt-60 irradiation facility

International Nuclear Information System (INIS)

Kanazawa, Tamotsu; Okamoto, Shinichi; Ohnishi, Tokuhiro; Tsujii, Yukio

1991-01-01

We attempted to evaluate skyshine dose due to gamma-rays from a cobalt-60 irradiation facility. As the first step, the results of measurements and calculations were compared of the skyshine dose due to gamma-rays from the cobalt-60 source of 1.45 PBq set in the No.4 irradiation room of our laboratory. Distances of measuring points from the cobalt source were in the range from 17 m to about 100 m in the site of our office. Calculation was carried out with simplified single scattering method. The calculated values of the skyshine dose were higher than the measured values. For more precise evaluation of the skyshine dose, the following factors are to be considered; the dose rate distribution on the roof above the source and the attenuation of gamma-rays by air. (author)

Creation of a new-generation research nuclear facility

International Nuclear Information System (INIS)

Girchenko, A.A.; Matyushin, A.P.; Kudryavtsev, E.M.; Skopin, V.P.; Shchepelev, R.M.

2013-01-01

The SO-2M research nuclear facility operated on the industrial area of the institute. The facility is now removed from service. In view of this circumstance, it is proposed to restore the facility at the new qualitative level, i.e., to create a new-generation research nuclear facility with a very high safety level consisting of a subcritical bench and a proton accelerator (electronuclear facility). Competitive advantages and design features have been discussed and the productive capacity of the research nuclear facility under development has been evaluated [ru

Strategic facility planning improves capital decision making.

Science.gov (United States)

Reeve, J R

2001-03-01

A large, Midwestern IDS undertook a strategic facility-planning process to evaluate its facility portfolio and determine how best to allocate future investments in facility development. The IDS assembled a facility-planning team, which initiated the planning process with a market analysis to determine future market demands and identify service areas that warranted facility expansion. The team then analyzed each of the IDS's facilities from the perspective of uniform capacity measurements, highest and best use compared with needs, building condition and investment-worthiness, and facility growth and site development opportunities. Based on results of the analysis, the strategy adopted entailed, in part, shifting some space from inpatient care to ambulatory care services and demolishing and replacing the 11 percent of facilities deemed to be in the worst condition.

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

Energy Technology Data Exchange (ETDEWEB)

DAVIS, W.E.

2000-03-08

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years.

Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

DAVIS, W.E.

2000-01-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years

Facility effluent monitoring plan for the tank farms facilities

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

Facility Effluent Monitoring Plan for the 2724-W Protective Equipment Decontamination Facility

International Nuclear Information System (INIS)

Carter, G.J.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updates as a minimum every three years

Proceeding of 31st domestic symposium on failure events and integrity evaluation of nuclear power generation facilities

International Nuclear Information System (INIS)

2003-07-01

As the 31st domestic symposium of Atomic Energy Research Committee, the Japan Welding Engineering Society, the symposium was held titled as 'Damage events and integrity evaluations of nuclear power facilities'. Six speakers gave lectures titled as 'Damages of structural materials in the LWR plants and their measures', 'Inspection and integrity evaluation method of SCC in the BWR plants', 'Measures with chloride SCC of piping', 'High cycle fatigue damage events of small diameter pipes and their measures', 'Management of SCC in in-core instrumentation thimbles' and 'Japanese lost ten years and American and other leaps'. (T. Tanaka)

Calculation of parameters for inspection planning and evaluation: low enriched uranium conversion and fuel fabrication facilities

International Nuclear Information System (INIS)

Reardon, P.T.; Mullen, M.F.; Harms, N.L.

1981-02-01

As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities at low-enriched uranium (LEU) conversion and fuel fabrication facilities. This report presents the results and conclusions of those analyses. Implementation of IAEA safeguards at LEU conversion and fuel fabrication facilities must take into account a variety of practical problems and constraints. One of the key concerns is the problem of flow verification, especially product verification. The objective of this report is to help put the problem of flow verification in perspective by presenting the results of some specific calculations of inspection effort and probability of detection for various product measurement strategies. In order to provide quantitative information about the advantages and disadvantages of the various strategies, eight specific cases were examined

Maintenance facilities, stores and records

International Nuclear Information System (INIS)

Fischer, K.

1986-01-01

The topics of this report are: on-site or off-site facilities. On-site facilities: workshops and special facilities. KWU's Service Center, a typical off-site supporting facility in Germany, capabilities and activities. A pool for special tools and equipment: devices for plugging of nozzles, for handling of RPU-studs and RPU internals etc. Devices for and management of radiological protection on-site for typical outage work. Spare parts and spare part management on site, typical examples. KWU's centralized spare part pools for components, generators and turbines etc. A computerized system for spare parts storage and maintenance planning. A system for mutual exchange of operational experience with respect to maintenance and repair activities. Systematic evaluation of failures and statistical results. (orig./GL)

Guidelines for the evaluation and assessment of the sustainable use of resources and of wastes management at healthcare facilities.

Science.gov (United States)

Townend, William K; Cheeseman, Christopher R

2005-10-01

This paper presents guidelines that can be used by managers of healthcare facilities to evaluate and assess the quality of resources and waste management at their facilities and enabling the principles of sustainable development to be addressed. The guidelines include the following key aspects which need to be considered when completing an assessment. They are: (a) general management; (b) social issues; (c) health and safety; (d) energy and water use; (e) purchasing and supply; (f) waste management (responsibility, segregation, storage and packaging); (g) waste transport; (h) recycling and re-use; (i) waste treatment; and (j) final disposal. They identify actions required to achieve a higher level of performance which can readily be applied to any healthcare facility, irrespective of the local level of social, economic and environmental development. The guidelines are presented, and the characteristics of facilities associated with sustainable (level 4) and unsustainable (level 0) healthcare resource and wastes management are outlined. They have been used to assess a major London hospital, and this highlighted a number of deficiencies in current practice, including a lack of control over purchasing and supply, and very low rates of segregation of municipal solid waste from hazardous healthcare waste.

Evaluation of bulk shield for the JHP facilities

International Nuclear Information System (INIS)

Uwamino, Yoshitomo; Shibata, Tokushi

1991-01-01

In the Japanese Hadron Project (JHP), a 1-GeV 200-μA proton beam will be handled, and the radiation shield of the facility will be very massive concrete and iron lump. Since the constructing cost is strongly affected by the shielding design, the design must be severely performed. The neutron yield in thin targets and a copper beam dump was calculated by the HETC-KFA-2 Monte Carlo code. For the evaluation of the calculational accuracy, the calculational results were compared with the experimental data by Cierjacks and Raupp. The calculated result of heavy element agreed well with the experiment at a low energy region, E n n >100 MeV) of 90 deg close to the calculated one of about 60 deg in the absolute value. The high energy neutron transport in a 5-m-thick iron slab and in an 8-m-thick ordinary concrete slab was calculated with the HETC code and also with the discrete ordinates transport code, ANISN. In the ANISN calculation, the DLC-87/HILO and the DLC-128/LAHIMAC group cross sections were used. The ANISN calculation with the LAHIMAC cross sections gave strong underestimation compared with the HETC calculation. The difference of the shielding lengths calculated by the HETC code and by the ANISN code used with the HILO cross sections was smaller than 6% for the both iron and concrete cases. (author)

Performance assessment of the proposed Monitored Retrievable Storage Facility

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.; Winter, C.

1986-02-01

Pacific Northwest laboratory (PNL) has completed a performance evaluation of the proposed monitored retrievable storage (MRS) facility. This study was undertaken as part of the Department of Energy MRS Program at PNL. The objective of the performance evaluation was to determine whether the conceptual MRS facility would be able to process spent fuel at the specified design rate of 3600 metric tons of uranium (MTU) per year. The performance of the proposed facility was assessed using the computer model COMPACT (Computer Optimization of Processing and Cask Transport) to simulate facility operations. The COMPACT model consisted of three application models each of which addressed a different aspect of the facility's operation: MRS/waste transportation interface; cask handling capability; and disassembly/consolidation (hot cell) operations. Our conclusions, based on the assessment of design criteria for the proposed facility, are as follows: Facilities and equipment throughout the facility have capability beyond the 3600 MTU/y design requirement. This added capability provides a reserve to compensate for unexpected perturbations in shipping or handling of the spent fuel. Calculations indicate that the facility's maximum maintainable processing capability is approximately 4800 MTU/y

Shielding structure analysis for LSDS facility

Energy Technology Data Exchange (ETDEWEB)

Choi, Hong Yeop; Kim, Jeong Dong; Lee, Yong Deok; Kim, Ho Dong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The nuclear material (Pyro, Spent nuclear fuel) itself and the target material to generate neutrons is the LSDS system for isotopic fissile assay release of high intensity neutron and gamma rays. This research was performed to shield from various strong radiation. A shielding evaluation was carried out with a facilities model of LSDS system. The MCNPX 2.5 code was used and a shielding evaluation was performed for the shielding structure and location. The radiation dose based on the hole structure and location of the wall was evaluated. The shielding evaluation was performed to satisfy the safety standard for a normal person (1 μSv/h) and to use enough interior space. The MCNPX2.5 code was used and a dose evaluation was performed for the location of the shielding material, shielding structure, and hole structure. The evaluation result differs according to the shielding material location. The dose rate was small when the shielding material was positioned at the center. The dose evaluation result regarding the location of the shielding material was applied to the facility and the shielding thickness was determined (In 50 cm + Borax 5 cm + Out 45cm). In the existing hole structure, the radiation leak is higher than the standard. A hole structure model to prevent leakage of radiation was proposed. The general public dose limit was satisfied when using the concrete reinforcement and a zigzag structure. The shielding result will be of help to the facility shielding optimization.

Shielding structure analysis for LSDS facility

International Nuclear Information System (INIS)

Choi, Hong Yeop; Kim, Jeong Dong; Lee, Yong Deok; Kim, Ho Dong

2014-01-01

The nuclear material (Pyro, Spent nuclear fuel) itself and the target material to generate neutrons is the LSDS system for isotopic fissile assay release of high intensity neutron and gamma rays. This research was performed to shield from various strong radiation. A shielding evaluation was carried out with a facilities model of LSDS system. The MCNPX 2.5 code was used and a shielding evaluation was performed for the shielding structure and location. The radiation dose based on the hole structure and location of the wall was evaluated. The shielding evaluation was performed to satisfy the safety standard for a normal person (1 μSv/h) and to use enough interior space. The MCNPX2.5 code was used and a dose evaluation was performed for the location of the shielding material, shielding structure, and hole structure. The evaluation result differs according to the shielding material location. The dose rate was small when the shielding material was positioned at the center. The dose evaluation result regarding the location of the shielding material was applied to the facility and the shielding thickness was determined (In 50 cm + Borax 5 cm + Out 45cm). In the existing hole structure, the radiation leak is higher than the standard. A hole structure model to prevent leakage of radiation was proposed. The general public dose limit was satisfied when using the concrete reinforcement and a zigzag structure. The shielding result will be of help to the facility shielding optimization

Evaluation of physical facilities and processing operations of major ...

African Journals Online (AJOL)

ADEYEYE

abattoirs were as a result of failure to enforce the use of standard facilities in carrying out abattoir operations and general maintenance ... incinerator, chemical treatment and disposal. Sub- .... Veterinary laboratory .... sustainable food security.

Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1

International Nuclear Information System (INIS)

Lewis, C.J.

1995-10-01

A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years

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

The application of SQUG to non-reactor facilities

International Nuclear Information System (INIS)

Hoskins, R.S.

1993-01-01

DOE Order 6430.1A mandates that facilities be designed and constructed to withstand Natural Phenomena Hazards in accordance with their hazard level. DOE has a program in progress to evaluate and then upgrade many of their existing medium and high hazard facilities where release of hazardous materials to the environment is a concern. This paper addresses a useful methodology which has been applied by SRS to evaluate and qualify equipment to withstand the ravenousness of earthquakes. The Seismic Qualification Utility Group was formed by a group of Electric Power Utilities whose Nuclear Power Plants predated the 10CFR50 Environmental design requirements to develop a methodology to evaluate and upgrade their operating plants against seismic events in answer to NRC generic letter USI-A46. SRS participated in this organization, since it operated reactors designed and constructed in the 1950's, and the application of the SQUG methodology was obvious. Nuclear Material Processing and Handling (NMPH) facilities utilize equipment similar to the nuclear industry, in fact, to industry in general. Consequently, it made sense to apply SQUG methodology to evaluate and qualify equipment in NMPH facilities against earthquakes. In order to utilize SQUG methodology, some changes are required since the goal of safe shutdown of a NMPH facility differs from a nuclear reactor, consequently, the generation of a Safe Shutdown Equipment List is modified by the requirements of each particular facility. Once the Safety Class Equipment List is developed denoting the qualification requirement for each piece of equipment, the SQUG walk downs can be performed as they are in commercial nuclear plants. SQUG methodology offers a cost effective approach for the seismic qualification of equipment at existing DOE NMPH facilities. SQUG cannot be applied to new or unique equipment since the experience database doesn't contain the needed information

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.

Earthquake damage to underground facilities and earthquake related displacement fields

International Nuclear Information System (INIS)

Pratt, H.R.; Stephenson, D.E.; Zandt, G.; Bouchon, M.; Hustrulid, W.A.

1982-01-01

The potential seismic risk for an underground facility is considered in the evaluation of its location and design. The possible damage resulting from either large-scale displacements or high accelerations should be considered in evaluating potential sites of underground facilities. Scattered through the available literature are statements to the effect that below a few hundred meters shaking and damage in mines is less than at the surface; however, data for decreased damage underground have not been completely reported or explained. In order to assess the seismic risk for an underground facility, a data base was established and analyzed to evaluate the potential for seismic disturbance. Substantial damage to underground facilities is usually the result of displacements primarily along pre-existing faults and fractures, or at the surface entrance to these facilities. Evidence of this comes from both earthquakes as a function of depth is important in the evaluation of the hazard to underground facilities. To evaluate potential displacements due to seismic effects of block motions along pre-existing or induced fractures, the displacement fields surrounding two types of faults were investigated. Analytical models were used to determine relative displacements of shafts and near-surface displacement of large rock masses. Numerical methods were used to determine the displacement fields associated with pure strike-slip and vertical normal faults. Results are presented as displacements for various fault lengths as a function of depth and distance. This provides input to determine potential displacements in terms of depth and distance for underground facilities, important for assessing potential sites and design parameters

Process Evaluation of a Quality Improvement Project to Decrease Hospital Readmissions From Skilled Nursing Facilities.

Science.gov (United States)

Meehan, Thomas P; Qazi, Daniel J; Van Hoof, Thomas J; Ho, Shih-Yieh; Eckenrode, Sheila; Spenard, Ann; Pandolfi, Michelle; Johnson, Florence; Quetti, Deborah

2015-08-01

To describe and evaluate the impact of quality improvement (QI) support provided to skilled nursing facilities (SNFs) by a Quality Improvement Organization (QIO). Retrospective, mixed-method, process evaluation of a QI project intended to decrease preventable hospital readmissions from SNFs. Five SNFs in Connecticut. SNF Administrators, Directors of Nursing, Assistant Directors of Nursing, Admissions Coordinators, Registered Nurses, Certified Nursing Assistants, Receptionists, QIO Quality Improvement Consultant. QIO staff provided training and technical assistance to SNF administrative and clinical staff to establish or enhance QI infrastructure and implement an established set of QI tools [Interventions to Reduce Acute Care Transfers (INTERACT) tools]. Baseline SNF demographic, staffing, and hospital readmission data; baseline and follow-up SNF QI structure (QI Committee), processes (general and use of INTERACT tools), and outcome (30-day all-cause hospital readmission rates); details of QIO-provided training and technical assistance; QIO-perceived barriers to quality improvement; SNF leadership-perceived barriers, accomplishments, and suggestions for improvement of QIO support. Success occurred in establishing QI Committees and targeting preventable hospital readmissions, as well as implementing INTERACT tools in all SNFs; however, hospital readmission rates decreased in only 2 facilities. QIO staff and SNF leaders noted the ongoing challenge of engaging already busy SNF staff and leadership in QI activities. SNF leaders reported that they appreciated the training and technical assistance that their institutions received, although most noted that additional support was needed to bring about improvement in readmission rates. This process evaluation documented mixed clinical results but successfully identified opportunities to improve recruitment of and provision of technical support to participating SNFs. Recommendations are offered for others who wish to conduct

Social-demographic profile and dose evaluation of the radiopharmaceutical facility workers

Energy Technology Data Exchange (ETDEWEB)

Sanches, Matias P.; Carneiro, Janete C. Gaburo; Sordi, Gian Maria A.A. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: msanches@ipen.br

2009-07-01

The main aims of this work are to identify the social-demographic profile of the workers based on stratification variables such as gender, age, and tasks performed by the workers, and to evaluate the annual collective doses of workers with potential risk of ionizing radiation exposure at the workplace during the years 2004 to 2008. In this context, the knowledge of the workforce composition in the facility responsible for the radioisotope production and its distribution was used. The individual monitoring programme has been carried out by individual dosimeters, TLDs, and internal contamination monitoring (in vivo method). The reported doses, in the period studied, suggest that the external exposure was the main source of occupational exposure in radioisotope production and distribution areas. The internal exposure was not included in the doses estimated, because it was negligible. This study has an important exploratory character, in order to analyze possible correlations related to adverse health effects, aiming to provide directions for occupational epidemiology research. (author)

Social-demographic profile and dose evaluation of the radiopharmaceutical facility workers

International Nuclear Information System (INIS)

Sanches, Matias P.; Carneiro, Janete C. Gaburo; Sordi, Gian Maria A.A.

2009-01-01

The main aims of this work are to identify the social-demographic profile of the workers based on stratification variables such as gender, age, and tasks performed by the workers, and to evaluate the annual collective doses of workers with potential risk of ionizing radiation exposure at the workplace during the years 2004 to 2008. In this context, the knowledge of the workforce composition in the facility responsible for the radioisotope production and its distribution was used. The individual monitoring programme has been carried out by individual dosimeters, TLDs, and internal contamination monitoring (in vivo method). The reported doses, in the period studied, suggest that the external exposure was the main source of occupational exposure in radioisotope production and distribution areas. The internal exposure was not included in the doses estimated, because it was negligible. This study has an important exploratory character, in order to analyze possible correlations related to adverse health effects, aiming to provide directions for occupational epidemiology research. (author)

Facility effluent monitoring plan for the uranium trioxide facility

International Nuclear Information System (INIS)

Thompson, R.J.; Sontag, S.

1991-11-01

A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

Risk management study for the retired Hanford Site facilities

International Nuclear Information System (INIS)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-04-01

Risk from retired surplus facilities has always been assumed to be low at the Hanford Site as the facilities are inactive and have few potentials for causing an offsite hazardous material release. However,the fatal accident that occurred in the spring of 1992 in which an employee fell through a deteriorated roof at the 105-F Reactor Building has raised the possibility that retired facilities represent a greater risk than was originally assumed. Therefore, Westinghouse Hanford Company and the US Department of Energy management have determined that facility risk management strategies and programmatic plans should be reevaluated to assure risks are identified and appropriate corrective action plans are developed. To evaluate risk management strategies, accurate risk information about the current and projected condition of the facilities must be developed. This work procedure has been created to address the development of accurate and timely risk information. By using the evaluation results in this procedure, it will be possible to create a prioritized baseline for managing facility risk until all retired surplus facilities are demolished

RETROFITTING CONTROL FACILITIES FOR WET-WEATHER FLOW TREATMENT

Science.gov (United States)

Available technologies were evaluated to demonstrate the technical feasibility and cost effectiveness of retrofitting existing facilities to handle wet-weather flow. Cost/benefit relationships were also compared to construction of new conventional control and treatment facilities...

Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

International Nuclear Information System (INIS)

WESTRA, A.G.

1999-01-01

This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility

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

Delivering Sustainable Facilities Management in Danish Housing Estates

DEFF Research Database (Denmark)

Nielsen, Susanne Balslev; Jensen, Jesper Ole; Jensen, Per Anker

2009-01-01

Housing plays a central role in sustainable development due to large resource consumption and as transition agent towards sustainable lifestyles. The aim is to evaluate current practice of housing administration in Denmark in order to evaluate if and how sustainable facilities management is suppo......Housing plays a central role in sustainable development due to large resource consumption and as transition agent towards sustainable lifestyles. The aim is to evaluate current practice of housing administration in Denmark in order to evaluate if and how sustainable facilities management...... is supporting social, economical and environmental sustainable development. Sustainable facility management (SFM) is as an 'umbrella' for various ways of reducing flows of energy, water and waste in the daily operation of the buildings, for instance by regular monitoring the consumption, by using 'green......-setting including the ownership of the building, the organisation of daily operation, the roles and relation between stakeholders are equally important in order to utilise the monitoring as a mean for transformation towards sustainable buildings and lifestyles....

Initial tank calibration at NUCEF critical facility. 2

International Nuclear Information System (INIS)

Yanagisawa, Hiroshi

1994-07-01

Analyses on initial tank calibration data were carried out for the purpose of the nuclear material accountancy and control for critical facilities in NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility. Calibration functions to evaluate volume of nuclear material solution in accountancy tanks were determined by regression analysis on the data considering dimension and shape of the tank. The analyses on dip-tube separation (probe separation), which are necessary to evaluate solution density in the tanks, were also carried out. As a result, regression errors of volume calculated with the calibration functions were within 0.05 lit. (0.01%) at a nominal level of Pu accountancy tanks. Errors of the evaluated dip-tube separations were also small, e.g. within 0.2mm (0.11%). Therefore, it was estimated that systematic errors of bulk measurements would satisfy the target value of NUCEF critical facilities (0.3% for Pu accountancy tanks). This paper summarizes the data analysis methods, results of analysis and evaluated errors. (author)

Facile synthesis of indole-pyrimidine hybrids and evaluation of their anticancer and antimicrobial activity

Directory of Open Access Journals (Sweden)

Nikhila Gokhale

2017-11-01

Full Text Available The paper describes the facile synthesis of new N-cyclopropyl-1-methyl-1H-indole-2-carboxamide derivatives bearing substituted 2-amino pyrimidine moiety at position-3 of the indole ring. All the intermediate and title compounds were characterized adeptly by 1H NMR, 13C NMR, ESI–MS and elemental analyses. These compounds were evaluated for their in vitro anticancer activity against HeLa, HepG2 and MCF-7 cells. Three among 22 molecules, showed more than 70% growth inhibition against all three tested cancer cells. The nature of the substituent group on the pyrimidine ring (R2 affected significantly the anti-proliferative activity of the molecules. The anti-microbial evaluation of the title molecules revealed the significance of fluoro/chloro groups (R2 in enhancing their inhibition activity. Eight molecules which contain fluoro/chloro groups showed potent anti-microbial activity. In addition, the active molecules displayed negligible toxicity to benign Vero cells.

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

International Nuclear Information System (INIS)

Xu, J.; Graves, H.

1991-01-01

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

Computer Profile of School Facilities Energy Consumption.

Science.gov (United States)

Oswalt, Felix E.

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

Risk management study for the retired Hanford Site facilities: Risk management executive summary

International Nuclear Information System (INIS)

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1994-02-01

This document provides a cost-comparison evaluation for implementing certain risk-reduction measures and their effect on the overall risk of the 100 and 200 Area retired, surplus facilities. The evaluation is based on conditions that existed at the time the risk evaluation team performed facility investigations, and does not acknowledge risk-reduction measures that occurred soon after risk identification. This evaluation is one part of an overall risk management study for these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1450-km 2 Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30 km southeast of the 200 Area. This document is the first in a four volume series that comprise the risk management study for the retired, surplus facilities. Volume 2 is the risk evaluation work procedure; volume 3 provides the results for the risk evaluation; and volume 4 is the risk-reduction cost comparison

Safety Evaluation Report, related to the renewal of the operating license for the critical experiment facility of the Rensselaer Polytechnic Institute (Docket No. 50-225)

International Nuclear Information System (INIS)

1983-10-01

This Safety Evaluation Report for the application filed by the Rensselaer Polytechnic Institute (RPI) for a renewal of operating license CX-22 to continue to operate a critical experiment facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Rensselaer Polytechnic Institute and is located at a site in the city of Schenectady, New York. The staff concludes that this critical facility can continue to be operated by RPI without endangering the health and safety of the public

The safety assessment system based on virtual networked environment for evaluation on the hazards from human errors during decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Jeong, Kwan Seong; Choi, Byung Seon; Moon, Jei Kwon; Hyun, Dong Jun; Lee, Jong Hwan; Kim, Ik June; Kang, Shin Young; Choi, Jong Won; Ahn, Sang Myeon; Lee, Jung Jun; Lee, Byung Sik

2016-01-01

This paper is intended to suggest a system for evaluation on the hazards from human errors during decommissioning of nuclear facilities. The system was developed under virtual networked environment. The innovative features are real-time changing direction of workers in a scenario and real-time measuring personal exposure dose and collective exposure dose. The system will be expected to be utilized as a training tool for improving familiarization of a workplace and for preventing workers from accidents. - Highlights: • A system for evaluation on the hazards from human errors during decommissioning of nuclear facilities. • Real-time changing direction of workers in a scenario. • Real-time measuring personal exposure dose and collective exposure dose. • A tool for improving familiarization of a workplace and for preventing workers from accidents.

Economic evaluation of slurry-, sewage-sludge, and crop disinfection facility applications based on industrial accelerator and 60Co radiation source

International Nuclear Information System (INIS)

Abelovszky, L.

1979-01-01

The degree of the compliance with the requirements of slurry and sewage treatment, the range of use of radiation sterilization procedures in agriculture and food industry, the possibilities of the complex application of radiation methods and factors influencing their economic efficiency, the economic evaluation of the versatile chargeable accelerators, the fixed and semi-mobile radioisotope facilities, the economic efficiency of the multipurpose utilization, the differences in the application of accelerators and radio isotopes as to the power source applied, the penetration, the dose rates and the radiation energy focusing are discussed. The radiation facility costs are compared. Conclusions concerning the choice of the most efficient applications are given. (author)

Parameterizations of Chromospheric Condensations in dG and dMe Model Flare Atmospheres

Science.gov (United States)

Kowalski, Adam F.; Allred, Joel C.

2018-01-01

The origin of the near-ultraviolet and optical continuum radiation in flares is critical for understanding particle acceleration and impulsive heating in stellar atmospheres. Radiative-hydrodynamic (RHD) simulations in 1D have shown that high energy deposition rates from electron beams produce two flaring layers at T ∼ 104 K that develop in the chromosphere: a cooling condensation (downflowing compression) and heated non-moving (stationary) flare layers just below the condensation. These atmospheres reproduce several observed phenomena in flare spectra, such as the red-wing asymmetry of the emission lines in solar flares and a small Balmer jump ratio in M dwarf flares. The high beam flux simulations are computationally expensive in 1D, and the (human) timescales for completing NLTE models with adaptive grids in 3D will likely be unwieldy for some time to come. We have developed a prescription for predicting the approximate evolved states, continuum optical depth, and emergent continuum flux spectra of RHD model flare atmospheres. These approximate prescriptions are based on an important atmospheric parameter: the column mass ({m}{ref}) at which hydrogen becomes nearly completely ionized at the depths that are approximately in steady state with the electron beam heating. Using this new modeling approach, we find that high energy flux density (>F11) electron beams are needed to reproduce the brightest observed continuum intensity in IRIS data of the 2014 March 29 X1 solar flare, and that variation in {m}{ref} from 0.001 to 0.02 g cm‑2 reproduces most of the observed range of the optical continuum flux ratios at the peak of M dwarf flares.

Material selection for Multi-Function Waste Tank Facility tanks

International Nuclear Information System (INIS)

Carlos, W.C.

1994-01-01

This report briefly summarizes the history of the materials selection for the US Department of Energy's high-level waste carbon steel storage tanks. It also provide an evaluation of the materials for the construction of new tanks at the Multi-Function Waste Tank Facility. The evaluation included a materials matrix that summarized the critical design, fabrication, construction, and corrosion resistance requirements; assessed each requirement; and cataloged the advantages and disadvantages of each material. This evaluation is based on the mission of the Multi-Function Waste Tank Facility. On the basis of the compositions of the wastes stored in Hanford waste tanks, it is recommended that tanks for the Multi-Function Waste Tank Facility be constructed of normalized ASME SA 516, Grade 70, carbon steel

Accident analysis for aircraft crash into hazardous facilities: DOE standard

International Nuclear Information System (INIS)

1996-10-01

This standard provides the user with sufficient information to evaluate and assess the significance of aircraft crash risk on facility safety without expending excessive effort where it is not required. It establishes an approach for performing a conservative analysis of the risk posed by a release of hazardous radioactive or chemical material resulting from an aircraft crash into a facility containing significant quantities of such material. This can establish whether a facility has a significant potential for an aircraft impact and whether this has the potential for producing significant offsite or onsite consequences. General implementation guidance, screening and evaluation guidelines, and methodologies for the evaluations are included

Evaluation of case management of uncomplicated malaria in Haiti: a national health facility survey, 2012.

Science.gov (United States)

Landman, Keren Z; Jean, Samuel E; Existe, Alexandre; Akom, Eniko E; Chang, Michelle A; Lemoine, Jean Frantz; Mace, Kimberly E

2015-10-09

Malaria is a public health concern in Haiti, although there are limited data on its burden and case management. National malaria guidelines updated in 2012 recommend treatment with chloroquine and primaquine. In December 2012, a nationally-representative cross-sectional survey of health facilities (HFs) was conducted to determine malaria prevalence among febrile outpatients and malaria case management quality at baseline before scale-up of diagnostics and case management training. Among all 833 HFs nationwide, 30 were selected randomly, in proportion to total HFs per region, for 2-day evaluations. Survey teams inventoried HF material and human resources. Outpatients of all ages were screened for temperature >37.5 °C or history of fever; those without severe symptoms were consented and enrolled. Providers evaluated and treated enrolled patients according to HF standards; the survey teams documented provider-ordered diagnostic tests and treatment decisions. Facility-based test results [microscopy and malaria rapid diagnostic tests (RDTs)] were collected from HF laboratories. Blood smears for gold-standard microscopy, and dried blood spots for polymerase chain reaction (PCR) were obtained. Malaria diagnostic capacity, defined as completing a test for an enrolled patient or having adequate resources for RDTs or microscopy, was present in 11 (37 %) HFs. Among 459 outpatients screened, 257 (56 %) were febrile, of which 193 (75 %) were eligible, and 153 (80 %) were enrolled. Among 39 patients with facility-level malaria test results available on the survey day, 11 (28 %) were positive, of whom 6 (55 %) were treated with an anti-malarial. Twenty-seven (95 %) of the 28 patients testing negative were not treated with an anti-malarial. Of 114 patients without test results available, 35 (31 %) were presumptively treated for malaria. Altogether, 42 patients were treated with an anti-malarial, one (2 %) according to Haiti's 2012 guidelines. Of 140 gold-standard smears, none

Architectural style and green spaces predict older adults' evaluations of residential facilities.

Science.gov (United States)

Cerina, Veronica; Fornara, Ferdinando; Manca, Sara

2017-09-01

The purpose of this study was to analyse the effects of residential facilities' design features on older adults' psychosocial responses. Participants ( N  = 192) were over 65-year-old residents who were randomly exposed to different experimental scenarios concerning a hypothetical residential facility for older adults, using a 3 × 2 between-subjects design (i.e. home-like vs. hotel-like vs. usual-standard architectural style; presence vs. absence of green spaces). After the experimental session, participants were asked to fill in a questionnaire that measured their attitudes towards short- and long-term relocation, anticipated residential satisfaction with the facility, and feelings of broken home attachment. The results showed (1) more positive responses to "home-like" and "hotel-like" architectural styles than the usual-standard type and (2) the positive impact of green spaces on the assessment of the facilities. These design features should thus play a role in both reducing the stressful impact of leaving home and promoting beneficial patterns, hence fostering "successful ageing".

The construction of irradiated material examination facility

International Nuclear Information System (INIS)

Ro, Seung Gy; Lee, Key Soon; Herr, Young Hoi

1990-03-01

A detail design of the examination process, the hot cell facility and the annexed facility of the irradiated material examination facility (IMEF) which will be utilized to examine and evaluate physical and mechanical properties of neutron-irradiated materials, has been performed. Also a start-up work of the underground structure construction has been launched out. The project management and tasks required for the license application were duly carried out. The resultant detail design data will be used for the next step. (author)

A landscape of sport facilities in the Netherlands

NARCIS (Netherlands)

Hoekman, R.H.A.; Kraaykamp, G.L.M.; Breedveld, K.

2016-01-01

This article explores the geographical distribution of sport facilities in the Netherlands and evaluates the supply and proximity of such facilities in relation to area level deprivation and urbanity. In today?s context of financial austerity, many municipalities must critically assess their

A human factors engineering evaluation of the Multi-Function Waste Tank Facility. Final report

Energy Technology Data Exchange (ETDEWEB)

Donohoo, D.T. [Pacific Northwest Lab., Richland, WA (United States); Sarver, T.L. [ARES Corp., San Francisco, CA (United States)

1995-06-05

This report documents the methods and results of a human factors engineering (HFE) review conducted on the Multi-Function Waste Tank Facility (MWTF), Westinghouse Hanford Company (WHC) Project 236A, to be constructed at the U.S. Department of Energy (DOE) facility at Hanford, Washington. This HFE analysis of the MWTF was initiated by WHC to assess how well the current facility and equipment design satisfies the needs of its operations and maintenance staff and other potential occupants, and to identify areas of the design that could benefit from improving the human interfaces at the facility. Safe and effective operations, including maintenance, is a primary goal for the MWTF. Realization of this goal requires that the MWTF facility, equipment, and operations be designed in a manner that is consistent with the abilities and limitations of its operating personnel. As a consequence, HFE principles should be applied to the MWTF design, construction, its operating procedures, and its training. The HFE review was focused on the 200-West Area facility as the design is further along than that of the 200-East Area. The review captured, to the greatest extent feasible at this stage of design, all aspects of the facility activities and included the major topics generally associated with HFE (e.g., communication, working environment). Lessons learned from the review of the 200 West facility will be extrapolated to the 200-East Area, as well as generalized to the Hanford Site.

A human factors engineering evaluation of the Multi-Function Waste Tank Facility. Final report

International Nuclear Information System (INIS)

Donohoo, D.T.; Sarver, T.L.

1995-01-01

This report documents the methods and results of a human factors engineering (HFE) review conducted on the Multi-Function Waste Tank Facility (MWTF), Westinghouse Hanford Company (WHC) Project 236A, to be constructed at the U.S. Department of Energy (DOE) facility at Hanford, Washington. This HFE analysis of the MWTF was initiated by WHC to assess how well the current facility and equipment design satisfies the needs of its operations and maintenance staff and other potential occupants, and to identify areas of the design that could benefit from improving the human interfaces at the facility. Safe and effective operations, including maintenance, is a primary goal for the MWTF. Realization of this goal requires that the MWTF facility, equipment, and operations be designed in a manner that is consistent with the abilities and limitations of its operating personnel. As a consequence, HFE principles should be applied to the MWTF design, construction, its operating procedures, and its training. The HFE review was focused on the 200-West Area facility as the design is further along than that of the 200-East Area. The review captured, to the greatest extent feasible at this stage of design, all aspects of the facility activities and included the major topics generally associated with HFE (e.g., communication, working environment). Lessons learned from the review of the 200 West facility will be extrapolated to the 200-East Area, as well as generalized to the Hanford Site

DOE LeRC photovoltaic systems test facility

Science.gov (United States)

Cull, R. C.; Forestieri, A. F.

1978-01-01

The facility was designed and built and is being operated as a national facility to serve the needs of the entire DOE National Photovoltaic Program. The object of the facility is to provide a place where photovoltaic systems may be assembled and electrically configured, without specific physical configuration, for operation and testing to evaluate their performance and characteristics. The facility as a breadboard system allows investigation of operational characteristics and checkout of components, subsystems and systems before they are mounted in field experiments or demonstrations. The facility as currently configured consist of 10 kW of solar arrays built from modules, two inverter test stations, a battery storage system, interface with local load and the utility grid, and instrumentation and control necessary to make a flexible operating facility. Expansion to 30 kW is planned for 1978. Test results and operating experience are summaried to show the variety of work that can be done with this facility.

Regional energy facility siting analysis

International Nuclear Information System (INIS)

Eberhart, R.C.; Eagles, T.W.

1976-01-01

Results of the energy facility siting analysis portion of a regional pilot study performed for the anticipated National Energy Siting and Facility Report are presented. The question of cell analysis versus site-specific analysis is explored, including an evaluation of the difference in depth between the two approaches. A discussion of the possible accomplishments of regional analysis is presented. It is concluded that regional sitting analysis could be of use in a national siting study, if its inherent limits are recognized

JOINT INTELLIGENCE, SURVEILLANCE, & RECONNAISSANCE (ISR) TEST & EVALUATION (JISR-TE) FACILITY

Data.gov (United States)

Federal Laboratory Consortium — To meet the needs of the Warfighter, the JISR-TE facility provides the US, NATO, and Coalition members standards conformance testing of imagery capabilities across...

Assessing the economic feasibility of flexible integrated gasification Co-generation facilities

NARCIS (Netherlands)

Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

2011-01-01

This paper evaluated the economic effects of introducing flexibility to state-of-the-art integrated gasification co-generation (IGCG) facilities equipped with CO2 capture. In a previous paper the technical and energetic performances of these flexible IG-CG facilities were evaluated. This paper

Shield wall evaluation of hot cell facility for advanced spent fuel conditioning process

International Nuclear Information System (INIS)

Cho, I. J.; Kuk, D. H.; Ko, J. H.; Jung, W. M.; Yoo, G. S.; Lee, E. P.; Park, S. W.

2002-01-01

The future hot cell is located in the Irradiated Material Experiment Facility (IMEF) at the Korea Atomic Energy Research Institute (KAERI). It is β-γ type hot cell that was constructed on the base floor in IMEF building for irradiated material testing. And this hot cell will be used for carrying out the Advanced spent fuel Conditioning Process (ACP). The radiation shielding capability of hot cell should be sufficient to meet the radiation dose requirements in the related regulations. Because the radioactive sources of ACP are expected to be higher than radioactive sources of IMEF design criteria, the future hot cell in current status is unsatisfactory to hot test of ACP. So the shielding analysis of the future hot cell is performed to evaluate shielding ability of concrete shield wall. The shielding analysis included (a) identification of ACP source term; (b) photon source spectrum; (c) shielding analysis by QADS and MCNP-4C; and (d) enhancement of concrete shield wall. In this research, dose rates are obtained according to ACP source, geometry and hot cell shield wall thickness. And the evaluation and reinforcement thickness of the shield wall about future hot cell are concluded

Engineered Barrier Test Facility status report, 1984

International Nuclear Information System (INIS)

Phillips, S.J.; Adams, M.R.; Gilbert, T.W.; Meinhardt, C.C.; Mitchell, R.M.; Waugh, W.J.

1985-02-01

This report provides a general summary of activities completed to date at the Hanford Engineered Barrier Test Facility. This facility is used to test and compare construction practices and performance of alternative designs of engineered barrier cover systems. These cover systems are being evaluated for potential use for isolation and confinement of buried waste disposal structures

Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA Critical Facility

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-04-15

The IAEA has facilitated an extensive programme that addresses the technical development of advanced gas cooled reactor technology. Included in this programme is the coordinated research project (CRP) on Evaluation of High Temperature Gas Cooled Reactor (HTGR) Performance, which is the focus of this TECDOC. This CRP was established to foster the sharing of research and associated technical information among participating Member States in the ongoing development of the HTGR as a future source of nuclear energy. Within it, computer codes and models were verified through actual test results from operating reactor facilities. The work carried out in the CRP involved both computational and experimental analysis at various facilities in IAEA Member States with a view to verifying computer codes and methods in particular, and to evaluating the performance of HTGRs in general. The IAEA is grateful to China, the Russian Federation and South Africa for providing their facilities and benchmark programmes in support of this CRP.

Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA Critical Facility

International Nuclear Information System (INIS)

2013-04-01

The IAEA has facilitated an extensive programme that addresses the technical development of advanced gas cooled reactor technology. Included in this programme is the coordinated research project (CRP) on Evaluation of High Temperature Gas Cooled Reactor (HTGR) Performance, which is the focus of this TECDOC. This CRP was established to foster the sharing of research and associated technical information among participating Member States in the ongoing development of the HTGR as a future source of nuclear energy. Within it, computer codes and models were verified through actual test results from operating reactor facilities. The work carried out in the CRP involved both computational and experimental analysis at various facilities in IAEA Member States with a view to verifying computer codes and methods in particular, and to evaluating the performance of HTGRs in general. The IAEA is grateful to China, the Russian Federation and South Africa for providing their facilities and benchmark programmes in support of this CRP.

Neutrons leaked from a 45 MeV linac facility

Energy Technology Data Exchange (ETDEWEB)

Kitaichi, Masatoshi; Sawamura, Sadashi; Yamada, Takuma; Sawamura, Teruko; Kaneko, Junnichi H. [Hokkaido Univ., Sapporo (Japan); Nojiri, Itiro [Japan Nuclear Cycle Development Institute, Ibaraki (Japan)

2002-07-01

Dose evaluation for skyshine from nuclear facilities is an issue in environmental evaluations. Therefore, benchmark data for skyshine and well-investigated codes for skyshine would be useful in the rational evaluations of nuclear facilities. The purpose of this study is to obtain benchmark data of skyshine and to investigate the effect of source spectra and angular distribution on the skyshine process. In this study spatial and time distributions of neutrons leaked from the Hokkaido University 45 MeV electron linac facility were measured and compared with calculations. Neutrons were emitted from the ( ,n) reaction produced by bremsstrahlung radiation in a lead target irradiated with electrons from the linac. The skyshine process of neutrons transported through the facility building to the outside was investigated. The source spectrum of the skyshine process was evaluated using a cylindrical multi-moderator spectrometer and unfolding code, the SAND-II, and the results were compared. Measurements were carried out to a distance of 330 m from the facility. The measured spatial dose distribution was found not to coincide with the calculations. The discrepancy is discussed based on an analysis of the spatial and time distributions, and the energy spectrum which suggests that the source spectrum and the angular distribution assumed in the calculation was not sufficiently similar to simulate the experimental situation. The time distribution introduced in this study appears to be useful in discussions of the skyshine process and its sources.

High-capacity neutron activation analysis facility

International Nuclear Information System (INIS)

Hochel, R.C.

1979-01-01

A high-capacity neutron activation analysis facility, the Reactor Activation Facility, was designed and built and has been in operation for about a year at one of the Savannah River Plant's production reactors. The facility determines uranium and about 19 other trace elements in hydrogeochemical samples collected in the National Uranium Resource Evaluation program. The facility has a demonstrated average analysis rate of over 10,000 samples per month, and a peak rate of over 16,000 samples per month. Uranium is determined by cyclic activation and delayed neutron counting of the U-235 fission products; other elements are determined from gamma-ray spectra recorded in subsequent irradiation, decay, and counting steps. The method relies on the absolute activation technique and is highly automated for round-the-clock unattended operation

Current status of ground motions evaluation in seismic design guide for nuclear power facilities. Investigation on IAEA and US.NRC

International Nuclear Information System (INIS)

Nakajima, Masato; Ito, Hiroshi; Hirata, Kazuta

2009-01-01

Recently, IAEA (International Atomic Energy Agency) and US.NRC (US. Nuclear Regulatory Commission) published several standards and technical reports on seismic design and safety evaluation for nuclear power facilities. This report summarizes the current status of the international guidelines on seismic design and safety evaluation for nuclear power facilities in order to explore the future research topics. The main results obtained are as follows: 1 IAEA: (1) In the safety standard series, two levels are defined as seismic design levels, and design earthquake ground motion is determined corresponding to each seismic design level. (2) A new framework on seismic design which consists of conventional deterministic method and risk-based method is discussed in the technical report although the framework is not adopted in the safety guidelines. 2 USA: (1) US.NRC discusses a performance-based seismic design framework which has been originally developed by the private organization (American Society of Civil Engineers). (2) Design earthquakes and earthquake ground motion are mainly evaluated and determined based on probabilistic seismic hazard evaluations. 3 Future works: It should be emphasized that IAEA and US.NRC have investigated the implementation of risk-based concept into seismic design. The implementation of risk-based concept into regulation and seismic design makes it possible to consider various uncertainties and to improve accountability. Therefore, we need to develop the methods for evaluating seismic risk of structures, and to correlate seismic margin and seismic risk quantitatively. Moreover, the probabilistic method of earthquake ground motions, that is required in the risk-based design, should be applied to sites in Japan. (author)

Management of Decommissioning on a Multi-Facility Site

International Nuclear Information System (INIS)

Laraia, Michele; McIntyre, Peter; Visagie, Abrie

2008-01-01

The management of the decommissioning of multi-facility sites may be inadequate or inappropriate if based on approaches and strategies developed for sites consisting of only a single facility. The varied nature of activities undertaken, their interfaces and their interdependencies are likely to complicate the management of decommissioning. These issues can be exacerbated where some facilities are entering the decommissioning phase while others are still operational or even new facilities are being built. Multi-facility sites are not uncommon worldwide but perhaps insufficient attention has been paid to optimizing the overall site decommissioning in the context of the entire life cycle of facilities. Decommissioning management arrangements need to be established taking a view across the whole site. A site-wide decommissioning management system is required. This should include a project evaluation and approval process and specific arrangements to manage identified interfaces and interdependencies. A group should be created to manage decommissioning across the site, ensuring adequate and consistent practices in accordance with the management system. Decommissioning management should be aimed at the entire life cycle of facilities. In the case of multi facility sites, the process becomes more complex and decommissioning management arrangements need to be established with a view to the whole site. A site decommissioning management system, a group that is responsible for decommissioning on site, a site project evaluation and approval process and specific arrangements to manage the identified interfaces are key areas of a site decommissioning management structure that need to be addressed to ensure adequate and consistent decommissioning practices. A decommissioning strategy based on single facilities in a sequential manner is deemed inadequate

Heat removal tests on dry storage facilities for nuclear spent fuels

International Nuclear Information System (INIS)

Wataru, M.; Saegusa, T.; Koga, T.; Sakamoto, K.; Hattori, Y.

1999-01-01

In Japan, spent fuel generated in NPP is controlled and stored in dry storage facility away-from reactor. Natural convection cooling system of the storage facility is considered advantageous from both safety and economic point of view. In order to realize this type of facility it is necessary to develop an evaluation method for natural convection characteristics and to make a rational design taking account safety and economic factors. Heat removal tests with the reduces scale models of storage facilities (cask, vault and silo) identified the the flow pattern in the test modules. The temperature and velocity distributions were obtained and the heat transfer characteristics were evaluated

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

International Nuclear Information System (INIS)

Xu, J.; Graves, H.

1990-01-01

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

Safety evaluation report of hot cell facilities for demonstration of advanced spent fuel conditioning process

International Nuclear Information System (INIS)

You, Gil Sung; Choung, W. M.; Ku, J. H.; Cho, I. J.; Kook, D. H.; Park, S. W.; Bek, S. Y.; Lee, E. P.

2004-10-01

The advanced spent fuel conditioning process(ACP) proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel. In the next phase(2004∼2006), the hot test will be carried out for verification of the ACP in a laboratory scale. For the hot test, the hot cell facilities of α- type and auxiliary facilities are required essentially for safe handling of high radioactive materials. As the hot cell facilities for demonstration of the ACP, a existing hot cell of β- type will be refurbished to minimize construction expenditures of hot cell facility. Up to now, the detail design of hot cell facilities and process were completed, and the safety analysis was performed to substantiate secure of conservative safety. The design data were submitted for licensing which was necessary for construction and operation of hot cell facilities. The safety investigation of KINS on hot cell facilities was completed, and the license for construction and operation of hot cell facilities was acquired already from MOST. In this report, the safety analysis report submitted to KINS was summarized. And also, the questionnaires issued from KINS and answers of KAERI in process of safety investigation were described in detail

Bioaerosol releases from compost facilities: Evaluating passive and active source terms at a green waste facility for improved risk assessments

Science.gov (United States)

Taha, M. P. M.; Drew, G. H.; Longhurst, P. J.; Smith, R.; Pollard, S. J. T.

The passive and active release of bioaerosols during green waste composting, measured at source is reported for a commercial composting facility in South East (SE) England as part of a research programme focused on improving risk assessments at composting facilities. Aspergillus fumigatus and actinomycetes concentrations of 9.8-36.8×10 6 and 18.9-36.0×10 6 cfu m -3, respectively, measured during the active turning of green waste compost, were typically 3-log higher than previously reported concentrations from static compost windrows. Source depletion curves constructed for A. fumigatus during compost turning and modelled using SCREEN3 suggest that bioaerosol concentrations could reduce to background concentrations of 10 3 cfu m -3 within 100 m of this site. Authentic source term data produced from this study will help to refine the risk assessment methodologies that support improved permitting of compost facilities.

Liquefied Gaseous Fuels Spill Test Facility

International Nuclear Information System (INIS)

1993-02-01

The US Department of Energy's liquefied Gaseous Fuels Spill Test Facility is a research and demonstration facility available on a user-fee basis to private and public sector test and training sponsors concerned with safety aspects of hazardous chemicals. Though initially designed to accommodate large liquefied natural gas releases, the Spill Test Facility (STF) can also accommodate hazardous materials training and safety-related testing of most chemicals in commercial use. The STF is located at DOE's Nevada Test Site near Mercury, Nevada, USA. Utilization of the Spill Test Facility provides a unique opportunity for industry and other users to conduct hazardous materials testing and training. The Spill Test Facility is the only facility of its kind for either large- or small-scale testing of hazardous and toxic fluids including wind tunnel testing under controlled conditions. It is ideally suited for test sponsors to develop verified data on prevention, mitigation, clean-up, and environmental effects of toxic and hazardous gaseous liquids. The facility site also supports structured training for hazardous spills, mitigation, and clean-up. Since 1986, the Spill Test Facility has been utilized for releases to evaluate the patterns of dispersion, mitigation techniques, and combustion characteristics of select materials. Use of the facility can also aid users in developing emergency planning under US P.L 99-499, the Superfund Amendments and Reauthorization Act of 1986 (SARA) and other regulations. The Spill Test Facility Program is managed by the US Department of Energy (DOE), Office of Fossil Energy (FE) with the support and assistance of other divisions of US DOE and the US Government. DOE/FE serves as facilitator and business manager for the Spill Test Facility and site. This brief document is designed to acquaint a potential user of the Spill Test Facility with an outline of the procedures and policies associated with the use of the facility

Power Systems Development Facility

International Nuclear Information System (INIS)

1993-06-01

The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell

Planning the School Food Service Facilities. Revised 1967.

Science.gov (United States)

Utah State Board of Education, Salt Lake City.

Evaluations of food service equipment, kitchen design and food service facilities are comprehensively reviewed for those concerned with the planning and equipping of new school lunchrooms or the remodeling of existing facilities. Information is presented in the form of general guides adaptable to specific local situations and needs, and is…

Waste reduction efforts through the evaluation and procurement of a digital camera system for the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory-East

International Nuclear Information System (INIS)

Bray, T. S.; Cohen, A. B.; Tsai, H.; Kettman, W. C.; Trychta, K.

1999-01-01

The Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory-East is a research facility where sample examinations involve traditional photography. The AGHCF documents samples with photographs (both Polaroid self-developing and negative film). Wastes generated include developing chemicals. The AGHCF evaluated, procured, and installed a digital camera system for the Leitz metallograph to significantly reduce labor, supplies, and wastes associated with traditional photography with a return on investment of less than two years

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

Facility Interface Capability Assessment (FICA) project report

International Nuclear Information System (INIS)

Pope, R.B.; MacDonald, R.R.; Viebrock, J.M.; Mote, N.

1995-09-01

The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified

Facility Interface Capability Assessment (FICA) project report

Energy Technology Data Exchange (ETDEWEB)

Pope, R.B. [ed.] [Oak Ridge National Lab., TN (United States); MacDonald, R.R. [ed.] [Civilian Radioactive Waste Management System, Vienna, VA (United States); Viebrock, J.M.; Mote, N. [Nuclear Assurance Corp., Norcross, GA (United States)

1995-09-01

The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified.

Support of Construction and Verification of Out-of-Pile Fuel Assembly Test Facilities

International Nuclear Information System (INIS)

Park, Nam Gyu; Kim, K. T.; Park, J. K.

2006-12-01

Fuel assembly and components should be verified by the out-of-pile test facilities in order to load the developed fuel in reactor. Even though most of the component-wise tests have been performed using the facilities in land, the assembly-wise tests has been depended on the oversees' facility due to the lack of the facilities. KAERI started to construct the assembly-wise mechanical/hydraulic test facilities and KNF, as an end user, is supporting the mechanical/hydraulic test facility construction by using the technologies studied through the fuel development programs. The works performed are as follows: - Test assembly shipping container design and manufacturing support - Fuel handling tool design : Gripper, Upper and lower core simulators for assembly mechanical test facility, Internals for assembly hydraulic test facility - Manufacture of test specimens : skeleton and assembly for preliminary functional verification of assembly mechanical/hydraulic test facilities, two assemblies for the verification of assembly mechanical/hydraulic test facilities, Instrumented rod design and integrity evaluation - Verification of assembly mechanical/hydraulic test facilities : test data evaluation

Support of Construction and Verification of Out-of-Pile Fuel Assembly Test Facilities

Energy Technology Data Exchange (ETDEWEB)

Park, Nam Gyu; Kim, K. T.; Park, J. K. [KNF, Daejeon (Korea, Republic of)] (and others)

2006-12-15

Fuel assembly and components should be verified by the out-of-pile test facilities in order to load the developed fuel in reactor. Even though most of the component-wise tests have been performed using the facilities in land, the assembly-wise tests has been depended on the oversees' facility due to the lack of the facilities. KAERI started to construct the assembly-wise mechanical/hydraulic test facilities and KNF, as an end user, is supporting the mechanical/hydraulic test facility construction by using the technologies studied through the fuel development programs. The works performed are as follows: - Test assembly shipping container design and manufacturing support - Fuel handling tool design : Gripper, Upper and lower core simulators for assembly mechanical test facility, Internals for assembly hydraulic test facility - Manufacture of test specimens : skeleton and assembly for preliminary functional verification of assembly mechanical/hydraulic test facilities, two assemblies for the verification of assembly mechanical/hydraulic test facilities, Instrumented rod design and integrity evaluation - Verification of assembly mechanical/hydraulic test facilities : test data evaluation.

Better antiretroviral therapy outcomes at primary healthcare facilities: an evaluation of three tiers of ART services in four South African provinces.

Science.gov (United States)

Fatti, Geoffrey; Grimwood, Ashraf; Bock, Peter

2010-09-21

There are conflicting reports of antiretroviral therapy (ART) effectiveness comparisons between primary healthcare (PHC) facilities and hospitals in low-income settings. This comparison has not been evaluated on a broad scale in South Africa. A retrospective cohort study was conducted including ART-naïve adults from 59 facilities in four provinces in South Africa, enrolled between 2004 and 2007. Kaplan-Meier estimates, competing-risks Cox regression, generalised estimating equation population-averaged models and logistic regression were used to compare death, loss to follow-up (LTFU) and virological suppression (VS) between PHC, district and regional hospitals. 29 203 adults from 47 PHC facilities, nine district hospitals and three regional hospitals were included. Patients at PHC facilities had more advanced WHO stage disease when starting ART. Retention in care was 80.1% (95% CI: 79.3%-80.8%), 71.5% (95% CI: 69.1%-73.8%) and 68.7% (95% CI: 67.0%-69.7%) at PHC, district and regional hospitals respectively, after 24 months of treatment (Phospitals (aHR 2.19; 95% CI: 1.94-2.47) and mortality was independently elevated at district hospitals (aHR 1.60; 95% CI: 1.30-1.99) compared to PHC facilities after 12 months of ART. District and regional hospital patients had independently reduced probabilities of VS, aOR 0.76 (95% CI: 0.59-0.97) and 0.64 (95% CI: 0.56-0.75) respectively compared to PHC facilities over 24 months of treatment. ART outcomes were superior at PHC facilities, despite PHC patients having more advanced clinical stage disease when starting ART, suggesting that ART can be adequately provided at this level and supporting the South African government's call for rapid up-scaling of ART at the primary level of care. Further prospective research is required to determine the degree to which outcome differences are attributable to either facility level characteristics or patient co-morbidity at hospital level.

Better antiretroviral therapy outcomes at primary healthcare facilities: an evaluation of three tiers of ART services in four South African provinces.

Directory of Open Access Journals (Sweden)

Geoffrey Fatti

Full Text Available BACKGROUND: There are conflicting reports of antiretroviral therapy (ART effectiveness comparisons between primary healthcare (PHC facilities and hospitals in low-income settings. This comparison has not been evaluated on a broad scale in South Africa. METHODOLOGY/PRINCIPAL FINDINGS: A retrospective cohort study was conducted including ART-naïve adults from 59 facilities in four provinces in South Africa, enrolled between 2004 and 2007. Kaplan-Meier estimates, competing-risks Cox regression, generalised estimating equation population-averaged models and logistic regression were used to compare death, loss to follow-up (LTFU and virological suppression (VS between PHC, district and regional hospitals. 29 203 adults from 47 PHC facilities, nine district hospitals and three regional hospitals were included. Patients at PHC facilities had more advanced WHO stage disease when starting ART. Retention in care was 80.1% (95% CI: 79.3%-80.8%, 71.5% (95% CI: 69.1%-73.8% and 68.7% (95% CI: 67.0%-69.7% at PHC, district and regional hospitals respectively, after 24 months of treatment (P<0.0001. In adjusted regression analyses, LTFU was independently increased at regional hospitals (aHR 2.19; 95% CI: 1.94-2.47 and mortality was independently elevated at district hospitals (aHR 1.60; 95% CI: 1.30-1.99 compared to PHC facilities after 12 months of ART. District and regional hospital patients had independently reduced probabilities of VS, aOR 0.76 (95% CI: 0.59-0.97 and 0.64 (95% CI: 0.56-0.75 respectively compared to PHC facilities over 24 months of treatment. CONCLUSIONS/SIGNIFICANCE: ART outcomes were superior at PHC facilities, despite PHC patients having more advanced clinical stage disease when starting ART, suggesting that ART can be adequately provided at this level and supporting the South African government's call for rapid up-scaling of ART at the primary level of care. Further prospective research is required to determine the degree to which

Space nuclear thermal propulsion test facilities accommodation at INEL

International Nuclear Information System (INIS)

Hill, T.J.; Reed, W.C.; Welland, H.J.

1993-01-01

The U.S. Air Force (USAF) has proposed to develop the technology and demonstrate the feasibility of a particle bed reactor (PBR) propulsion system that could be used to power an advanced upper stage rocket engine. The U.S. Department of Energy (DOE) is cooperating with the USAF in that it would host the test facility if the USAF decides to proceed with the technology demonstration. Two DOE locations have been proposed for testing the PBR technology, a new test facility at the Nevada Test Site, or the modification and use of an existing facility at the Idaho National Engineering Laboratory. The preliminary evaluations performed at the INEL to support the PBR technology testing has been completed. Additional evaluations to scope the required changes or upgrade needed to make the proposed USAF PBR test facility meet the requirements for testing Space Exploration Initiative (SEI) nuclear thermal propulsion engines are underway

Space nuclear thermal propulsion test facilities accommodation at INEL

Science.gov (United States)

Hill, Thomas J.; Reed, William C.; Welland, Henry J.

1993-01-01

The U.S. Air Force (USAF) has proposed to develop the technology and demonstrate the feasibility of a particle bed reactor (PBR) propulsion system that could be used to power an advanced upper stage rocket engine. The U.S. Department of Energy (DOE) is cooperating with the USAF in that it would host the test facility if the USAF decides to proceed with the technology demonstration. Two DOE locations have been proposed for testing the PBR technology, a new test facility at the Nevada Test Site, or the modification and use of an existing facility at the Idaho National Engineering Laboratory. The preliminary evaluations performed at the INEL to support the PBR technology testing has been completed. Additional evaluations to scope the required changes or upgrade needed to make the proposed USAF PBR test facility meet the requirements for testing Space Exploration Initiative (SEI) nuclear thermal propulsion engines are underway.

A Fisheries Evaluation of the Richland and Toppenish/Satus Canal Fish Screening Facilities, Spring 1986 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Neitzel, D.A.; Abernethy, C. Scott; Lusty, E. William

1987-05-01

The fisheries evaluation phase of diversion screen effectiveness summarizes the results of work at the Richland and Toppenish/Satus Fish screening facilities (Richland Screens and Toppenish/Satus Screens) during 1986. More than 10,000 steelhead, Salmo gairdneri, and chinook salmon, Oncorhynchus tshawytscha, were released at the screen diversions. At the Richland Screens, 61% of the released steelhead were recovered and 1.1% were descaled; 93% of the spring chinook salmon were recovered and less than 1% were descaled. At the Toppenish/Satus Screens, only steelhead were evaluated for descaling; 88.9% were recovered and 23.9% were descaled. Only steelhead were evaluated because the Yakima River fisheries managers did not expect any other smolts to occur in Toppenish Creek. Because of the acclimation conditions and the amount of time the fish had to be held before testing, some of the test population were descaled during holding and transportation. The 23.9% descaling for the test fish was compared to 26.4% for the controls.

2727-S Nonradioactive Dangerous Waste Storage Facility clean closure evaluation report

International Nuclear Information System (INIS)

Luke, S.N.

1994-01-01

This report presents the analytical results of 2727-S NRDWS facility closure verification soil sampling and compares these results to clean closure criteria. The results of this comparison will determine if clean closure of the unit is regulatorily achievable. This report also serves to notify regulators that concentrations of some analytes at the site exceed sitewide background threshold levels (DOE-RL 1993b) and/or the limits of quantitation (LOQ). This report also presents a Model Toxics Control Act Cleanup (MTCA) (WAC 173-340) regulation health-based closure standard under which the unit can clean close in lieu of closure to background levels or LOQ in accordance with WAC 173-303-610. The health-based clean closure standard will be closure to MTCA Method B residential cleanup levels. This report reconciles all analyte concentrations reported above background or LOQ to this health-based cleanup standard. Regulator acceptance of the findings presented in this report will qualify the TSD unit for clean closure in accordance with WAC 173-303-610 without further TSD unit soil sampling, or soil removal and/or decontamination. Nondetected analytes require no further evaluation

Activation analysis for the IFF system in RAON facility

International Nuclear Information System (INIS)

LEE, Cheol Woo; LEE, Young-Ouk; KIM, Jong Won; KIM, Mijung

2014-01-01

A heavy-ion accelerator facility is under a development in Korea to use in the basic science research and various application areas. In this facility, the In-Flight Fragment (IFF) target and isotope separator has been designed to produce various isotopes and transport the interesting isotopes into the experimental rooms. In this work, activation analysis for the pre-separator was performed in the IFF target room. In this work, activation analysis for the pre-separator was performed for the IFF target system in RAON heavy-ion accelerator facility. At first, radiation source terms were evaluated with the primary beams and target conditions. Using the evaluated source terms, induced activities in all component of pre-separator were calculated. The decay gamma-rays produced after a shutdown was estimated based on the activation analysis and gamma-ray dose rate according to the cooling time was evaluated

A calibration facility for radon fluxmeter

International Nuclear Information System (INIS)

Li Xianjie; Qiu Shoukang; Zhou Jianliang; Liu Chunkui; Pan Jialin; Yang Mingli

1998-01-01

Calibration facilities for radon fluxmeter with three kinds of different emanation medium have been developed. The stability of radon flux is 5%, 9% (RSD) respectively. The uniformity of radon flux is 4.5%, 8.5% (RSD) respectively. These specifications fulfill the calibration requirement for radon fluxmeter. The determination of radon flux of facility takes full account of eliminating the main error source-attenuation effect (including leakage and back diffusion etc.): not only prevent attenuation and make a relevant correction. Therefore the accuracy of determination is assured. The calibration, intercomparison of radon flux meter and the quantitatively evaluation on the measurement method of radon flux are made to be possible by the successful establishment of this facility. (author)

Simulation for evaluation of the multi-ion-irradiation Laboratory of TechnoFusion facility and its relevance for fusion applications

International Nuclear Information System (INIS)

Jimenez-Rey, D.; Mota, F.; Vila, R.; Ibarra, A.; Ortiz, Christophe J.; Martinez-Albertos, J.L.; Roman, R.; Gonzalez, M.; Garcia-Cortes, I.; Perlado, J.M.

2011-01-01

Thermonuclear fusion requires the development of several research facilities, in addition to ITER, needed to advance the technologies for future fusion reactors. TechnoFusion will focus in some of the priority areas identified by international fusion programmes. Specifically, the TechnoFusion Area of Irradiation of Materials aims at surrogating experimentally the effects of neutron irradiation on materials using a combination of ion beams. This paper justifies this approach using computer simulations to validate the multi-ion-irradiation Laboratory. The planned irradiation facility will investigate the effects of high energetic radiations on reactor-relevant materials. In a second stage, it will also be used to analyze the performance of such materials and evaluate newly designed materials. The multi-ion-irradiation Laboratory, both triple irradiation and high-energy proton irradiation, can provide valid experimental techniques to reproduce the effect of neutron damage in fusion environment.

Approaches used for clearance of land from nuclear facilities among several countries; evaluation for regulatory input

International Nuclear Information System (INIS)

Meck, Robert A.

2012-01-01

The purpose of this report is to describe, compare and evaluate the pros and cons of different methods for radiological characterisation of land areas after decommissioning of nuclear facilities. Specifically, it describes and examines the applied methods for the final status survey used in France, Germany, Spain, the United Kingdom (UK), and the United States (US).The Swedish Radiation Authority (Straalsaekerhetsmyndigheten, SSM) has authorised this comparison and evaluation for dissemination to industry and other interested parties. The information from the five countries in the study came from several kinds of sources. Professional network referrals identified subject matter experts in each of the five countries who were then contacted. The contacts provided electronic documents or online links to the publicly available information. The online links often led to additional world-wide-web searches and more information. In addition, some information was provided by private communication in e-mails. Other experts provided electronic proceedings of a conference or symposium. The information was compared and evaluated on for each country according to each of ten attributes: 1. Regulatory basis; 2. Scope; 3. Applicability; 4. Flexibility; 5. Transparency; 6. Roles and responsibilities of parties involved; 7. Quality program; 8. Detail of measurements descriptions; 9. Mathematical approaches; 10. Available assessment tools. A summary comparison across all countries for each attribute is presented in a table. Overall, it appears that each country has a goal of clearing lands from nuclear facilities at a risk of a fatality from residual radioactivity of on the order of one-in-a-million per year. However, their approaches vary in a number of aspects, and evaluation of these different approaches should take into account the regulatory culture of the respective country. High level considerations for developing regulations and guidance for implementation of final status

Mechanistic facility safety and source term analysis

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

A PC-based computer program was created for facility safety and source term analysis at Hanford The program has been successfully applied to mechanistic prediction of source terms from chemical reactions in underground storage tanks, hydrogen combustion in double contained receiver tanks, and proccss evaluation including the potential for runaway reactions in spent nuclear fuel processing. Model features include user-defined facility room, flow path geometry, and heat conductors, user-defined non-ideal vapor and aerosol species, pressure- and density-driven gas flows, aerosol transport and deposition, and structure to accommodate facility-specific source terms. Example applications are presented here

User's manual of a computer code for seismic hazard evaluation for assessing the threat to a facility by fault model. SHEAT-FM

International Nuclear Information System (INIS)

Sugino, Hideharu; Onizawa, Kunio; Suzuki, Masahide

2005-09-01

To establish the reliability evaluation method for aged structural component, we developed a probabilistic seismic hazard evaluation code SHEAT-FM (Seismic Hazard Evaluation for Assessing the Threat to a facility site - Fault Model) using a seismic motion prediction method based on fault model. In order to improve the seismic hazard evaluation, this code takes the latest knowledge in the field of earthquake engineering into account. For example, the code involves a group delay time of observed records and an update process model of active fault. This report describes the user's guide of SHEAT-FM, including the outline of the seismic hazard evaluation, specification of input data, sample problem for a model site, system information and execution method. (author)

Ecotoxicity of Wastewater from Medical Facilities: A Review

Directory of Open Access Journals (Sweden)

Cidlinová A.

2018-03-01

Full Text Available Wastewater from medical facilities contains a wide range of chemicals (in particular pharmaceuticals, disinfectants, heavy metals, contrast media, and radionuclides and pathogens, therefore it constitutes a risk to the environment and human health. Many micropollutants are not efficiently eliminated during wastewater treatment and contaminate both surface water and groundwater. As we lack information about the long-term effects of low concentrations of micropollutants in the aquatic environment, it is not possible to rule out their adverse effects on aquatic organisms and human health. It is, therefore, necessary to focus on the evaluation of chronic toxicity in particular when assessing the environmental and health risks and to develop standards for the regulation of hazardous substances in wastewater from medical facilities on the basis of collected data. Wastewater from medical facilities is a complex mixture of many compounds that may have synergetic, antagonistic or additive effects on organisms. To evaluate the influence of a wide range of pollutants contained in the effluents from medical facilities on aquatic ecosystems, it is necessary to determine their ecotoxicity.

Thermionic system evaluation test (TSET) facility construction: A United States and Russian effort

International Nuclear Information System (INIS)

Wold, S.K.

1993-01-01

The Thermionic System Evaluation Test (TSET) is a ground test of an unfueled Russian TOPAZ-II in-core thermionic space reactor powered by electric heaters. The facility that will be used for testing of the TOPAZ-II systems is located at the New Mexico Engineering Research Institute (NMERI) complex in Albuquerque, NM. The reassembly of the Russian test equipment is the responsibility of International Scientific Products (ISP), a San Jose, CA, company and Inertek, a Russian corporation, with support provided by engineers and technicians from Phillips Laboratory (PL), Sandia National Laboratories (SNL), Los Alamos National Laboratory (LANL), and the University of New Mexico (UNM). This test is the first test to be performed under the New Mexico Strategic Alliance agreement. This alliance consists of the PL, SNL, LANL, and UNM. The testing is being funded by the Strategic Defense Initiative Organization (SDIO) with the PL responsible for project execution

Thermodynamic Evaluation of Floating Production Storage and Offloading Facilities with Liquefaction Processes

DEFF Research Database (Denmark)

Nguyen, Tuong-Van; Sánchez, Yamid Alberto Carranza; Junior, Silvio de Oliveira

2016-01-01

Floating, production, storage and offloading (FPSO) plants are facilities used in upstream petroleum processing.They have gained interest because they are more flexible than conventional plants and can be used for producingoil and gas in deep-water fields. In general, gas export is challenging...... because of the lack of infrastructure in remotelocations. The present work investigates the possibility of integrating liquefaction processes on such facilities, consideringfour possible petroleum compositions, which differ in their contents of carbon dioxide, light and heavy hydrocarbons.The performance...

An Operator Perspective from a Facility Evaluation of an RFID-Based UF6 Cylinder Accounting and Tracking System

International Nuclear Information System (INIS)

Martyn, Rose; Fitzgerald, Peter; Stehle, Nicholas D.; Rowe, Nathan C.; Younkin, James R.

2011-01-01

An operational field test of a Radio-Frequency Identification (RFID) system for tracking and accounting UF6 cylinders was conducted at the Global Nuclear Fuel Americas (GNF) fuel fabrication plant in 2009. The Cylinder Accountability and Tracking System (CATS) was designed and deployed by Oak Ridge National Laboratory (ORNL) and evaluated in cooperation with GNF. The system required that passive RFID be attached to several UF6 30B cylinders as they were received at the site; then the cylinders were tracked as they proceeded to interim storage, to processing in an autoclave, and eventually to disposition from the site. This CATS deployment also provided a direct integration of scale data from the site accountability scales. The integration of this information into the tracking data provided an attribute for additional safeguards for evaluation. The field test provided insight into the advantages and challenges of using RFID at an operating nuclear facility. The RFID system allowed operators to interact with the technology and demonstrated the survivability of the tags and reader equipment in the process environment. This paper will provide the operator perspective on utilizing RFID technology for locating cylinders within the facility, thereby tracking the cylinders for process and for Material Control and Accounting functions. The paper also will present the operator viewpoint on RFID implemented as an independent safeguards system.

Facility effluent monitoring plan for the 284-E and 284-W power plants

International Nuclear Information System (INIS)

Nickels, J.M.; Herman, D.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. A facility effluent monitoring plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

High-capacity neutron activation analysis facility

International Nuclear Information System (INIS)

Hochel, R.C.; Bowman, W.W.; Zeh, C.W.

1980-01-01

A high-capacity neutron activation analysis facility, the Reactor Activation Facility, was designed and built and has been in operation for about a year at one of the Savannah River Plant's production reactors. The facility determines uranium and about 19 other elements in hydrogeochemical samples collected in the National Uranium Resource Evaluation program, which is sponsored and funded by the United States Department of Energy, Grand Junction Office. The facility has a demonstrated average analysis rate of over 10,000 samples per month, and a peak rate of over 16,000 samples per month. Uranium is determined by cyclic activation and delayed neutron counting of the U-235 fission products; other elements are determined from gamma-ray spectra recorded in subsequent irradiation, decay, and counting steps. The method relies on the absolute activation technique and is highly automated for round-the-clock unattended operation

Statistical evaluation of effluent monitoring data for the 200 Area Treated Effluent Disposal Facility

International Nuclear Information System (INIS)

Chou, C.J.; Johnson, V.G.

2000-01-01

The 200 Area Treated Effluent Disposal Facility (TEDF) consists of a pair of infiltration basins that receive wastewater originating from the 200 West and 200 East Areas of the Hanford Site. TEDF has been in operation since 1995 and is regulated by State Waste Discharge Permit ST 4502 (Ecology 1995) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216. The permit stipulates monitoring requirements for effluent (or end-of-pipe) discharges and groundwater monitoring for TEDF. Groundwater monitoring began in 1992 prior to TEDF construction. Routine effluent monitoring in accordance with the permit requirements began in late April 1995 when the facility began operations. The State Waste Discharge Permit ST 4502 included a special permit condition (S.6). This condition specified a statistical study of the variability of permitted constituents in the effluent from TEDF during its first year of operation. The study was designed to (1) demonstrate compliance with the waste discharge permit; (2) determine the variability of all constituents in the effluent that have enforcement limits, early warning values, and monitoring requirements (WHC 1995); and (3) determine if concentrations of permitted constituents vary with season. Additional and more frequent sampling was conducted for the effluent variability study. Statistical evaluation results were provided in Chou and Johnson (1996). Parts of the original first year sampling and analysis plan (WHC 1995) were continued with routine monitoring required up to the present time

Antimicrobial stewardship in long term care facilities: what is effective?

Science.gov (United States)

Nicolle, Lindsay E

2014-02-12

Intense antimicrobial use in long term care facilities promotes the emergence and persistence of antimicrobial resistant organisms and leads to adverse effects such as C. difficile colitis. Guidelines recommend development of antimicrobial stewardship programs for these facilities to promote optimal antimicrobial use. However, the effectiveness of these programs or the contribution of any specific program component is not known. For this review, publications describing evaluation of antimicrobial stewardship programs for long term care facilities were identified through a systematic literature search. Interventions included education, guidelines development, feedback to practitioners, and infectious disease consultation. The studies reviewed varied in types of facilities, interventions used, implementation, and evaluation. Comprehensive programs addressing all infections were reported to have improved antimicrobial use for at least some outcomes. Targeted programs for treatment of pneumonia were minimally effective, and only for indicators of uncertain relevance for stewardship. Programs focusing on specific aspects of treatment of urinary infection - limiting treatment of asymptomatic bacteriuria or prophylaxis of urinary infection - were reported to be effective. There were no reports of cost-effectiveness, and the sustainability of most of the programs is unclear. There is a need for further evaluation to characterize effective antimicrobial stewardship for long term care facilities.

A cask maintenance facility feasibility study

International Nuclear Information System (INIS)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1989-01-01

The Oak Ridge National Laboratory (ORNL) is supporting the USDOE Office of Civilian Radioactive Waste Management (OCRWM) in developing a transportation system for spent nuclear fuel (SNF) and defense high level waste (HLW) as a part of the Federal Waste Management System (FWMS). In early 1988, a feasibility study was undertaken to design a stand-alone, green field facility for maintaining the FWMS casks. The feasibility study provided an initial layout facility design, an estimate of the construction cost, and an acquisition schedule for a Cask Maintenance Facility (CMF). The study also helped to define the interfaces between the transportation system and the waste generators, the repository, and a Monitored Retrieveable Storage (MRS) facility. The data, design, and estimated cost resulting from the study have been organized for use in the total transportation system decision-making process. Most importantly, the feasibility study also provides a foundation for continuing design and planning efforts. The feasibility study was based on an assumed stand-alone green field configuration because of the flexibility this design approach provides. A stand-alone facility requires the inclusion with support functions as well as the primary process facilities thus yielding a comprehensive design evaluation and cost estimate. For example, items such as roads, security and waste processing which might be shared with an integrated or collocated facility have been fully costed in the feasibility study. Thus, while the details of the facility design might change, the overall concept used in the study can be applied to other facility configurations as planning for the total FWMS develops

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

The Nature of Scatter at the DARHT Facility and Suggestions for Improved Modeling of DARHT Facility

Energy Technology Data Exchange (ETDEWEB)

Morneau, Rachel Anne [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-11-09

This report describes the US Stockpile Stewardship Program which is meant to sustain and evaluate nuclear weapon stockpile with no underground nuclear tests. This research will focus on DARHT, the Dual Axis Radiographic Hydrodynamic Test facility.

Usability Briefing - a process model for healthcare facilities

DEFF Research Database (Denmark)

Fronczek-Munter, Aneta

2014-01-01

Background: In complex buildings with many types of users it can be difficult to satisfy the numerous, often contradictory requirements. Research in usability mostly focuses on evaluating products or facilities with users, after they were built. This paper is part of a PhD project “Usability...... with various users/stakeholders, using creative boundary objects at workshops.  Practical Implications: The research results have relevance to researchers, client organisations, facility managers and architects planning new complex facilities.  Research limitations: The proposed model is theoretical and needs...... briefing for hospitals”, where methods for capturing user needs and experiences at hospital facilities are investigated in order to feed into design processes and satisfy the users’ needs and maximise the effectiveness of facilities. Purpose: This paper introduces the concept of usability briefing...

Analysis format and evaluation methods for effluent particle sampling systems in nuclear facilities

International Nuclear Information System (INIS)

Schwendiman, L.C.; Glissmeyer, J.A.

1976-06-01

Airborne effluent sampling systems for nuclear facilities are frequently designed, installed, and operated without a systematic approach which discloses and takes into account all the circumstances and conditions which would affect the validity and adequacy of the sample. Without a comprehensive check list or something similar, the designer of the system may not be given the important information needed to provide a good design. In like manner, an already operating system may be better appraised. Furthermore, the discipline of a more formal approach may compel the one who will use the system to make sure he knows what he wants and can thus give the designer the needed information. An important consideration is the criteria to be applied to the samples to be taken. This analysis format consists of a listing of questions and statements calling forth the necessary information required to analyze a sampling system. With this information developed, one can proceed with an evaluation, the methodology of which is also discussed in the paper. Errors in probe placement, failure to sample at the proper rate, delivery line losses, and others are evaluated using mathematical models and empirically derived relationships. Experimental methods are also described for demonstrating that quality sampling will be achieved. The experiments include using a temporary, simple, but optimal sample collection system to evaluate the more complex systems. The use of tracer particles injected in the stream is also discussed. The samples obtained with the existing system are compared with those obtained by the temporary, optimal system

Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

CERN Document Server

American Society for Testing and Materials. Philadelphia

2002-01-01

1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

Application of an infiltration evaluation methodology to a hypothetical low-level waste disposal facility

International Nuclear Information System (INIS)

Meyer, P.D.

1993-12-01

This report provides an analysis of infiltration and percolation at a hypothetical low-level waste (LLW) disposal facility was carried out. The analysis was intended to illustrate general issues of concern in assessing the performance of LLW disposal facilities. Among the processes considered in the analysis were precipitation, runoff, information, evaporation, transpiration, and redistribution. The hypothetical facility was located in a humid environment characterized by frequent and often intense precipitation events. The facility consisted of a series of concrete vaults topped by a multilayer cover. Cover features included a sloping soil surface to promote runoff, plant growth to minimize erosion and promote transportation, a sloping clay layer, and a sloping capillary barrier. The analysis within the root zone was carried out using a one-dimensional, transient simulation of water flow. Below the root zone, the analysis was primarily two-dimensional and steady-state

Development of decommissioning management system for nuclear fuel cycle facilities (DECMAN)

Energy Technology Data Exchange (ETDEWEB)

Ogawa, Ryuichirou; Ishijima, Noboru; Tanimoto, Ken-ichi [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

1999-04-01

In making a plan of decommissioning of nuclear fuel facilities, it is important to optimize the plan on the standpoint of a few viewpoints, that is, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost (they are called evaluation indexes). In the midst of decommissioning, the decommissioning plan would be modified suitably to optimize the evaluation indexes adjusting to progress of the decommissioning. The decommissioning management code (DECMAN), that is support system on computer, has been developed to assist the decommissioning planning. The system calculates the evaluation indexes quantitatively. The system consists of three fundamental codes, facility information database code, technical know-how database code and index evaluation code, they are composed using Oracle' database and 'G2' expert system. The functions of the system are as follows. (1) Facility information database code. Information of decommissioning facility and its rooms, machines and pipes in the code. (2) Technical know-how database code. Technical Information of tools to use in decommissioning work, cutting, dose measure, and decontamination are there. (3) Index evaluation code. User build decommissioning program using above two database codes. The code evaluates five indexes, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost, on planning decommissioning program. Results of calculation are shown in table, chart, and etc. (author)

Utility industry evaluation of the metal fuel facility and metal fuel performance for liquid metal reactors

International Nuclear Information System (INIS)

Burstein, S.; Gibbons, J.P.; High, M.D.; O'Boyle, D.R.; Pickens, T.A.; Pilmer, D.F.; Tomonto, J.R.; Weinberg, C.J.

1990-02-01

A team of utility industry representatives evaluated the liquid metal reactor metal fuel process and facility conceptual design being developed by Argonne National Laboratory (ANL) under Department of Energy sponsorship. The utility team concluded that a highly competent ANL team was making impressive progress in developing high performance advanced metal fuel and an economic processing and fabrication technology. The utility team concluded that the potential benefits of advanced metal fuel justified the development program, but that, at this early stage, there are considerable uncertainties in predicting the net overall economic benefit of metal fuel. Specific comments and recommendations are provided as a contribution towards enhancing the development program. 6 refs

A Medical Research and Evaluation Facility (MREF) and Studies Supporting the Medical Chemical Defense Program. Evaluation of the Passive Protection Against Five Serotypes of Botulinum Toxin Provided by Botulinum Human Immune Globulin in an Animal Model

National Research Council Canada - National Science Library

Olson, Carl

1998-01-01

Pentavalent (ABCDE) botulinum toxoid vaccine is intended for use as a prophylactic measure to protect combat troops against the lethal effects of botulinum toxins A-E, a group of toxins considered to be a serious biological warfare threat...

Air pollution control system testing at the DOE offgas components test facility

International Nuclear Information System (INIS)

Burns, D.B.; Speed, D.; VanPelt, W.; Burns, H.H.

1997-01-01

In 1997, the Department of Energy (DOE) Savannah River Site (SRS) plans to begin operation of the Consolidated Incineration Facility (CIF) to treat solid and liquid RCRA hazardous and mixed wastes. The Savannah River Technology Center (SRTC) leads an extensive technical support program designed to obtain incinerator and air pollution control equipment performance data to support facility start-up and operation. A key component of this technical support program includes the Offgas Components Test Facility (OCTF), a pilot-scale offgas system test bed. The primary goal for this test facility is to demonstrate and evaluate the performance of the planned CIF Air Pollution Control System (APCS). To accomplish this task, the OCTF has been equipped with a 1/10 scale CIF offgas system equipment components and instrumentation. In addition, the OCTF design maximizes the flexibility of APCS operation and facility instrumentation and sampling capabilities permit accurate characterization of all process streams throughout the facility. This allows APCS equipment performance to be evaluated in an integrated system under a wide range of possible operating conditions. This paper summarizes the use of this DOE test facility to successfully demonstrate APCS operability and maintainability, evaluate and optimize equipment and instrument performance, and provide direct CIF start-up support. These types of facilities are needed to permit resolution of technical issues associated with design and operation of systems that treat and dispose combustible hazardous, mixed, and low-level radioactive waste throughout and DOE complex

Evaluation of pelletron accelerator facility to study radiation effects on semiconductor devices

Energy Technology Data Exchange (ETDEWEB)

Prakash, A. P. Gnana; Pushpa, N.; Praveen, K. C.; Naik, P. S.; Revannasiddaiah, D. [Department of Studies in Physics, University of Mysore, Manasagangotri, Mysore-570006, Karnataka (India)

2012-06-05

In this paper we present the comprehensive results on the effects of different radiation on the electrical characteristics of different semiconductor devices like Si BJT, n-channel MOSFETs, 50 GHz and 200 GHz silicon-germanium heterojunction bipolar transistor (SiGe HBTs). The total dose effects of different radiation are compared in the same total dose ranging from 100 krad to 100 Mrad. We show that the irradiation time needed to reach very high total dose can be reduced by using Pelletron accelerator facilities instead of conventional irradiation facilities.

Evaluation of pelletron accelerator facility to study radiation effects on semiconductor devices

International Nuclear Information System (INIS)

Prakash, A. P. Gnana; Pushpa, N.; Praveen, K. C.; Naik, P. S.; Revannasiddaiah, D.

2012-01-01

In this paper we present the comprehensive results on the effects of different radiation on the electrical characteristics of different semiconductor devices like Si BJT, n-channel MOSFETs, 50 GHz and 200 GHz silicon-germanium heterojunction bipolar transistor (SiGe HBTs). The total dose effects of different radiation are compared in the same total dose ranging from 100 krad to 100 Mrad. We show that the irradiation time needed to reach very high total dose can be reduced by using Pelletron accelerator facilities instead of conventional irradiation facilities.

Reliability study: maintenance facilities Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

Post, B.E.; Sikorski, P.A.; Fankell, R.; Johnson, O.; Ferryman, D.S.; Miller, R.L.; Gearhart, E.C.; Rafferty, M.J.

1981-08-01

A reliability study of the maintenance facilities at the Portsmouth Gaseous Diffusion Plant has been completed. The reliability study team analyzed test data and made visual inspections of each component contributing to the overall operation of the facilities. The impacts of facilities and equipment failures were given consideration with regard to personnel safety, protection of government property, health physics, and environmental control. This study revealed that the maintenance facilities are generally in good condition. After evaluating the physical condition and technology status of the major components, the study team made several basic recommendations. Implementation of the recommendations proposed in this report will help assure reliable maintenance of the plant through the year 2000

Performance Evaluation of the International Space Station Flow Boiling and Condensation Experiment (FBCE) Test Facility

Science.gov (United States)

Hasan, Mohammad; Balasubramaniam, R.; Nahra, Henry; Mackey, Jeff; Hall, Nancy; Frankenfield, Bruce; Harpster, George; May, Rochelle; Mudawar, Issam; Kharangate, Chirag R.;

Safety study of fire protection for nuclear fuel cycle facility

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Based on the investigation of fire protection standards for domestic and foreign nuclear facilities, the fire protection guideline for nuclear fuel cycle facility has been completed. In 2012, trial operation is started by private company using the guideline. In addition, the acquisition of fire evaluation data for a components (electric cable) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

Safety study of fire protection for nuclear fuel cycle facility

International Nuclear Information System (INIS)

2013-01-01

Based on the investigation of fire protection standards for domestic and foreign nuclear facilities, the fire protection guideline for nuclear fuel cycle facility has been completed. In 2012, trial operation is started by private company using the guideline. In addition, the acquisition of fire evaluation data for a components (electric cable) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

Validity and Utilization of the Out-Pile Testing Facilities at HANARO

Energy Technology Data Exchange (ETDEWEB)

Choo, Kee-Nam; Cho, Man-Soon; Yang, Sung-Woo; Shin, Yoon-Taek; Park, Seng-Jae; Jun, Byung-Hyuk; Kim, Myong-Seop [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Various neutron irradiation facilities such as rabbit irradiation facilities, loop facilities and the capsule irradiation facilities for irradiation tests of nuclear materials, fuels and radioisotope products have been developed at HANARO. Among these irradiation facilities, the capsule is the most useful device for coping with the various test requirements at HANARO. To support the national research and development programs on nuclear reactors and the nuclear fuel cycle technology in Korea, new irradiation capsules have been developed and actively utilized for the irradiation tests requested by numerous users. The environmental conditions for these reactors are generally beyond present day reactor technology, especially regarding the higher neutron fluence and higher operating temperature. To effectively support the national R and Ds relevant to the future nuclear systems, the development of advanced irradiation technologies concerning higher neutron fluence and irradiation temperature are being preferentially developed at HANARO. The utilization of the out-pile testing facilities to satisfy the criteria of safety evaluation for a new device installed in the core of HANARO was summarized. In addition, the validity of the out-pile testing facilities was evaluated and proved to be effective for verifying the integrity of irradiation capsule.

Validity and Utilization of the Out-Pile Testing Facilities at HANARO

International Nuclear Information System (INIS)

Choo, Kee-Nam; Cho, Man-Soon; Yang, Sung-Woo; Shin, Yoon-Taek; Park, Seng-Jae; Jun, Byung-Hyuk; Kim, Myong-Seop

2016-01-01

Various neutron irradiation facilities such as rabbit irradiation facilities, loop facilities and the capsule irradiation facilities for irradiation tests of nuclear materials, fuels and radioisotope products have been developed at HANARO. Among these irradiation facilities, the capsule is the most useful device for coping with the various test requirements at HANARO. To support the national research and development programs on nuclear reactors and the nuclear fuel cycle technology in Korea, new irradiation capsules have been developed and actively utilized for the irradiation tests requested by numerous users. The environmental conditions for these reactors are generally beyond present day reactor technology, especially regarding the higher neutron fluence and higher operating temperature. To effectively support the national R and Ds relevant to the future nuclear systems, the development of advanced irradiation technologies concerning higher neutron fluence and irradiation temperature are being preferentially developed at HANARO. The utilization of the out-pile testing facilities to satisfy the criteria of safety evaluation for a new device installed in the core of HANARO was summarized. In addition, the validity of the out-pile testing facilities was evaluated and proved to be effective for verifying the integrity of irradiation capsule

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