1998 interim 242-A Evaporator tank system integrity assessment report

Energy Technology Data Exchange (ETDEWEB)

Jensen, C.E.

1998-07-02

This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ``dangerous waste storage or treatment tank and its ancillary equipment and containment.`` This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, as a result of project B-534, were evaluated in the 1993 facility interim integrity assessment. Since that time, the following upgrades have occurred in the facility: installation of a process condensate recycle system, and installation of a package steam boiler to provide steam for the facility. The package boiler is not within the scope of the facility TSD.

1998 interim 242-A Evaporator tank system integrity assessment report

International Nuclear Information System (INIS)

Jensen, C.E.

1998-01-01

This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ''dangerous waste storage or treatment tank and its ancillary equipment and containment.'' This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, as a result of project B-534, were evaluated in the 1993 facility interim integrity assessment. Since that time, the following upgrades have occurred in the facility: installation of a process condensate recycle system, and installation of a package steam boiler to provide steam for the facility. The package boiler is not within the scope of the facility TSD

Power system technical performance issues related to the application of long HVAC cables

DEFF Research Database (Denmark)

Wiechowski, on behalf of Cigre WG C4.502, W.; Sluis, L. V. der; Ohno, Teruo

2011-01-01

This paper reports the progress of work of Cigre Working Group C4.502 “Power system technical performance issues related to the application of long HVAC cables”. The primary goal of the WG C4.502 is to write a technical brochure that will serve as practical guide for performing studies necessary...... for assessing the technical performance of HV/EHV systems with large share of AC cable lines. This paper besides providing a background for formulation of WG C4.502 and its overall aim, describes the tasks that were accomplished before the interim report was submitted to Study Committee C4 System Technical...... Performance in August 2010. The work in the WG is ongoing and final report will be ready according to the time schedule in 2012. The focus of this paper is in particular to show all issues related to system technical performance with assigned weights in terms of their importance and/or uniqueness for cable...

Feasibility study on commercialization of fast breeder reactor cycle systems interim report of phase II. Technical study report for nuclear fuel cycle systems

International Nuclear Information System (INIS)

Sato, Koji; Amamoto, Ippei; Inoue, Akira

2004-06-01

As a part of the feasibility study on commercialization of fast breeder reactor cycle systems, the plant concept concerning the fuel cycle systems (combination of the reprocessing and the fuel fabrication) has been constructed to reduce their total cost by the introduction of various innovative techniques and to apply their utmost superior efficiency from such standpoints of a decrease in the environmental burden, better resource utilization and proliferation resistance improvement by the low decontamination transuranium element (TRU) recycle. This interim report of Phase II describes the results of an on-going study which will cover a five-year period. For oxide fuels, the system which combines the use of the advanced aqueous reprocessing using three main methods such as the crystallization method, the simplified solvent extraction method, and the extraction chromatography method for minor actinide (MA) recovery, as well as the simplified pelletizing fuel fabrication which rationalized a powder mixing process etc., has abundant current results and a high technical feasibility for the basic process. Though this system faces difficulties in the technical development of control technology of the extraction chromatography and the fabrication technology of low decontamination TRU fuel etc., its expected practical use is possible at an early stage. As for the super-critical direct extraction reprocessing, it is necessary to fulfill more basic data although further economical improvement of an advanced aqueous reprocessing is expected. The system which combines the advanced aqueous reprocessing and the gelation sphere packing fuel fabrication has the advantage of lesser dispersion of the fine powder due to the use of solution and granule in the fuel fabrication process. However, this system will shoulder additional cost for the reagent recovery process and the waste liquid treatment process due to need to dispose of a large bulk of process waste liquid. The system which

Solid waste burial grounds interim safety analysis

International Nuclear Information System (INIS)

Saito, G.H.

1994-01-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

Solid waste burial grounds interim safety analysis

Energy Technology Data Exchange (ETDEWEB)

Saito, G.H.

1994-10-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

Effectiveness of interim stage filter in the exhaust system of glove boxes

International Nuclear Information System (INIS)

Patre, D.K.; Vangara, H.; Thanamani, S.; Gopalakrishnan, R.K.; Mhatre, Amol M.

2018-01-01

All operations in radiochemical laboratories are carried out in containment systems like Glove boxes and Fume hoods. For controlling air contamination two separate air cleaning systems are incorporated. Laboratory has general ventilation system and glove boxes are provided with a negative pressure system (NPS). Glove box exhaust air is passed through three stage filtration systems: in situ, interim and final before discharging to the atmosphere. In addition to the individual HEPA filters of each glove box, there is an interim HEPA filter bank introduced at the laboratory end. This was introduced to reduce a load on main exhaust filter system. Finally the exhaust air is discharged through the final stage HEPA filter located in the filter house through the Stack. The interim HEPA filter bank provides additional protection for the release of particulate activity and reduces load on the final stage filters. In the present work efforts have been put to validate the interim stage filter, which has been introduced, to limit the environmental release

Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983

International Nuclear Information System (INIS)

Patrick, W.C.; Butkovich, T.R.; Carlson, R.C.

1984-02-01

The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables

Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983

Energy Technology Data Exchange (ETDEWEB)

Patrick, W.C.; Butkovich, T.R.; Carlson, R.C.; Durham, W.B.; Ganow, H.C.; Hage, G.L.; Majer, E.L.; Montan, D.N.; Nyholm, R.A.; Rector, N.L.

1984-02-01

The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables.

Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

Energy Technology Data Exchange (ETDEWEB)

Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

2012-05-07

This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

Interim storage of radioactive waste packages

International Nuclear Information System (INIS)

1998-01-01

This report covers all the principal aspects of production and interim storage of radioactive waste packages. The latest design solutions of waste storage facilities and the operational experiences of developed countries are described and evaluated in order to assist developing Member States in decision making and design and construction of their own storage facilities. This report is applicable to any category of radioactive waste package prepared for interim storage, including conditioned spent fuel, high level waste and sealed radiation sources. This report addresses the following issues: safety principles and requirements for storage of waste packages; treatment and conditioning methods for the main categories of radioactive waste; examples of existing interim storage facilities for LILW, spent fuel and high level waste; operational experience of Member States in waste storage operations including control of storage conditions, surveillance of waste packages and observation of the behaviour of waste packages during storage; retrieval of waste packages from storage facilities; technical and administrative measures that will ensure optimal performance of waste packages subject to various periods of interim storage

Laboratory technical services provides business opportunities for supervisory control and data acquisition systems

International Nuclear Information System (INIS)

Ballard, W.

1994-01-01

The author presents some additional information about what he considers are some really great opportunities for the business community to participate in developing the greatest scientific project in the history of mankind. Facility Engineering Services is part of Laboratory Technical Services. As part of this group, it has the responsibility to direct the construction of interim facilities, scientific labs, production process, cooling towers, cooling ponds and the operation and control of SSC Laboratory conventional support systems. These operations and controls will be accomplished through the employment of a Supervisory Control and Data Acquisition system (SCADA)

Interim research assessment 2003-2005 - Computer Science

NARCIS (Netherlands)

Mouthaan, A.J.; Hartel, Pieter H.

This report primarily serves as a source of information for the 2007 Interim Research Assessment Committee for Computer Science at the three technical universities in the Netherlands. The report also provides information for others interested in our research activities.

Single-shell tank interim stabilization project plan

Energy Technology Data Exchange (ETDEWEB)

Ross, W.E.

1998-03-27

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

Single-shell tank interim stabilization project plan

International Nuclear Information System (INIS)

Ross, W.E.

1998-01-01

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE's Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

1987 Federal interim storage fee study: A technical and economic analysis

International Nuclear Information System (INIS)

1987-09-01

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs

1987 Federal interim storage fee study: A technical and economic analysis

Energy Technology Data Exchange (ETDEWEB)

1987-09-01

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs.

System Specification for Immobilized High-Level Waste Interim Storage

International Nuclear Information System (INIS)

CALMUS, R.B.

2000-01-01

This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

Functions and requirements document for interim store solidified high-level and transuranic waste

Energy Technology Data Exchange (ETDEWEB)

Smith-Fewell, M.A., Westinghouse Hanford

1996-05-17

The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

Interim Hanford Waste Management Technology Plan

International Nuclear Information System (INIS)

1985-09-01

The Interim Hanford Waste Management Technology Plan (HWMTP) is a companion document to the Interim Hanford Waste Management Plan (HWMP). A reference plan for management and disposal of all existing and certain projected future radioactive Hanford Site Defense Wastes (HSDW) is described and discussed in the HWMP. Implementation of the reference plan requires that various open technical issues be satisfactorily resolved. The principal purpose of the HWMTP is to present detailed descriptions of the technology which must be developed to close each of the technical issues associated with the reference plan identified in the HWMP. If alternative plans are followed, however, technology development efforts including costs and schedules must be changed accordingly. Technical issues addressed in the HWMTP and HWMP are those which relate to disposal of single-shell tank wastes, contaminated soil sites, solid waste burial sites, double-shell tank wastes, encapsulated 137 CsCl and 90 SrF 2 , stored and new solid transuranic (TRU) wastes, and miscellaneous wastes such as contaminated sodium metal. Among the high priority issues to be resolved are characterization of various wastes including early determination of the TRU content of future cladding removal wastes; completion of development of vitrification (Hanford Waste Vitrification Plant) and grout technology; control of subsidence in buried waste sites; and development of criteria and standards including performance assessments of systems proposed for disposal of HSDW. Estimates of the technology costs shown in this report are made on the basis that all identified tasks for all issues associated with the reference disposal plan must be performed. Elimination of, consolidation of, or reduction in the scope of individual tasks will, of course, be reflected in corresponding reduction of overall technology costs

Technical study of a thermally dense long term interim storage facility

International Nuclear Information System (INIS)

Le Duigou, A.; Badie, M.; Duret, B.; Bricard, A.

2001-01-01

The COFRE concept is aimed at the surface and thermal densification of the interim storage facility for irradiated fuels. The facility provides the biological shielding. A conditioning cell is used to load and retrieve the fuel assemblies. The facility container is the second containment barrier. The high power levels are managed by an auxiliary cooling system whose original feature is the passive use of a water evaporation-condensation cycle in a sealed circuit. The removable evaporator abuts the container. The air cooled condenser is placed outside the facility. Contact resistance and heat pipe mode were successfully modelled and are undergoing experimental validation on the THERESE and REBECA loops. (author)

Single-shell tank interim stabilization project plan

Energy Technology Data Exchange (ETDEWEB)

Ross, W.E.

1998-05-11

This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

Safety of Long-term Interim Storage Facilities - Workshop Proceedings

International Nuclear Information System (INIS)

2014-01-01

The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided as well as a summary of the results of the workshop with the text of the papers given and presentations made

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

International Nuclear Information System (INIS)

1978-01-01

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-31

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein.

Standard Technical Specifications, Babcock and Wilcox Plants

International Nuclear Information System (INIS)

1992-09-01

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

Feasibility study on commercialization of fast breeder reactor cycle system. Interim report of phase 2. Technical study report on synthetic evaluation for FBR cycle

International Nuclear Information System (INIS)

Shiotani, Hiroki; Ohtaki, Akira; Ono, Kiyoshi; Yasumatsu, Naoto; Kubota, Sadae; Heta, Masanori

2004-09-01

This report presents the outline of the development and the results of Synthetic evaluation on the candidate Fast Reactor (FR) cycle system concepts, scenario study on FR cycle deployment and cost-benefit analysis on the candidate FR cycle system concepts in the interim evaluation (FY2001 through FY2003) of the phase 2 of the Japanese 'Feasibility Study on Commercialization of Fast Reactor Cycle System (FS)'. The characteristic evaluation extended to evaluate a new view point of social acceptance besides the viewpoints of safety, economics, reduction of environmental burden, efficient utilization of uranium resource, proliferation resistance, and technical feasibility, which has been considered since the phase 1 of FS. As for the six view points, hierarchy structures and utility functions for quantitative evaluation have been developed and/or improved. Furthermore, the methodology for weighing the viewpoints, which was also developed, made it possible to examine the characteristics of the candidate concepts from all the seven viewpoints. Generally, the FR cycles with sodium-cooled FR were highly evaluated. The characteristic evaluation for alternative power supply systems was also tried in this report for the first time. FR cycle deployment scenarios clarified the necessity of FR cycle deployment and the desirable core features, etc. through the long-term mass flow analysis, which includes comparison among other nuclear fuel cycle schemes and analysis for evaluating the degree to meet future needs, on the typical FR cycle systems. Regarding cost-benefit analysis, both the amount of the cost estimated by the past R and D and the cost in the Road map of FS are used as the investment for FR cycle research and development (R and D), the results showed that the benefit derived from the commercialization of FR cycle will be more than the investment. (author)

Cna 1 spent fuel element interim dry storage system thermal analysis

International Nuclear Information System (INIS)

Hilal, R. E; Garcia, J. C; Delmastro, D. F

2006-01-01

At the moment, the Atucha I Nuclear Power Plant (Cnea-I) located in the city of Lima, has enough room to store its spent fuel (Sf) in their two pools spent fuel until about 2015.In case of life extension a spend fuel element interim dry storage system is needed.Nucleolectrica Argentina S.A. (N A-S A) and the Comision Nacional de Energia Atomica (Cnea), have proposed different interim dry storage systems.These systems have to be evaluated in order to choose one of them.The present work's objective is the thermal analysis of one dry storage alternative for the Sf element of Cna 1.In this work a simple model was developed and used to perform the thermal calculations corresponding to the system proposed by Cnea.This system considers the store of sealed containers with 37 spent fuels in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.Fulfill the maximum cladding temperature requirement ( [es

Single-Shell Tank (SST) Interim Stabilization Project Plan

International Nuclear Information System (INIS)

VLADIMIROFF, D.T.; BOYLES, V.C.

2000-01-01

This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline

FRACTIONAL CRYSTALLIZATION TESTING WITH INTERIM PRETREATMENT SYSTEM FEEDS

International Nuclear Information System (INIS)

HERTING DL

2008-01-01

The fractional crystallization process was developed as a pretreatment method for saltcake waste retrieved from Hanford single-shell tanks (SST). The process separates the retrieved SST waste into a high-level waste stream containing the bulk of the radionuclides and a low-activity waste stream containing the bulk of the nonradioactive sodium salts. The Interim Pretreatment System project shifted the focus on pretreatment planning from SST waste to double-shell tank waste

Interim dry storage system technologies and innovations VARNA 2002

International Nuclear Information System (INIS)

Chollet, P.; Guenon, Y.

2002-01-01

The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

75 FR 13680 - Commutation of Sentence: Technical Change

Science.gov (United States)

2010-03-23

... Sentence: Technical Change AGENCY: Bureau of Prisons, Justice. ACTION: Interim rule. SUMMARY: This document makes a minor technical change to the Bureau of Prisons (Bureau) regulations on sentence commutation to.... Commutation of Sentence: Technical Change This document makes a minor technical change to the Bureau...

Cost Implications of an Interim Storage Facility in the Waste Management System

Energy Technology Data Exchange (ETDEWEB)

Jarrell, Joshua J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Joseph, III, Robert Anthony [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howard, Rob L [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Petersen, Gordon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Nutt, Mark [Argonne National Lab. (ANL), Argonne, IL (United States); Carter, Joe [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cotton, Thomas [Complex Systems Group, Bozeman, MT (United States)

2016-09-01

This report provides an evaluation of the cost implications of incorporating a consolidated interim storage facility (ISF) into the waste management system (WMS). Specifically, the impacts of the timing of opening an ISF relative to opening a repository were analyzed to understand the potential effects on total system costs.

Interim restorations.

Science.gov (United States)

Gratton, David G; Aquilino, Steven A

2004-04-01

Interim restorations are a critical component of fixed prosthodontic treatment, biologically and biomechanically. Interim restoration serves an important diagnostic role as a functional and esthetic try-in and as a blueprint for the design of the definitive prosthesis. When selecting materials for any interim restoration, clinicians must consider physical properties, handling properties, patient acceptance, and material cost. Although no single material meets all the requirements and material classification alone of a given product is not a predictor of clinical performance, bis-acryl materials are typically best suited to single-unit restorations, and poly(methylmethacrylate) interim materials are generally ideal for multi-unit, complex, long-term, interim fixed prostheses. As with most dental procedures, the technique used for fabrication has a greater effect on the final result than the specific material chosen.

Pathways to deep decarbonization - Interim 2014 Report

International Nuclear Information System (INIS)

2014-01-01

The interim 2014 report by the Deep Decarbonization Pathways Project (DDPP), coordinated and published by IDDRI and the Sustainable Development Solutions Network (SDSN), presents preliminary findings of the pathways developed by the DDPP Country Research Teams with the objective of achieving emission reductions consistent with limiting global warming to less than 2 deg. C. The DDPP is a knowledge network comprising 15 Country Research Teams and several Partner Organizations who develop and share methods, assumptions, and findings related to deep decarbonization. Each DDPP Country Research Team has developed an illustrative road-map for the transition to a low-carbon economy, with the intent of taking into account national socio-economic conditions, development aspirations, infrastructure stocks, resource endowments, and other relevant factors. The interim 2014 report focuses on technically feasible pathways to deep decarbonization

Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

International Nuclear Information System (INIS)

Hauer, K.A.; Wilson, J.F.

1992-01-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC)

Tribal child welfare. Interim final rule.

Science.gov (United States)

2012-01-06

The Administration for Children and Families (ACF) is issuing this interim final rule to implement statutory provisions related to the Tribal title IV-E program. Effective October 1, 2009, section 479B(b) of the Social Security Act (the Act) authorizes direct Federal funding of Indian Tribes, Tribal organizations, and Tribal consortia that choose to operate a foster care, adoption assistance and, at Tribal option, a kinship guardianship assistance program under title IV-E of the Act. The Fostering Connections to Success and Increasing Adoptions Act of 2008 requires that ACF issue interim final regulations which address procedures to ensure that a transfer of responsibility for the placement and care of a child under a State title IV-E plan to a Tribal title IV-E plan occurs in a manner that does not affect the child's eligibility for title IV-E benefits or medical assistance under title XIX of the Act (Medicaid) and such services or payments; in-kind expenditures from third-party sources for the Tribal share of administration and training expenditures under title IV-E; and other provisions to carry out the Tribal-related amendments to title IV-E. This interim final rule includes these provisions and technical amendments necessary to implement a Tribal title IV-E program.

Interim Policy Options for Commercialization of Solar Heating and Cooling Systems.

Science.gov (United States)

Bezdek, Roger

This interim report reviews the major incentive policy options available to accelerate market penetration of solar heating and cooling (SHAC) systems. Feasible policy options designed to overcome existing barriers to commercial acceptance and market penetration are identified and evaluated. The report is divided into seven sections, each dealing…

Interim Measures Work Plan Expanded Bioventing System SWMU 55 (IRP Site FT-03)

National Research Council Canada - National Science Library

1997-01-01

This interim measures work plan (IMWP) presents the scope for an expanded bioventing system to conduct in situ treatment of the remaining fuel-contaminated soils at solid waste management unit (SWMU...

Overview of technical Issues Associated with the Long Term Storage of Light Water Reactor used Nuclear Fuel

International Nuclear Information System (INIS)

Sorenson, Ken B.

2014-01-01

The nuclear power technical community is developing the technical basis for demonstrating the safety of storing used nuclear fuel for extended periods of time. The combination of reactor operations that off-load spent fuel to interim storage, coupled with delays in repository construction, has resulted in the expectation that storage periods may be for longer periods of time than originally intended. As more fuel continues to be off-loaded from operating reactors, the need for expanded interim storage also increases. As repository programs are delayed, interim storage requirements will likely exceed licensing term limits. To address these operational realities, there has been a concerted international effort to identify and prioritize the technical issues that need to be addressed in order to demonstrate the safety of storing used nuclear fuel for extended periods of time. Since this is an international effort, different storage systems, regulations, and policies need to be considered. This results in differences in technical issues, as well as differences in priorities. However, this effort also identifies important commonalities in some technical areas that need to be addressed. A broad-based international evaluation of these technical issues provides a better understanding of technical concerns as they relate to individual storage systems and specific national regulatory frameworks. While there are several international activities underway that are focused on long term storage, this paper will discuss the activities of the Electric Power Research Institute (EPRI)/Extended Storage Collaboration Program (ESCP) International Subcommittee. A status report detailing the identification and prioritization of the technical issues was presented at the PSAM11 Conference in June 2012 (1). Since that conference, a final report has been completed by the EPRI/ESCP International Subcommittee (2). This paper will provide important results of the final report as well as

National NIF Diagnostic Program Interim Management Plan

International Nuclear Information System (INIS)

Warner, B

2002-01-01

The National Ignition Facility (NIF) has the mission of supporting Stockpile Stewardship and Basic Science research in high-energy-density plasmas. To execute those missions, the facility must provide diagnostic instrumentation capable of observing and resolving in time events and radiation emissions characteristic of the plasmas of interest. The diagnostic instrumentation must conform to high standards of operability and reliability within the NIF environment. These exacting standards, together with the facility mission of supporting a diverse user base, has led to the need for a central organization charged with delivering diagnostic capability to the NIF. The National NIF Diagnostics Program (NNDP) has been set up under the aegis of the NIF Director to provide that organization authority and accountability to the wide user community for NIF. The funds necessary to perform the work of developing diagnostics for NIF will be allocated from the National NIF Diagnostics Program to the participating laboratories and organizations. The participating laboratories and organizations will design, build, and commission the diagnostics for NIF. Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize NIF Core Diagnostics Systems and Cryogenic Target Handing Systems, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NIF Core Diagnostics Systems. Preparation of a Program Execution Plan for NIF Core Diagnostics Systems has been initiated and a current draft is provided as Attachment 1 to this document. The National NIF Diagnostics Program Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope

A web-based endpoint adjudication system for interim analyses in clinical trials.

Science.gov (United States)

Nolen, Tracy L; Dimmick, Bill F; Ostrosky-Zeichner, Luis; Kendrick, Amy S; Sable, Carole; Ngai, Angela; Wallace, Dennis

2009-02-01

A data monitoring committee (DMC) is often employed to assess trial progress and review safety data and efficacy endpoints throughout a trail. Interim analyses performed for the DMC should use data that are as complete and verified as possible. Such analyses are complicated when data verification involves subjective study endpoints or requires clinical expertise to determine each subject's status with respect to the study endpoint. Therefore, procedures are needed to obtain adjudicated data for interim analyses in an efficient manner. In the past, methods for handling such data included using locally reported results as surrogate endpoints, adjusting analysis methods for unadjudicated data, or simply performing the adjudication as rapidly as possible. These methods all have inadequacies that make their sole usage suboptimal. For a study of prophylaxis for invasive candidiasis, adjudication of both study eligibility criteria and clinical endpoints prior to two interim analyses was required. Because the study was expected to enroll at a moderate rate and the sponsor required adjudicated endpoints to be used for interim analyses, an efficient process for adjudication was required. We created a web-based endpoint adjudication system (WebEAS) that allows for expedited review by the endpoint adjudication committee (EAC). This system automatically identifies when a subject's data are complete, creates a subject profile from the study data, and assigns EAC reviewers. The reviewers use the WebEAS to review the subject profile and submit their completed review form. The WebEAS then compares the reviews, assigns an additional review as a tiebreaker if needed, and stores the adjudicated data. The study for which this system was originally built was administratively closed after 10 months with only 38 subjects enrolled. The adjudication process was finalized and the WebEAS system activated prior to study closure. Some website accessibility issues presented initially. However

Interim report to the Nuclear Regulatory Commission on radioactive waste classification

International Nuclear Information System (INIS)

King, W.C.; Cohen, J.J.

1977-01-01

The Lawrence Livermore Laboratory assisted the Nuclear Regulatory Commission in the development of a radioactive waste classification system that will satisfy technical, environmental, and societal concerns. This is an interim report to the NRC on work accomplished to date. It describes a proposed waste-classification system that is based on the final disposition of waste material. The system consists of three classes of radioactive waste. The classification of any radioactive waste will depend primarily on its hazard potential. Other characteristics such as longevity (half-size) will be considered also. The levels of hazard that differentiate the three classes of radioactive waste will be determined by ongoing work. This report describes other work to be completed before a suitable radioactive waste-classificaion system is established

Standard Technical Specifications, Westinghouse Plants

International Nuclear Information System (INIS)

1992-09-01

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

How the University of Texas system responded to the need for interim storage of low-level radioactive waste materials.

Science.gov (United States)

Emery, Robert J

2012-11-01

Faced with the prospect of being unable to permanently dispose of low-level radioactive wastes (LLRW) generated from teaching, research, and patient care activities, component institutions of the University of Texas System worked collaboratively to create a dedicated interim storage facility to be used until a permanent disposal facility became available. Located in a remote section of West Texas, the University of Texas System Interim Storage Facility (UTSISF) was licensed and put into operation in 1993, and since then has provided safe and secure interim storage for up to 350 drums of dry solid LLRW at any given time. Interim storage capability provided needed relief to component institutions, whose on-site waste facilities could have possibly become overburdened. Experiences gained from the licensing and operation of the site are described, and as a new permanent LLRW disposal facility emerges in Texas, a potential new role for the storage facility as a surge capacity storage site in times of natural disasters and emergencies is also discussed.

Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

Energy Technology Data Exchange (ETDEWEB)

Hauer, K.A. (Westinghouse Savannah River Co., Aiken, SC (United States)); Wilson, J.F. (PRC, Inc. (US))

1992-01-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

Software Verification and Validation Report for the 244-AR Vault Interim Stabilization Ventilation System

International Nuclear Information System (INIS)

YEH, T.

2002-01-01

This document reports on the analysis, testing and conclusions of the software verification and validation for the 244-AR Vault Interim Stabilization ventilation system. Automation control system will use the Allen-Bradley software tools for programming and programmable logic controller (PLC) configuration. The 244-AR Interim Stabilization Ventilation System will be used to control the release of radioactive particles to the environment in the containment tent, located inside the canyon of the 244-AR facility, and to assist the waste stabilization efforts. The HVAC equipment, ducts, instruments, PLC hardware, the ladder logic executable software (documented code), and message display terminal are considered part of the temporary ventilation system. The system consists of a supply air skid, temporary ductwork (to distribute airflow), and two skid-mounted, 500-cfm exhausters connected to the east filter building and the vessel vent system. The Interim Stabilization Ventilation System is a temporary, portable ventilation system consisting of supply side and exhaust side. Air is supplied to the containment tent from an air supply skid. This skid contains a constant speed fan, a pre-filter, an electric heating coil, a cooling coil, and a constant flow device (CFD). The CFD uses a passive component that allows a constant flow of air to pass through the device. Air is drawn out of the containment tent, cells, and tanks by two 500-cfm exhauster skids running in parallel. These skids are equipped with fans, filters, stack, stack monitoring instrumentation, and a PLC for control. The 500CFM exhaust skids were fabricated and tested previously for saltwell pumping activities. The objective of the temporary ventilation system is to maintain a higher pressure to the containment tent, relative to the canyon and cell areas, to prevent contaminants from reaching the containment tent

Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

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

Expansion of storage capacity of interim spent fuel storage (MSVP) Bohunice

International Nuclear Information System (INIS)

Pilat, P.; Fridrich, V.

2005-01-01

This article describes modifications of Interim spent fuel storage, performed with aim of storage capacity expansion, seismic stability enhancement, and overall increase of service life as well as assuring of MSVP safe operation. Uniqueness of adopted technical solutions is based upon the fact that mentioned innovations and modifications were performed without any changes, neither in ground plan nor architecture of MSVP structure. It also important to mention that all modifications were performed during continual operation of MSVP without any breaks of limits or operational regulations. Reconstruction and innovation of existing construction and technological systems of MSVP has assured required quality standard comparable with actual trends. (authors)

Safety report for Central Interim Storage facility for radioactive waste from small producers

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.

2004-01-01

In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage (CIS) in Brinje, intended only for radioactive waste from industrial, medical and research applications. With the transfer of the responsibilities for the storage operation, ARAO, the new operator of the facility, received also the request from the Slovenian Nuclear Safety Administration for refurbishment and reconstruction of the storage and for preparation of the safety report for the storage with the operational conditions and limitations. In order to fulfill these requirements ARAO first thoroughly reviewed the existing documentation on the facility, the facility itself and the stored inventory. Based on the findings of this review ARAO prepared several basic documents for improvement of the current conditions in the storage facility. In October 2000 the Plan for refurbishment and modernization of the CIS was prepared, providing an integral approach towards remediation and refurbishment of the facility, optimization of the inventory arrangement and modernization of the storage and storing utilization. In October 2001 project documentation for renewal of electric installations, water supply and sewage system, ventilation system, the improvements of the fire protection and remediation of minor defects discovered in building were completed according to the Act on Construction. In July 2003 the safety report was prepared, based on the facility status after the completion of the reconstruction works. It takes into account all improvements and changes introduced by the refurbishment and reconstruction of the facility according to project documentation. Besides the basic characteristics of the location and its surrounding, it also gives the technical description of the facility together with proposed solutions for the renewal of electric installations, renovation of water supply and sewage system, refurbishment of the ventilation system, the improvement of fire

Reliability Centered Maintenance for Savannah River Site`s interim waste management facilities. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hauer, K.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilson, J.F. [PRC, Inc. (US)

1992-06-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

Evaluation of Hose in Hose Transfer Line Service Life for Hanford's Interim Stabilization Program

International Nuclear Information System (INIS)

TORRES, T.D.

2000-01-01

RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program, defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program, has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning. Prudent engineering dictates that the equipment placed in service have a working life in excess of this forecasted time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer and published literature. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are process fluid characteristics, ambient environmental conditions, and the manufacturer's stated shelf life. This evaluation examines the manufacturer's certification of shelf life, the manufacturer's certifications of chemical compatibility with waste, and published literature on the effects of exposure to ionizing radiation on the mechanical properties of elastomeric materials to evaluate transfer line service life

78 FR 76160 - Public Housing Assessment System (PHAS) Capital Fund Interim Scoring Notice: Reinstitution of...

Science.gov (United States)

2013-12-16

... System (PHAS) Capital Fund Interim Scoring Notice: Reinstitution of Five Points for Occupancy Sub... intended to help lessen the impact of decreases in funding in recent appropriations acts. Adding automatic... to adjust their systems and procedures to the new scoring regime. As a result of automatic across-the...

Long-term interim storage concepts with conditioning strategies ensuring compatibility with subsequent disposal or reprocessing

International Nuclear Information System (INIS)

Moitrier, C.; Tirel, I.; Villard, C.

2000-01-01

The objective of the CEA studies carried out under research topic 3 (long-term interim storage) of the 1991 French radioactive waste management law is to demonstrate the industrial feasibility of a comprehensive, flexible interim storage facility by thoroughly evaluating and comparing all the basic components of various interim storage concepts. In this context, the CEA is considering reference solutions or concepts based on three primary components (the package, the interim storage facility and the site) suitable for determining the specifications of a very long-term solution. Some aspects are examined in greater detail, such as the implementation of long-term technologies, conditioning processes ensuring the absence of water and contamination in the facility, or allowance for radioactive decay of the packages. The results obtained are continually compiled in reports substantiating the design options. These studies should also lead to an overall economic assessment in terms of the capital and operating cost requirements, thereby providing an additional basis for selecting the design options. The comparison with existing industrial facilities highlights the technical and economic progress represented by the new generation of interim storage units. (authors)

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

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

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

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

National Ignition Facility Cryogenic Target Systems Interim Management Plan

International Nuclear Information System (INIS)

Warner, B

2002-01-01

Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety and Health (ES and H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

An interim report on the Zenith Exponential Experiments

Energy Technology Data Exchange (ETDEWEB)

Absalom, R M; Cameron, I R; Kinchin, G H; Sanders, J E; Wilson, D J [Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)

1959-06-15

The following memorandum gives an interim account of the exponential experiments with Zenith-type fuel elements being carried out at Winfrith. Results quoted are still subject to revision: however it is hoped that the description of the work at this stage will stimulate discussion and suggestions for further measurements before the experiment is dismantled later in the year. The measurements are being undertaken in order to form some initial understanding of the reactor physics of uranium 235-thorium-graphite systems of the type later to be studied in Zenith. There have been no previous investigations of this type of system in the U.K. though measurements on enriched uranium-graphite systems have been reported from the U.S.A.. A practical result of the measurements will be a revision of the estimated critical loadings for Zenith, since the exponential systems studied cover the range of loadings proposed for the first critical assemblies. The theoretical work on these systems includes a two-group analysis being carried on in the Zenith group and a multigroup analysis being made by the H.T.G.C. Technical Assessments Group, including a Monte Carlo study of resonance capture.

Evaluation of internal fit of interim crown fabricated with CAD/CAM milling and 3D printing system.

Science.gov (United States)

Lee, Wan-Sun; Lee, Du-Hyeong; Lee, Kyu-Bok

2017-08-01

This study is to evaluate the internal fit of the crown manufactured by CAD/CAM milling method and 3D printing method. The master model was fabricated with stainless steel by using CNC machine and the work model was created from the vinyl-polysiloxane impression. After scanning the working model, the design software is used to design the crown. The saved STL file is used on the CAD/CAM milling method and two types of 3D printing method to produce 10 interim crowns per group. Internal discrepancy measurement uses the silicon replica method and the measured data are analyzed with One-way ANOVA to verify the statistic significance. The discrepancy means (standard deviation) of the 3 groups are 171.6 (97.4) µm for the crown manufactured by the milling system and 149.1 (65.9) and 91.1 (36.4) µm, respectively, for the crowns manufactured with the two types of 3D printing system. There was a statistically significant difference and the 3D printing system group showed more outstanding value than the milling system group. The marginal and internal fit of the interim restoration has more outstanding 3D printing method than the CAD/CAM milling method. Therefore, the 3D printing method is considered as applicable for not only the interim restoration production, but also in the dental prosthesis production with a higher level of completion.

Immobilized high-level waste interim storage alternatives generation and analysis and decision report

International Nuclear Information System (INIS)

CALMUS, R.B.

1999-01-01

This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward

Design requirements document for Project W-465, immobilized low-activity waste interim storage

International Nuclear Information System (INIS)

Burbank, D.A.

1998-01-01

The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

RANET technical guidelines: Interim technical guidelines for national assistance capabilities. Emergency preparedness and response. Date effective: 1 January 2007

International Nuclear Information System (INIS)

2006-12-01

The publication is issued as an attachment to EPR-RANET (2006) and has the same status. It provides administrative and technical guidelines for National Assistance Capabilities and enters into effect on 1 January 2007. Additional technical guidelines are under development by assistance work group under international Action Plan for Strengthening the International Preparedness and Response System for Nuclear and Radiological Emergencies. As these are finalised they will be included in this document

Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks

International Nuclear Information System (INIS)

Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

2004-01-01

Based on the German decision to minimise transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities have been licensed till the end of 2003. Because of the large amount of type-B transport casks which are going to be used for long-term interim storage the question of time limited type-B license maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of transport cask qualification for interim storage is the long-term behaviour of the metallic seal lid system. Concerning this results from current experimental long-term tests with metallic ''Helicoflex''-seals in which pool water is enclosed are presented. The test series has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an authorities' and technical experts' exchange of experience, know-how and state of the art referring to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called ''co-ordinating institution for cask dispatching information'' (''KOBAF'') which contains an online data base and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the next decades

Disposal facility data for the interim performance

International Nuclear Information System (INIS)

Eiholzer, C.R.

1995-01-01

The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

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

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

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

Interim report on research and development of super heat pump energy accumulation system by the evaluation working group; Super heat pump energy shuseki system hyoka work group chukan hyoka hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-03-01

The evaluation working group of the Large-scale Energy-saving Technology Research and Development Promotion Council has made an interim evaluation of the results obtained so far by the R and D project for the super heat pump energy accumulation systems. The working group evaluates the bench plant operation test results comprehensively, covering technical, economic and social aspects, and R and D promotion methodology. The working group has concluded that a significant technological break-through is made for the super high performance compression heat pumps, and the technological groundwork is now established for the future pilot system. For the chemical heat storage technologies, it is concluded that system feasibility is demonstrated, and the technological groundwork for the future development is established. The super heat pump is evaluated to potentially realize significant economic superiority over the conventional devices both in the domestic and industrial areas, and to be highly rated potentially in the areas of energy-saving, power load leveling and environmental preservation. (NEDO)

Evaluation of Hose in Hose Transfer Line Service Life for Hanford's Interim Stabilization Program

Energy Technology Data Exchange (ETDEWEB)

TORRES, T.D.

2000-08-24

RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program, defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program, has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning. Prudent engineering dictates that the equipment placed in service have a working life in excess of this forecasted time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer and published literature. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are process fluid characteristics, ambient environmental conditions, and the manufacturer's stated shelf life. This evaluation examines the manufacturer's certification of shelf life, the manufacturer's certifications of chemical compatibility with waste, and published literature on the effects of exposure to ionizing radiation on the mechanical properties of elastomeric materials to evaluate transfer line service life.

Conceptual design of interim storage facility for CNAI

International Nuclear Information System (INIS)

Fuenzalida Troyano, Carlos S.; Bergallo, Juan E.; Nassini, Horacio E.P.; Blanco, Anibal; Delmastro, Dario F.

2007-01-01

The reduced storage capacity available in the two spent fuel pools of argentine PHWR Atucha-1 power plant, the current plans for extending the reactor operation beyond its design lifetime, and the government decision on Atucha-2 NPP construction ending, have motivated the evaluation of a dry storage option for the interim management of spent fuel assemblies. Two different designs are presently being analyzed by an expert working group, from both technical and economical points of views. Authors are proposing a modular system consisting of an arrangement of reinforced concrete structures into which welded metallic canisters loaded with 37 spent fuel assemblies each stored in horizontal position. The reinforced concrete module is designed to provide the necessary physical protection and biological shielding to the loaded canisters during long-term storage, as well as passive means to remove the spent fuel decay heat by a combination of radiation, conduction and natural air convection. In this works are presented advances in the conceptual designs for a spent nuclear fuel system to Atucha I nuclear power plant. (author) [es

Permitting plan for the high-level waste interim storage

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

Interim overdentures.

Science.gov (United States)

Fenton, A H

1976-07-01

The construction of an interim overdenture using existing removable partial dentures with natural tooth crowns and artificial teeth can be a simple and economical method of providing patients with dentures while tissues heal and teeth are prepared and restored. A more definite prognosis for both the patient and his remaining dentition can be established before the final overdenture is completed. The procedures necessary to provide three types of interim overdentures have been outlined. Patients tolerate this method of changing their dentitions extremely well.

Safety aspects of long-term dry interim storage of Type B spent fuel and high-level transport casks

International Nuclear Information System (INIS)

Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

2004-01-01

Based on the German decision to minimise transport of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities were licensed until the end of 2003. Because of the large amount of Type B(U) transport casks which are going to be used for long-term interim storage the question of time-limited Type B(U) licence maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of qualification of transport casks for interim storage is the long-term behaviour of the metallic seal-lid system. Here we present results from current long-term experimental tests with metallic 'Helicoflex' seals in which pool water is enclosed. This series of tests has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an exchange of experience, know-how and state-of-the-art between authorities and technical experts with regard to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called 'coordinating institution for cask dispatching information' ('KOBAF') which entails management of an online database of cask-specific documents and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the coming decades. (author)

Radioactive waste interim storage in Germany

International Nuclear Information System (INIS)

2015-12-01

The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

Federal interim storage fee study for civilian spent nuclear fuel: a technical and economical analysis

International Nuclear Information System (INIS)

1983-07-01

This report describes the study conducted by the Department of Energy (the Department) regarding payment charges for the federal interim storage (FIS) of spent fuel and presents the details of the study results. It describes the selection of a methodology for calculating a FIS fee schedule, sets forth the estimates of cost for construction and operation of FIS facilities, provides a range of estimates for the fee for FIS services, and identifies special contractual considerations associated with providing FIS services to authorized users. The fee is structured for a range of spent fuel capacities because of uncertainties regarding the schedule of availability and amount of spent fuel that may require and qualify for FIS. The results set forth in the report were used as a basis for development of the report entitled Payment Charges for Federal Interim Storage of Spent Nuclear Fuel from Civilian Nuclear Power Plants in the United States, dated July 1983

Results from the Interim Salt Disposition Program Macrobatch 11 Tank 21H Acceptance Samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-11-13

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of verification of Macrobatch (Salt Batch) 11 for the Interim Salt Disposition Program (ISDP) for processing. This document reports characterization data on the samples of Tank 21H and fulfills the requirements of Deliverable 3 of the Technical Task Request (TTR).

Waste Management System Description Document (WMSD)

International Nuclear Information System (INIS)

1992-02-01

This report is an appendix of the ''Waste Management Description Project, Revision 1''. This appendix is about the interim approach for the technical baseline of the waste management system. It describes the documentation and regulations of the waste management system requirements and description. (MB)

Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

The challenges facing the long term interim storage

Energy Technology Data Exchange (ETDEWEB)

Iracane, D. [CEA Sacaly, Dir. de la Simulation et des Outils Experimentaux-DSOE, 91 - Gif sur Yvette (France); Marvy, A. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares-DDIN, 91 - Gif Sur Yvette (France)

2001-07-01

In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

The challenges facing the long term interim storage

International Nuclear Information System (INIS)

Iracane, D.; Marvy, A.

2001-01-01

In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-09-01

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

Interim Corrective Measures Work Plan for the Expanded Bioventing System Eglin Main Base Old Fire Training Area

National Research Council Canada - National Science Library

1997-01-01

This interim corrective measures work plan (ICM work plan) presents the scope for an expanded bioventing system for in situ treatment of fuel-contaminated soils at the Eglin Main Base Old Fire Training Area (old Eglin FTA...

An Experimental Seismic Data and Parameter Exchange System for Interim NEAMTWS

Science.gov (United States)

Hanka, W.; Hoffmann, T.; Weber, B.; Heinloo, A.; Hoffmann, M.; Müller-Wrana, T.; Saul, J.

2009-04-01

In 2008 GFZ Potsdam has started to operate its global earthquake monitoring system as an experimental seismic background data centre for the interim NEAMTWS (NE Atlantic and Mediterranean Tsunami Warning System). The SeisComP3 (SC3) software, developed within the GITEWS (German Indian Ocean Tsunami Early Warning System) project was extended to test the export and import of individual processing results within a cluster of SC3 systems. The initiated NEAMTWS SC3 cluster consists presently of the 24/7 seismic services at IMP, IGN, LDG/EMSC and KOERI, whereas INGV and NOA are still pending. The GFZ virtual real-time seismic network (GEOFON Extended Virtual Network - GEVN) was substantially extended by many stations from Western European countries optimizing the station distribution for NEAMTWS purposes. To amend the public seismic network (VEBSN - Virtual European Broadband Seismic Network) some attached centres provided additional private stations for NEAMTWS usage. In parallel to the data collection by Internet the GFZ VSAT hub for the secured data collection of the EuroMED GEOFON and NEAMTWS backbone network stations became operational and the first data links were established. In 2008 the experimental system could already prove its performance since a number of relevant earthquakes have happened in NEAMTWS area. The results are very promising in terms of speed as the automatic alerts (reliable solutions based on a minimum of 25 stations and disseminated by emails and SMS) were issued between 2 1/2 and 4 minutes for Greece and 5 minutes for Iceland. They are also promising in terms of accuracy since epicenter coordinates, depth and magnitude estimates were sufficiently accurate from the very beginning, usually don't differ substantially from the final solutions and provide a good starting point for the operations of the interim NEAMTWS. However, although an automatic seismic system is a good first step, 24/7 manned RTWCs are mandatory for regular manual verification

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

International Nuclear Information System (INIS)

1978-01-01

This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited

78 FR 63276 - Interim Policy, FAA Review of Solar Energy System Projects on Federally Obligated Airports

Science.gov (United States)

2013-10-23

... the orientation and tilt of the solar energy panels, reflectance, environment, and ocular factors are... energy systems on the airport must attach the SGHAT report, outlining solar panel glare and ocular impact... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration Interim Policy, FAA Review of Solar...

Interim process report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Sellin, Patrick

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

Interim process report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrick (ed.)

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

7 CFR 1738.21 - Interim financing.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1738.21 Section 1738.21... Interim financing. (a) Upon notification by RUS that an applicant's application is considered complete, the applicant may enter into an interim financing agreement with a lender other than RUS or use its...

Safety research activities for Japanese regulations of spent fuel interim storage facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-31

This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited (BNFL).

Technical guideline technology according to the X-ray regulations

International Nuclear Information System (INIS)

2011-01-01

The guideline covers the required technical knowledge concerning radiation protection and knowledge concerning for the operation of X-ray devices for technical purposes and stray radiation sources requiring licensing, and requirements for the qualification of officially authorized inspectors. The guidelines includes the following chapters: (1) introductory regulations; (2) Volume of the required technical knowledge; (3) Acquirement and certification of the technical knowledge; (4) Actualization of the technical knowledge; (5)Approval of courses and other training measures; (6) Combination of courses and training measures according to the guideline; (7) Requirements for qualification of officially authorized inspectors; (8) Interim regulations.

Interim data quality objectives for waste pretreatment and vitrification. Revision 1

International Nuclear Information System (INIS)

Kupfer, M.J.; Conner, J.M.; Kirkbride, R.A.; Mobley, J.R.

1994-01-01

The Tank Waste Remediation System (TWRS) is responsible for storing, processing, and immobilizing the Hanford Site tank wastes. Characterization information on the tank wastes is needed so that safety concerns can be addressed, and retrieval, pretreatment, and immobilization processes can be designed, permitted, and implemented. This document describes the near-term tank waste sampling and characterization needs of the Pretreatment, High-Level Waste (HLW) Disposal, and Low-Level Waste (LLW) Disposal Programs to support the TWRS disposal mission. The final DQO (Data Quality Objective) will define specific waste tanks to be sampled, sample timing requirements, an appropriate analytical scheme, and a list of required analytes. This interim DQO, however, focuses primarily on the required analytes since the tanks to be sampled in FY 1994 and early FY 1995 are being driven most heavily by other considerations, particularly safety. The major objective of this Interim DQO is to provide guidance for tank waste characterization requirements for samples taken before completion of the final DQO. The characterization data needs defined herein will support the final DQO to help perform the following: Support the TWRS technical strategy by identification of the chemical and physical composition of the waste in the tanks and Guide development efforts to define waste pretreatment processes, which will in turn define HLW and LLW feed to vitrification processes

7 CFR 1735.75 - Interim financing.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1735.75 Section 1735.75... Involving Loan Funds § 1735.75 Interim financing. (a) A borrower may submit a written request for RUS approval of interim financing if it is necessary to close an acquisition before the loan to finance the...

216-T-4 interim stabilization final report

International Nuclear Information System (INIS)

Smith, D.L.

1996-01-01

This report provides a general description of the activities performed for the interim stabilization of the 216-T-4-1 ditch, 216-T-4-2 ditch, and 216-T-4-2 pond. Interim stabilization was required to reduce the amount of surface-contaminated acres and to minimize the migration of radioactive contamination. Work associated with the 216-T4-1 ditch and 216-T-4-2 pond was performed by the Radiation Area Remedial Action (RARA) Project. Work associated with the 216-T-4-2 ditch was done concurrently but was funded by Westinghouse Hanford Company (WHC) Tank Waste Remediation Systems (TWRS)

Flammable gas deflagration consequence calculations for the tank waste remediation system basis for interim operation

Energy Technology Data Exchange (ETDEWEB)

Van Vleet, R.J., Westinghouse Hanford

1996-08-13

This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.The attached SD documents the originator`s analysis only. It shall not be used as the final or sole document for effecting changes to an authorization basis or safety basis for a facility or activity.

Honeywell Cascade Distiller System Performance Testing Interim Results

Science.gov (United States)

Callahan, Michael R.; Sargusingh, Miriam

2014-01-01

The ability to recover and purify water through physiochemical processes is crucial for realizing long-term human space missions, including both planetary habitation and space travel. Because of their robust nature, distillation systems have been actively pursued as one of the technologies for water recovery. The Cascade Distillation System (CDS) is a vacuum rotary distillation system with potential for greater reliability and lower energy costs than existing distillation systems. The CDS was previously under development through Honeywell and NASA. In 2009, an assessment was performed to collect data to support down-selection and development of a primary distillation technology for application in a lunar outpost water recovery system. Based on the results of this testing, an expert panel concluded that the CDS showed adequate development maturity, TRL-4, together with the best product water quality and competitive weight and power estimates to warrant further development. The Advanced Exploration Systems (AES) Water Recovery Project (WRP) worked to address weaknesses identified by The Panel; namely bearing design and heat pump power efficiency. Testing at the NASA-JSC Advanced Exploration System Water Laboratory (AES Water Lab) using a prototype Cascade Distillation Subsystem (CDS) wastewater processor (Honeywell International, Torrance, Calif.) with test support equipment and control system developed by Johnson Space Center was performed to evaluate performance of the system with the upgrades. The CDS will also have been challenged with ISS analog waste streams and a subset of those being considered for Exploration architectures. This paper details interim results of the AES WRP CDS performance testing.

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard technical specifications combustion engineering plants

International Nuclear Information System (INIS)

1992-09-01

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

Waste management system functional requirements for Interim Waste Management Facilities (IWMFs) and technology demonstrations, LLWDDD [Low-Level Disposal Development and Demonstration] Program

International Nuclear Information System (INIS)

1988-03-01

The purpose of this report is to build upon the preceding decisions and body of information to prepare draft system functional requirements for each classification of waste disposal currently proposed for Low-Level Waste Disposal Development Demonstration (LLWDDD) projects. Functional requirements identify specific information and data needs necessary to satisfy engineering design criteria/objectives for Interim Waste Management Facilities. This draft will suppor the alternatives evaluation process and will continue to evolve as strategy is implemented, regulatory limits are established, technical and economic uncertainties are resolved, and waste management plans are being implemented. This document will become the planning basis for the new generation of solid LLW management facilities on new sites on the Reservation. Eighteen (18) general system requirements are identified which are applicable to all four Low-Level Waste (LLW) disposal classifications. Each classification of LLW disposal is individually addressed with respect ot waste characteristics, site considerations, facility operations, facility closure/post-closure, intruder barriers, institutional control, and performance monitoring requirements. Three initial LLW disposal sites have been proposed as locations on the ORR for the first demonstrations

13 CFR 120.890 - Source of interim financing.

Science.gov (United States)

2010-01-01

... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Source of interim financing. 120... Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may use interim financing for all Project costs except the Borrower's contribution. Any source (including...

Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

International Nuclear Information System (INIS)

Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

1982-01-01

The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test

Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

Energy Technology Data Exchange (ETDEWEB)

Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

1982-04-30

The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test.

Surface Water Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document for South Walnut Creek Basin (Operable Unit No. 2)

International Nuclear Information System (INIS)

1991-01-01

The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This IM/IRA is to be conducted to minimize the release from these areas of hazardous substances that pose a potential threat to the public health and environment. The Plan involved the collection of contaminated surface water at specific locations, treatment by chemical precipitation, cross-flow membrane filtration and granular activated carbon (GAC) adsorption, and surface discharge of treated water. Information for the initial configuration of the Plan is presented in the document entitled ''Proposed Interim Measures/Interim Remedial Action Plan and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2'' (IM/IRAP) dated 26 September 1990. Information concerning the proposed Surface Water IM/IRA was presented during a public meeting held from 7 to 10 p.m., Tuesday, 23 October 1990, at the Westminster City Park Recreation Center in Westminster, Colorado. This Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to DOE during the public comment period which ended 24 November 1990. There were a number of technical comments on the plan that DOE has addressed herein. It is noted that several major issues were raised by the comments. Regardless of the estimated low risk to the public from construction and water transport activities, the popular sentiment of the public, based on comments received, is strong concern over worker and public health risks from these activities. In the light of public and municipal concerns, DOE proposes to eliminate from this IM/IRA the interbasin transfer of Woman Creek seepage to the South Walnut Creek drainage and to address collection and treatment of contaminated South Walnut Creek and Woman Creek surface water under two separate IM/IRAs

Composite Socio-Technical Systems: A Method for Social Energy Systems

Energy Technology Data Exchange (ETDEWEB)

Zhang, Yingchen [National Renewable Energy Laboratory (NREL), Golden, CO (United States); He, Fulin [Huazhong University of Science & Technology; Hao, Jun [University of Denver; Dai, Xiaoxiao [University of Denver; Zhang, Jun Jason [University of Denver; Wei, Jiaolong [Huazhong University of Science & Technology

2017-12-01

In order to model and study the interactions between social on technical systems, a systemic method, namely the composite socio-technical systems (CSTS), is proposed to incorporate social systems, technical systems and the interaction mechanism between them. A case study on University of Denver (DU) campus grid is presented in paper to demonstrate the application of the proposed method. In the case study, the social system, technical system, and the interaction mechanism are defined and modelled within the framework of CSTS. Distributed and centralized control and management schemes are investigated, respectively, and numerical results verifies the feasibility and performance of the proposed composite system method.

Project management plan for Reactor 105-C Interim Safe Storage project

International Nuclear Information System (INIS)

Plagge, H.A.

1996-09-01

Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

Burn site groundwater interim measures work plan.

Energy Technology Data Exchange (ETDEWEB)

Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

2005-05-01

This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

42 CFR Appendix to Subpart G of... - Interim Procedures and Criteria for Review by Health Systems Agencies of Applications Under...

Science.gov (United States)

2010-10-01

... Health Systems Agencies of Applications Under Section 1625 of the Public Health Service Act Appendix to..., App. Appendix to Subpart G of Part 124—Interim Procedures and Criteria for Review by Health Systems... section 1625 of the Act, health systems agencies shall use the procedures and criteria stated below. A...

24 CFR 35.1330 - Interim controls.

Science.gov (United States)

2010-04-01

... Lead-Paint Hazard Evaluation and Hazard Reduction Activities § 35.1330 Interim controls. Interim..., cleanable covering or coating, such as metal coil stock, plastic, polyurethane, or linoleum. (3) Surfaces...

Interim performance criteria for photovoltaic energy systems. [Glossary included

Energy Technology Data Exchange (ETDEWEB)

DeBlasio, R.; Forman, S.; Hogan, S.; Nuss, G.; Post, H.; Ross, R.; Schafft, H.

1980-12-01

This document is a response to the Photovoltaic Research, Development, and Demonstration Act of 1978 (P.L. 95-590) which required the generation of performance criteria for photovoltaic energy systems. Since the document is evolutionary and will be updated, the term interim is used. More than 50 experts in the photovoltaic field have contributed in the writing and review of the 179 performance criteria listed in this document. The performance criteria address characteristics of present-day photovoltaic systems that are of interest to manufacturers, government agencies, purchasers, and all others interested in various aspects of photovoltaic system performance and safety. The performance criteria apply to the system as a whole and to its possible subsystems: array, power conditioning, monitor and control, storage, cabling, and power distribution. They are further categorized according to the following performance attributes: electrical, thermal, mechanical/structural, safety, durability/reliability, installation/operation/maintenance, and building/site. Each criterion contains a statement of expected performance (nonprescriptive), a method of evaluation, and a commentary with further information or justification. Over 50 references for background information are also given. A glossary with definitions relevant to photovoltaic systems and a section on test methods are presented in the appendices. Twenty test methods are included to measure performance characteristics of the subsystem elements. These test methods and other parts of the document will be expanded or revised as future experience and needs dictate.

Transportation Systems Center Bibliography of Technical Reports, July 1970 - December 1976,

Science.gov (United States)

1977-04-01

Systems Center. AD-733-763 Judith Gertler, Herbert Glynn, Vivian Hobbs, Frederick Interim Report. June 1971. 16p. Woolfall. AD-733-764 Air Traffic Control...of Deployment Cost Analysis .. .......... FAA-76-20 Airspace Control Environmnent Simulator - Final Report.... ............ .. TSC-131.3 *All- Wether

The socio-technical system and nuclear safety

International Nuclear Information System (INIS)

Stefanescu, Petre; Mihailescu, Nicolae; Dragusin, Octavian

1999-01-01

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

Stabilization of in-tank residuals and external-tank soil contamination: FY 1997 interim report

International Nuclear Information System (INIS)

Becker, D.L.

1997-01-01

This interim report evaluates various ways to stabilize decommissioned waste tanks and contaminated soils at the AX Tank Farm as part of a preliminary evaluation of end-state options for the Hanford tanks. Five technical areas were considered: (1) emplacement of smart grouts and/or other materials, (2) injection of chemical-getters into contaminated soils surrounding tanks (soil mixing), (3) emplacement of grout barriers under and around the tanks, (4) the use of engineered barriers over the tanks, and (5) the explicit recognition that natural attenuation processes do occur. Research topics are identified in support of key areas of technical uncertainty, in each of the five technical areas. Detailed cost/benefit analyses of the recommended technologies are not provided in this evaluation, performed by Sandia National Laboratories, Albuquerque, New Mexico

ASPECTS CONCERNING INTERIM FINANCIAL REPORTING IN ROMANIA: STANDARDS AND REGULATIONS

Directory of Open Access Journals (Sweden)

Aristita Rotila

2014-12-01

Full Text Available The mechanisms employed for the communication of accounting information that is necessary for users in their economic decision-making process consist of the financial statements of an entity. All legal entities, no matter the domain of their activity, have the obligation to draw up annual financial statements for every completed financial year. For certain categories of entities, reporting obligations are also required for periods other than the annual reporting, throughout the financial year. It is the case of interim financial reporting. At the level of the international accounting framework, the aspects related to interim financial reporting are the subject of a separate standard, namely, IAS 34 Interim Financial Reporting. In Romania, the current system of accounting regulations concerning the annual financial statements comprises accounting regulations that comply with the European directives and which apply to the various categories of entities, on the one hand and, on the other, accounting regulations in line with the IFRS, which are applicable to other classes of entities from certain activity sectors. The accounting regulations that apply to each category refer to, among other things, the contents and the format of financial statements that have to be presented. Analysing the system of norms and regulations, this article identifies the requirements concerning interim financial reporting in Romania, with reference to the different types of entities.

Independent Technical Review of the C-400 Interim Remedial Project Phase I Results, Paducah, Kentucky

International Nuclear Information System (INIS)

Looney, B.; Rossabi, J.; Stewart, L.; Richards, W.

2010-01-01

The groundwater and soil in the vicinity of the C-400 Building at the Paducah Gaseous Diffusion Plant (PGDP), is contaminated with substantial quantities of industrial solvents, primarily trichoroethene (TCE). This solvent 'source' is recognized as a significant challenge and an important remediation target in the overall environmental cleanup strategy for PGDP. Thus, the cleanup of the C-400 TCE Source is a principal focus for the Department of Energy (DOE) and its contractors, and for PGDP regulators and stakeholders. Using a formal investigation, feasibility study and decision process, Electrical Resistance Heating (ERH) was selected for the treatment of the soil and groundwater in the vicinity of C-400. ERH was selected as an interim action to remove 'a significant portion of the contaminant mass of TCE at the C-400 Cleaning Building area through treatment' with the longer term goal of reducing 'the period the TCE concentration in groundwater remains above its Maximum Contaminant Level (MCL).' ERH is a thermal treatment that enhances the removal of TCE and related solvents from soil and groundwater. The heterogeneous conditions at PGDP, particularly the high permeability regional gravel aquifer (RGA), are challenging to ERH. Thus, a phased approach is being followed to implement this relatively expensive and complex remediation technology. Conceptually, the phased approach encourages safety and efficiency by providing a 'lessons learned' process and allowing appropriate adjustments to be identified and implemented prior to follow-on phase(s) of treatment. More specifically, early deployment targeted portions of the challenging RGA treatment zone with relatively little contamination reducing the risk of adverse collateral impacts from underperformance in terms of heating and capture. Because of the importance and scope of the C-400 TCE source remediation activities, DOE chartered an Independent Technical Review (ITR) in 2007 to assess the C-400 ERH plans prior

INDEPENDENT TECHNICAL REVIEW OF THE C-400 INTERIM REMEDIAL PROJECT PHASE I RESULTS, PADUCAH, KENTUCKY

Energy Technology Data Exchange (ETDEWEB)

Looney, B.; Rossabi, J.; Stewart,L.; Richards, W.

2010-10-29

The groundwater and soil in the vicinity of the C-400 Building at the Paducah Gaseous Diffusion Plant (PGDP), is contaminated with substantial quantities of industrial solvents, primarily trichoroethene (TCE). This solvent 'source' is recognized as a significant challenge and an important remediation target in the overall environmental cleanup strategy for PGDP. Thus, the cleanup of the C-400 TCE Source is a principal focus for the Department of Energy (DOE) and its contractors, and for PGDP regulators and stakeholders. Using a formal investigation, feasibility study and decision process, Electrical Resistance Heating (ERH) was selected for the treatment of the soil and groundwater in the vicinity of C-400. ERH was selected as an interim action to remove 'a significant portion of the contaminant mass of TCE at the C-400 Cleaning Building area through treatment' with the longer term goal of reducing 'the period the TCE concentration in groundwater remains above its Maximum Contaminant Level (MCL).' ERH is a thermal treatment that enhances the removal of TCE and related solvents from soil and groundwater. The heterogeneous conditions at PGDP, particularly the high permeability regional gravel aquifer (RGA), are challenging to ERH. Thus, a phased approach is being followed to implement this relatively expensive and complex remediation technology. Conceptually, the phased approach encourages safety and efficiency by providing a 'lessons learned' process and allowing appropriate adjustments to be identified and implemented prior to follow-on phase(s) of treatment. More specifically, early deployment targeted portions of the challenging RGA treatment zone with relatively little contamination reducing the risk of adverse collateral impacts from underperformance in terms of heating and capture. Because of the importance and scope of the C-400 TCE source remediation activities, DOE chartered an Independent Technical Review (ITR) in

PROJECT W-551 DETERMINATION DATA FOR EARLY LAW INTERIM PRETREATMENT SYSTEM SELECTION

Energy Technology Data Exchange (ETDEWEB)

TEDESCHI AR

2008-08-11

This report provides the detailed assessment forms and data for selection of the solids separation and cesium separation technology for project W-551, Interim Pretreatment System. This project will provide early pretreated low activity waste feed to the Waste Treatment Plant to allow Waste Treatment Plan Low Activity Waste facility operation prior to construction completion of the Pretreatment and High Level Waste facilities. The candidate solids separations technologies are rotary microfiltration and crossflow filtration, and the candidate cesium separation technologies are fractional crystallization, caustic-side solvent extraction, and ion-exchange using spherical resorcinol-formaldehyde resin. This data was used to prepare a cross-cutting technology summary, reported in RPP-RPT-37740.

A Real-Time Systems Symposium Preprint.

Science.gov (United States)

1983-09-01

Real - Time Systems Symposium Preprint Interim Tech...estimate of the occurence of the error. Unclassii ledSECUqITY CLASSIF’ICA T" NO MI*IA If’ inDI /’rrd erter for~~ble. ’Corrputnqg A REAL - TIME SYSTEMS SYMPOSIUM...ABSTRACT This technical report contains a preprint of a paper accepted for presentation at the REAL - TIME SYSTEMS SYMPOSIUM, Arlington,

Evaluation of Hose in Hose Transfer Line Service Life for Hanfords Interim Stabilization Program

International Nuclear Information System (INIS)

TORRES, T.D.

2001-01-01

RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program (Torres, 2000a), defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of waste transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program (Torres, 2000b), has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications associated with Interim Stabilization. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning, RPP-6028 Section 3.2.7. Performance Incentive Number ORP-05 requires that all the Single Shell Tanks be Interim Stabilized by September 30, 2003. The Tri-Party Agreement (TPA) milestone M-41-00, enforced by a federal consent decree, requires all the Single Shell Tanks to be Interim stabilized by September 30, 2004. By meeting the Performance Incentive the TPA milestone is met. Prudent engineering dictates that the equipment used to transfer waste have a life in excess of the forecasted operational time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer, published literature and calculations. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are the hose material's resistance to the harmful effects of process fluid characteristics, ambient environmental conditions, exposure to ionizing radiation and the

Industrial complementarities between interim storage and reversible geological repository - 59237

International Nuclear Information System (INIS)

Hoorelbeke, Jean-Michel

2012-01-01

The French Act voted in 2006 made the choice of deep geological disposal as the reference option for the long term management of high level (HLW) and intermediate level long-lived waste. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management on a duration which is comparable to new storage facility. Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and to limit cost. Preliminary simulations of storage-disposal scenarios are presented. Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of waste emplacement flow during the first operation phase of the repository. It is then possible to stabilize the industrial activity level of the repository site. An optimal utilization of interim storage can also limit the diversity of waste packages emplaced simultaneously, which facilitates the operation of the repository. 60 years minimum interim storage duration is generally required with respect to HLW thermal output. Extending this interim storage period may reduce the underground footprint of the repository. Regarding reversibility, the capability to manage waste packages potentially retrieved from the repository should be analyzed. The

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)

Interim Administrators in Higher Education: A National Study

Science.gov (United States)

Huff, Marie Thielke; Neubrander, Judy

2015-01-01

The focus of this paper is on the roles and experiences of interim administrators in higher education. A survey was given to current and recent interim administrators in four-year public universities and colleges across the United States. The goals were to identify the advantages and disadvantages of using and serving as interims, and to solicit…

Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, Operable Unit No. 2

International Nuclear Information System (INIS)

1992-01-01

The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This IM/IRAP/EA identifies and evaluates interim remedial actions for removal of residual free-phase VOC contamination from three different subsurface environments at OU2. The term ''residual'' refers to the non-aqueous phase contamination remaining in the soil matrix (by capillary force) subsequent to the passage of non-aqueous or free-phase liquid through the subsurface. In addition to the proposed actions, this IM/IRAP/EA presents an assessment of the No Action Alternative. This document also considers an interim remedial action for the removal of radionuclides from beneath the 903 Pad

Designing socio-technical systems : Structures and processes

NARCIS (Netherlands)

Bots, P.W.G.; Van Daalen, C.

2012-01-01

The Systems Engineering, Policy Analysis and Management (SEPAM) MSc curriculum taught at Delft University of Technology focuses on the design of socio-technical systems (STS). We teach our students to structure design activities by considering what we call the TIP aspects: Technical systems,

Peer Review of the Waste Package Material Performance Interim Report

International Nuclear Information System (INIS)

J. A. Beavers; T. M. Devine, Jr.; G. S. Frankel; R. H. Jones; R. G. Kelly; R. M. Latanision; J. H. Payer

2001-01-01

At the request of the U.S. Department of Energy, Bechtel SAIC Company, LLC, formed the Waste Package Materials Performance Peer Review Panel (the Panel) to review the technical basis for evaluating the long-term performance of waste package materials in a proposed repository at Yucca Mountain, Nevada. This is the interim report of the Panel; a final report will be issued in February 2002. In its work to date, the Panel has identified important issues regarding waste package materials performance. In the remainder of its work, the Panel will address approaches and plans to resolve these issues. In its review to date, the Panel has not found a technical basis to conclude that the waste package materials are unsuitable for long-term containment at the proposed Yucca Mountain Repository. Nevertheless, significant technical issues remain unsettled and, primarily because of the extremely long life required for the waste packages, there will always be some uncertainty in the assessment. A significant base of scientific and engineering knowledge for assessing materials performance does exist and, therefore, the likelihood is great that uncertainty about the long-term performance can be substantially reduced through further experiments and analysis

State child health; revisions to the regulations implementing the State Children's Health Insurance Program. Interim final rule with comment period; revisions, delay of effective date, and technical amendments to final rule.

Science.gov (United States)

2001-06-25

Title XXI authorizes the State Children's Health Insurance Program (SCHIP) to assist State efforts to initiate and expand the provision of child health assistance to uninsured, low-income children. On January 11, 2001 we published a final rule in the Federal Register to implement SCHIP that has not gone into effect. This interim final rule further delays the effective date, revises certain provisions and solicits public comment, and makes technical corrections and clarifications to the January 2001 final rule based on further review of the comments received and applicable law. Only the provisions set forth in this document have changed. All other provisions set forth in the January 2001 final rule will be implemented without change.

Decision on performing interim analysis for comparative clinical trials.

Science.gov (United States)

Pak, Kyongsun; Jacobus, Susanna; Uno, Hajime

2017-09-01

In randomized-controlled trials, interim analyses are often planned for possible early trial termination to claim superiority or futility of a new therapy. While unblinding is necessary to conduct the formal interim analysis in blinded studies, blinded data also have information about the potential treatment difference between the groups. We developed a blinded data monitoring tool that enables investigators to predict whether they observe such an unblinded interim analysis results that supports early termination of the trial. Investigators may skip some of the planned interim analyses if an early termination is unlikely. We specifically focused on blinded, randomized-controlled studies to compare binary endpoints of a new treatment with a control. Assuming one interim analysis is planned for early termination for superiority or futility, we conducted extensive simulation studies to assess the impact of the implementation of our tool on the size, power, expected number of interim analyses, and bias in the treatment effect. The numerical study showed the proposed monitoring tool does not affect size or power, but dramatically reduces the expected number of interim analyses when the effect of the treatment difference is small. The tool serves as a useful reference when interpreting the summary of the blinded data throughout the course of the trial, without losing integrity of the study. This tool could potentially save the study resources and budget by avoiding unnecessary interim analyses.

Addendum to IFMIF-CDA interim report

Energy Technology Data Exchange (ETDEWEB)

Maekawa, Hiroshi; Ida, Mizuho [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

1996-08-01

During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of `IFMIF-CDA Interim Report` were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the `Interim Report`. This report describes the outline of these modification. (author)

Addendum to IFMIF-CDA interim report

International Nuclear Information System (INIS)

Maekawa, Hiroshi; Ida, Mizuho

1996-08-01

During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of 'IFMIF-CDA Interim Report' were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the 'Interim Report'. This report describes the outline of these modification. (author)

Sustainable Solutions for Nuclear used Fuels Interim Storage

International Nuclear Information System (INIS)

Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

2014-01-01

AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

Retention of long-term interim restorations with sodium fluoride enriched interim cement

Science.gov (United States)

Strash, Carolyn

Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

The Nord interim store

International Nuclear Information System (INIS)

Leushacke, D.F.; Rittscher, D.

1996-01-01

In line with the decision taken in 1990 to shut down and decommission the Greifswald and Rheinsberg Nuclear Power Stations, the waste management concept of the Energiewerke Nord is based on direct and complete decommissioning of the six shut down reactor units within the next fifteen years. One key element of this concept is the construction and use of the Zwischenlager Nord (Nord Interim Store, ZLN) for holding the existing nuclear fuels and for interim and decay storage of the radioactive materials arising in decommissioning and demolition. The owner and operator of the store is Energiewerke Nord GmbH. The interim store has the functions of a processing and Energiewerke Nord GmbH. The interim store has the functions of a processing and treatment station and buffer store for the flows of residues arising. As a radioactive waste management station, it accommodates nuclear fuels, radioactive waste or residues which are not treated any further. It is used as a buffer store to allow the materials accumulating in disassembly to be stored temporarily before or after treatment in order to ensure continuous loading of the treatment plants. When operated as a processing station, the ZLN is able to handle nearly all types of radioactive waste and residues arising, except for nuclear fuels. These installations allow the treatment of radioactive residues to be separated from the demolition work both physically and in time. The possibilities of interium storage and buffer storage of untreated waste and waste packages make for high flexibility in logistics and waste management strategy. (orig.) [de

40 CFR 57.302 - Performance level of interim constant controls.

Science.gov (United States)

2010-07-01

... correction of the effects of any serious deficiencies in the system. For the purpose of this paragraph, at... system if the smelter owner has not upgraded serious deficiencies in the constant control system in... 40 Protection of Environment 5 2010-07-01 2010-07-01 false Performance level of interim constant...

Interim Service ISDN Satellite (ISIS) simulator development for advanced satellite designs and experiments

Science.gov (United States)

Pepin, Gerard R.

1992-01-01

The simulation development associated with the network models of both the Interim Service Integrated Services Digital Network (ISDN) Satellite (ISIS) and the Full Service ISDN Satellite (FSIS) architectures is documented. The ISIS Network Model design represents satellite systems like the Advanced Communications Technology Satellite (ACTS) orbiting switch. The FSIS architecture, the ultimate aim of this element of the Satellite Communications Applications Research (SCAR) Program, moves all control and switching functions on-board the next generation ISDN communications satellite. The technical and operational parameters for the advanced ISDN communications satellite design will be obtained from the simulation of ISIS and FSIS engineering software models for their major subsystems. Discrete event simulation experiments will be performed with these models using various traffic scenarios, design parameters, and operational procedures. The data from these simulations will be used to determine the engineering parameters for the advanced ISDN communications satellite.

Technical note on drainage systems

DEFF Research Database (Denmark)

Bentzen, Thomas Ruby

This technical note will present simple but widely used methods for the design of drainage systems. The note will primarily deal with surface water (rainwater) which on a satisfactorily way should be transport into the drainage system. Traditional two types of sewer systems exist: A combined system......, where rainwater and sewage is transported in the same pipe, and a separate system where the two types of water are transported in individual pipe. This note will only focus on the separate rain/stormwater system, however, if domestic sewage should be included in the dimensioning procedure, it......’s not major different than described below - just remember to include this contribution for combined systems where the surface water (rain) and sewage are carried in the same pipes in the system and change some of the parameters for failure allowance (this will be elaborated further later on). The technical...

Palisades technical specification conversion from custom to new industry standard

International Nuclear Information System (INIS)

Foley, D.J.; Young, B.

1990-01-01

Consumers Power Company's (CPCo) Palisades plant is in the process of converting from custom technical specifications to the new industry standard, Restructured Standard Technical Specifications (RSTS). Custom technical specifications were the precursor to standard technical specifications, being issued to plants built prior to 1972. In May 1989, each of the four light water reactor owners' groups completed topical reports presenting their version of Restructured Standard Technical Specifications to the Nuclear Regulatory Commission (NRC). After approval of the owners' groups versions of the RSTs by the NRC, individual operating reactors will begin to make the conversion to the RSTS. Each owners' group has designated a lead plant, which will be the first of that vendor type to convert. All of the lead plants currently operate under standard technical specifications. The content of the RSTS was determined by comparing the standard technical specifications with selection criteria specified in the Commissions Interim Policy Statement

76 FR 58790 - Notice of Interim Approval

Science.gov (United States)

2011-09-22

... to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third rate alternative... an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third... allocated on an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The...

Technical and economic optimization study for HLW waste management

International Nuclear Information System (INIS)

Deffes, A.

1989-01-01

This study was conducted to assess the technical and economic aspects of high level waste (HLW) management with the objective of optimizing the interim storage duration and the dimensions of the underground repository site. The procedure consisted in optimizing the economic criterion under specified constraints. The results are intended to identify trends and guide the choice from among available options; simple and highly flexible models were therefore used in this study, and only nearfield thermal constraints were taken into consideration. Because of the present uncertainty on the physicochemical properties of the repository environment and on the unit cost figures, this study focused on developing a suitable method rather than on obtaining definitive results. With the physical and economic data bases used for the two media investigated (granite and salt) the optimum values found show that it is advisable to minimize the interim storage time, and that the geological repository should feature a high degree of spatial dilution. These results depend to a considerable extent on the assumption of high interim storage costs

Current status of the first interim spent fuel storage facility in Japan

International Nuclear Information System (INIS)

Shinbo, Hitoshi; Kondo, Mitsuru

2008-01-01

In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

The Interim Financial Statements: The Case of Greece

OpenAIRE

Rogdaki, E.I.; Kazantzis, Ch.

1999-01-01

The following paper refers to the accounting and auditing issues which emerge in the preparation of the interim financial statements of the companies: Firstly, the interim financial statements are defined as being the financial statements that provide useful information about the financial position and the financial results of a company which are realized and accrued during the fiscal year. The interim financial statements can be prepared on a monthly basis, on a quarterly basis or covering a...

FFTF/IEM [Fast Flux Test Facility/Interim Examination and Maintenance] cell fuel pin weighing system: Remote maintenance design considerations

International Nuclear Information System (INIS)

Gibbons, P.W.

1986-06-01

A Fuel Pin Weighing Machine has been developed for use in the Fast Flux Test Facility (FFTF) Interim Examination and Maintenance (IEM) Cell to assist in identifying an individual breached fuel pin from its fuel assembly pin bundle. Optimum configuration for remote maintenance was a major consideration in the design of each element of the Pin Weighing System

77 FR 64464 - Information Systems Technical Advisory Committee

Science.gov (United States)

2012-10-22

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, November 7...

Effects of Medicare payment reform: evidence from the home health interim and prospective payment systems.

Science.gov (United States)

Huckfeldt, Peter J; Sood, Neeraj; Escarce, José J; Grabowski, David C; Newhouse, Joseph P

2014-03-01

Medicare continues to implement payment reforms that shift reimbursement from fee-for-service toward episode-based payment, affecting average and marginal payment. We contrast the effects of two reforms for home health agencies. The home health interim payment system in 1997 lowered both types of payment; our conceptual model predicts a decline in the likelihood of use and costs, both of which we find. The home health prospective payment system in 2000 raised average but lowered marginal payment with theoretically ambiguous effects; we find a modest increase in use and costs. We find little substantive effect of either policy on readmissions or mortality. Copyright © 2014 Elsevier B.V. All rights reserved.

Effectiveness of interim remedial actions at a radioactive waste facility

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

1989-01-01

Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

Interim reliability evaluation program, Browns Ferry fault trees

International Nuclear Information System (INIS)

Stewart, M.E.

1981-01-01

An abbreviated fault tree method is used to evaluate and model Browns Ferry systems in the Interim Reliability Evaluation programs, simplifying the recording and displaying of events, yet maintaining the system of identifying faults. The level of investigation is not changed. The analytical thought process inherent in the conventional method is not compromised. But the abbreviated method takes less time, and the fault modes are much more visible

Report on achievements in fiscal 1998. Development of an interim processing technology to re-commercialize mixed waste plastics; 1998 nendo kongo haipura saishohinka no tame no chukan shori system gijutsu no kaihatsu seika hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-09-01

The container and package recycling law is fully enforced starting fiscal 2000. Recycling obligation is placed also on plastic containers and packages discharged from households, excepting PET bottles for beverages and soy sauce. Therefore, it is required to establish an interim processing technology to process these materials into shapes easy for re-utilization and transportation, that is a technology to manufacture granules with adequate diameters. The purpose of this research is to develop the interim processing system technology. Design, fabrication and installation were performed on an interim processing system plant (a mixed waste plastic granule manufacturing facility) that can process annually waste plastics of 3,000 tons (0.5 t/h). The plant consists of the following four pieces of equipment: (1) a pulverizer, (2) a PVC sorting device, (3) a granulating device, and (4) a sizer. After the installed interim processing system demonstration plant has been trially operated and adjusted by each device, the whole plant was given the trial operation and adjustment to have verified that all the devices function normally. In addition, in order to evaluate economy of the waste plastics interim processing, the processing cost was calculated and the economic performance was evaluated preliminarily by using the rated electric power setting and trial operation data of each device. (NEDO)

In vitro evaluation of the marginal integrity of CAD/CAM interim crowns.

Science.gov (United States)

Kelvin Khng, Kwang Yong; Ettinger, Ronald L; Armstrong, Steven R; Lindquist, Terry; Gratton, David G; Qian, Fang

2016-05-01

The accuracy of interim crowns made with computer-aided design and computer-aided manufacturing (CAD/CAM) systems has not been well investigated. The purpose of this in vitro study was to evaluate the marginal integrity of interim crowns made by CAD/CAM compared with that of conventional polymethylmethacrylate (PMMA) crowns. A dentoform mandibular left second premolar was prepared for a ceramic crown and scanned for the fabrication of 60 stereolithical resin dies, half of which were scanned to fabricate 15 Telio CAD-CEREC and 15 Paradigm MZ100-E4D-E4D crowns. Fifteen Caulk and 15 Jet interim crowns were made on the remaining resin dies. All crowns were cemented with Tempgrip under a 17.8-N load, thermocycled for 1000 cycles, placed in 0.5% acid fuschin for 24 hours, and embedded in epoxy resin before sectioning from the mid-buccal to mid-lingual surface. The marginal discrepancy was measured using a traveling microscope, and dye penetration was measured as a percentage of the overall length under the crown. The mean vertical marginal discrepancy of the conventionally made interim crowns was greater than for the CAD/CAM crowns (P=.006), while no difference was found for the horizontal component (P=.276). The mean vertical marginal discrepancy at the facial surface of the Caulk crowns was significantly greater than that of the other 3 types of interim crowns (Pmargin, the mean horizontal component of the Telio crowns was significantly larger than that of the other 3 types, with no difference at the lingual margins (P=.150). The mean percentage dye penetration for the Paradigm MZ100-E4D crowns was significantly greater and for Jet crowns significantly smaller than for the other 3 crowns (Pmarginal discrepancies of the Jet interim crowns at the facial surface and with the horizontal marginal discrepancies of the Caulk interim crowns at the lingual surface (Pmarginal discrepancy was found with the interim crowns fabricated by CAD/CAM as compared with PMMA crowns

Formal modelling and analysis of socio-technical systems

DEFF Research Database (Denmark)

Probst, Christian W.; Kammüller, Florian; Hansen, Rene Rydhof

2016-01-01

systems are still mostly identified through brainstorming of experts. In this work we discuss several approaches to formalising socio-technical systems and their analysis. Starting from a flow logic-based analysis of the insider threat, we discuss how to include the socio aspects explicitly, and show......Attacks on systems and organisations increasingly exploit human actors, for example through social engineering. This non-technical aspect of attacks complicates their formal treatment and automatic identification. Formalisation of human behaviour is difficult at best, and attacks on socio-technical...... a formalisation that proves properties of this formalisation. On the formal side, our work closes the gap between formal and informal approaches to socio-technical systems. On the informal side, we show how to steal a birthday cake from a bakery by social engineering....

Health condition and residual life of deteriorating technical systems

Energy Technology Data Exchange (ETDEWEB)

Reinertsen, Rune

1998-12-31

Many offshore installations in the Norwegian Sector of the North Sea approach the end of their useful life. The same is true of many power plants and technical systems in general. This thesis describes the theory and improves the methods for the determination of the health condition and residual life of technical systems. Rather than developing new methods it discusses new ways of using existing statistical methods. The main contributions are: (1) A survey of the literature of diagnosis, prediction and life extension for deteriorating technical systems, (2) A discussion of some consequences of selecting the wrong life model, (3) A description of problems related to the determination of mean residual life of non-repairable technical systems, (4) Presentation of the concept of `technical health` to describe the soundness of a system exposed to failure mechanisms, (5) A model for predicting the technical health and residual life of a corroding system, (6) Recommends requirements and methods for using expert knowledge in safety and reliability analysis, (7) A general inspection strategy for system fault diagnosis by using Shannon entropy, (8) Points out weaknesses and strengths of risk measures used in the offshore industry today. 237 refs., 23 figs., 6 tabs.

Health condition and residual life of deteriorating technical systems

Energy Technology Data Exchange (ETDEWEB)

Reinertsen, Rune

1997-12-31

Many offshore installations in the Norwegian Sector of the North Sea approach the end of their useful life. The same is true of many power plants and technical systems in general. This thesis describes the theory and improves the methods for the determination of the health condition and residual life of technical systems. Rather than developing new methods it discusses new ways of using existing statistical methods. The main contributions are: (1) A survey of the literature of diagnosis, prediction and life extension for deteriorating technical systems, (2) A discussion of some consequences of selecting the wrong life model, (3) A description of problems related to the determination of mean residual life of non-repairable technical systems, (4) Presentation of the concept of `technical health` to describe the soundness of a system exposed to failure mechanisms, (5) A model for predicting the technical health and residual life of a corroding system, (6) Recommends requirements and methods for using expert knowledge in safety and reliability analysis, (7) A general inspection strategy for system fault diagnosis by using Shannon entropy, (8) Points out weaknesses and strengths of risk measures used in the offshore industry today. 237 refs., 23 figs., 6 tabs.

FFTF [Fast Flux Test Facility]/IEM [Interim Examination and Maintenance] Cell Fuel Pin Weighing System

International Nuclear Information System (INIS)

Gibbons, P.W.

1987-09-01

A Fuel Pin Weighing Machine has been developed for use in the Fast Flux Test Facility (FFTF) Interim Examination and Maintenance (IEM) Cell to assist in identifying an individual breached fuel pin from its fuel assembly pin bundle. A weighing machine, originally purchased for use in the Fuels and Materials Examination Facility (FMEF) at Hanford, was used as the basis for the IEM Cell system. Design modifications to the original equipment were centered around: 1) adapting the FMEF machine for use in the IEM Cell and 2) correcting operational deficiencies discovered during functional testing in the IEM Cell Mockup

Decommissioning costs of WWER-440 nuclear power plants. Interim report: Data collection and preliminary evaluations

International Nuclear Information System (INIS)

2002-11-01

Based on the interest in decommissioning costs within Member States, especially in WWER- 440 operating countries that face the complex decision about continued operation vs. decommissioning in the near future, the IAEA launched the task to prepare a technical document on decommissioning costs of WWER-440 nuclear power plants. The main objectives of this publication were to present the decommissioning costs of WWER-440 NPPs in a uniform manner, i.e. using the cost item and cost group system of the Interim Technical Document on Nuclear Decommissioning 'A Proposed Standardised List of Items for Costing Purposes' developed jointly by the EC, the IAEA and the OECD Nuclear Energy Agency (NEA), and providing, as such, a basis for understanding decommissioning costs differences. Member States operating WWER-440 NPPs or having such units under shutdown or even under decommissioning conditions have been requested to provide cost estimates and other input data in order to facilitate understanding of their cost figures. Both decommissioning options, i.e. immediate decommissioning and safe enclosure, have been considered. In the aforementioned joint Interim Technical Document, cost items related to activities that are carried out with a similar emphasis, whether or not tied to a similar time schedule for decommissioning, or that are based on overall activities that cannot be categorised in a specific time period, are grouped as follows: pre-decommissioning actions; facility shutdown activities; procurement of general equipment and material; dismantling activities; waste processing, storage and disposal; site security, surveillance and maintenance; site restoration, cleanup and landscaping; project management, engineering and site support; research and development; fuel and nuclear material; other costs. Before starting implementation of the study, agreement was obtained on general financial, technical and social boundary conditions that should be used in order to facilitate

75 FR 20817 - Information Systems Technical Advisory Committee

Science.gov (United States)

2010-04-21

... equipment and technology. Wednesday, May 5 Public Session 1. Welcome and Introduction. 2. Working Group... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC...

Public School Finance Problems in Texas. An Interim Report.

Science.gov (United States)

Texas Research League, Austin.

The U.S. District Court ruling in Rodriguez vs San Antonio Independent School District, which struck down Texas' school finance system as inequitable and unconstitutional, provided the impetus for publishing this interim report. The report documents the growing cost of State-supported public school programs--the primary concern prior to the…

Subsurface Interim Measures/Interim Remedial Action Plan/ Environmental Assessment and Decision Document, Operable Unit No. 2

International Nuclear Information System (INIS)

1992-01-01

The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This volume contains five appendices

Catastrophic failure in complex socio-technical systems

International Nuclear Information System (INIS)

Weir, D.

2004-01-01

This paper reviews the sequences leading to catastrophic failures in complex socio-technical systems. It traces some of the elements of an analytic framework to that proposed by Beer in Decision and Control, first published in 1966, and argues that these ideas are centrally relevant to a topic on which research interest has developed subsequently, the study of crises, catastrophes and disasters in complex socio-technical systems in high technology sectors. But while the system perspective is central, it is not by itself entirely adequate. The problems discussed cannot be discussed simply in terms of system parameters like variety, redundancy and complexity. Much empirical research supports the view that these systems typically operate in degraded mode. The degradations may be primarily initiated within the social components of the socio-technical system. Such variables as hierarchical position, actors' motivations and intentions are relevant to explain the ways in which communication systems typically operate to filter out messages from lower participants and to ignore the 'soft signals' issuing from small-scale and intermittent malfunctions. (author)

CMM Interim Check Design of Experiments (U)

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-07-29

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

Modernization and refurbishment of the Central Interim Storage

International Nuclear Information System (INIS)

Mele, I.; Zeleznik, N.

2002-01-01

The Central Interim Storage for radioactive waste in Brinje, being put into operation in 1986, needs refurbishment and modernization in order to meet the up-to-date operational and safety requirements and to ensure the normal and undisturbed acceptance of radioactive waste from small producers in the future. Because of the waste, being already stored in the storage, the lack of reprocessing capacities and the lack of auxiliary room, the refurbishment and modernization is a complex problem, which needs to be addressed with care. The plan of refurbishment and modernization requires an integral approach, covering all different aspects of renewal and reconstruction. The implementation plan, however, must be based on the actual state of the storage and real conditions for the implementations: from technical to financial. In this paper the project for refurbishment and modernization of the storage, and some activities that have already been implemented, are presented.(author)

System for technical innovation support

International Nuclear Information System (INIS)

2011-08-01

This book lists field of support system, which includes tax, development work, basic research project, industrial technology, information and communications field, energy field, part and materials field, local industry, the small and medium business such as technical development field, and industry-university collaboration like summary of investment and financing support and guarantee, support of manpower such as brain pool and contact Korea, support of technique like development technology and strategy for patent, support on certification such as company and technical goods, purchase support.

Technical Design of Flexible Sustainable Energy Systems

DEFF Research Database (Denmark)

Lund, Henrik

2003-01-01

The paper presents technical designs of potential future flexible energy systems in Denmark, which will be able both to balance production and demand and to secure voltage and frequency requirements on the grid.......The paper presents technical designs of potential future flexible energy systems in Denmark, which will be able both to balance production and demand and to secure voltage and frequency requirements on the grid....

NHI Component Technical Readiness Evaluation System

International Nuclear Information System (INIS)

Sherman, S.; Wilson, Dane F.; Pawel, Steven J.

2007-01-01

A decision process for evaluating the technical readiness or maturity of components (i.e., heat exchangers, chemical reactors, valves, etc.) for use by the U.S. DOE Nuclear Hydrogen Initiative is described. This system is used by the DOE NHI to assess individual components in relation to their readiness for pilot-scale and larger-scale deployment and to drive the research and development work needed to attain technical maturity. A description of the evaluation system is provided, and examples are given to illustrate how it is used to assist in component R and D decisions.

Norm-Aware Socio-Technical Systems

Science.gov (United States)

Savarimuthu, Bastin Tony Roy; Ghose, Aditya

The following sections are included: * Introduction * The Need for Norm-Aware Systems * Norms in human societies * Why should software systems be norm-aware? * Case Studies of Norm-Aware Socio-Technical Systems * Human-computer interactions * Virtual environments and multi-player online games * Extracting norms from big data and software repositories * Norms and Sustainability * Sustainability and green ICT * Norm awareness through software systems * Where To, From Here? * Conclusions

Data management implementation plan for interim action at the Gunite and Associated Tanks, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-03-01

The Gunite and Associated Tanks (GAAT) Project is currently conducting a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interim Remedial Action to reduce uncertainties on the potential cost and effectiveness of remote tank cleaning equipment being produced jointly between the US Department of Energy (DOE); Oak Ridge National Laboratory (ORNL); Lockheed Martin Energy Systems, Inc.; and associated subcontractors with the DOE EM-50 Program. The goal of this document is to ensure that all procedures have been followed to provide reliable, verifiable data that are technically defensible. The data collected will be used to support closure of the tanks, compare the expected versus actual waste volume and curies to aid in conducting operations, and verify the performance of developmental equipment

Commonwealth Edison's approach to enhanced on-shift technical capability

International Nuclear Information System (INIS)

Toscas, J.G.

1981-01-01

A long-term plan was formulated that called for the integration of accident assessment and operational supervisory functions into a new operating position called the Station Control Room Engineer (SCRE). Pending implementation of the long-term plan, an alternative to the Shift Technical Advisor concept was selected as an interim plan. This alternative, called the SRO Augmentation program, involved giving five modules of specialized training to shift Senior Operators

Evaluation of ERA-Interim precipitation data in complex terrain

Science.gov (United States)

Gao, Lu; Bernhardt, Matthias; Schulz, Karsten

2013-04-01

Precipitation controls a large variety of environmental processes, which is an essential input parameter for land surface models e.g. in hydrology, ecology and climatology. However, rain gauge networks provides the necessary information, are commonly sparse in complex terrains, especially in high mountainous regions. Reanalysis products (e.g. ERA-40 and NCEP-NCAR) as surrogate data are increasing applied in the past years. Although they are improving forward, previous studies showed that these products should be objectively evaluated due to their various uncertainties. In this study, we evaluated the precipitation data from ERA-Interim, which is a latest reanalysis product developed by ECMWF. ERA-Interim daily total precipitation are compared with high resolution gridded observation dataset (E-OBS) at 0.25°×0.25° grids for the period 1979-2010 over central Alps (45.5-48°N, 6.25-11.5°E). Wet or dry day is defined using different threshold values (0.5mm, 1mm, 5mm, 10mm and 20mm). The correspondence ratio (CR) is applied for frequency comparison, which is the ratio of days when precipitation occurs in both ERA-Interim and E-OBS dataset. The result shows that ERA-Interim captures precipitation occurrence very well with a range of CR from 0.80 to 0.97 for 0.5mm to 20mm thresholds. However, the bias of intensity increases with rising thresholds. Mean absolute error (MAE) varies between 4.5 mm day-1 and 9.5 mm day-1 in wet days for whole area. In term of mean annual cycle, ERA-Interim almost has the same standard deviation of the interannual variability of daily precipitation with E-OBS, 1.0 mm day-1. Significant wet biases happened in ERA-Interim throughout warm season (May to August) and dry biases in cold season (November to February). The spatial distribution of mean annual daily precipitation shows that ERA-Interim significant underestimates precipitation intensity in high mountains and northern flank of Alpine chain from November to March while pronounced

12 CFR 541.18 - Interim Federal savings association.

Science.gov (United States)

2010-01-01

... an existing savings and loan holding company or to facilitate any other transaction the Office may... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Interim Federal savings association. 541.18... REGULATIONS AFFECTING FEDERAL SAVINGS ASSOCIATIONS § 541.18 Interim Federal savings association. The term...

Performance and technical feasibility comparison of reusable launch systems: A synthesis of the ESA winged launcher studies

Science.gov (United States)

Berry, W.; Grallert, H.

1996-02-01

The paper presents a synthesis of the performance and technical feasibility assessment of 7 reusable launcher types, comprising 13 different vehicles, studied by European Industry for ESA in the ESA Winged Launcher Study in the period January 1988 to May 1994. The vehicles comprised single-stage-to-orbit (SSTO) and two-stage-to-orbit (TSTO) vehicles, propelled by either air-breathing/rocket propulsion or entirely by rocket propulsion. The results showed that an SSTO vehicle of the HOTOL-type, propelled by subsonic combustion air-breathing/rocket engines could barely deliver the specified payload mass and was aerodynamically unstable; that a TSTO vehicle of the Saenger type, employing subsonic combustion airbreathing propulsion in its first stage and rocket propulsion in its second stage, could readily deliver the specified payload mass and was found to be technically feasible and versatile; that an SSTO vehicle of the NASP type, propelled by supersonic combustion airbreathing/rocket propulsion was able to deliver a reduced payload mass, was very complex and required very advanced technologies; that an air-launched rocket propelled vehicle of the Interim HOTOL type, although technically feasible, could deliver only a reduced payload mass, being constrained by the lifting capability of the carrier airplane; that three different, entirely rocket-propelled vehicles could deliver the specified payload mass, were technically feasible but required relatively advanced technologies.

Failsafe automation of Phase II clinical trial interim monitoring for stopping rules.

Science.gov (United States)

Day, Roger S

2010-02-01

In Phase II clinical trials in cancer, preventing the treatment of patients on a study when current data demonstrate that the treatment is insufficiently active or too toxic has obvious benefits, both in protecting patients and in reducing sponsor costs. Considerable efforts have gone into experimental designs for Phase II clinical trials with flexible sample size, usually implemented by early stopping rules. The intended benefits will not ensue, however, if the design is not followed. Despite the best intentions, failures can occur for many reasons. The main goal is to develop an automated system for interim monitoring, as a backup system supplementing the protocol team, to ensure that patients are protected. A secondary goal is to stimulate timely recording of patient assessments. We developed key concepts and performance needs, then designed, implemented, and deployed a software solution embedded in the clinical trials database system. The system has been in place since October 2007. One clinical trial tripped the automated monitor, resulting in e-mails that initiated statistician/investigator review in timely fashion. Several essential contributing activities still require human intervention, institutional policy decisions, and institutional commitment of resources. We believe that implementing the concepts presented here will provide greater assurance that interim monitoring plans are followed and that patients are protected from inadequate response or excessive toxicity. This approach may also facilitate wider acceptance and quicker implementation of new interim monitoring algorithms.

76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

Science.gov (United States)

2011-04-14

... mandatory deposit requirements of the copyright law. The objective is to identify file submission, packaging... mandatory deposit provisions of the copyright law. Under the interim regulation, certain works available... LIBRARY OF CONGRESS Copyright Office [Docket No. 2011-3] Notice of Public Meeting: Technical...

40 CFR 80.141 - Interim detergent gasoline program.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Interim detergent gasoline program. 80... (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Detergent Gasoline § 80.141 Interim detergent gasoline... apply to: (i) All gasoline sold or transferred to a party who sells or transfers gasoline to the...

Interim Stabilization Equipment Essential and Support Drawing Plan

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings: Those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. Support Drawings: Those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings

Engineering study: disposition of terminal liquors for interim storage

International Nuclear Information System (INIS)

Metz, W.P.; Ogren, W.E.

1975-02-01

Eight alternative processes were chosen as being technologically feasible within the time frame dictated by budgeting procedures and terminal liquor availability. Solidified waste products acceptable for single-shell tank storage were assumed to be placed in available single-shell tanks. Double-shell tanks were used only for the more mobile terminal liquors or semi-solid mush products. The mush, chemical neutralization, and clay in-tank processes offer potential savings of tens of millions of dollars over double-shell tank storage of terminal liquors. In order to achieve this cost savings, the process development and demonstration must be completed prior to the beginning of double-shell tank construction (Dec. 1976) expected to be funded from a fiscal year 1977 line item. Budgeting for these additional double-shell tanks must proceed since the processing options discussed here are not yet available and may not prove to be available at the required time. This study indicates the following topics for additional study: Process technology development to achieve interim storage of terminal liquor products receives the greatest emphasis as a means of reducing capital expenditures. Interim storage product criteria, waste inventory, and conversion to final form require definition to allow comparison of the alternatives for disposition of terminal liquors. The pseudotechnical nature of product acceptability criteria is important to the evaluation of the partial neutralization and aluminum removal alternatives. More accurate estimates of terminal liquor quantity and composition are required to give a sound technical basis for choosing the appropriate processing alternative. Retrieval and reprocessing operations may affect the comparisons presented by this study

Results from the interim salt disposition program macrobatch 10 tank ²¹H qualification samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-02-23

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 10 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H and fulfills the requirements of Deliverable 3 of the Technical Task Request (TTR). Further work will report the results of the Extraction-Scrub-Strip (ESS) testing (Task 5 of the TTR) using the Tank 21H material. Task 4 of the TTR (MST Strike) will not be completed for Salt Batch 10.

Expert Systems as Tools for Technical Communicators.

Science.gov (United States)

Grider, Daryl A.

1994-01-01

Discusses expertise, what an expert system is, what an expert system shell is, what expert systems can and cannot do, knowledge engineering and technical communicators, and planning and managing expert system projects. (SR)

Design review report FFTF interim storage cask

International Nuclear Information System (INIS)

Scott, P.L.

1995-01-01

Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

Prototype for an automated technical specification information system

International Nuclear Information System (INIS)

Quinn, E.L.; Mills, R.H.; Groves, J.E.

1985-01-01

The Southern California Edison (SCE) Automated Technical Specification Information System (ATSIS) at the San Onofre nuclear generating station (SONGS) has been developed as a prototype for an on-line information management system. This system provides an appropriate level of update, inquiry, and report generation capabilities to help support plant operators at SONGS in their efforts to anticipate, identify, document, and track certain actions and activities associated with plant technical specifications and associated limiting conditions of operation (LCOs). Substantially increased emphasis is being placed on adherence to nuclear regulatory requirements and commitments contained on the operating licenses of nuclear power plants. Additionally, as each year passes, such requirements are becoming increasingly detailed and complex, making it more and more difficult to track and ensure total compliance with the many and varied requirements. To assist the operations department at SONGs in meeting their regulatory commitments, in January 1985 SCE commenced gathering together the leading technical expertise available in the industry to develop a computerized system to track all technical specification-related equipment for operability and impact on LCOs

1984 Federal Interim Storage fee study: a technical and economic analysis

International Nuclear Information System (INIS)

Engel, R.L.

1984-07-01

JAI examined alternative methods for structuring charges for Federal Interim Storage (FIS) services were examined and the conclusion reached that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, and (4) impact aid payments made in accordance with section 136(e) of the Act. The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under-or over-estimation in the costs used to calculate the Initial Payment of the fee including savings due to rod consolidation), (2) module costs (i.e., storage casks, drywells, or silos), and (3) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management and impact aid). Charges for the transport of spent fuel from the reactor site to FIS facilities would be separately assessed at cost since these will be specific to each reactor site and destination

78 FR 67442 - Congestion Mitigation and Air Quality Improvement Program Interim Guidance

Science.gov (United States)

2013-11-12

...] Congestion Mitigation and Air Quality Improvement Program Interim Guidance AGENCY: Federal Highway... Comment. SUMMARY: The FHWA is issuing Interim Guidance on the Congestion Mitigation and Air Quality.../environment/air_quality/cmaq/policy_and_guidance/2008_guidance/ guidance/. DATES: This Interim Guidance is...

47 CFR 51.715 - Interim transport and termination pricing.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51.715 Section 51.715 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER... Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

ITER Conceptual design: Interim report

International Nuclear Information System (INIS)

1990-01-01

This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project

A comparison of the value relevance of interim and annual financial statements

Directory of Open Access Journals (Sweden)

Mbalenhle Zulu

2017-03-01

Aim: It explores whether the value relevance of interim financial statements is higher than the value relevance of annual financial statements. Finally, it investigates whether accounting information published in interim and annual financial statements has incremental value relevance. Setting: Data for the period from 1999 to 2012 were collected from a sample of non-financial companies listed on the Johannesburg Stock Exchange. Method: The Ohlson model to investigate the value relevance of accounting information was used for the study. Results: The results show that interim book value of equity is value relevant while interim earnings are not. Interim financial statements appear to have higher value relevance than annual financial statements. The value relevance of interim and annual accounting information has remained fairly constant over the sample period. Incremental comparisons provide evidence that additional book value of equity and earnings that accrue to a company between interim and annual reporting dates are value relevant. Conclusion: The study was conducted over a long sample period (1999–2012, in an era when a technology-driven economy and more timely reporting media could have had an effect on the value relevance of published accounting information. To the best of our knowledge, this is the first study to evaluate and compare the value relevance of published interim and annual financial statements.

AGR-1 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Machael

2009-01-01

Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

TurboTech Technical Evaluation Automated System

Science.gov (United States)

Tiffany, Dorothy J.

2009-01-01

TurboTech software is a Web-based process that simplifies and semiautomates technical evaluation of NASA proposals for Contracting Officer's Technical Representatives (COTRs). At the time of this reporting, there have been no set standards or systems for training new COTRs in technical evaluations. This new process provides boilerplate text in response to interview style questions. This text is collected into a Microsoft Word document that can then be further edited to conform to specific cases. By providing technical language and a structured format, TurboTech allows the COTRs to concentrate more on the actual evaluation, and less on deciding what language would be most appropriate. Since the actual word choice is one of the more time-consuming parts of a COTRs job, this process should allow for an increase in quantity of proposals evaluated. TurboTech is applicable to composing technical evaluations of contractor proposals, task and delivery orders, change order modifications, requests for proposals, new work modifications, task assignments, as well as any changes to existing contracts.

Interim reliability evaluation program (IREP)

International Nuclear Information System (INIS)

Carlson, D.D.; Murphy, J.A.

1981-01-01

The Interim Reliability Evaluation Program (IREP), sponsored by the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission, is currently applying probabilistic risk analysis techniques to two PWR and two BWR type power plants. Emphasis was placed on the systems analysis portion of the risk assessment, as opposed to accident phenomenology or consequence analysis, since the identification of risk significant plant features was of primary interest. Traditional event tree/fault tree modeling was used for the analysis. However, the study involved a more thorough investigation of transient initiators and of support system faults than studies in the past and substantially improved techniques were used to quantify accident sequence frequencies. This study also attempted to quantify the potential for operator recovery actions in the course of each significant accident

Technical guide to criticality alarm system design

International Nuclear Information System (INIS)

Greenfield, B.

2009-01-01

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

Interim FEP report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

2004-08-01

This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

Interim FEP report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Skagius, Kristina

2004-08-01

This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

Hanford low-level tank waste interim performance assessment

International Nuclear Information System (INIS)

Mann, F.M.

1997-01-01

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives

Interim reliability-evaluation program: analysis of the Browns Ferry, Unit 1, nuclear plant. Appendix B - system descriptions and fault trees

International Nuclear Information System (INIS)

Mays, S.E.; Poloski, J.P.; Sullivan, W.H.; Trainer, J.E.; Bertucio, R.C.; Leahy, T.J.

1982-07-01

This report describes a risk study of the Browns Ferry, Unit 1, nuclear plant. The study is one of four such studies sponsored by the NRC Office of Research, Division of Risk Assessment, as part of its Interim Reliability Evaluation Program (IREP), Phase II. This report is contained in four volumes: a main report and three appendixes. Appendix B provides a description of Browns Ferry, Unit 1, plant systems and the failure evaluation of those systems as they apply to accidents at Browns Ferry. Information is presented concerning front-line system fault analysis; support system fault analysis; human error models and probabilities; and generic control circuit analyses

Single-shell tank interim stabilization risk analysis

International Nuclear Information System (INIS)

Basche, A.D.

1998-01-01

The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation

TWRS HLW interim storage facility search and evaluation

Energy Technology Data Exchange (ETDEWEB)

Calmus, R.B., Westinghouse Hanford

1996-05-16

The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.

105-H Reactor Interim Safe Storage Project Final Report

International Nuclear Information System (INIS)

Ison, E.G.

2008-01-01

The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D and D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

Gaz de France interim financial report 2007

International Nuclear Information System (INIS)

2007-01-01

This financial report contains the unaudited condensed financial statements of Gaz de France Group for the first half ended June 30, 2007, which were reviewed by the audit committee on August 27, 2007 and by the board of directors at its meeting on August 28, 2007. It includes forward-looking statements concerning the objectives, strategies, financial position, future operating results and the operations of Gaz de France Group. These statements reflect the Group's current perception of its activities and the markets in which it operates, as well as various estimates and assumptions considered to be reasonable. Content: interim management report (highlights of the first half of 2007, revenues and results for the period, financial structure, data on outstanding stock, outlook); interim consolidated financial statements (consolidated statements of income, consolidated balance sheets, consolidated statements of cash flows, recognized income and expenses, statements of changes in shareholders' equity, note to the consolidated financial statements); statement by the person responsible for the interim financial report; statutory auditors' report. (J.S.)

Interim Stabilization Equipment Essential and Support Drawing Plan

International Nuclear Information System (INIS)

HORNER, T.M.

2000-01-01

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. [CHG 2000a]. Support Drawings are those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings. [CHG 2000a

Retrievable surface storage: interim storage of solidified high-level waste

International Nuclear Information System (INIS)

LaRiviere, J.R.; Nelson, D.C.

1976-01-01

Studies have been conducted on retrievable-surface-storage concepts for the interim storage of solidified high-level wastes. These studies have been reviewed by the Panel on Engineered Storage, convened by the Committee on Radioactive Waste Management of the National Research Council-National Academy of Sciences. The Panel has concluded that ''retrievable surface storage is an acceptable interim stage in a comprehensive system for managing high-level radioactive wastes.'' The scaled storage cask concept, which was recommended by the Panel on Engineered Storage, consists of placing a canister of waste inside a carbon-steel cask, which in turn is placed inside a thick concrete cylinder. The waste is cooled by natural convection air flow through an annulus between the cask and the inner wall of the concrete cylinder. The complete assembly is placed above ground in an outdoor storage area

Fire Hazards Analysis for the 200 Area Interim Storage Area

International Nuclear Information System (INIS)

JOHNSON, D.M.

2000-01-01

This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards

Physical protection of shipments of irradiated reactor fuel; Interim guidance. Regulatory report

International Nuclear Information System (INIS)

1980-06-01

During May, 1979, the U.S. Nuclear Regulatory Commission approved for issuance in effective form new interim regulations for strengthening the protection of spent fuel shipments against sabotage and diversion. The new regulations were issued without benefit of public comment, but comments from the public were solicited after the effective date. Based upon the public comments received, the interim regulations were amended and reissued in effective form as a final interim rule in May, 1980. The present document supersedes a previously issued interim guidance document, NUREG-0561 (June, 1979) which accompanied the original rule. This report has been revised to conform to the new interim regulations on the physical protection of shipments of irradiated reactor fuel which are likely to remain in effect until the completion of an ongoing research program concerning the response of spent fuel to certain forms of sabotage, at which time the regulations may be rescinded, modified or made permanent, as appropriate. This report discusses the amended regulations and provides a basis on which licensees can develop an acceptable interim program for the protection of spent fuel shipments

Formal Modelling and Analysis of Socio-Technical Systems

NARCIS (Netherlands)

Probst, Christian W.; Kammüller, Florian; Rydhof Hansen, René; Probst, Christian W.; Hankin, Chris; Rydhof Hansen, René

2015-01-01

Attacks on systems and organisations increasingly exploit human actors, for example through social engineering. This non-technical aspect of attacks complicates their formal treatment and automatic identification. Formalisation of human behaviour is difficult at best, and attacks on socio-technical

Use of alternative dispute resolution--HHS. Notice of interim policy.

Science.gov (United States)

1992-10-27

The Department has developed an interim policy to address the use of alternative dispute resolution (ADR) as required by the Administrative Dispute Resolution Act (ADR Act), Public Law No. 101-552. This interim policy also responds to the Negotiated Rulemaking Act, Public Law No. 101-648, and relevant elements of the Executive Order on Civil Justice Reform (E.O. 12778). The Department is adopting an interim policy because we need a baseline of experience and knowledge from our own pilot activities and those of other agencies before finalizing a policy.

50 CFR 660.720 - Interim protection for sea turtles.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 9 2010-10-01 2010-10-01 false Interim protection for sea turtles. 660.720 Section 660.720 Wildlife and Fisheries FISHERY CONSERVATION AND MANAGEMENT, NATIONAL OCEANIC AND... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707...

MATHEMATICAL MODELS OF PROCESSES AND SYSTEMS OF TECHNICAL OPERATION FOR ONBOARD COMPLEXES AND FUNCTIONAL SYSTEMS OF AVIONICS

Directory of Open Access Journals (Sweden)

Sergey Viktorovich Kuznetsov

2017-01-01

Full Text Available Modern aircraft are equipped with complicated systems and complexes of avionics. Aircraft and its avionics tech- nical operation process is observed as a process with changing of operation states. Mathematical models of avionics pro- cesses and systems of technical operation are represented as Markov chains, Markov and semi-Markov processes. The pur- pose is to develop the graph-models of avionics technical operation processes, describing their work in flight, as well as during maintenance on the ground in the various systems of technical operation. The graph-models of processes and sys- tems of on-board complexes and functional avionics systems in flight are proposed. They are based on the state tables. The models are specified for the various technical operation systems: the system with control of the reliability level, the system with parameters control and the system with resource control. The events, which cause the avionics complexes and func- tional systems change their technical state, are failures and faults of built-in test equipment. Avionics system of technical operation with reliability level control is applicable for objects with constant or slowly varying in time failure rate. Avion- ics system of technical operation with resource control is mainly used for objects with increasing over time failure rate. Avionics system of technical operation with parameters control is used for objects with increasing over time failure rate and with generalized parameters, which can provide forecasting and assign the borders of before-fail technical states. The pro- posed formal graphical approach avionics complexes and systems models designing is the basis for models and complex systems and facilities construction, both for a single aircraft and for an airline aircraft fleet, or even for the entire aircraft fleet of some specific type. The ultimate graph-models for avionics in various systems of technical operation permit the beginning of

CMM Interim Check (U)

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-23

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

Technical and socio-political issues in radioactive waste disposal 1986. Vol. 1

International Nuclear Information System (INIS)

Parker, F.L.; Kasperson, R.E.; Andersson, T.L.; Parker, S.A.

1987-11-01

The purpose of the study was to provide an integrated technical and socio-political analysis of how six countries (Federal Republic of Germany, France, Sweden, Switzerland, United Kingdom and the United States of America) have responded to four key issues in radioactive waste management: a) What constitutes 'safe' or 'absolutely safe' disposal, b) site selection processes, c) timing and type of interim storage. (orig./HP)

ALARACT Demonstration for Primary Ventilation Systems at the DST Tank Farms for the Interim Stabilization Project (Saltwell Pumping) [SEC 1 Thru 3

International Nuclear Information System (INIS)

STAM, E.C.

2002-01-01

A demonstration of As Low As Reasonably Achievable Control Technology (ALARACT) was performed for the existing Double Shell Tank (DST) farm primary ventilation systems in support of the Single Shell Tanks (SSTs) Interim Stabilization Project. The primary ventilation systems evaluated in this ALARACT are located at the 241-AW, AN, AP, and SY tank farms. Of these farms, only the AP and SY farms are scheduled to receive SST waste prior to new ventilation systems being installed at the farms. As a result, full evaluations were performed for the 241-AP and SY systems, whereas only partial evaluations were performed for the 241-AN and AW systems. The full evaluation included the evaluation of the stack sampling system, whereas the partial evaluation did not. Also, 241-AY and AZ are not scheduled to receive SST waste so they were both excluded completely from the evaluation. This ALARACT demonstration evaluated the ability of the abatement and control technologies in the DST ventilation systems identified above to function during SST waste transfers as part of the SST Interim Stabilization Project. Where available, field data (waste temperatures) gathered during actual saltwell pumping activities, were used to support this demonstration. Also used were other process data and equipment capacities associated with the system evaluation. Where actual field data were not available, conservative assumptions, based upon process knowledge and standard engineering calculation methodologies, were used. The DST ventilation systems were also evaluated for compliance against the technology standards identified in Washington Administrative Code (WAC) 246-247, Radioactive Air Emissions, as well as other governing codes and standards

Vehicle Systems Analysis Technical Team Roadmap

Energy Technology Data Exchange (ETDEWEB)

None

2013-06-01

The mission of the Vehicle Systems Analysis Technical Team (VSATT) is to evaluate the performance and interactions of proposed advanced automotive powertrain components and subsystems, in a vehicle systems context, to inform ongoing research and development activities and maximize the potential for fuel efficiency improvements and emission reduction.

Primer Control System Cyber Security Framework and Technical Metrics

Energy Technology Data Exchange (ETDEWEB)

Wayne F. Boyer; Miles A. McQueen

2008-05-01

The Department of Homeland Security National Cyber Security Division supported development of a control system cyber security framework and a set of technical metrics to aid owner-operators in tracking control systems security. The framework defines seven relevant cyber security dimensions and provides the foundation for thinking about control system security. Based on the developed security framework, a set of ten technical metrics are recommended that allow control systems owner-operators to track improvements or degradations in their individual control systems security posture.

Developing new transportable storage casks for interim dry storage

International Nuclear Information System (INIS)

Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

2004-01-01

Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

42 CFR 413.350 - Periodic interim payments for skilled nursing facilities receiving payment under the skilled...

Science.gov (United States)

2010-10-01

... facilities receiving payment under the skilled nursing facility prospective payment system for Part A... nursing facilities receiving payment under the skilled nursing facility prospective payment system for... SNF receiving payment under the prospective payment system may receive periodic interim payments (PIP...

Data monitoring system of technical diagnosis system for EAST

International Nuclear Information System (INIS)

Qian Jing; Weng Peide; Chen Zhuomin; Wu Yu; Xi Weibin; Luo Jiarong

2010-01-01

Technical diagnosis system (TDS) is an important subsystem to monitor status parameters of EAST (experimental advanced superconducting tokamak). The upgraded TDS data monitoring system is comprised of management floor, monitoring floor and field floor.. Security protection, malfunction record and analysis are designed to make the system stable, robust and friendly. During the past EAST campaigns, the data monitoring system has been operated reliably and stably. The signal conditioning system and software architecture are described. (authors)

200-ZP-1 phase 2 interim remedial measure quarterly report, August--October 1996

International Nuclear Information System (INIS)

Freeman-Pollard, J.R.; Jacques, I.D.; McMahon, W.J.; Singleton, K.M.; Strope, S.A.; Swanson, L.C.; Windmueller, C.R.

1996-11-01

A groundwater pump-and-treat system is being operated in the 200-ZP-1 Operable Unit under authority of the Hanford Federal Facility Agreement and Consent Order . The purpose of the pump-and-treat system is to accomplish the following: Minimize further migration of the high-concentration portion of the carbon tetrachloride plume and co-contaminants chloroform and trichlorethylene in the 200-ZP-1 Operable Unit Provide data for evaluation of final remedy selection. The 200-ZP-1 pump-and-treat operations were conducted as a pilot-scale treatability test and interim remedial measure treatment system between August 1994 and July 1996 to assess the effectiveness of liquid-phase granular activated carbon carbon tetrachloride removal. The pilot-scale treatability test's removal efficiently was determined to be 99.96% for carbon tetrachloride, chloroform, and trichloroethylene. This report summarizes and evaluates treatment, hydraulic, and hydrochemistry data collected for the 200-ZP-1 interim remedial measure from August through September 1996

Materials behavior in interim storage of spent fuel

International Nuclear Information System (INIS)

Johnson, A.B. Jr.; Bailey, W.J.; Gilbert, E.R.; Inman, S.C.

1982-01-01

Interim storage has emerged as the only current spent-fuel management method in the US and is essential in all countries with nuclear reactors. Materials behavior is a key aspect in licensing interim-storage facilities for several decades of spent-fuel storage. This paper reviews materials behavior in wet storage, which is licensed for light-water reactor (LWR) fuel, and dry storage, for which a licensing position for LWR fuel is developing

Interim Safety Basis for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines

78 FR 49782 - Interim Staff Guidance on Changes During Construction

Science.gov (United States)

2013-08-15

... Construction AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim staff guidance; request for comment... During Construction.'' This ISG provides guidance to the NRC staff on the Preliminary Amendment Request...-ISG-025 ``Interim Staff Guidance on Changes during Construction under 10 CFR Part 52'' is available...

1986 Federal Interim Storage fee study: a technical and economic analysis

International Nuclear Information System (INIS)

1986-09-01

JAI examined alternative methods for structuring charges for federal interim storage (FIS) services and concluded that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, (4) impact aid payments made in accordance with Section 136(e) of the Act, and (5) module costs (i.e., storage casks, drywells or silos). The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under- or over-estimation in the costs used to calculate the Initial Payment of the fee (including savings due to rod consolidation), and (2) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management and impact aid). The module costs were included in the Initial Payment to preclude the possible need to obtain appropriations for federal funds to support the purchase of the modules in advance of receipt of the Final Payment. Charges for the transport of spent fuel from the reactor site to FIS facilities would be separately assessed at actual cost since these will be specific to each reactor site and destination

Development of a behavioural marker system for scrub practitioners' non-technical skills (SPLINTS system).

Science.gov (United States)

Mitchell, Lucy; Flin, Rhona; Yule, Steven; Mitchell, Janet; Coutts, Kathy; Youngson, George

2013-04-01

Adverse events still occur despite ongoing efforts to reduce harm to patients. Contributory factors to adverse events are often due to limitations in clinicians' non-technical skills (e.g. communication, situation awareness), rather than deficiencies in technical competence. We developed a behavioural rating system to provide a structured means for teaching and assessing scrub practitioners' (i.e. nurse, technician, operating department practitioner) non-technical skills. Psychologists facilitated focus groups (n = 4) with experienced scrub practitioners (n = 16; 4 in each group) to develop a preliminary taxonomy. Focus groups reviewed lists of non-technical-skill-related behaviours that were extracted from an interview study. The focus groups labelled skill categories and elements and also provided examples of good and poor behaviours for those skills. An expert panel (n = 2 psychologists; n = 1 expert nurse) then used an iterative process to individually and collaboratively review and refine those data to produce a prototype skills taxonomy. A preliminary taxonomy containing eight non-technical skill categories with 28 underlying elements was produced. The expert panel reduced this to three categories (situation awareness, communication and teamwork, task management), each with three underlying elements. The system was called the Scrub Practitioners' List of Intraoperative Non-Technical Skills system. A scoring system and a user handbook were also developed. A prototype behavioural rating system for scrub practitioners' non-technical skills was developed, to aid in teaching and providing formative assessment. This important aspect of performance is not currently explicitly addressed in any educational route to qualify as a scrub practitioner. © 2012 Blackwell Publishing Ltd.

Dry interim storage of radioactive material in Germany

International Nuclear Information System (INIS)

Drobniewski, Christian; Palmes, Julia

2013-01-01

In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

Gamma dose rate calculations for conceptual design of a shield system for spent fuel interim dry storage in CNA 1

International Nuclear Information System (INIS)

Blanco, A; Gomez S

2012-01-01

After completing the rearrangement of the Spent Fuel Elements (SFE) into a compact arrangement in the two storage water pools, Atucha Nuclear Reactor 1 (ANR 1) will leave free position for the wet storage of the SFE discharged until December 2014. Even, in two possible scenarios, such as extending operation from 2015 or the cessation of operation after that date, it will be necessary to empty the interim storage water pools transferring the SFE to a temporary dry storage system. Because the law 25.018 'Management of Radioactive Wastes' implies for the first scenario - operation beyond 2015 - that Nucleoelectrica Argentina S.A. will still be in charge of the dry storage system and for the second - the cessation of operation after 2015 - the National Commission of Atomic Energy (CNEA) will be in charge by the National Management Program of Radioactive Wastes, the interim dry storage system of SNF is an issue of common interest which justifies go forward together. For that purpose and in accordance with the criticality and shielding calculations relevant to the project, in this paper we present the dose rate calculations for shielding conceptual design of a system for dry interim storage of the SFE of ANR 1. The specifications includes that the designed system must be suitable without modification for the SFE of the ANR 2. The results for the calculation of the photon dose rate, in touch and at one meter far, for the Transport Module and the Container of the SFE, are presented, which are required and controlled by the National Regulatory Authority (NRA) and the International Atomic Energy Agency (IAEA). It was used the SAS4 module of SCALE5.1 system and MCNP5. As a design tool for the photon shielding in order to meet current standards for allowable dose rates, a radial and axial parametric analysis were developed based on the thickness of lead of the Transport Module. The results were compared and verified between the two computing systems. Before this

Volume reduction system by soil classifying. Soil-washing system and problems to be solved

International Nuclear Information System (INIS)

Oshino, Yoshio

2016-01-01

Radioactive contamination of ground surfaces, buildings and forests in a broad area was caused by the accident at the Fukushima Daiichi Nuclear Power Plant in Japan. The national government and municipalities have still been carrying out the decontamination works for livelihood areas after five years from the accident. The government estimated that the amounts of soils and wastes removed by the decontamination works would be about 28,000,000 cubic meters maximum including 20,000,000 cubic meters maximum of soils. The removed soils will be stored in “Interim Storage Facility” then will be finally disposed outside of Fukushima prefecture within 30 years. On the other hand, shortage of the soils as materials needed for the revitalization in Fukushima prefecture is expected. Technical Advisory Council on Remediation and Waste Management, which consists of about 90 companies, started a working group to investigate solutions to these problems. The working group focused on the investigation of the possibility to recycle the soils by washing and classification to use them as the materials for civil engineering works, and to reduce the volume of the interim storage. In the first part of this report, we have evaluated the applicability of various technologies for purification and volume reduction of the removed soils, and have researched usages, required quantities and specifications of the recycled soils. In the second part, we have made trial calculations of the volume reduction effects and costs using the washing and classification system. The calculated results showed the possibilities of reducing the storage capacity of the interim storage facility, as well as the construction and the operation costs by recycling the removed soils with the washing and classification system inside the interim storage facility. At the end of this report, we proposed problems to be solved in order to adopt the washing and classification system. (author)

Modelling and Reasoning about Security Requirements in Socio-Technical Systems

NARCIS (Netherlands)

Paja, Elda; Dalpiaz, Fabiano; Giorgini, Paolo

2015-01-01

Modern software systems operate within the context of larger socio-technical systems, wherein they interact—by exchanging data and outsourcing tasks—with other technical components, humans, and organisations. When interacting, these components (actors) operate autonomously; as such, they may

Planning of Maintenance and Repair of Complicated Technical Systems

Directory of Open Access Journals (Sweden)

N. I. Liseychikov

2004-01-01

Full Text Available It is expedient to use mathematical models for substantiation of operational material consumption at maintenance of complicated technical systems. The appropriate tasks have been considered: minimization of operational material consumption; determination of maximum scope of work to be executed while maintaining one system; optimization of operational material consumption while organizing maintenance of a system group; planning of technical maintenance and determination of a number of systems to be maintained. Formalization and solution of the above problems have been accomplished.

General certification procedure of enterprises and interim job enterprises

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This procedure defines the certification global process of enterprises employing workers of A or B category for nuclear facilities and interim job enterprises proposing workers of A or B category for nuclear facilities. This certification proves the enterprises ability to satisfy the specification ''E'' of the CEFRI and the interim job enterprises to satisfy the specification ''I'' of the CEFRI. (A.L.B.)

Climate change : we are at risk : interim report

International Nuclear Information System (INIS)

Oliver, D.; Wiebe, J.

2003-06-01

Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs

Climate change : we are at risk : interim report

Energy Technology Data Exchange (ETDEWEB)

Oliver, D.; Wiebe, J.

2003-06-01

Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs.

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.

Site safety progress review of spent fuel central interim storage facility. Final report

International Nuclear Information System (INIS)

Gurpinar, A.; Serva, L.; Giuliani

1995-01-01

Following the request of the Czech Power Board (CEZ) and within the scope of the Technical Cooperation Project CZR/9/003, a progress review of the site safety of the Spent Fuel Central Interim Storage Facility (SFCISF) was performed. The review involved the first two stages of the works comprising the regional survey and identification of candidate sites for the underground and surface storage options. Five sites have been identified as a result of the previous works. The following two stages will involved the identification of the preferred candidate sites for the two options and the final site qualification. The present review had the purpose of assessing the work already performed and making recommendations for the next two stages of works

Presidential Transition: The Experience of Two Community College Interim Presidents

Science.gov (United States)

Thompson, Matthew D.

2010-01-01

The purpose of this qualitative case study was to understand the experiences of two community college interim presidents, their characteristics, and how they led institutions following an abrupt presidential departure. There were two fundamental questions framing this research study, 1. How do two interim community college presidents lead…

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

Fast Flux Test Facility interim examination and maintenance cell: Past, present, and future

International Nuclear Information System (INIS)

Vincent, J.R.

1990-09-01

The Fast Flux Test Facility Interim Examination and Maintenance Cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The Interim Examination and Maintenance Cell equipment developed and used for the first ten years of operation has been primarily devoted to the disassembly and examination of core component test assemblies. While no major reactor equipment has required remote repair or maintenance, the Interim Examina Examination and Maintenance Cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished. The Interim Examination and Maintenance Cell's demonstrated versatility has shown its capability to support a challenging future. 12 refs., 9 figs

TADS: Technical Assistance Development System.

Science.gov (United States)

Epting, Rosemary, Ed.

Described is the Technical Assistance Development System (TADS), a component of the Frank Porter Graham Child Development Center of the University of North Carolina at Chapel Hill which offers support services to preschool demonstration centers for handicapped children in the First Chance Network. Discussed are the four types of services offered:…

Interim Reliability Evaluation Program procedures guide

International Nuclear Information System (INIS)

Carlson, D.D.; Gallup, D.R.; Kolaczkowski, A.M.; Kolb, G.J.; Stack, D.W.; Lofgren, E.; Horton, W.H.; Lobner, P.R.

1983-01-01

This document presents procedures for conducting analyses of a scope similar to those performed in Phase II of the Interim Reliability Evaluation Program (IREP). It documents the current state of the art in performing the plant systems analysis portion of a probabilistic risk assessment. Insights gained into managing such an analysis are discussed. Step-by-step procedures and methodological guidance constitute the major portion of the document. While not to be viewed as a cookbook, the procedures set forth the principal steps in performing an IREP analysis. Guidance for resolving the problems encountered in previous analyses is offered. Numerous examples and representative products from previous analyses clarify the discussion

New York State interim waste management cost evaluation

International Nuclear Information System (INIS)

Ma, M.S.; Watts, R.J.; Jorgensen, J.R.; Rochester Gas and Electric Corp., NY)

1985-01-01

The purpose of this study is to investigate and quantify the comparative costs associated with including or excluding Class A utility wastes at a centralized interim waste management facility in New York State. The objective of the study is to assess the unit costs and total statewide costs associated with two distinct scenarios: (1) the case where non-utility Class A LLRW is received, incinerated and stored at the centralized interim facility, and utility Class A wastes are held without incineration at respective nuclear power plant interim onsite facilities without incineration; and (2) the alternative case where both utility and non-utility Class A wastes are accepted, incinerated and stored at the centralized facility. Unit costs to waste generators are estimated for each of the two cases described. This is followed by an estimation of the statewide cost impact to the public. The cost impact represents the cost differential resulting from the exclusion of utility Class A waste from the centralized NYS interim waste management facility. The principal factors comprising the cost differential include (1) higher unit disposal fees charged to non-utility waste generators, which are passed along in the costs of products and services; and (2) costs to utilities due to construction of additional onsite storage capacity, which in turn are charged to electric rate payers

Lessons for outsourcing and interim management relationships.

Science.gov (United States)

Macko, W; Kostyack, P T

1999-01-01

Few decisions can affect an organization more than the selection of an outsourcing or interim management partner. More and more health care organizations face such decisions in today's competitive market in order to face new business needs. Making these relationships successful can be important for health care organizations seeking competitive advantages or seeking immediately accessible management support. These relationships, however, require careful partner selection and development. Success in outsourcing and interim management relationships is contingent upon a thorough selection process, a strong contract that has clearly and explicitly detailed responsibilities and a culture-sensitive business rapport between the client and selected partner.

Do Interim Assessments Reduce the Race and SES Achievement Gaps?

Science.gov (United States)

Konstantopoulos, Spyros; Li, Wei; Miller, Shazia R.; van der Ploeg, Arie

2017-01-01

The authors examined differential effects of interim assessments on minority and low socioeconomic status students' achievement in Grades K-6. They conducted a large-scale cluster randomized experiment in 2009-2010 to evaluate the impact of Indiana's policy initiative introducing interim assessments statewide. The authors used 2-level models to…

Alternatives generation and analysis report for immobilized low-level waste interim storage architecture

Energy Technology Data Exchange (ETDEWEB)

Burbank, D.A., Westinghouse Hanford

1996-09-01

The Immobilized Low-Level Waste Interim Storage subproject will provide storage capacity for immobilized low-level waste product sold to the U.S. Department of Energy by the privatization contractor. This report describes alternative Immobilized Low-Level Waste storage system architectures, evaluation criteria, and evaluation results to support the Immobilized Low-Level Waste storage system architecture selection decision process.

Interim Report by Asia International Grid Connection Study Group

Science.gov (United States)

Omatsu, Ryo

2018-01-01

The Asia International Grid Connection Study Group Interim Report examines the feasibility of developing an international grid connection in Japan. The Group has investigated different cases of grid connections in Europe and conducted research on electricity markets in Northeast Asia, and identifies the barriers and challenges for developing an international grid network including Japan. This presentation introduces basic contents of the interim report by the Study Group.

Sustainability and deliberate transition of socio-technical systems

DEFF Research Database (Denmark)

Hansen, Ole Erik; Søndergård, Bent; Stærdahl, Jens

or developing socio-technical systems in order to integrate the concept of sustainability as a driver for the deliberate and purposeful shaping and transition. The article discusses the requirements to effective governance networks and governing of governance networks. Research within innovation systems......The article suggests that deliberate planning for sustainability demands a focus on the transition of socio-technical systems in order to establish robust and more sustainable patterns of production and consumption. This implies the necessity of a new perspective for environmental planning......, transition management and technology systems combined with planning and experimental activities provides both a theoretical and empirical body of knowledge of such governance processes. The article discusses how this perspective can be used in relation to the process of developing bio-fuel systems...

German Approach for the Transport of Spent Fuel Packages after Interim Storage

International Nuclear Information System (INIS)

Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

2014-01-01

In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

Comparative technical-economic analysis of the low temperature heating systems

International Nuclear Information System (INIS)

Sharevski, Vasko; Sharevski, Milan

1994-01-01

A method for comparative technical-economic analysis between low temperature heating systems and heating systems with fossil fuel boiler plant, heat pump heating system and electrical heating systems is presented. The single and combined heating systems are analyzed. The technical-economic priority application of the heating system is determined according to the prices of the low temperature heat energy, fossil fuel heat energy, electrical energy, as well as to the coefficient of the annual use of the installed heating capacity, investment expenses, structure of the combined heating system and coefficient of performances of the heat pump. The combined heating system, composed with a low temperature heating subsystem, which is used to cover the base heat demands, and a oil boiler plant heating subsystem, for the top heat demands, have technical-economic justification and wide range of priority application, in comparison with single heating systems. (author)

Development of dual-purpose metal cask for interim storage of spent nuclear fuel (1). Outline of cask structure

International Nuclear Information System (INIS)

Shimizu, Masashi; Hayashi, Makoto; Kashiwakura, Jun

2003-01-01

Spent fuels discharged from nuclear power plants in Japan are planed to be reprocessed at the nuclear fuel recycle plant under construction at Rokkasho-mura. Since the amount of the spent fuels exceeds that of recycled fuel, the spent fuels have to be properly stored and maintained as recycle fuel resource until the beginning of the reprocessing. For that sake, interim storage installations are being constructed outside the nuclear power plants by 2010. The storage dry casks have been practically used as the interim storage in the nuclear power plants. From this reason, the storage system using the storage dry casks is promising as the interim storage installations away form the reactors, which are under discussion. In the interim storage facilities, the storage using the dry cask of the storage metal cask with business showings, having the function of transportation is now under discussion. By employing transportation and storage dual-purpose cask, the repack equipments can be exhausted, and the reliability of the interim storage installations can be increased. Hitachi, Ltd. has been developing the high reliable and economical transportation and storage dry metal cask. In this report, the outline of our developing transportation and storage dry cask is described. (author)

The AECL study for an intense neutron - generator (technical details)

Energy Technology Data Exchange (ETDEWEB)

Bartholomew, G A; Tunnicliffe, P R

1966-07-01

The AECL study for an intense neutron-generator has been in progress for two years. Recently the scientific and technical details and the conceptual designs were compiled in a report supporting proposals addressed to AECL's Board of Directors for further work. The compilation is being issued in this form to permit further discussion of the technical aspects. However readers are asked to appreciate that it was written primarily for an AECL audience, and specifically that those chapters giving tentative information about costs, the rate of investment and similar items have been omitted or modified, many references have been made to interim internal reports in order to complete the local documentation, but these references do not imply that the reports themselves can be made generally available. (author)

The AECL study for an intense neutron - generator (technical details)

International Nuclear Information System (INIS)

Bartholomew, G.A.; Tunnicliffe, P.R.

1966-01-01

The AECL study for an intense neutron-generator has been in progress for two years. Recently the scientific and technical details and the conceptual designs were compiled in a report supporting proposals addressed to AECL's Board of Directors for further work. The compilation is being issued in this form to permit further discussion of the technical aspects. However readers are asked to appreciate that it was written primarily for an AECL audience, and specifically that those chapters giving tentative information about costs, the rate of investment and similar items have been omitted or modified, many references have been made to interim internal reports in order to complete the local documentation, but these references do not imply that the reports themselves can be made generally available. (author)

Chaotic Phenomena in Technical Control Systems

DEFF Research Database (Denmark)

Mosekilde, Erik

1997-01-01

The paper discusses a number of examples of technical control systems that can exhibit deterministic chaos and other forms of complex nonlinear behavior. These examples include thermostatically regulated radiators, closely placed refrigirators, and industrial cooling compressors. The paper contin...

TCR as supervisor of technical systems

CERN Document Server

Laeger, H

1998-01-01

Our Technical Control Room (TCR) provides continuous supervision of CERN's technical infrastructure. It also serves the inhabitants of CERN's premises as a contact point in case of problems. Every year we initiate eleven thousand recorded corrective interventions; about half subsequent to user phone calls, the other half to automatic alarms. TCR tasks are essentially fourfold: collect and distribute information on abnormal operation states; supervise those technical systems for which we have a mandate; initiate corrective interventions; and perform corrective on-site interventions outside normal working hours. A TCR operator normally has an education corresponding to a French BTS and initially little professional experience. He holds short-term contracts, up to a maximum of six years. This paper outlines TCR tasks and presents some statistical data. It also indicates relations between users, equipment groups, contract firms and the TCR as go-between. Finally, it gives an account of our seven years experience ...

Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

Energy Technology Data Exchange (ETDEWEB)

CARRELL, R D

2002-07-16

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

Modelling and Analysing Socio-Technical Systems

DEFF Research Database (Denmark)

Aslanyan, Zaruhi; Ivanova, Marieta Georgieva; Nielson, Flemming

2015-01-01

Modern organisations are complex, socio-technical systems consisting of a mixture of physical infrastructure, human actors, policies and processes. An in-creasing number of attacks on these organisations exploits vulnerabilities on all different levels, for example combining a malware attack...

Modeling and Analysing Socio-Technical Systems

NARCIS (Netherlands)

Aslanyan, Zaruhi; Ivanova, Marieta G.; Nielson, Flemming; Probst, Christian W.

2015-01-01

Modern organisations are complex, socio-technical systems consisting of a mixture of physical infrastructure, human actors, policies and processes. An in- creasing number of attacks on these organisations exploits vulnerabilities on all different levels, for example combining a malware attack with

The Interim Financial Reporting in the Spirit of the IAS 34 Norm

OpenAIRE

Ovidia Doinea

2008-01-01

The role of an interim financial reporting is to allow the information users to acknowledge the activity of an entity on period shorter than financial exercise from the perspective of the available profits and cash flows generated as well as from the point of view of its financial position and liquidity. The interim financial reporting includes a complete or condensed set of financial statements which target to update the last financial reporting, usually the annual report. The interim financ...

Quantifying resilience for resilience engineering of socio technical systems

OpenAIRE

Häring, Ivo; Ebenhöch, Stefan; Stolz, Alexander

2016-01-01

Resilience engineering can be defined to comprise originally technical, engineering and natural science approaches to improve the resilience and sustainability of socio technical cyber-physical systems of various complexities with respect to disruptive events. It is argued how this emerging interdisciplinary technical and societal science approach may contribute to civil and societal security research. In this context, the article lists expected benefits of quantifying resilience. Along the r...

Conceptual design of an interim dry storage system for the Atucha nuclear power plant spent fuels

International Nuclear Information System (INIS)

Nassini, Horacio E.P.; Fuenzalida Troyano, C.S.; Bevilacqua, Arturo M.; Bergallo, Juan E.

2005-01-01

The Atucha I nuclear power station, after completing the rearrangement and consolidation of the spent fuels in the two existing interim wet storage pools, will have enough room for the storage of spent fuel from the operation of the reactor till December 2014. If the operation is extended beyond 2014, or if the reactor is decommissioned, it will be necessary to empty both pools and to transfer the spent fuels to a dry storage facility. This paper shows the progress achieved in the conceptual design of a dry storage system for Atucha I spent fuels, which also has to be adequate, without modifications, for the storage of fuels from the second unity of the nuclear power station, Atucha II, that is now under construction. (author) [es

Transuranic waste storage and assay facility (TRUSAF) interim safety basis

International Nuclear Information System (INIS)

Gibson, K.D.

1995-09-01

The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

Albany Interim Landfill gas extraction and mobile power system: Using landfill gas to produce electricity. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

The Albany Interim Landfill Gas Extraction and Mobile Power System project served three research objectives: (1) determination of the general efficiency and radius of influence of horizontally placed landfill gas extraction conduits; (2) determination of cost and effectiveness of a hydrogen sulfide gas scrubber utilizing Enviro-Scrub{trademark} liquid reagent; and (3) construction and evaluation of a dual-fuel (landfill gas/diesel) 100 kW mobile power station. The horizontal gas extraction system was very successful; overall, gas recovery was high and the practical radius of influence of individual extractors was about 50 feet. The hydrogen sulfide scrubber was effective and its use appears feasible at typical hydrogen sulfide concentrations and gas flows. The dual-fuel mobile power station performed dependably and was able to deliver smooth power output under varying load and landfill gas fuel conditions.

Methodology for quantitative assessment of technical condition in industrial systems

Energy Technology Data Exchange (ETDEWEB)

Steinbach, C [Marintek AS (Norway); Soerli, A [Statoil (Norway)

1999-12-31

As part of the Eureka project Ageing Management a methodology has been developed to assess the technical condition of industrial systems. The first part of the presentation argues for the use of technical condition parameters in the context of maintenance strategies. Thereafter the term `technical condition` is defined more thoroughly as it is used within the project. It is claimed that the technical condition of a system - such as a feed water system of a nuclear power plant, or a water injection system on an oil platform - may be determined by aggregating the condition of its smaller components using a hierarchic approach. The hierarchy has to be defined in co-operation with experienced personnel and reflects the impact of degradation of elements on a lower level to nodes higher in the hierarchy. The impact is divided into five categories with respect to safety, environment, availability, costs and man-hours. To determine the technical condition of the bottom elements of the hierarchy, available data is used from both an on-line condition monitoring system and maintenance history. The second part of the presentation introduces the prototype software tool TeCoMan which utilises the theory and applies it to installations of the participating companies. First results and gained experiences with the method and tool are discussed. (orig.)

Methodology for quantitative assessment of technical condition in industrial systems

Energy Technology Data Exchange (ETDEWEB)

Steinbach, C. [Marintek AS (Norway); Soerli, A. [Statoil (Norway)

1998-12-31

As part of the Eureka project Ageing Management a methodology has been developed to assess the technical condition of industrial systems. The first part of the presentation argues for the use of technical condition parameters in the context of maintenance strategies. Thereafter the term `technical condition` is defined more thoroughly as it is used within the project. It is claimed that the technical condition of a system - such as a feed water system of a nuclear power plant, or a water injection system on an oil platform - may be determined by aggregating the condition of its smaller components using a hierarchic approach. The hierarchy has to be defined in co-operation with experienced personnel and reflects the impact of degradation of elements on a lower level to nodes higher in the hierarchy. The impact is divided into five categories with respect to safety, environment, availability, costs and man-hours. To determine the technical condition of the bottom elements of the hierarchy, available data is used from both an on-line condition monitoring system and maintenance history. The second part of the presentation introduces the prototype software tool TeCoMan which utilises the theory and applies it to installations of the participating companies. First results and gained experiences with the method and tool are discussed. (orig.)

Security analysis of socio-technical physical systems

NARCIS (Netherlands)

Lenzini, Gabriele; Mauw, Sjouke; Ouchani, Samir

2015-01-01

Recent initiatives that evaluate the security of physical systems with objects as assets and people as agents – here called socio-technical physical systems – have limitations: their agent behavior is too simple, they just estimate feasibility and not the likelihood of attacks, or they do estimate

Commentary: Interim leadership of academic departments at U.S. medical schools.

Science.gov (United States)

Grigsby, R Kevin; Aber, Robert C; Quillen, David A

2009-10-01

Medical schools and teaching hospitals are experiencing more frequent turnover of department chairs. Loss of a department chair creates instability in the department and may have a negative effect on the organization at large. Interim leadership of academic departments is common, and interim chairs are expected to immediately demonstrate skills and leadership abilities. However, little is known about how persons are prepared to assume the interim chair role. Newer competencies for effective leadership include an understanding of the business of medicine, interpersonal and communication skills, the ability to deal with conflict and solve adaptive challenges, and the ability to build and work on teams. Medical schools and teaching hospitals need assistance to meet the unique training and support needs of persons serving as interim leaders. For example, the Association of American Medical Colleges and individual chair societies can develop programs to allow current chairs to reflect on their present positions and plan for the future. Formal leadership training, mentorship opportunities, and conscientious succession planning are good first steps in preparing to meet the needs of academic departments during transitions in leadership. Also, interim leadership experience may be useful as a means for "opening the door" to underrepresented persons, including women, and increasing the diversity of the leadership team.

Tele-maintenance 'intelligent' system for technical plants result management

International Nuclear Information System (INIS)

Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

2009-01-01

The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

K basins interim remedial action health and safety plan

Energy Technology Data Exchange (ETDEWEB)

DAY, P.T.

1999-09-14

The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

Interim safety basis for fuel supply shutdown facility

International Nuclear Information System (INIS)

Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

1995-01-01

This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings

Radiation shielding at interim storage facility for CANDU-type nuclear spent fuel

International Nuclear Information System (INIS)

Mateescu, S.; Radu, M. Pantazi D.; Stanciu, M.

1997-01-01

Technical measures in radiological protection are taken in the interim storage facility design to ensure that, during normal operation, exposures of workers and members of public to ionizing radiation are limited to levels lower than regulatory limits. The spent fuel storage design provides for radiation exposure to be as low as reasonable achievable (ALARA principles). The evaluation of radiation shields includes the most conservative provisions: - all locations which may contain spent fuel are full; - the spent fuel has reached the maximum burnup; - the post irradiation cooling period should be the minimum reasonable; - equipment for handling contains the maximum amount of spent fuel. Radiation shields should ensure that external radiation fields do not exceed limits accepted by the Regulatory Body Module. The evaluation has been performed with two computer codes, QAD-5K and MICROSHIELD-4. (authors)

Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

International Nuclear Information System (INIS)

Klett, R.D.

1997-06-01

The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

Interim Design Report

CERN Document Server

Choubey, S.; Goswami, S.; Berg, J.S.; Fernow, R.; Gallardo, J.C.; Gupta, R.; Kirk, H.; Simos, N.; Souchlas, N.; Ellis, M.; Kyberd, P.; Benedetto, E.; Fernandez-Martinez, E.; Efthymiopoulos, I.; Garoby, R.; Gilardoni, S.; Martini, M.; Prior, G.; Ballett, P.; Pascoli, S.; Bross, A.; Geer, S.; Johnstone, C.; Kopp, J.; Mokhov, N.; Morfin, J.; Neuffer, D.; Parke, S.; Popovic, M.; Strait, J.; Striganov, S.; Blondel, A.; Dufour, F.; Laing, A.; Soler, F.J.P; Lindner, M.; Schwetz, T.; Alekou, A.; Apollonio, M.; Aslaninejad, M.; Bontoiu, C.; Dornan, P.; Eccleston, R.; Kurup, A.; Long, K.; Pasternak, J.; Pozimski, J.; Bogacz, A.; Morozov, V.; Roblin, Y.; Bhattacharya, S.; Majumdar, D.; Mori, Y.; Planche, T.; Zisman, M.; Cline, D.; Stratakis, D.; Ding, X.; Coloma, P.; Donini, A.; Gavela, B.; Lopez Pavon, J.; Maltoni, M.; Bromberg, C.; Bonesini, M.; Hart, T.; Kudenko, Y.; Mondal, N.; Antusch, S.; Blennow, M.; Ota, T.; Abrams, R.J.; Ankenbrandt, C.M.; Beard, K.B.; Cummings, M.A.C.; Flanagan, G.; Johnson, R.P.; Roberts, T.J.; Yoshikawa, C.Y.; Migliozzi, P.; Palladino, V.; de Gouvea, A.; Graves, V.B.; Kuno, Y.; Peltoniemi, J.; Blackmore, V.; Cobb, J.; Witte, H.; Mezzetto, M.; Rigolin, S.; McDonald, K.T.; Coney, L.; Hanson, G.; Snopok, P.; Tortora, L.; Andreopoulos, C.; Bennett, J.R.J.; Brooks, S.; Caretta, O.; Davenne, T.; Densham, C.; Edgecock, R.; Kelliher, D.; Loveridge, P.; McFarland, A.; Machida, S.; Prior, C.; Rees, G.; Rogers, C.; Thomason, J.W.G.; Booth, C.; Skoro, G.; Karadzhov, Y.; Matev, R.; Tsenov, R.; Samulyak, R.; Mishra, S.R.; Petti, R.; Dracos, M.; Yasuda, O.; Agarwalla, S.K.; Cervera-Villanueva, A.; Gomez-Cadenas, J.J.; Hernandez, P.; Li, T.; Martin-Albo, J.; Huber, P.; Back, J.; Barker, G.; Harrison, P.; Meloni, D.; Tang, J.; Winter, W.

2011-01-01

The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites shou...

Technical study report on fuel fabrication system

International Nuclear Information System (INIS)

Kono, Shusaku; Tanaka, Kenya; Ono, Kiyoshi; Iwasa, Katsuyoshi; Hoshino, Yasushi; Shinkai, Yasuo

2000-07-01

The feasibility study of FBR and related fuel cycle is performed for developing the FBR recycle system which ensures safety, economic competitiveness, efficient utilization of resources, reduction of environmental burden and enhancement of nuclear non-proliferation under consistency of FBR reactor and fuel cycle systems. In this study, a conceptual design study and system characteristics evaluation are conducted for fuel fabrication systems of pellet process, vibropack process for oxide and nitride fuel and casting process for metal fuel. Technical issues in each process are also extracted. In 1999 fiscal year, a conceptual design study were conducted for the fuel fabrication plants adopting (1) the short pellet process which simplifies the conventional MOX pellet fabrication processes, (2) vibropack processes of aqueous gelation process, improved RIAR process, improved ANL process and fluoride volatility process, (3) casting processes of injection process, centrifuging process. As a result, attainable perspective was obtained for each fuel fabrication system through the evaluation of apparatuses, layout and facility volume, etc. In each fuel fabrication system, technical issues for practical use were made clear. Hereafter, more detailed study will be performed for each system, and research programs for phase II study will be planned. (author)

Internet application: production-technical information system MoNET

International Nuclear Information System (INIS)

Tomiga, J.

2004-01-01

MoNET is the production-technical information system supporting engineering, operational and maintenance processes of distribution network administrator. It utilizes the model of distribution network that is situated in the geo-space relational database. The geo-space database represents an information base of operational-technical processes. It contains elements and equipment s of the distribution network, failures, operational events, maintenance records, but also, parcels, reference planimetry, e.g. and other subjects for which is relevant the positional datum - geo-space information. MoNET is typically exploited in the fields: - evidence of the subjects and equipment of network, technical documentation; - property administration; - planning of network development, support of designing and construction; - technical calculation; - breakdown controller centre; - maintenance management. MoNET can be implemented as the desktop application, however its first benefit is derived from its usage as the intranet application MoNET WEB for the whole enterprise or organisation. This version enables an unrestricted number of end-users to enter this system. The end-users don't need any special software to enter the data of MoNet WEB application, the pre-installed Internet Explorer will do. (author)

Residual life of technical systems; diagnosis, prediction and life extension

International Nuclear Information System (INIS)

Reinertsen, Rune

1996-01-01

The paper presents and discusses research related to residual life of non-repairable and repairable technical systems. Diagnosis of systems and extension of residual life of technical systems are also presented and discussed. This paper concludes that research published describing determination and extension of residual life as well as methods for diagnosis of non-repairable and repairable technical systems, is somewhat limited. Many papers have a rather pragmatic approach. The authors only describe special cases from their own plant and do not provide any explanation of a more academical nature. The other papers are mainly describing very specific applications of statistical models, leaving the more general case out of consideration. One of the main results of this paper is to point out these facts, and thereby identify the need for future research in this area

Developing new transportable storage casks for interim dry storage

Energy Technology Data Exchange (ETDEWEB)

Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

2004-07-01

Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

Technical Issues Map for the NHI System Interface and Support Systems Area: 3rd Quarter FY 07

International Nuclear Information System (INIS)

Steven R. Sherman

2007-01-01

This document provides a mapping of technical issues associated with development of the Next Generation Nuclear Plant (NGNP) intermediate heat transport loop and nuclear hydrogen plant support systems to the work that has been accomplished or is currently underway. The technical issues are ranked according to priority and by assumed resolution dates. Due to funding limitations, not all high-priority technical issues are under study at the present time, and more resources will need to be dedicated to tackling such issues in the future. This technical issues map is useful for understanding the relative importance of various technical challenges and will be used as a planning tool by the NHI technical leadership for future work package planning. The technical map in its present form will be discontinued in FY08 and will be folded into a larger NHI System Interface and Support Systems project management plan and scope baseline statement in FY08

Measurable Control System Security through Ideal Driven Technical Metrics

Energy Technology Data Exchange (ETDEWEB)

Miles McQueen; Wayne Boyer; Sean McBride; Marie Farrar; Zachary Tudor

2008-01-01

The Department of Homeland Security National Cyber Security Division supported development of a small set of security ideals as a framework to establish measurable control systems security. Based on these ideals, a draft set of proposed technical metrics was developed to allow control systems owner-operators to track improvements or degradations in their individual control systems security posture. The technical metrics development effort included review and evaluation of over thirty metrics-related documents. On the bases of complexity, ambiguity, or misleading and distorting effects the metrics identified during the reviews were determined to be weaker than necessary to aid defense against the myriad threats posed by cyber-terrorism to human safety, as well as to economic prosperity. Using the results of our metrics review and the set of security ideals as a starting point for metrics development, we identified thirteen potential technical metrics - with at least one metric supporting each ideal. Two case study applications of the ideals and thirteen metrics to control systems were then performed to establish potential difficulties in applying both the ideals and the metrics. The case studies resulted in no changes to the ideals, and only a few deletions and refinements to the thirteen potential metrics. This led to a final proposed set of ten core technical metrics. To further validate the security ideals, the modifications made to the original thirteen potential metrics, and the final proposed set of ten core metrics, seven separate control systems security assessments performed over the past three years were reviewed for findings and recommended mitigations. These findings and mitigations were then mapped to the security ideals and metrics to assess gaps in their coverage. The mappings indicated that there are no gaps in the security ideals and that the ten core technical metrics provide significant coverage of standard security issues with 87% coverage. Based

PVUSA model technical specification for a turnkey photovoltaic power system

Energy Technology Data Exchange (ETDEWEB)

Dows, R.N.; Gough, E.J.

1995-11-01

One of the five objectives of PVUSA is to offer U.S. utilities hands-on experience in designing, procuring, and operating PV systems. The procurement process included the development of a detailed set of technical requirements for a PV system. PVUSA embodied its requirements in a technical specification used as an attachment to its contracts for four utility-scale PV systems in the 200 kW to 500 kW range. The technical specification has also been adapted and used by several utilities. The PVUSA Technical Specification has now been updated and is presented here as a Model Technical Specification (MTS) for utility use. The MTS text is also furnished on a computer disk in Microsoft Word 6.0 so that it may be conveniently adapted by each user. The text includes guidance in the form of comments and by the use of parentheses to indicate where technical information must be developed and inserted. Commercial terms and conditions will reflect the procurement practice of the buyer. The reader is referred to PG&E Report Number 95-3090000. 1, PVUSA Procurement, Acceptance and Rating Practices for Photovoltaic Power Plants (1995) for PVUSA experience and practice. The MTS is regarded by PVUSA as a use-proven document, but needs to be adapted with care and attention to detail.

Technically-oriented operation management systems in conjunction with commercial DB systems

Energy Technology Data Exchange (ETDEWEB)

Lex, M.; Heselmann, B. [GiS mbH, Erlangen (Germany); Eschbach, P. [BASF Consult GmbH, Muenchen (Germany)

2001-07-01

Due to the liberalization of the electricity market, the efficiency and competitiveness of a power plant is increasingly measured at the cost per amount of energy generated. Thus, aspects of market-orientation and clearly cheaper electricity generation are in the foreground. Technically-oriented DP systems are necessary to save operating cost. These systems have structures differing from the mere business-oriented systems, because of the different frame conditions and operators' desire to stand out against rivalling competitors by technical and organizational measures. (orig.) [German] Die Effektivitaet und damit Konkurrenzfaehigkeit eines Kraftwerkes wird mit der Liberalisierung des Strommarktes verstaerkt an den Kosten je erzeugter Energieeinheit gemessen. Fuer den Betrieb ruecken damit Aspekte einer marktgerechten und somit deutlich kostenguenstigeren Stromerzeugung verstaerkt in den Vordergrund. Wer Betriebskosten sparen will, braucht technisch orientierte DV-Systeme, die aufgrund der unterschiedlichen Rahmenbedingungen und des Wunsches aller Anlagenbetreiber, sich durch technisch-organisatorische Massnahmen vom Wettbewerb vorteilhaft abzuheben, voellig andere Strukturen aufweisen als die betriebswirtschaftlich orientierten Systeme. (orig.)

Interim FDG-PET Scan in Hodgkin's Lymphoma: Hopes and Caveats

Directory of Open Access Journals (Sweden)

M. André

2011-01-01

Full Text Available FDG-PET has recently emerged as an important tool for the management of Hodgkins lymphoma. Although its use for initial staging and response evaluation at the end of treatment is well established, the place of interim PET for response assessment and subsequent treatment tailoring is still quite controversial. The use of interim PET after a few cycles of chemotherapy may allow treatment reduction for good responders, leading to lesser treatment toxicities as well as early treatment adaptation for bad responders with a potential higher chance for cure. Interpretation of interim PET is a rapidly moving field. Actually, visual interpretation is preferred over quantitative interpretation in this situation. The notion of minimal residual uptake emerged for faint persisting FDG uptake, but has evolved during the recent years. Guidelines using mediastinum and liver as references have been proposed at the expert meeting in Deauville 2009. Actually, several trials are ongoing both for localised and advanced disease to evaluate the FDG-PET potential for early treatment monitoring and tailoring. Until the results of these prospective randomized trials become available, treatment changes according to the interim PET results should remain inappropriate and limited to well-conducted clinical trials.

42 CFR 93.401 - Interaction with other offices and interim actions.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Interaction with other offices and interim actions. 93.401 Section 93.401 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES... Human Services General Information § 93.401 Interaction with other offices and interim actions. (a) ORI...

42 CFR 417.572 - Budget and enrollment forecast and interim reports.

Science.gov (United States)

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... PLANS, AND HEALTH CARE PREPAYMENT PLANS Medicare Payment: Cost Basis § 417.572 Budget and enrollment forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating budget...

Technical description - interim storage, encapsulation and disposal of spent nuclear fuel

International Nuclear Information System (INIS)

2010-07-01

The purpose of the annex Technical description is, in accordance with Chapter 22 paragraph 1 Environmental Code to describe the candidate operations and facilities. In particular, things that are important for their environmental impact are described. SKB's goal of the appendix is to describe the facilities, activities, pollution sources, land usage and more during construction, operation and decommissioning, to the extent and on a level of detail, so that the Environment Court without requiring additions can prepare the matter for the government's admissibility test

Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 and 2

International Nuclear Information System (INIS)

CARRELL, R.D.

2002-01-01

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

TECHNICAL SUPPORT AS A BASIS OF HIGH AVAILABILITY LEVEL AND IT SYSTEM SERVICE QUALITY

Directory of Open Access Journals (Sweden)

Dejan Vidojevic

2007-06-01

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

Early interim 18F-FDG PET in Hodgkin's lymphoma: evaluation on 304 patients

International Nuclear Information System (INIS)

Zinzani, Pier Luigi; Stefoni, Vittorio; Broccoli, Alessandro; Argnani, Lisa; Baccarani, Michele; Rigacci, Luigi; Puccini, Benedetta; Castagnoli, Antonio; Vaggelli, Luca; Zanoni, Lucia; Fanti, Stefano

2012-01-01

The use of early (interim) PET restaging during first-line therapy of Hodgkin's lymphoma (HL) in clinical practice has considerably increased because of its ability to provide early recognition of treatment failure allowing patients to be transferred to more intensive treatment regimens. Between June 1997 and June 2009, 304 patients with newly diagnosed HL (147 early stage and 157 advanced stage) were treated with the ABVD regimen at two Italian institutions. Patients underwent PET staging and restaging at baseline, after two cycles of therapy and at the end of the treatment. Of the 304 patients, 53 showed a positive interim PET scan and of these only 13 (24.5%) achieved continuous complete remission (CCR), whereas 251 patients showed a negative PET scan and of these 231 (92%) achieved CCR. Comparison between interim PET-positive and interim PET-negative patients indicated a significant association between PET findings and 9-year progression-free survival and 9-year overall survival, with a median follow-up of 31 months. Among the early-stage patients, 19 had a positive interim PET scan and only 4 (21%) achieved CCR; among the 128 patients with a negative interim PET scan, 122 (97.6%) achieved CCR. Among the advanced-stage patients, 34 showed a persistently positive PET scan with only 9 (26.4%) achieving CCR, whereas 123 showed a negative interim PET scan with 109 (88.6%) achieving CCR. Our results demonstrate the role of an early PET scan as a significant step forward in the management of patients with early-stage or advanced-stage HL. (orig.)

10 CFR 431.401 - Petitions for waiver, and applications for interim waiver, of test procedure.

Science.gov (United States)

2010-01-01

... Renewable Energy, U.S. Department of Energy. Each Application for Interim Waiver must reference the Petition... Renewable Energy. (e) Provisions specific to interim waivers—(1) Disposition of application. If... 10 Energy 3 2010-01-01 2010-01-01 false Petitions for waiver, and applications for interim waiver...

Advanced Exploration Systems Water Architecture Study Interim Results

Science.gov (United States)

Sargusingh, Miriam J.

2013-01-01

The mission of the Advanced Exploration System (AES) Water Recovery Project (WRP) is to develop advanced water recovery systems that enable NASA human exploration missions beyond low Earth orbit (LEO). The primary objective of the AES WRP is to develop water recovery technologies critical to near-term missions beyond LEO. The secondary objective is to continue to advance mid-readiness-level technologies to support future NASA missions. An effort is being undertaken to establish the architecture for the AES Water Recovery System (WRS) that meets both near- and long-term objectives. The resultant architecture will be used to guide future technical planning, establish a baseline development roadmap for technology infusion, and establish baseline assumptions for integrated ground and on-orbit Environmental Control and Life Support Systems definition. This study is being performed in three phases. Phase I established the scope of the study through definition of the mission requirements and constraints, as well as identifying all possible WRS configurations that meet the mission requirements. Phase II focused on the near-term space exploration objectives by establishing an International Space Station-derived reference schematic for long-duration (>180 day) in-space habitation. Phase III will focus on the long-term space exploration objectives, trading the viable WRS configurations identified in Phase I to identify the ideal exploration WRS. The results of Phases I and II are discussed in this paper.

The AECL study for an intense neutron - generator (technical details)

Energy Technology Data Exchange (ETDEWEB)

Bartholomew, G.A.; Tunnicliffe, P.R

1966-07-01

The AECL study for an intense neutron-generator has been in progress for two years. Recently the scientific and technical details and the conceptual designs were compiled in a report supporting proposals addressed to AECL's Board of Directors for further work. The compilation is being issued in this form to permit further discussion of the technical aspects. However readers are asked to appreciate that it was written primarily for an AECL audience, and specifically that those chapters giving tentative information about costs, the rate of investment and similar items have been omitted or modified, many references have been made to interim internal reports in order to complete the local documentation, but these references do not imply that the reports themselves can be made generally available. (author)

Fit of interim crowns fabricated using photopolymer-jetting 3D printing.

Science.gov (United States)

Mai, Hang-Nga; Lee, Kyu-Bok; Lee, Du-Hyeong

2017-08-01

The fit of interim crowns fabricated using 3-dimensional (3D) printing is unknown. The purpose of this in vitro study was to evaluate the fit of interim crowns fabricated using photopolymer-jetting 3D printing and to compare it with that of milling and compression molding methods. Twelve study models were fabricated by making an impression of a metal master model of the mandibular first molar. On each study model, interim crowns (N=36) were fabricated using compression molding (molding group, n=12), milling (milling group, n=12), and 3D polymer-jetting methods. The crowns were prepared as follows: molding group, overimpression technique; milling group, a 5-axis dental milling machine; and polymer-jetting group using a 3D printer. The fit of interim crowns was evaluated in the proximal, marginal, internal axial, and internal occlusal regions by using the image-superimposition and silicone-replica techniques. The Mann-Whitney U test and Kruskal-Wallis tests were used to compare the results among groups (α=.05). Compared with the molding group, the milling and polymer-jetting groups showed more accurate results in the proximal and marginal regions (P3D printing significantly enhanced the fit of interim crowns, particularly in the occlusal region. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

Interim report spent nuclear fuel retrieval system fuel handling development testing

Energy Technology Data Exchange (ETDEWEB)

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Criticality and shielding calculations of an interim dry storage system for the spent fuel from Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Silva, M

2006-01-01

The Atucha I Nuclear Power Plant (CNA-I) has enough room to store its spent fuel (SF) in damp in its two pool houses until the middle of 2015.Before that date there is the need to have an interim dry storage system for spent fuel that would make possible to empty at least one of the pools, whether to keep the plant operating if its useful life is extended, or to be able to empty the reactor core in case of decommissioning.Nucleolectrica Argentina S.A. (NA-SA) and the Comision Nacional de Energia Atomica (CNEA), due to their joint responsibility in the management of the SF, have proposed interim dry storage systems.These systems have to be evaluated in order to choose one of them by the end of 2006.In this work the Monte Carlo code MCNP was used to make the criticality and shielding calculations corresponding to the model proposed by CNEA.This model suggests the store of sealed containers with 36 or 37 SF in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.The results of the criticality calculations indicates that the solutions of SF proposed have widely fulfilled the requirements of subcriticality, even in supposed extreme accidental situations.Regarding the transference cask, the SF dose rate estimations allow us to make a feedback for the design aiming to the geometry and shielding improvements.Regarding the store modules, thicknesses ranges of concrete walls are suggested in order to fulfill the dose requirements stated by the Autoridad Regulatoria Nuclear Argentina [es

Program system RALLY - for probabilistic safety analysis of large technical systems

International Nuclear Information System (INIS)

Gueldner, W.; Polke, H.; Spindler, H.; Zipf, G.

1982-03-01

This report describes the program system RALLY to compute the reliability of large and intermeshed technical systems. In addition to a short explanation of the different programs, the possible applications of the program system RALLY are demonstrated. Finally, the most important studies carried out so far on RALLY are discussed. (orig.) [de

Interim Guidance for the Sanitary Control and Surveillance of Field Water Supplies

Science.gov (United States)

2005-07-15

on field water site/area restoration , including the removal and disposal of waste (see chapter 11 and FM 4-02.17). CHAPTER 3 INTRODUCTION TO...chemical addition, coagulation, sedimentation, and various kinds of filtration including multimedia filtration, cartridge filtration, microfiltration ... microfiltration membrane-based pretreatment system. Interim Guidance Pending Publication of TBMED 577 15 July 2005 53 Figure 9-1

Capturing socio-technical systems with agent-based modelling

NARCIS (Netherlands)

Van Dam, K.H.

2009-01-01

What is a suitable modelling approach for socio-technical systems? The answer to this question is of great importance to decision makers in large scale interconnected network systems. The behaviour of these systems is determined by many actors, situated in a dynamic, multi-actor, multi-objective and

Engineering study: disposition of terminal liquors for interim storage. [Eight alternative processes

Energy Technology Data Exchange (ETDEWEB)

Metz, W.P.; Ogren, W.E.

1975-02-01

Eight alternative processes were chosen as being technologically feasible within the time frame dictated by budgeting procedures and terminal liquor availability. Solidified waste products acceptable for single-shell tank storage were assumed to be placed in available single-shell tanks. Double-shell tanks were used only for the more mobile terminal liquors or semi-solid mush products. The mush, chemical neutralization, and clay in-tank processes offer potential savings of tens of millions of dollars over double-shell tank storage of terminal liquors. In order to achieve this cost savings, the process development and demonstration must be completed prior to the beginning of double-shell tank construction (Dec. 1976) expected to be funded from a fiscal year 1977 line item. Budgeting for these additional double-shell tanks must proceed since the processing options discussed here are not yet available and may not prove to be available at the required time. This study indicates the following topics for additional study: Process technology development to achieve interim storage of terminal liquor products receives the greatest emphasis as a means of reducing capital expenditures. Interim storage product criteria, waste inventory, and conversion to final form require definition to allow comparison of the alternatives for disposition of terminal liquors. The pseudotechnical nature of product acceptability criteria is important to the evaluation of the partial neutralization and aluminum removal alternatives. More accurate estimates of terminal liquor quantity and composition are required to give a sound technical basis for choosing the appropriate processing alternative. Retrieval and reprocessing operations may affect the comparisons presented by this study. (DLC)

Annex D 200 Area Interim Storage Area Final Safety Analysis Report Volume 5 (FSAR) (Section 1 and 2)

International Nuclear Information System (INIS)

CARRELL, R.D.

2003-01-01

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped offsite to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility (FFTF) Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the FFTF SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF)TRIGA--One Rad-Vault container stores two DOT-6M 3 containers and six NRF TRIGA casks. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-1 cask with an inner commercial light water reactor (LWR) canister, are used for storing commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

Engineering Task Plan for Hose-In-Hose Transfer Lines for the Interim Stabilization Program

International Nuclear Information System (INIS)

TORRES, T.D.

2000-01-01

The document is the Engineering Task Plan for the engineering, design services, planning, project integration and management support for the design, modification, installation and testing of an over ground transfer (OGT) system to support the interim stabilization of S/SX and U Tank Farms

Cost Sensitivity Analysis for Consolidated Interim Storage of Spent Fuel: Evaluating the Effect of Economic Environment Parameters

Energy Technology Data Exchange (ETDEWEB)

Cumberland, Riley M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Williams, Kent Alan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jarrell, Joshua J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Joseph, III, Robert Anthony [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-12-01

This report evaluates how the economic environment (i.e., discount rate, inflation rate, escalation rate) can impact previously estimated differences in lifecycle costs between an integrated waste management system with an interim storage facility (ISF) and a similar system without an ISF.

Introducing Systematic Aging Management for Interim Storage Facilities in Germany

International Nuclear Information System (INIS)

Spieth-Achtnich, Angelika; Schmidt, Gerhard

2014-01-01

In Germany twelve at-reactor and three central (away from reactor) dry storage facilities are in operation, where the fuel is stored in combined transport-and-storage casks. The safety of the storage casks and facilities has been approved and is licensed for up to 40 years operating time. If the availability of a final disposal facility for the stored wastes (spent fuel and high-level wastes from reprocessing) will be further delayed the renewal of the licenses can become necessary in future. Since 2001 Germany had a regulatory guideline for at-reactor dry interim storage of spent fuel. In this guideline some elements of ageing were implemented, but no systematic approach was made for a state-of-the-art ageing management. Currently the guideline is updated to include all kind of storage facilities (central storages as well) and all kinds of high level waste (also waste from reprocessing). Draft versions of the update are under discussion. In these drafts a systematic ageing management is seen as an instrument to upgrade the available technical knowledge base for possible later regulatory decisions, should it be necessary to prolong storage periods to beyond the currently approved limits. It is further recognized as an instrument to prevent from possible and currently unrecognized ageing mechanisms. The generation of information on ageing can be an important basis for the necessary safety-relevant verifications for long term storage. For the first time, the demands for a systematic monitoring of ageing processes for all safety-related components of the storage system are described. In addition, for inaccessible container components such as the seal system, the neutron shielding, the baskets and the waste inventory, the development of a monitoring program is recommended. The working draft to the revised guideline also contains recommendations on non-technical ageing issues such as the long-term preservation of knowledge, long term personnel planning and long term

A Non-Traditional Interim Project.

Science.gov (United States)

Brown, Diane; Ward, Dorothy

1980-01-01

Describes a project initiated by the Foreign Language Department of Birmingham-Southern College for their Interim term and discusses an interdisciplinary course focusing on Medieval Europe. The course included presentations on German and French language and literature, as well as lectures on the arts, philosophy, and family life of the period.…

Ideal Based Cyber Security Technical Metrics for Control Systems

Energy Technology Data Exchange (ETDEWEB)

W. F. Boyer; M. A. McQueen

2007-10-01

Much of the world's critical infrastructure is at risk from attack through electronic networks connected to control systems. Security metrics are important because they provide the basis for management decisions that affect the protection of the infrastructure. A cyber security technical metric is the security relevant output from an explicit mathematical model that makes use of objective measurements of a technical object. A specific set of technical security metrics are proposed for use by the operators of control systems. Our proposed metrics are based on seven security ideals associated with seven corresponding abstract dimensions of security. We have defined at least one metric for each of the seven ideals. Each metric is a measure of how nearly the associated ideal has been achieved. These seven ideals provide a useful structure for further metrics development. A case study shows how the proposed metrics can be applied to an operational control system.

Coordination of the commissioning of the LHC technical systems

CERN Document Server

Saban, R; Casas Lino, M P; Fernandez Robles, C; Pojer, M; Schmidt, R; Solfaroli Camillocci, M; Vergara Fernandez, A

2008-01-01

The Large Hadron Collider operation relies on 1232 superconducting dipoles with a field of 8.33T and 400 superconducting quadrupoles with a strength of 220 T/m powered at 12kA, operating in superfluid He at 1.9K. For dipoles and quadrupoles as well as for many other magnets more than 1700 power converters are necessary to feed the superconducting circuits. A sophisticated magnet protection system is crucial to detect a quench and safely extract the energy stored in the circuits (about 1GJ only in one of the dipole circuits) after a resistive transition. Besides, in such complex architecture, many technical services (e.g. cooling and ventilation, technical network, electrical distribution, GSM network, controls system, etc.) have to be reliably available during commissioning. Consequently, the commissioning of the technical systems and the associated infrastructures has been carefully studied. Procedures, automatic control and analysis tools, repositories for test data, management structures for carrying out a...

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

International Nuclear Information System (INIS)

Ware, A.G.; Morton, D.K.; Nitzel, M.E.

1995-03-01

Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants

Concept study for interim storage of research reactor fuel elements in transport and storage casks. Transport and storage licensing procedure for the CASTOR MTR 2 cask. Final report

International Nuclear Information System (INIS)

Weiss, M.

2001-01-01

As a result of the project, a concept was to be developed for managing spent fuel elements from research reactors on the basis of the interim storage technology existing in Germany, in order to make the transition to direct disposal possible in the long term. This final report describes the studies for the spent fuel management concept as well as the development of a transport and storage cask for spent fuel elements from research reactors. The concept analyses were based on data of the fuel to be disposed of, as well as the handling conditions for casks at the German research reactors. Due to the quite different conditions for handling of casks at the individual reactors, it was necessary to examine different cask concepts as well as special solutions for loading the casks outside of the spent fuel pools. As a result of these analyses, a concept was elaborated on the basis of a newly developed transport and storage cask as well as a mobile fuel transfer system for the reactor stations, at which a direct loading of the cask is not possible, as the optimal variant. The cask necessary for this concept with the designation CASTOR trademark MTR 2 follows in ist design the tried and tested principles of the CASTOR trademark casks for transport and interim storage of spent LWR fuel. With the CASTOR trademark MTR 2, it is possible to transport and to place into long term interim storage various fuel element types, which have been and are currently used in German research reactors. The technical development of the cask has been completed, the documents for the transport license as type B(U)F package design and for obtaining the storage license at the interim storage facility of Ahaus have been prepared, submitted to the licensing authorities and to a large degree already evaluated positively. The transport license of the CASTOR trademark MTR 2 has been issued for the shipment of VKTA-contents and FRM II compact fuel elements. (orig.)

Safety regulations for radioisotopes, etc. (interim report)

International Nuclear Information System (INIS)

1980-01-01

An (interim) report by an ad hoc expert committee to the Nuclear Safety Commission, on the safety regulations for radioisotopes, etc., was presented. For the utilization of radioisotopes, etc., there is the Law Concerning Prevention of Radiation Injury Due to Radioisotopes, etc. with the advances in this field and the improvement in international standards, the regulations by the law have been examined. After explaining the basic ideas of the regulations, the problems and countermeasures in the current regulations are described: legal system, rationalization in permission procedures and others, inspection on RI management, the system of the persons in charge of radiation handling, RI transport, low-level radioactive wastes, consumer goods, definitions of RIs, radiation and sealed sources, regulations by group partitioning, RI facilities, system of personnel exposure registration, entrusting of inspection, etc. to private firms, and reduction in the works for permission among governmental offices. (author)

Engineering Task Plan for Hose-In-Hose Transfer Lines for the Interim Stabilization Program

International Nuclear Information System (INIS)

RUNG, M.P.

2000-01-01

This document is the Engineering Task Plan for the engineering, design services, planning, project integration and management support for the design, modification, installation and testing of an over ground transfer (OGT) system to support the interim stabilization of nine tanks in the 241-S/SX Tank Farms

75 FR 35510 - License Renewal Interim Staff Guidance Process, Revision 2 Notice of Availability

Science.gov (United States)

2010-06-22

... Related Regulatory Functions.'' An electronic copy of the revised LR-ISG process is available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML100920158. The revised LR-ISG... interim changes to certain NRC license renewal guidance documents. These guidance documents facilitate the...

Agent-Based Modeling and Analysis of Socio-Technical Systems

NARCIS (Netherlands)

Sharpanskykh, O.

2011-01-01

Socio-technical systems are characterized by high structural and behavioral complexities, which impede understanding and modeling of such systems. In particular, reciprocal relations between diverse local system processes that determine global system dynamics are not well understood. In this article

Interim and final storage casks

International Nuclear Information System (INIS)

Stumpfrock, L.; Kockelmann, H.

2012-01-01

The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

Interim storage report

International Nuclear Information System (INIS)

Rawlins, J.K.

1998-02-01

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

ITER interim design report package documents

International Nuclear Information System (INIS)

1996-01-01

This publication contains the Excerpt from the ITER Council (IC-8), the ITER Interim Design Report, Cost Review and Safety Analysis, ITER Site Requirements and ITER Site Design Assumptions and the Excerpt from the ITER Council (IC-9). 8 figs, 2 tabs

Satellite power system concept development and evaluation program system definition technical assessment report

Energy Technology Data Exchange (ETDEWEB)

1980-12-01

The results of the system definition studies conducted by NASA as a part of the Department of Energy/National Aeronautics and Space Administration SPS Concept Development and Evaluation Program are summarized. The purpose of the system definition efforts was to identify and define candidate SPS concepts and to evaluate the concepts in terms of technical and cost factors. Although the system definition efforts consisted primarily of evaluation and assessment of alternative technical approaches, a reference system was also defined to facilitate economic, environmental, and societal assessments by the Department of Energy. This reference system was designed to deliver 5 GW of electrical power to the utility grid. Topics covered include system definition; energy conversion and power management; power transmission and reception; structures, controls, and materials; construction and operations; and space transportation.

Spent fuel interim storage

International Nuclear Information System (INIS)

Bilegan, Iosif C.

2003-01-01

The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

A randomized controlled trial of interim methadone maintenance.

Science.gov (United States)

Schwartz, Robert P; Highfield, David A; Jaffe, Jerome H; Brady, Joseph V; Butler, Carol B; Rouse, Charles O; Callaman, Jason M; O'Grady, Kevin E; Battjes, Robert J

2006-01-01

Effective alternatives to long waiting lists for entry into methadone hydrochloride maintenance treatment are needed to reduce the complications of continuing heroin dependence and to increase methadone treatment entry. To compare the effectiveness of interim methadone maintenance with that of the usual waiting list condition in facilitating methadone treatment entry and reducing heroin and cocaine use and criminal behavior. Randomized, controlled, clinical trial using 2 conditions, with treatment assignment on a 3:2 basis to interim maintenance-waiting list control. A methadone treatment program in Baltimore. A total of 319 individuals meeting the criteria for current heroin dependence and methadone maintenance treatment. Participants were randomly assigned to either interim methadone maintenance, consisting of an individually determined methadone dose and emergency counseling only for up to 120 days, or referral to community-based methadone treatment programs. Entry into comprehensive methadone maintenance therapy at 4 months from baseline; self-reported days of heroin use, cocaine use, and criminal behavior; and number of urine drug test results positive for heroin and cocaine at the follow-up interview conducted at time of entry into comprehensive methadone treatment (or at 4 months from baseline for participants who did not enter regular treatment). Significantly more participants assigned to the interim methadone maintenance condition entered comprehensive methadone maintenance treatment by the 120th day from baseline (75.9%) than those assigned to the waiting list control condition (20.8%) (Pmethadone maintenance results in a substantial increase in the likelihood of entry into comprehensive treatment, and is an effective means of reducing heroin use and criminal behavior among opioid-dependent individuals awaiting entry into a comprehensive methadone treatment program.

Development of technical information processing system (VII)

International Nuclear Information System (INIS)

Kim, Tae Whan; Choi, Kwang; Oh, Jeong Hoon; Jeong, Hyun Sook; Keum, Jong Yong

1995-12-01

The goal of this project is to establish integrated environment focused on enhanced information services to researchers through the providing of acquisition information, key phrase retrieval function, journal content information linked with various subsystems already developed. The results of the project are as follows. 1. It is possible to serve information on unreceivable materials among required materials throughout the system. 2. Retrieval efficiency is increased by the adding of key phrase retrieval function. 3. Rapidity of information service is enhanced by the providing of journal contents of each issue received and work performance of contents service is become higher. 4. It is possible to acquire, store, serve technical information needed in R and D synthetically and systematically throughout the development of total system linked with various subsystems required to technical information management and service. 21 refs. (Author)

Conduct of the Persian Gulf Conflict: An Interim Report to Congress

Science.gov (United States)

1991-07-01

a danger that we will assume that this war is a paradigm for the next, that subconsciously we’ll presume all future wars can be relatively pain free...CENTCOM. The experience elicited arecmmndtin o hagethe threshold for reprogram - JSTARS was an integral part of the system used to recommendation to...This Includes the realignment, reprogramming , or transfer of funds appropriated for activities unrelated to the Persian Gulf conflict. Interim Report

Interim evaluation report of the mutually operable database systems by different computers; Denshi keisanki sogo un'yo database system chukan hyoka hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-03-01

This is the interim report on evaluation of the mutually operable database systems by different computers. The techniques for these systems fall into four categories of those related to (1) dispersed data systems, (2) multimedia, (3) high reliability, and (4) elementary techniques for mutually operable network systems. The techniques for the category (1) include those for vertically dispersed databases, database systems for multiple addresses in a wide area, and open type combined database systems, which have been in progress generally as planned. Those for the category (2) include the techniques for color document inputting and information retrieval, meaning compiling, understanding highly overlapping data, and controlling data centered by drawings, which have been in progress generally as planned. Those for the category (3) include the techniques for improving resistance of the networks to obstruction, and security of the data in the networks, which have been in progress generally as planned. Those for the category (4) include the techniques for rule processing for development of protocols, protocols for mutually connecting the systems, and high-speed, high-function networks, which have been in progress generally as planned. It is expected that the original objectives are finally achieved, because the development programs for these categories have been in progress generally as planned. (NEDO)

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

International Nuclear Information System (INIS)

Pickett, W.W.

1997-01-01

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

Energy Technology Data Exchange (ETDEWEB)

Pickett, W.W.

1997-12-30

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

EFFECT OF REHABILITATION DURING INTERIM STAY IN AALBORG MUNICIPALITY, DENMARK: A STUDY PROTOCOL

DEFF Research Database (Denmark)

Villumsen, Sidsel Maria Monrad; Villumsen, Morten

2016-01-01

Background: In the municipality of Aalborg, Denmark, the aim is to support citizens’ rehabilitation through training and learning in order to be self-reliant. This effort is supported at interim stays at the nursing homes [1]. A recent external report has outlined that citizen are highly satis ed...... are available in the systems, containing information on rehabilitation services rendered during interim stays. However, available data on the effect of the rehabilitation are currently unstructured in free-text, which impedes the assessment of rehabilitation effect and thereby the quality assurance. Objectives...... on rehabilitation of the citizen. The rehabilitation effect will be extracted from the free-text in the records. The free-text will be categorized into rehabilitation effects of i) deterioration, ii) no effect, iii) effect of rehabilitation, or iv) not possible to classify from the text. Results: This study...

LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

Science.gov (United States)

A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

DOE UST interim subsurface barrier technologies workshop

International Nuclear Information System (INIS)

1992-09-01

This document contains information which was presented at a workshop regarding interim subsurface barrier technologies that could be used for underground storage tanks, particularly the tank 241-C-106 at the Hanford Reservation

Acquisition and Development of System Command (SYSCOM) Technical Manuals

National Research Council Canada - National Science Library

2003-01-01

... (NAVSEA) and Space and Naval Warfare Systems Command (SPAWAR). TMs are the primary information source for technical training, installation, operation, testing, maintenance, and repair associated with NAVSEA/SPAWAR systems or equipment...

Systems for deep brain stimulation: review of technical features.

Science.gov (United States)

Amon, A; Alesch, F

2017-09-01

The use of deep brain stimulation (DBS) is an important treatment option for movement disorders and other medical conditions. Today, three major manufacturers provide implantable systems for DBS. Although the underlying principle is basically the same for all available systems, the differences in the technical features vary considerably. This article outlines aspects regarding the technical features of DBS systems. The differences between voltage and current sources are addressed and their effect on stimulation is shown. To maintain clinical benefit and minimize side effects the stimulation field has to be adapted to the requirements of the patient. Shaping of the stimulation field can be achieved by the electrode design and polarity configuration. Furthermore, the electric signal consisting of stimulation rate, stimulation amplitude and pulse width affect the stimulation field. Interleaving stimulation is an additional concept, which permits improved treatment outcomes. Therefore, the electrode design, the polarity, the electric signal, and the concept of interleaving stimulation are presented. The investigated systems can be also categorized as rechargeable and non-rechargeable, which is briefly discussed. Options for interconnecting different system components from various manufacturers are presented. The present paper summarizes the technical features and their combination possibilities, which can have a major impact on the therapeutic effect.

Integrated waste management system costs in a MPC system

International Nuclear Information System (INIS)

Supko, E.M.

1995-01-01

The impact on system costs of including a centralized interim storage facility as part of an integrated waste management system based on multi-purpose canister (MPC) technology was assessed in analyses by Energy Resources International, Inc. A system cost savings of $1 to $2 billion occurs if the Department of Energy begins spent fuel acceptance in 1998 at a centralized interim storage facility. That is, the savings associated with decreased utility spent fuel management costs will be greater than the cost of constructing and operating a centralized interim storage facility

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-10-20

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

International Nuclear Information System (INIS)

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-01-01

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ''stabilized'' form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision

A conservative method of retaining an interim obturator for a total maxillectomy patient

Directory of Open Access Journals (Sweden)

Nirmal Famila Bettie

2017-01-01

Full Text Available Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

A Conservative Method of Retaining an Interim Obturator for a Total Maxillectomy Patient.

Science.gov (United States)

Bettie, Nirmal Famila

2017-11-01

Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

International validation study for interim PET in ABVD-treated, advanced-stage hodgkin lymphoma

DEFF Research Database (Denmark)

Biggi, Alberto; Gallamini, Andrea; Chauvie, Stephane

2013-01-01

At present, there are no standard criteria that have been validated for interim PET reporting in lymphoma. In 2009, an international workshop attended by hematologists and nuclear medicine experts in Deauville, France, proposed to develop simple and reproducible rules for interim PET reporting...... in lymphoma. Accordingly, an international validation study was undertaken with the primary aim of validating the prognostic role of interim PET using the Deauville 5-point score to evaluate images and with the secondary aim of measuring concordance rates among reviewers using the same 5-point score...

Interim report on the TMI-2 purification filter examination

International Nuclear Information System (INIS)

Mason, R.E.; Hobbins, R.R.; Cook, B.A.; MacDonald, P.E.

1983-02-01

Filters from the purification/makeup system of the Three Mile Island Unit 2 Reactor were examined after the March 28, 1979, accident to determine the character of the debris transported to the filters. The general condition of the filters is presented. Material was removed from the filters and examined. The elemental and radionuclide makeup of the debris is discussed. Distribution of particle size and shape is presentd for some of the material examined. This is an interim report. When the investigation is completed, another report summarizing all of the data will be issued

78 FR 41125 - Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting

Science.gov (United States)

2013-07-09

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0114] Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement; revision. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an interim Enforcement Policy that allows...

Predictive probability methods for interim monitoring in clinical trials with longitudinal outcomes.

Science.gov (United States)

Zhou, Ming; Tang, Qi; Lang, Lixin; Xing, Jun; Tatsuoka, Kay

2018-04-17

In clinical research and development, interim monitoring is critical for better decision-making and minimizing the risk of exposing patients to possible ineffective therapies. For interim futility or efficacy monitoring, predictive probability methods are widely adopted in practice. Those methods have been well studied for univariate variables. However, for longitudinal studies, predictive probability methods using univariate information from only completers may not be most efficient, and data from on-going subjects can be utilized to improve efficiency. On the other hand, leveraging information from on-going subjects could allow an interim analysis to be potentially conducted once a sufficient number of subjects reach an earlier time point. For longitudinal outcomes, we derive closed-form formulas for predictive probabilities, including Bayesian predictive probability, predictive power, and conditional power and also give closed-form solutions for predictive probability of success in a future trial and the predictive probability of success of the best dose. When predictive probabilities are used for interim monitoring, we study their distributions and discuss their analytical cutoff values or stopping boundaries that have desired operating characteristics. We show that predictive probabilities utilizing all longitudinal information are more efficient for interim monitoring than that using information from completers only. To illustrate their practical application for longitudinal data, we analyze 2 real data examples from clinical trials. Copyright © 2018 John Wiley & Sons, Ltd.

Computer-aided System of Semantic Text Analysis of a Technical Specification

OpenAIRE

Zaboleeva-Zotova, Alla; Orlova, Yulia

2008-01-01

The given work is devoted to development of the computer-aided system of semantic text analysis of a technical specification. The purpose of this work is to increase efficiency of software engineering based on automation of semantic text analysis of a technical specification. In work it is offered and investigated the model of the analysis of the text of the technical project is submitted, the attribute grammar of a technical specification, intended for formalization of limited Ru...

33 CFR 385.38 - Interim goals.

Science.gov (United States)

2010-07-01

..., monitoring and assessment; (ii) Be provided to the independent scientific review panel established in.... The interim goals shall be developed through the use of appropriate models and tools and shall provide... to be required to meet long-term hydrological and ecological restoration goals, based on best...

Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

International Nuclear Information System (INIS)

Klein, A.R.; Bloom, C.W.

1989-07-01

This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

75 FR 39919 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2010-07-13

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, July 28 Public...

75 FR 64258 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2010-10-19

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, November 3 Public...

78 FR 63162 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2013-10-23

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, November 6...

78 FR 42753 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2013-07-17

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... of export controls applicable to information systems equipment and technology. Wednesday, July 31...

76 FR 64895 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2011-10-19

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, November 2 Public...

76 FR 39845 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2011-07-07

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... export controls applicable to information systems equipment and technology. Wednesday, July 27 Public...

Technical Area 55 Entry Control System (ECS)

International Nuclear Information System (INIS)

Beaumont, A.; Brundige, E.; DesJardin, R.; Rivera, R.

1984-01-01

The exchange badge system which was used at the Plutonium Facility located in Technical Area 55 was replaced on a trial basis with an automated Entry Control System. As a result of the success of the trial system, a new system incorporating expanded features and increased reliability is being implemented. The new Entry Control System incorporates several features not previously available in relatively inexpensive entry systems. The reliability of the system is enhanced by redundant microprocessors incorporating bubble memory for nonvolatile storage of the system data base. The badge readers incorporate dual communication lines to two different controllers to further increase the total system reliability

78 FR 1198 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2013-01-08

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... to information systems equipment and technology. Wednesday, January 23 Open Session 1. Welcome and...

77 FR 37652 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2012-06-22

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... that affect the level of export controls applicable to information systems equipment and technology...

77 FR 1666 - Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2012-01-11

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems, Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... information systems equipment and technology. Wednesday, January 25 Open Session 1. Welcome and Introductions...

Interim format and content for a physical security plan for nuclear power plants

International Nuclear Information System (INIS)

1977-02-01

The document serves as interim guidance to assist the licensee or applicant in the preparation of a physical security plan. It is to be used in conjunction with interim acceptance criteria for physical security programs, which will be distributed at a later date

BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

Energy Technology Data Exchange (ETDEWEB)

Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mertyurek, Ugur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scaglione, John M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-10-01

The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is

An investigation on technical feasibilities of fuel cycle for high temperature gas-cooled reactor (Case study)

International Nuclear Information System (INIS)

Sumita, Junya; Ueta, Shohei; Aihara, Jun; Shibata, Taiju; Sawa, Kazuhiro

2008-03-01

In accordance with the basic policy of effectively using nuclear fuel resources, the FBR cycle, one of the most possible fuel cycle in the future, will be adapted after plu-thermal program by LWR in Japanese nuclear cycle plan. In this paper, a case study of technical investigation of HTGR fuel cycle based on HTGR fuel cycle proposed to adapt to Japanese nuclear fuel cycle plan were carried out from the viewpoint of effective utilization of uranium, fabrication technologies of MOX fuel, reprocessing technologies, amount of interim storage of HTGR fuel and graphite waste. As a result, the fuel cycle for HTGR is expected to be possible technically. (author)

Basis for Interim Operation for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2003-01-01

This document establishes the Basis for Interim Operation (BIO) for the Fuel Supply Shutdown Facility (FSS) as managed by the 300 Area Deactivation Project (300 ADP) organization in accordance with the requirements of the Project Hanford Management Contract procedure (PHMC) HNF-PRO-700, ''Safety Analysis and Technical Safety Requirements''. A hazard classification (Benecke 2003a) has been prepared for the facility in accordance with DOE-STD-1027-92 resulting in the assignment of Hazard Category 3 for FSS Facility buildings that store N Reactor fuel materials (303-B, 3712, and 3716). All others are designated Industrial buildings. It is concluded that the risks associated with the current and planned operational mode of the FSS Facility (uranium storage, uranium repackaging and shipment, cleanup, and transition activities, etc.) are acceptable. The potential radiological dose and toxicological consequences for a range of credible uranium storage building have been analyzed using Hanford accepted methods. Risk Class designations are summarized for representative events in Table 1.6-1. Mitigation was not considered for any event except the random fire event that exceeds predicted consequences based on existing source and combustible loading because of an inadvertent increase in combustible loading. For that event, a housekeeping program to manage transient combustibles is credited to reduce the probability. An additional administrative control is established to protect assumptions regarding source term by limiting inventories of fuel and combustible materials. Another is established to maintain the criticality safety program. Additional defense-in-depth controls are established to perform fire protection system testing, inspection, and maintenance to ensure predicted availability of those systems, and to maintain the radiological control program. It is also concluded that because an accidental nuclear criticality is not credible based on the low uranium enrichment

Taking interim actions: Integrating CERCLA and NEPA to move ahead with site cleanup

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.; Valett, G.L.; McCracken, S.H.

1991-01-01

The cleanup of contaminated sites can be expedited by using interim response actions in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, and the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). In fact, a major portion of some Superfund sites can be cleaned up using interim actions. For CERCLA sites being remediated by the US Department of Energy (DOE), such actions must also comply with the National Environmental Policy Act (NEPA) because the DOE has established a policy for integrating CERCLA and NEPA requirements. A strategy for the integrated documentation with implementation of interim actions has been applied successfully at the Weldon Spring site, and major cleanup projects are currently underway. This paper discusses some of the issues associated with integrating CERCLA and NEPA for interim actions and summarizes those actions that have been identified for the Weldon Spring site

Taking interim actions: Integrating CERCLA and NEPA to move ahead with site cleanup

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.; Valett, G.L.; McCracken, S.H.

1991-01-01

The cleanup of contaminated sites can be expedited by using interim response actions in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, and the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). In fact, a major portion of some Superfund sites can be cleaned up using interim actions. For CERCLA sites being remediated by the US Department of Energy (DOE), such actions must also comply with the National Environmental Policy Act (NEPA) because the DOE has established a policy for integrating CERCLA and NEPA requirements. A strategy for the integrated documentation and implementation of interim actions has been applied successfully at the Weldon Spring site, and major cleanup projects are currently underway. This paper discusses some of the issues associated with integrating CERCLA and NEPA for interim actions and summarizes those actions that have been identified for the Weldon Spring site

78 FR 24160 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2013-04-24

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... controls applicable to information systems equipment and technology. Tuesday, May 7 Open Session 1. Welcome...

77 FR 24178 - Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting

Science.gov (United States)

2012-04-23

... DEPARTMENT OF COMMERCE Bureau of Industry and Security Information Systems Technical Advisory Committee; Notice of Partially Closed Meeting The Information Systems Technical Advisory Committee (ISTAC... controls applicable to information systems equipment and technology. Tuesday, May 8 Open Session 1. Welcome...

Using communication norms in socio-technical systems

NARCIS (Netherlands)

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

2009-01-01

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

47 CFR 15.513 - Technical requirements for medical imaging systems.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Technical requirements for medical imaging... DEVICES Ultra-Wideband Operation § 15.513 Technical requirements for medical imaging systems. (a) The UWB... MHz and 10,600 MHz. (b) Operation under the provisions of this section is limited to medical imaging...

19 CFR 354.8 - Interim sanctions.

Science.gov (United States)

2010-04-01

... reconsider imposition of interim sanctions on the basis of new and material evidence or other good cause... Secretary may petition a presiding official to impose such sanctions. (b) The presiding official may impose... person to return material previously provided by the Department and all other materials containing the...

Interim evaluation report on research and development of automatic sewing systems; Jido hosei system no kenkyu kaihatsu chukan hyoka hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-03-01

The research and development project for automatic sewing systems is aimed at establishing the techniques necessary for developing (automatic sewing systems) which efficiently produce diversified types of products in small quantities, to cope with various requirements, e.g., diversified consumers' needs and reduced cycle periods. This project covers R and D of the sewing preparation/processing, sewing/assembling, cloth handling, and system management/control techniques. The program for developing the total systems and elementary techniques draws the conceptual designs of their functions, performance and shapes, to outline the overall R and D project. The programs for the individual elementary techniques include studies on their basic functions and performance; design works from the basic designs to determine the specifications to the detailed designs of the devices to be developed; construction of the test units on a trial basis; and function confirming tests to confirm operability of the unit components and device performance, where these works are simultaneously implemented. This paper describes the interim results of evaluation of the elements developed for the elementary techniques, summarizing the results obtained so far. It is concluded that most of the targets of the R and D themes are sufficiently achieved by the end of FY 1987, and that the project can be now advanced to the next phase, construction of the test plants. (NEDO)

Advanced Public Transportation Systems. Technical Assistance Brief 2

Science.gov (United States)

1993-01-01

The Advanced Public Transportation Systems (APTS) Program requires evaluation : of pilot projects. This technical assistance brief discusses the guidelines set : for developing evaluation framework and methodology for local projects. 4p.

Nuclear waste: Is there a need for federal interim storage

International Nuclear Information System (INIS)

1989-01-01

The Congress created the Monitored Retrievable Storage Review Commission to provide a report on the need for a Federal monitored retrievable storage facility (MRS) as part of the Nation's nuclear waste management system. The Commission concludes that the MRS as presently described in the law, which links the capacity and schedule of operation of the MRS to a permanent geologic repository, cannot be justified. The Commission finds, however, that while no single factor would favor an MRS over the No-MRS option, cumulatively the advantages of an MRS would justify the building of an MRS if: there were no linkages between the MRS and the repository; the MRS could be constructed at an early date; and the opening of the repository were delayed considerably beyond its presently scheduled date of operation. The Commission therefore recommends that the Congress take the following actions: Authorize construction of a Federal Emergency Storage facility with a capacity limit of 2,000 metric tons of uranium; Authorize construction of a User-Funded Interim Storage facility with a capacity limit of 5,000 metric tons of uranium; Reconsider the subject of interim storage by the year 2000

Integrated system of safety features for spent fuel interim storage

International Nuclear Information System (INIS)

Pantazi, Doina; Stanciu, Marcela; Mateescu, Silvia; Marin, Ion

1999-01-01

The design of the spent fuel interim storage facility (SFISF) must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility. To elaborate the safety documentation necessary for licensing, we were trying to chose the most appropriate approach related to safety features for SFISF, based on national and international regulations, standards and recommendations, as well as on the experience of other countries with similar facilities and finally, on our own experience in designing other nuclear objectives in Romania. The paper presents the issues that we consider important for the safety evaluation and are developed as a detailed diagram. The diagram contains in a logical succession the following issues: - fundamental principles of radioprotection; - fundamental safety principles of radioactive waste management; - safety objectives of SFISF; - safety criteria for SFISF; - safety requirements for SFISF; - siting criteria for SFISF; - siting requirements for SFISF. (authors)

The Commissioning of the LHC Technical Systems

CERN Document Server

Saban, R; Baggiolini, V; Ballarino, A; Barbero-Soto, E; Bellesia, B; Bordry, Frederick; Bozzini, D; Casas-Lino, M-P; Chareyre, V; Claudet, S; Coelingh, G-J; Dahlerup-Petersen, K; Denz, R; Fehér, S; Flora, R; Gruwé, M; Kain, V; Kirby, G; Koratzinos, M; Lauckner, R; Le Naour, S; Mess, K-H; Millet, F; Montabonnet, V; Nisbet, D; Perea-Solano, B; Pojer, M; Principe, R; Rabehl, R; Rijllart, A; Redaelli, S; Rodríguez-Mateos, F; Schmidt, R; Serio, L; Siemko, A; Solfaroli-Camillocci, M; Thiesen, H; Venturini, W; Vergara-Fernandez, A; Verweij, A; Zerlauth, M

2007-01-01

The LHC is an accelerator with unprecedented complexity where the energy stored in magnets and the beams exceeds other accelerators by one-to-two orders of magnitude. To ensure a safe and efficient machine start-up without being plagued by technical problems, a phase of "hardware commissioning" was introduced: a thorough commissioning of technical systems without beam. This activity started in June 2005 with the commissioning of individual systems, followed by operating a full sector, one eighth of the machine; the commissioning is expected to last until spring 2008 when commissioning with beam will start. The LHC architecture allows the commissioning of each of the eight sectors independently from the others, before the installation of other sectors is complete. An important effort went into the definition of the programme and the organization of the coordination in the field, as well as in the preparation of the tools to record and analyze test results. This paper discusses the experience with this approach...

Technical description of the Swedish natural gas distribution system

Energy Technology Data Exchange (ETDEWEB)

Nilsson, Ronny [KM Miljoeteknik AB (Sweden)

1997-06-01

This description of the Swedish distribution network has been produced to provide information for distribution companies, trade organisations, etc., who have an interest in getting a clear understanding of the technical design and standards, technical directives, etc., which have served as guidance in the development. The technical description covers the piping system from a measuring and regulating station (MR station) up to the consumer`s substation, however, only sections with a maximum operating pressure of 4 bar. By way of introduction, the description contains introductory information on supply channels, consumption patterns and the principal design of the high pressure network in Sweden 10 refs, 10 figs, 1 tab

Theory of Technical Systems--Educational Tool for Engineering

Science.gov (United States)

Eder, Wolfgang Ernst

2016-01-01

Hubka's theory of technical systems (TTS) is briefly outlined. It describes commonalities in all engineering devices, whatever their physical principles of action. This theory is based on a general transformation system (TrfS), which can be used to show engineering in the contexts of society, economics and historic developments. The life cycle of…

Interim evaluation report of the mutually operable database systems by different computers; Denshi keisanki sogo un'yo database system chukan hyoka hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-03-01

This is the interim report on evaluation of the mutually operable database systems by different computers. The techniques for these systems fall into four categories of those related to (1) dispersed data systems, (2) multimedia, (3) high reliability, and (4) elementary techniques for mutually operable network systems. The techniques for the category (1) include those for vertically dispersed databases, database systems for multiple addresses in a wide area, and open type combined database systems, which have been in progress generally as planned. Those for the category (2) include the techniques for color document inputting and information retrieval, meaning compiling, understanding highly overlapping data, and controlling data centered by drawings, which have been in progress generally as planned. Those for the category (3) include the techniques for improving resistance of the networks to obstruction, and security of the data in the networks, which have been in progress generally as planned. Those for the category (4) include the techniques for rule processing for development of protocols, protocols for mutually connecting the systems, and high-speed, high-function networks, which have been in progress generally as planned. It is expected that the original objectives are finally achieved, because the development programs for these categories have been in progress generally as planned. (NEDO)

Exploration Medical System Technical Architecture Overview

Science.gov (United States)

Cerro, J.; Rubin, D.; Mindock, J.; Middour, C.; McGuire, K.; Hanson, A.; Reilly, J.; Burba, T.; Urbina, M.

2018-01-01

The Exploration Medical Capability (ExMC) Element Systems Engineering (SE) goals include defining the technical system needed to support medical capabilities for a Mars exploration mission. A draft medical system architecture was developed based on stakeholder needs, system goals, and system behaviors, as captured in an ExMC concept of operations document and a system model. This talk will discuss a high-level view of the medical system, as part of a larger crew health and performance system, both of which will support crew during Deep Space Transport missions. Other mission components, such as the flight system, ground system, caregiver, and patient, will be discussed as aspects of the context because the medical system will have important interactions with each. Additionally, important interactions with other aspects of the crew health and performance system are anticipated, such as health & wellness, mission task performance support, and environmental protection. This talk will highlight areas in which we are working with other disciplines to understand these interactions.

An interim report on the State of Nevada socioeconomic studies

International Nuclear Information System (INIS)

1989-06-01

This Interim Report is a report on work in progress and presents findings from the research to date on the potential consequences of a repository for the citizens of Nevada. The research and findings in the Report have been subjected to rigorous peer review as part of the state's effort to insure independent, objective analysis that meets the highest professional standards. The basic research effort will continue through June 1990 and will enable the state to refine and clarify the findings presented in this Interim Report

Chat as a technically mediated social system

DEFF Research Database (Denmark)

Tække, Jesper

2008-01-01

This paper provides an analysis of chat as a technical media for communication. This is realized using the strategy for analyzing that I have called Media Sociography (Tække 2006). The Media Sociography is a synthesis of Medium Theory and the Systems Theoretical Sociology of Niklas Luhmann. The aim...

75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

Science.gov (United States)

2010-01-07

...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

Index of hazard for radioactive waste (revised). Interim technical report PR 78-10-80R

International Nuclear Information System (INIS)

Watson, S.R.

1978-06-01

This is an interim report of a study to establish a risk measure for radioactive waste repositories and to generate radiological performance objectives. The problem of regulating radioactive waste repositories is reviewed, and the difficulties associated with this activity are discussed. Risk-benefit analysis as a tool for regulation has been suggested, and its contribution is assessed. Decision analysis as a development of risk-benefit analysis is suggested as an alternative approach, in particular, employing the concept of expected utility. A utility function which describes the possible consequences of a radioactive waste repository is discussed in some detail, paying particular attention to the public concerns which must be addressable through such a function and how it is recommended to capture them. A specific utility function is developed, and its elicitation from a particular subject is described. The representation of public values in a decision-analytic approach presents some problems and these are fully discussed; recommendations are made as to appropriate methods to carry this out. The vexed question of determining an acceptable safety limit is studied and recommendations are made concerning the most suitable way to determine ''how safe is safe enough.'' Finally a brief discussion is given of how these concepts may be employed to generate radiological performance objectives

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

Energy Technology Data Exchange (ETDEWEB)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

International Nuclear Information System (INIS)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J.; Nass, R.

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

Technical study report on reprocessing system

International Nuclear Information System (INIS)

Tanaka, Hiroshi; Kasai, Yoshimitsu; Kawamura, Fumio

2000-07-01

The feasibility studies on commercialized fast breeder reactor (FBR) recycle system, in which reactor system and recycle technologies are related on consideration, are performed considering the attainable perspectives for the followings: ensuring safety, economic competitiveness to future LWRs, efficient utilization of resources, reduction of environmental burden, and enhancement of nuclear non-proliferation. In the studies of Reprocessing system of FBR, evaluation was made for the non-aqueous reprocessing of pyrochemical and fluoride volatility process and also for the aqueous reprocessing with a view to streamlining. As a result, it was estimated that each system has prospects of coming into practical use in terms of technique. In the economical efficiency assessment, it was estimated to have economic competitiveness to future LWRs. And the technical research items of each system are picked out. Hereafter, more detail design study will be performed for each system. (author)

DATA MINING METHODOLOGY FOR DETERMINING THE OPTIMAL MODEL OF COST PREDICTION IN SHIP INTERIM PRODUCT ASSEMBLY

Directory of Open Access Journals (Sweden)

Damir Kolich

2016-03-01

Full Text Available In order to accurately predict costs of the thousands of interim products that are assembled in shipyards, it is necessary to use skilled engineers to develop detailed Gantt charts for each interim product separately which takes many hours. It is helpful to develop a prediction tool to estimate the cost of interim products accurately and quickly without the need for skilled engineers. This will drive down shipyard costs and improve competitiveness. Data mining is used extensively for developing prediction models in other industries. Since ships consist of thousands of interim products, it is logical to develop a data mining methodology for a shipyard or any other manufacturing industry where interim products are produced. The methodology involves analysis of existing interim products and data collection. Pre-processing and principal component analysis is done to make the data “user-friendly” for later prediction processing and the development of both accurate and robust models. The support vector machine is demonstrated as the better model when there are a lower number of tuples. However as the number of tuples is increased to over 10000, then the artificial neural network model is recommended.

Safety Consideration for a Wet Interim Spent Fuel Store at Conceptual Design Stage

International Nuclear Information System (INIS)

Astoux, Marion

2014-01-01

EDF Energy plans to build and operate two UK EPRs at the Hinkley Point C (HPC) site in Somerset, England. Spent fuel from the UK EPRs will need to be managed from the time it is discharged from the reactor until it is ultimately disposed of and this will involve storing the spent fuel for a period in the fuel building and thereafter in a dedicated interim facility until it can be emplaced within the UK Geological Disposal Facility. EDF Energy has proposed that this interim store should be located on the Hinkley Point site which is consistent with UK policy. This Interim Spent Fuel Store (ISFS) will have the capability to store for at least one hundred years the spent fuel arising from the operation of the two EPR units (sixty years operation). Therefore, specificities regarding the lifetime of the facility have to be accounted for its design. The choice of interim storage technology was considered in some depth for the HPC project and wet storage (pool) was selected. The facility is currently at conceptual design stage, although its construction will be part of main site construction phase. Safety functions and safety requirements for this storage facility have been defined, in compliance with WENRA 'Waste and Spent Fuel Storage - Safety Reference Level Report' and IAEA Specific Safety Guide no. 15 'Storage of Spent Nuclear Fuel'. EDF technical know-how, operational feedback on existing storage pools, UK regulatory context and Fukushima experience feedback have also been accounted for. Achievement of the safety functions as passively as reasonably practicable is a key issue for the design, especially in accident situations. Regarding lifetime aspects, ageing management of equipments, optimisation of the refurbishment, climate change, passivity of the facility, and long-term achievement of the safety functions are among the subjects to consider. Adequate Operational Limits and Conditions will also have to be defined, to enable the long-term achievement of the safety

18 CFR 300.20 - Interim acceptance and review of Bonneville Power Administration rates.

Science.gov (United States)

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Interim acceptance and review of Bonneville Power Administration rates. 300.20 Section 300.20 Conservation of Power and Water... Director of the Office of Energy Market Regulation; or (ii) Deny the Administrator's interim rate request...

Fuel Supply Shutdown Facility Interim Operational Safety Requirements

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

Technical database and management system (DBMS) for the UMTRA project processing sites

International Nuclear Information System (INIS)

Hillman, R.L.; Mohr, D.E.

1985-01-01

The technical DBMS is a structured and organized method for collecting, storing, retrieving, and analyzing technical data based upon standard operating procedures and quality control measures. The automated environment created by this design exists both as a repository for processing site technical data and the analysis techniques used against this data for site characterization, evaluation, and design. The system is composed of diverse technical subjects that are collectively used to address remedial action problems associated with mill tailings disposal. These technical subjects include hydrology, geology, geochemistry, radiology, and engineering

Subsurface Interim Measures/Interim Remedial Action Plan and Decision Document for the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2)

International Nuclear Information System (INIS)

1992-01-01

The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This MIRA is to be conducted to provide information that will aid in the selection and design of final remedial actions at OU2 that will address removal of suspected free-phase volatile organic compound (VOC) contamination. The Plan involves investigating the removal of residual free-phase VOCs by in situ vacuum-enhanced vapor extraction technology at 3 suspected VOC source areas within OU2. VOC-contaminated vapors extracted from the subsurface would be treated by granular activated carbon (GAC) adsorption and discharged. The Plan also includes water table depression, when applicable at the test sites, to investigate the performance of vapor extraction technology in the saturated zone. The Plan provides for treatment of any contaminated ground water recovered during the IM/IRA at existing RFP treatment facilities. The proposed MVIRA Plan is presented in the document entitled ''Proposed Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2, '' dated 20 March 1992. Information concerning the proposed Subsurface IM/IRA was presented during a DOE Quarterly Review meeting held on 07 April 1992 and a public meeting held on 07 May 1992, at the Marriott Hotel in Golden, Colorado. The Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to date to DOE during the public comment period

Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

Energy Technology Data Exchange (ETDEWEB)

Orban, G.; Shelton, C.

2015-07-01

Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

Verification and validation interim report for portable 1,000 CFM exhauster skids POR-007/Skid E and POR-008/Skid F

International Nuclear Information System (INIS)

Nelson, O.D.

1998-01-01

This Verification and Validation (V/V) interim report summarizes to date the results of the V/V tasks performed in each of the following life cycle phases: concept, requirements, design, implementation, test, installation and checkout, and operation and maintenance. At the end of the installation and checkout phase, the V/V final report will be issued. This interim report contains or references the following for each phase: Description of V/V tasks performed; Summary of task results; Summary of anomalies and resolution; Assessment of system quality; Recommendations

Alternatives for high-level waste forms, containers, and container processing systems

International Nuclear Information System (INIS)

Crawford, T.W.

1995-01-01

This study evaluates alternatives for high-level waste forms, containers, container processing systems, and onsite interim storage. Glass waste forms considered are cullet, marbles, gems, and monolithic glass. Small and large containers configured with several combinations of overpack confinement and shield casks are evaluated for these waste forms. Onsite interim storage concepts including canister storage building, bore holes, and storage pad were configured with various glass forms and canister alternatives. All favorable options include the monolithic glass production process as the waste form. Of the favorable options the unshielded 4- and 7-canister overpack options have the greatest technical assurance associated with their design concepts due to their process packaging and storage methods. These canisters are 0.68 m and 0.54 m in diameter respectively and 4.57 m tall. Life-cycle costs are not a discriminating factor in most cases, varying typically less than 15 percent

Design of Technical Support System for Retail Company Based on Cloud

Directory of Open Access Journals (Sweden)

Shao Ping

2017-01-01

Full Text Available With the retail side of the market in China, the sale of electricity companies as a new source of power retail, they participate in the electricity market business. National and local governments subsequently introduced the corresponding policies and rules, the technical support system becomes one of the necessary conditions for the access of the retail company. Retail electricity companies have started the system construction, but has not yet formed a standardized, complete architecture. This paper analyzes the business and data interaction requirements of retail electricity companies, and then designs the functional architecture based on basic application, advanced application and value-added application, and the technical architecture based on “cloud”. On this basis, the paper discusses the selection of private cloud, public cloud and mixed cloud model, and the rationalization suggestion of system construction. Which can provide reference for the construction of the technical support system of the domestic retail enterprises.

On-site interim storage of spent nuclear fuel: Emerging public issues

International Nuclear Information System (INIS)

Feldman, D.L.; Tennessee Univ., Knoxville, TN

1992-01-01

Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

Development of interim test methods and procedures for determining the performance of small photovoltaic systems

Energy Technology Data Exchange (ETDEWEB)

McNutt, P.; Kroposki, B.; Hansen, R.; Algra, K.; DeBlasio, R. [National Renewable Energy Lab., Golden, CO (United States)

1998-09-01

The National Renewable Energy Laboratory (NREL) is developing tests and procedures that will determine if the configuration of a small photovoltaic (PV) system is suitable for its intended use, and if the system will perform as specified. An overview of these procedures is presented in this paper. Development of standard test procedures will allow designers, manufacturers, system integrators, users, and independent laboratories to assess the performance of PV systems under outdoor prevailing conditions. An NREL Technical Report detailing the procedures is under way, and the IEEE Standards Coordinating Committee 21 (SCC21) has established a project on this subject. The work will be submitted to the IEEE SCC21 and International Electrotechnical Commission Technical Committee 82 (IEC TC82) for consideration as a consensus standard. Certification bodies such as PowerMark and PV Global Approval Program (PVGAP) may adopt the IEC and IEEE documents when testing systems. Developing standardized test methods and procedures at NREL to evaluate the outdoor performance of PV systems will encourage product quality and promote PV standards development. Standardized tests will assure people that PV systems will perform as specified for their intended applications. As confidence in PV systems increases, the successful commercialization of PV will grow internationally.

Applicability of Socio-Technical Model (STM in Working System of Modern Organizations

Directory of Open Access Journals (Sweden)

Rosmaini Tasmin

2011-10-01

Full Text Available Knowledge has been identified as one of the most important resources in organization that contributes to competitive advantages. Organizations around the world realize and put into practice an approach that bases on technological and sociological aspects to fill-up the gaps in their workplaces. The Socio-Technical Model (STM is an established organizational model introduced by Trist since 1960s at Tavistock Institute, London. It relates two most common components exist in all organizations, namely social systems (human and technological systems (information technology, machinery and equipment in organizations over many decades. This paper reviews the socio-technical model from various perspectives of its developmental stages and ideas written by researchers. Therefore, several literature reviews on socio-technical model have been compiled and discussed to justify whether its basic argument matches with required practices in Techno-Social environments. Through a socio-technical perspective on Knowledge Management, this paper highlights the interplay between social systems and technological system. It also suggests that management and leadership play critical roles in establishing the techno-social perspective for the effective assimilation of Knowledge Management practices.

Environmental assessment for 881 Hillside (High Priority Sites) interim remedial action

International Nuclear Information System (INIS)

1990-01-01

This Environmental Assessment evaluates the impact of an interim remedial action proposed for the High Priority Sites (881 Hillside Area) at the Rocky Flats Plant (RFP). This interim action is to be conducted to minimize the release of hazardous substances from the 881 Hillside Area that pose a potential long-term threat to public health and the environment. This document integrates current site characterization data and environmental analyses required by the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) or ''Superfund'' process, into an environmental assessment pursuant to the National Environmental Policy Act (NEPA). Characterization of the 881 Hillside Area is continuing. Consequently, a final remedial action has not yet been proposed. Environmental impacts associated with the proposed interim remedial action and reasonable alternatives designed to remove organic and inorganic contaminants, including radionuclides, from alluvial groundwater in the 881 Hillside Area are addressed. 24 refs., 5 figs., 23 tabs

Transitioning aluminum clad spent fuels from wet to interim dry storage

International Nuclear Information System (INIS)

Louthan, M.R. Jr.; Iyer, N.C.; Sindelar, R.L.; Peacock, H.B. Jr.

1994-01-01

The United States Department of Energy (DOE) currently owns several hundred metric tons of aluminum clad, spent nuclear fuel and target assemblies. The vast majority of these irradiated assemblies are currently stored in water basins that were designed and operated for short term fuel cooling prior to fuel reprocessing. Recent DOE decisions to severely limit the reprocessing option have significantly lengthened the time of storage, thus increasing the tendency for corrosion induced degradation of the fuel cladding and the underlying core material. The portent of continued corrosion, coupled with the age of existing wet storage facilities and the cost of continuing basin operations, including necessary upgrades to meet current facility standards, may force the DOE to transition these wet stored, aluminum clad spent fuels to interim dry storage. The facilities for interim dry storage have not been developed, partially because fuel storage requirements and specifications for acceptable fuel forms are lacking. In spite of the lack of both facilities and specifications, current plans are to dry store fuels for approximately 40 to 60 years or until firm decisions are developed for final fuel disposition. The transition of the aluminum clad fuels from wet to interim dry storage will require a sequence of drying and canning operations which will include selected fuel preparations such as vacuum drying and conditioning of the storage atmosphere. Laboratory experiments and review of the available literature have demonstrated that successful interim dry storage may also require the use of fuel and canister cleaning or rinsing techniques that preclude, or at least minimize, the potential for the accumulation of chloride and other potentially deleterious ions in the dry storage environment. This paper summarizes an evaluation of the impact of fuel transitioning techniques on the potential for corrosion induced degradation of fuel forms during interim dry storage

A process of spent nuclear fuel treatment with the interim storage of TRU by use amidic extractants

International Nuclear Information System (INIS)

Tachimori, Shoichi; Suzuki, Shinichi; Sasaki, Yuji

2001-01-01

A new chemical process, ARTIST process, is proposed for the treatment of spent nuclear fuel. The main concept of the ARTIST process is to recover and stock separately all actinides, uranium and a mixture of transuranics, and to dispose fission products. The process composed of two main steps, a uranium exclusive isolation and a total recovery of transuranium elements (TRU); which copes with the nuclear non-proliferation measures, and additional processes. Both actinide products are solidified by calcination and allowed to the interim storage for future utilization. These separations are achieved by use of amidic extractants in accord with the CHON principle. The technical feasibility of the ARTIST process was explained by the experimental results of both the branched-alkyl monoamides in extracting uranium and suppressing the extraction of tetravalent actinides due to the steric effect and the diglycolic amide in thorough extraction of all TRU by tridentate coordination. When these TRU are requested to put into reactors, LWR or FBR, for power generation or the Accelerator-Driven System (ADS) for transmutation, lanthanides are to be removed from TRU by utilizing a soft nitrogen donor ligand. (author)

Emulytics for Cyber-Enabled Physical Attack Scenarios: Interim LDRD Report of Year One Results.

Energy Technology Data Exchange (ETDEWEB)

Clem, John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Urias, Vincent [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Atkins, William Dee [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Symonds, Christopher J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-12-08

Sandia National Laboratories has funded the research and development of a new capability to interactively explore the effects of cyber exploits on the performance of physical protection systems. This informal, interim report of progress summarizes the project’s basis and year one (of two) accomplishments. It includes descriptions of confirmed cyber exploits against a representative testbed protection system and details the development of an emulytics capability to support live, virtual, and constructive experiments. This work will support stakeholders to better engineer, operate, and maintain reliable protection systems.

Experimental results obtained with the simulated cold moderator system. System characteristics and technical issues

CERN Document Server

Aso, T; Hino, R; Kaminaga, M; Kinoshita, H; Takahashi, T

2002-01-01

The Japan Atomic Energy Research Institute and the High Energy Accelerator Research Organization have been developing a Mega-Watt scale spallation target system. In the system, neutrons generated in a target are sorted out their energy to the proper values in liquid-hydrogen moderators. Then, the liquid-hydrogen is forced to circulate in order to suppress hydrogen temperature increase. In the operation of moderators, it is very important to establish a safety protection system against emergency shutdown of the accelerator or accidents of the cold moderator system. In order to obtain a technical data for design and safety review of the liquid-hydrogen system, we have fabricated an experimental apparatus simulated the cold moderator system using liquid nitrogen (max. 1.5 MPa, mini. 77 K) instead of liquid hydrogen. The experiments on a controllability of the system were carried out to investigate dynamic characteristics of the system. This report presents the experimental results and technical issues for the co...

Technical Meeting on Grading of the Application of Management System Requirements. Presentations

International Nuclear Information System (INIS)

2012-01-01

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

Administrative Court Stade, decision of March 22, 1985 (interim storage facility at Gorleben)

International Nuclear Information System (INIS)

Anon.

1985-01-01

This decision deals with the planned interim storage facility of Gorleben (F.R.G.). The provisions introduced by the 4th ammendment to sec. 5 para. 6 and 9a to 9c of the German Atomic Energy Act might contain a definite regulation of the 'Entsorgung' of nuclear power stations. Sec. 6 of the Atomic Energy Act is not applicable to interim storage facilities because irradiated nuclear fuel has a double nature: It is spent fuel and nuclear waste as well. Considering current licensing procedures of construction and operation of nuclear installations in the field of 'Entsorgung', special legal regulations for the construction and operation of an interim storage facility have to be required. (CW)

Interim storage study report

Energy Technology Data Exchange (ETDEWEB)

Rawlins, J.K.

1998-02-01

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

FRAM Modelling Complex Socio-technical Systems

CERN Document Server

Hollnagel, Erik

2012-01-01

There has not yet been a comprehensive method that goes behind 'human error' and beyond the failure concept, and various complicated accidents have accentuated the need for it. The Functional Resonance Analysis Method (FRAM) fulfils that need. This book presents a detailed and tested method that can be used to model how complex and dynamic socio-technical systems work, and understand both why things sometimes go wrong but also why they normally succeed.

Interim report on the Global Design Effort Global International Linear Collider (ILC) R&D

Energy Technology Data Exchange (ETDEWEB)

Harrison, M.

2011-04-30

The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R&D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

Comparative risk assessments for the production and interim storage of glass and ceramic waste forms: defense waste processing facility

International Nuclear Information System (INIS)

Huang, J.C.; Wright, W.V.

1982-04-01

The Defense Waste Processing Facility (DWPF) for immobilizing nuclear high level waste (HLW) is scheduled to be built at the Savannah River Plant (SRP). High level waste is produced when SRP reactor components are subjected to chemical separation operations. Two candidates for immobilizing this HLW are borosilicate glass and crystalline ceramic, either being contained in weld-sealed stainless steel canisters. A number of technical analyses are being conducted to support a selection between these two waste forms. The present document compares the risks associated with the manufacture and interim storage of these two forms in the DWPF. Process information used in the risk analysis was taken primarily from a DWPF processibility analysis. The DWPF environmental analysis provided much of the necessary environmental information. To perform the comparative risk assessments, consequences of the postulated accidents are calculated in terms of: (1) the maximum dose to an off-site individual; and (2) the dose to off-site population within 80 kilometers of the DWPF, both taken in terms of the 50-year inhalation dose commitment. The consequences are then multiplied by the estimated accident probabilities to obtain the risks. The analyses indicate that the maximum exposure risk to an individual resulting from the accidents postulated for both the production and interim storage of either waste form represents only an insignificant fraction of the natural background radiation of about 90 mrem per year per person in the local area. They also show that there is no disaster potential to the off-site population. Therefore, the risks from abnormal events in the production and the interim storage of the DWPF waste forms should not be considered as a dominant factor in the selection of the final waste form

Agenda 21 interim balance, 1997

Energy Technology Data Exchange (ETDEWEB)

Van Vuuren, D.P.; Bakkes, J.A.

1997-10-01

Five years after the `United Nations Conference on Environment and Development (UNCED)`, an interim balance was drawn up to see what was done to meet the ambitious challenges adopted in Agenda 21 during this conference. Such a balance is presented in this report and the complementary brochure, `Developments in Sustainability 1992-1997`, reflecting societal developments and changes in environmental quality, as well as changes in responses to environmental concerns. 24 figs., 12 tabs., 68 refs.

Data Analysis of GPM Constellation Satellites-IMERG and ERA-Interim precipitation products over West of Iran

Science.gov (United States)

Sharifi, Ehsan; Steinacker, Reinhold; Saghafian, Bahram

2016-04-01

Precipitation is a critical component of the Earth's hydrological cycle. The primary requirement in precipitation measurement is to know where and how much precipitation is falling at any given time. Especially in data sparse regions with insufficient radar coverage, satellite information can provide a spatial and temporal context. Nonetheless, evaluation of satellite precipitation is essential prior to operational use. This is why many previous studies are devoted to the validation of satellite estimation. Accurate quantitative precipitation estimation over mountainous basins is of great importance because of their susceptibility to hazards. In situ observations over mountainous areas are mostly limited, but currently available satellite precipitation products can potentially provide the precipitation estimation needed for meteorological and hydrological applications. One of the newest and blended methods that use multi-satellites and multi-sensors has been developed for estimating global precipitation. The considered data set known as Integrated Multi-satellitE Retrievals (IMERG) for GPM (Global Precipitation Measurement) is routinely produced by the GPM constellation satellites. Moreover, recent efforts have been put into the improvement of the precipitation products derived from reanalysis systems, which has led to significant progress. One of the best and a worldwide used model is developed by the European Centre for Medium Range Weather Forecasts (ECMWF). They have produced global reanalysis daily precipitation, known as ERA-Interim. This study has evaluated one year of precipitation data from the GPM-IMERG and ERA-Interim reanalysis daily time series over West of Iran. IMERG and ERA-Interim yield underestimate the observed values while IMERG underestimated slightly and performed better when precipitation is greater than 10mm. Furthermore, with respect to evaluation of probability of detection (POD), threat score (TS), false alarm ratio (FAR) and probability

REQUIREMENT VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM

Science.gov (United States)

2017-09-01

VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM by Theresa L. Thomas September... ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM 5. FUNDING NUMBERS 6. AUTHOR(S) Theresa L. Thomas 7...CODE 13. ABSTRACT (maximum 200 words) The Naval Air Systems Command (NAVAIR) systems engineering technical review (SETR) process does not

Caustic-Side Solvent-Extraction Modeling for Hanford Interim Pretreatment System

International Nuclear Information System (INIS)

Moyer, B.A.; Birdwell, J.F.; Delmau, L. H.; McFarlane, J.

2008-01-01

The purpose of this work is to examine the applicability of the Caustic-Side Solvent Extraction (CSSX) process for the removal of cesium from Hanford tank-waste supernatant solutions in support of the Hanford Interim Pretreatment System (IPS). The Hanford waste types are more challenging than those at the Savannah River Site (SRS) in that they contain significantly higher levels of potassium, the chief competing ion in the extraction of cesium. It was confirmed by use of the CSSX model that the higher levels of potassium depress the cesium distribution ratio (DCs), as validated by measurement of DCs values for four of eight specified Hanford waste-simulant compositions. The model predictions were good to an apparent standard error of ±11%. It is concluded from batch distribution experiments, physical-property measurements, equilibrium modeling, flowsheet calculations, and contactor sizing that the CSSX process as currently employed for cesium removal from alkaline salt waste at the SRS is capable of treating similar Hanford tank feeds. For the most challenging waste composition, 41 stages would be required to provide a cesium decontamination factor (DF) of 5000 and a concentration factor (CF) of 5. Commercial contacting equipment with rotor diameters of 10 in. for extraction and 5 in. for stripping should have the capacity to meet throughput requirements, but testing will be required to confirm that the needed efficiency and hydraulic performance are actually obtainable. Markedly improved flowsheet performance was calculated for a new solvent formulation employing the more soluble cesium extractant BEHBCalixC6 used with alternative scrub and strip solutions, respectively 0.1 M NaOH and 10 mM boric acid. The improved system can meet minimum requirements (DF = 5000 and CF = 5) with 17 stages or more ambitious goals (DF = 40,000 and CF = 15) with 19 stages. Potential benefits of further research and development are identified that would lead to reduced costs, greater

Experiences with a technically oriented plant management system; Erfahrungen mit einem technisch orientierten Betriebs-Management-System

Energy Technology Data Exchange (ETDEWEB)

Haffmann, E. [GiS Gesellschaft fuer integrierte Systemplanung mbH, Erlangen (Germany)

2000-07-01

This contribution first deals with the duality of mercantile and technical plant management systems. The following aspects are considered: reasons for and history of this duality; different approaches taken by mercantile and technical plant management systems; differences in the standardisability of mercantile and technical tasks. Dissolution of the duality through coordinated interplay. The author then goes on to explain the most important components of technically oriented maintenance management. These include the collection of technical plant data (with maintenance-relevant data and relations); the establishment of recurring tasks, the commissioning method (involving occupational safety, packaging and evaluation), compilation of manuals, reporting and accompanying plant documentation. The following tools are useful for DP-assisted maintenance: depiction of organisational and operational structures (authorisation system + IBFS application); workflow systems; modelling (data and object models); navigators; form and dialogue generators; integration of external software (project planning, CAD and Office); interface to mercantile systems. Some highlights of the C/S-IBFS were demonstrated in practice at the symposium. [German] Das Referat behandelt zunaechst die Dualitaet von kaufmaennischen und technischen Betriebs-Management-Systemen anhand folgender Aspekte: - Gruende und Historie dieser Dualitaet, - unterschiedliche Loesungsansaetze von kaufmaennischen und technischen Betriebs-Management-Systemen, - unterschiedliche Standardisierbarkeit von kaufmaennischen und technischen Aufgabenstellungen, - Aufloesung der Dualitaet durch koordniertes Zusammenwirken. Sodann werden wichtige Bausteine eines technisch orientierten Instandhaltungs-Managements erlaeutert. Dazu gehoeren die technische Anlagenerfassung (mit instandhaltungsrelevanten Daten und Relationen), die Einrichtung wiederkehrender Aufgaben, das Arbeitsauftragsverfahren (mit Arbeitssicherheit, Paketierung und

THE IMPORTANCE OF FINANCIAL INTERIM REPORTING FOR THE POSITION OF COMPANIES

Directory of Open Access Journals (Sweden)

Claudia‐Elena\tGRIGORAȘ‐ICHIM

2015-12-01

Full Text Available The importance that each company must grant to the strategic sources of information generates our concern for analysis of the interim financial reporting. In every enterprise, there are doubts on the usefulness of interim financial reports, given the following elements: the necessary time for their preparation (relatively long, their restricted character and the resources necessary to establish them. Finding a common solution to these problems and, implicitly, increasing the interest for interim financial reporting, can help to increase the economic performance of the company, either by reducing the unnecessary costs related to time, or by increasing communication and transparency with third parties. An appropriate management can act early in the direction of counteracting the negative effects in their company or prevention of any commercial or production failures, the overall economic trends in that field and increasing productivity. Starting from these premises, we propose a research in order to capture the main aspects related to the mentioned issues.

The influence of system interactivity and technical support on learning management system utilization

Directory of Open Access Journals (Sweden)

Sousan Baleghi-Zadeh

2017-03-01

Full Text Available In recent years, there has been a growing increase in using Learning Management System (LMS by universities. However, its utilization by students is limited in Malaysia. The main purpose of the present study is to develop and test a model that predicts LMS utilization by Malaysian higher education students. Based on the Technology Acceptance Model, the study investigated the relationships among six constructs (system interactivity, technical support, perceived ease of use, perceived usefulness, behavioral intention to use and LMS use through structural equation modelling. The participants were 216 undergraduate students from a local university in Malaysia. The result of the study revealed that system interactivity had a significant effect on perceived usefulness, but not on perceived ease of use; technical support had a significant effect on perceived ease of use, but not on perceived usefulness.

The training system for technical personnel of producers

International Nuclear Information System (INIS)

Kleiner, E.

1980-01-01

The training system of BBC Mannheim for technical personnel is divided in different activities, according to the different target groups and tenors. Different departments take care of this activities, which supply one another. Problem, training activities and methods are described. (orig.) [de

Experimental results obtained with the simulated cold moderator system. System characteristics and technical issues

Energy Technology Data Exchange (ETDEWEB)

Aso, Tomokazu; Kaminaga, Masanori; Haga, Katsuhiro; Kinoshita, Hidetaka; Takahashi, Toshio; Hino, Ryutaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-12-01

The Japan Atomic Energy Research Institute and the High Energy Accelerator Research Organization have been developing a Mega-Watt scale spallation target system. In the system, neutrons generated in a target are sorted out their energy to the proper values in liquid-hydrogen moderators. Then, the liquid-hydrogen is forced to circulate in order to suppress hydrogen temperature increase. In the operation of moderators, it is very important to establish a safety protection system against emergency shutdown of the accelerator or accidents of the cold moderator system. In order to obtain a technical data for design and safety review of the liquid-hydrogen system, we have fabricated an experimental apparatus simulated the cold moderator system using liquid nitrogen (max. 1.5 MPa, mini. 77 K) instead of liquid hydrogen. The experiments on a controllability of the system were carried out to investigate dynamic characteristics of the system. This report presents the experimental results and technical issues for the construction of a practical liquid-hydrogen moderator system of the Mega-Watt scale target system. (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)

Interim data report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Vahlund, Fredrik; Andersson, Johan

2004-08-01

This document is the interim data report in the project SR-Can. The purpose of the data report is to present input data, with uncertainty estimates, for the SR-Can assessment calculations. Besides input data, the report also describes the standardised procedures used when deriving the input data and the corresponding uncertainty estimates. However, in the present interim version of the report (written in the initial stage of the project when site characterisation has yet not been completed) the standardised procedures have not been possible to apply for most of the data and, in order to present a compilation of the data used in the assessment, much of the input data is presented without following the standardised procedures. This will however be changed for the final version of the SR-Can data report, in order to show the methodology that will be used in the final version one example of how input data will be presented is included (migration data for buffer) . The recommended input data for the assessment calculations are, for the interim version, mainly based on SR 97 Beberg data, these are merely presented without any background or uncertainty discussion (this is presented in the SR 97 data report)

Interim Storage Facility decommissioning. Final report

International Nuclear Information System (INIS)

Johnson, R.P.; Speed, D.L.

1985-01-01

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

14 CFR 136.41 - Interim operating authority.

Science.gov (United States)

2010-01-01

... AND NATIONAL PARKS AIR TOUR MANAGEMENT National Parks Air Tour Management § 136.41 Interim operating... terminate 180 days after the date on which an air tour management plan is established for the park and tribal lands; (6) Shall promote protection of national park resources, visitor experiences, and tribal...

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

International Nuclear Information System (INIS)

1976-05-01

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives

Comparisons of Cooperative and Non-Cooperative Students: An Analysis of Student Accounting System Data. Interim Report, June, 1981.

Science.gov (United States)

Frazier, Don

The major purpose of this study was to identify unique effects of cooperative vocational education. This interim report is of results of the analyses of existing data bases. Comparisons of cooperative and non-cooperative vocational programs are made on the following variables: enrollments by age, sex and race, school status, work status,…

DOUBLE TRACKS Test Site interim corrective action plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

The DOUBLE TRACKS site is located on Range 71 north of the Nellis Air Force Range, northwest of the Nevada Test Site (NTS). DOUBLE TRACKS was the first of four experiments that constituted Operation ROLLER COASTER. On May 15, 1963, weapons-grade plutonium and depleted uranium were dispersed using 54 kilograms of trinitrotoluene (TNT) explosive. The explosion occurred in the open, 0.3 m above the steel plate. No fission yield was detected from the test, and the total amount of plutonium deposited on the ground surface was estimated to be between 980 and 1,600 grams. The test device was composed primarily of uranium-238 and plutonium-239. The mass ratio of uranium to plutonium was 4.35. The objective of the corrective action is to reduce the potential risk to human health and the environment and to demonstrate technically viable and cost-effective excavation, transportation, and disposal. To achieve these objectives, Bechtel Nevada (BN) will remove soil with a total transuranic activity greater then 200 pCI/g, containerize the soil in ``supersacks,`` transport the filled ``supersacks`` to the NTS, and dispose of them in the Area 3 Radioactive Waste Management Site. During this interim corrective action, BN will also conduct a limited demonstration of an alternative method for excavation of radioactive near-surface soil contamination.

Model-Driven Information Security Risk Assessment of Socio-Technical Systems

NARCIS (Netherlands)

Ionita, Dan

2018-01-01

As more aspects of life transition to the digital domain, computer systems become increasingly complex but also more social. But assessing a socio-technical system is no trivial task: it often requires intimate knowledge of the system, awareness of the social dynamics and trust relationships of its

Rosiglitazone evaluated for cardiovascular outcomes--an interim analysis

DEFF Research Database (Denmark)

Home, Philip D; Pocock, Stuart J; Beck-Nielsen, Henning

2007-01-01

BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open...... group). The primary end point was hospitalization or death from cardiovascular causes. RESULTS: Because the mean follow-up was only 3.75 years, our interim analysis had limited statistical power to detect treatment differences. A total of 217 patients in the rosiglitazone group and 202 patients...... in the control group had the adjudicated primary end point (hazard ratio, 1.08; 95% confidence interval [CI], 0.89 to 1.31). After the inclusion of end points pending adjudication, the hazard ratio was 1.11 (95% CI, 0.93 to 1.32). There were no statistically significant differences between the rosiglitazone...

Poor predictive value of positive interim FDG-PET/CT in primary mediastinal large B-cell lymphoma

Energy Technology Data Exchange (ETDEWEB)

Lazarovici, Julien; Petrovanu, Cynthia; Danu, Alina; Ferme, Christophe; Ribrag, Vincent; Ghez, David [Gustave Roussy, Villejuif (France). Dept. of Hematology; Paris Saclay Univ., Saint-Aubin (France); Terroir, Marie [Gustave Roussy, Villejuif (France). Dept. of Nuclear Medicine and Endocrine Oncology; Paris Saclay Univ., Saint-Aubin (France); Arfi-Rouche, Julia [Gustave Roussy, Villejuif (France). Dept. of Radiology; Paris Saclay Univ., Saint-Aubin (France); Michot, Jean-Marie [Gustave Roussy, Villejuif (France). Dept. of Drug Development (DITEP); Paris Saclay Univ., Saint-Aubin (France); Mussot, Sacha; Florea, Valentina [Marie Lannelongue Hospital, Le Plessis Robinson (France). Dept. of Thoracic Surgery; Ghigna, Maria-Rosa [Marie Lannelongue Hospital, Le Plessis Robinson (France). Dept. of Pathology; Dartigues, Peggy [Gustave Roussy, Villejuif (France). Dept. of Pathology; Paris Saclay Univ., Saint-Aubin (France)

2017-11-15

Though commonly used to assess response to therapy, the prognostic value of interim FDG-PET/CT in Primary Mediastinal Large B-cell Lymphoma (PMBCL) is unclear. We conducted a retrospective study on 36 consecutive patients treated at our institution for a PMBCL between 2006 and 2014. All patients with a positive interim FDG-PET/CT had undergone histological restaging consisting either in a surgical debulking of the residual lesion (15 patients) or a CT-guided core needle biopsy (two patients). All FDG-PET/CT were secondarily reviewed according to the more recent Deauville criteria. Interim FDG-PET/CT was considered positive in 17/36 patients using visual evaluation. Among these patients, 14 had a Deauville score of 4. Histological restaging was negative in all but one case, showing inflammation and/or fibrosis. After a median follow-up of 48.5 months, a total of five patients have relapsed, two patients in the positive FDG-PET/CT group, and three patients in the negative FDG-PET/CT group, respectively. These data indicate that a positive interim FDG-PET/CT does not reflect persistence of active disease in the vast majority of PMBCL cases. The relapse rate appears similar regardless of interim FDG-PET/CT results and interpretation criteria. This suggests that interim FDG-PET/CT has a poor positive predictive value, thus kt should be used with caution in PMBCL. (orig.)

On sustainability assessment of technical systems. Experience from systems analysis with the ORWARE and Ecoeffect tools

Energy Technology Data Exchange (ETDEWEB)

Assefa, Getachew [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Chemical Engineering

2006-06-15

Engineering research and development work is undergoing a reorientation from focusing on specific parts of different systems to a broader perspective of systems level, albeit at a slower pace. This reorientation should be further developed and enhanced with the aim of organizing and structuring our technical systems in meeting sustainability requirements in face of global ecological threats that have far-reaching social and economic implications, which can no longer be captured using conventional approach of research. Until a list of universally acceptable, clear, and measurable indicators of sustainable development is developed, the work with sustainability metrics should continue to evolve as a relative measure of ecological, economic, and social performance of human activities in general, and technical systems in particular. This work can be done by comparing the relative performance of alternative technologies of providing the same well-defined function or service; or by characterizing technologies that enjoy different levels of societal priorities using relevant performance indicators. In both cases, concepts and methods of industrial ecology play a vital role. This thesis is about the development and application of a systematic approach for the assessment of the performance of technical systems from the perspective of systems analysis, sustainability, sustainability assessment, and industrial ecology. The systematic approach developed and characterized in this thesis advocates for a simultaneous assessment of the ecological, economic, and social dimensions of performance of technologies in avoiding sub-optimization and problem shifting between dimensions. It gives a holistic picture by taking a life cycle perspective of all important aspects. The systematic assessment of technical systems provides an even-handed assessment resulting in a cumulative knowledge. A modular structure of the approach makes it flexible enough in terms of comparing a number of

Interim report on evaluation of research and development of manganese nodule exploitation system; Mangan dankai saiko system no kenkyu kaihatsu chukan hyoka hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-03-01

This research and development project is aimed at development of the techniques which allow exploitation of manganese nodules occurring on deep sea bottoms (4,000 to 6,000 m deep) on a commercial scale, in order to secure stable supply of the non-ferrous metallic resource and improve general ocean development techniques. This project, established by the national project system, has been implemented cooperatively by the government, academic and industrial circles since 1981. Described herein are the interim results, summarized in the FY 1985. The targets of the phase for developing the individual techniques were set to develop the exploitation system design procedures, and to advance to the next phase by the end of FY 1985, where the consistent, integrated system is to be constructed and tested. The results obtained so far are satisfactory as a whole, both in the elementary techniques and their consistency. The simulations have been conducted, where various conditions are inputted to estimate the movement and exploitation characteristics of the system as a whole in the comprehensive ocean tests. It has been found that the nodule-collecting machine shows nonlinear tracking characteristics (i.e., movement different from that of the exploitation ship), and unsteady movements (i.e., repeated movements of rapid starting and stopping). (NEDO)

Technical and economic viability of automated highway systems : preliminary analysis

Science.gov (United States)

1997-01-01

Technical and economic investigations of automated highway systems (AHS) are addressed. It has generally been accepted that such systems show potential to alleviate urban traffic congestion, so most of the AHS research has been focused instead on tec...

110 kV NETWORK TECHNICAL LOSSES ASSESSMENT. REAL DISTRIBUTION SYSTEM CASE STUDY

Directory of Open Access Journals (Sweden)

BARBULESCU C.

2015-06-01

Full Text Available The paper is focusing on evaluating the technical losses within a real distribution network. The study was conducted for a distribution system operator within the Romanian Power System. The analysed area is represented by a real part of the Romanian Power System. It is modelled in a computer aided power system analysis tool. Several power system operating conditions are analysed. Power system optimization measures are provided having as a goal to reduce the technical losses' value. Values obtained based on the field measurement are compared to the ones provided by computer simulations. These conclusions are very useful for the distribution network operator.

Development of a Behavioural Marker System for Rating Cadet’s Non-Technical Skills

Directory of Open Access Journals (Sweden)

Victor Fernando PlÁcido da ConceiçÌo

2017-06-01

Full Text Available Despite the adoption of crew resource management training for bridge teams over the last decades, the training is still heavily focussed on technical achievements. In an educational context, the situation is more problematical, since with requirement of developing the technical skills, there is a need to build and evaluate the non-technical skills of cadets with little experience in bridge team management. In parallel with the application of team leadership models, the Portuguese Naval Academy conducted a research to improve the development and assessment of non-technical skills in bridge simulators. This paper describes the method used to identify the key non-technical skills required for naval cadets and to develop a behavioural marker system for their measurement. A literature review of behavioural marker systems was supplemented with an analysis of interviews conducted with students and simulator instructors. Additionally, further analysis of Portuguese Navy accidents reports was made, applying the HFACS framework to identify the relevant non-technical skills involved in the accidents. The resulting rating system covers five skill categories (leadership, situational awareness, communication, team work and decision making, each one with three rating elements. The framework is currently under evaluation tests in bridge simulators sessions, within an educational context.

78 FR 59726 - Interim Final Appendix D of OMB Circular No. A-123, “Management's Responsibility for Internal...

Science.gov (United States)

2013-09-27

... Management Systems'' September 27, 2013. ACTION: Notice. SUMMARY: OMB Circular No. A-123, ``Management's Responsibility for Internal Control,'' defines management's responsibility for internal control in Federal... OFFICE OF MANAGEMENT AND BUDGET Interim Final Appendix D of OMB Circular No. A-123, ``Management's...

75 FR 13484 - Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA...

Science.gov (United States)

2010-03-22

... DEPARTMENT OF COMMERCE [Docket T-1-2010] Foreign-Trade Zones Board Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA, Inc. (Cell Phones); Notice of.../ interim manufacturing (T/IM) authority, on behalf of LG Electronics Mobilecomm USA, Inc. (LGEMU), to...

Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

International Nuclear Information System (INIS)

Bradley, J.

2002-01-01

The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

Interim storage packagings for spent fuels : how to optimize an universal design to local needs

International Nuclear Information System (INIS)

Konirsch, O.; Kawabata, T.; Hunter, I.

2003-01-01

For the last ten years, the interim storage market for spent fuels issued from Nuclear Power Plants has significantly increased all over the world: there are presently many storage projects either in Asia, in North America and in Europe. Even if there is no international regulation on that field, there is a big concern from all the nuclear industry to try to harmonise the specification for the definition of the Interim Storage Systems. One example of this harmonisation is the common and general wish to develop systems, which allow to be easily transportable either to a final repository or to a reprocessing plant. As this destination is generally not yet known, the storage system should be able to be transported all over the world. On the other hand, the specific requirement for the storage facility and its associated equipment are subject to local and/or national regulation. COGEMA LOGISTICS Group has developed two different technologies which are compatible with this principle of harmonisation: dual purpose metallic cask represented by the TN24 family and the concrete storage system NUHOMS(R). For both technologies, basic designs can be adapted to the local needs in term of performance and of national regulation. To cover all the world, COGEMA LOGISTICS Group has its own subsidiaries, in Asia, in North America and in Europe with their own autonomous engineers teams for designing, licensing, manufacturing and delivering the transport/storage products. COGEMA LOGISTICS Group is presently the leader on the dry interim storage market. The purpose of the present paper is to show how it is possible to optimise a basic existing design of a dual purpose metallic cask for a local need of storage. Taking into account the national rules for storage and the international regulation for transport, the designer shall minimise the development cost for a completely new design and maximise the capacity of the packaging regarding the allowable limits in the Nuclear Power Plant, in

340 waste handling facility interim safety basis

Energy Technology Data Exchange (ETDEWEB)

VAIL, T.S.

1999-04-01

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

340 waste handling facility interim safety basis

International Nuclear Information System (INIS)

VAIL, T.S.

1999-01-01

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

International Nuclear Information System (INIS)

Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

1985-07-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

Estimation of regulated term of technical systems further operation

International Nuclear Information System (INIS)

Strel'nikov, V.P.

2008-01-01

The technique of estimating the regulated term of technical systems further operation on the basis of data on failures during operation and use of probabilistic-physical model of failures (DN-distribution) is proposed

Reliability of Dubbed Technical Systems with Built-In Control Device

Directory of Open Access Journals (Sweden)

V. A. Аnischenko

2013-01-01

Full Text Available The paper substantiates a selection of passive or active system for dubbing technical systems in accordance with characteristics pertaining to probability of no-failure operation and mean–time-between failures with due account of non-reliability of a built-in control device and systems complexity. 

National climate change action plans: Interim report for developing and transition countries

Energy Technology Data Exchange (ETDEWEB)

Benioff, R.; Ness, E.; Hirst, J. [eds.

1997-10-01

Under its Support for National Action Plans (SNAP) initiative, the U.S. Country Studies Program is providing financial and technical assistance to 18 countries for the development of climate change action plans. Although most of the countries have not yet completed their plans, the important lessons learned thus far are valuable and should be shared with other countries and international institutions that have an interest in the process of action plan development. This interim report describes the experience of 11 countries that are the furthest along in their planning activity and who have offered to share their results to date with the larger community of interested nations. These action plans delineate specific mitigation and adaptation measures that the countries will implement and integrate into their ongoing development programs. This report focuses on the measures the countries have selected and the methods they used to prepare their action plans. This executive summary presents key lessons and common themes using a structure similar to that used in the individual country chapters.

Cost estimation of interim dry storage for Atucha I NPP

International Nuclear Information System (INIS)

Bergallo, Juan E.; Fuenzalida Troyano, Carlos S.

2007-01-01

A joint effort between NASA and CNEA has been performed in order to evaluate and fix the strategy of interim spent fuel storage for Atucha I nuclear power plant. In this work the cost estimation on the proposed system was performed in order to fix the parameter and design criteria for the next engineering step. The main results achieved show that both alternatives are all in the same range of costs per unit of mass to be stored, the impact on electricity cost is less than 1 US mills/KWh and the scaling factor achieved is 0.85. (author) [es

Socio-technical systems and interaction design - 21st century relevance.

Science.gov (United States)

Maguire, Martin

2014-03-01

This paper focuses on the relationship between the socio-technical system and the user-technology interface. It looks at specific aspects of the organisational context such as multiple user roles, job change, work processes and workflows, technical infrastructure, and the challenges they present for the interaction designer. The implications of trends such as more mobile and flexible working, the use of social media, and the growth of the virtual organisation, are also considered. The paper also reviews rapidly evolving technologies such as pervasive systems and artificial intelligence, and the skills that workers will need to engage with them. Copyright © 2013 Elsevier Ltd and The Ergonomics Society. All rights reserved.

Development of the standard classification system of technical information in the field of RI-biomics and its application to the web system

International Nuclear Information System (INIS)

Jang, Sol Ah; Kim, Joo Yeon; Park, Tai Jin

2014-01-01

RI-Biomics is a new concept that combines radioisotopes (RI) and Biomics. For efficient collection of information, establishment of database for technical information system and its application to the system, there is an increasing need for constructing the standard classification system of technical information by its systematical classification. In this paper, we have summarized the development process of the standard classification system of technical information in the field of RI-Biomics and its application to the system. Constructing the draft version for the standard classification system of technical information was based on that standard classification one in national science and technology in Korea. The final classification system was then derived through the reconstruction and the feedback process based on the consultation from the 7 experts. These results were applied to the database of technical information system after transforming as standard code. Thus, the standard classification system were composed of 5 large classifications and 20 small classifications, and those classification are expected to establish the foundation of information system by achieving the circular structure of collection-analysis-application of information

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

Waste Management System Requirements Document

International Nuclear Information System (INIS)

1992-02-01

This DCP establishes an interim plan for the Office of Civilian Radioactive Waste Management (OCRWM) technical baseline until the results of the OCRWM Document Hierarchy Task Force can be implemented. This plan is needed to maintain continuity in the Program for ongoing work in the areas of Waste Acceptance, Transportation, Monitored Retrievable Storage (MRS) and Yucca Mountain Site Characterization

78 FR 70244 - Electronic Interim Assistance Reimbursement Program

Science.gov (United States)

2013-11-25

..., Social Security Online, at http://www.socialsecurity.gov . SUPPLEMENTARY INFORMATION: Background To be... SOCIAL SECURITY ADMINISTRATION 20 CFR Part 416 [Docket No. SSA-2011-0104] RIN 0960-AH45 Electronic Interim Assistance Reimbursement Program AGENCY: Social Security Administration. ACTION: Notice of...

Interim report on evaluation of research and development of manganese nodule exploitation system; Mangan dankai saiko system no kenkyu kaihatsu chukan hyoka chukan hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-05-01

This research and development project is aimed at development of the techniques which allow exploitation of manganese nodules occurring on deep sea bottoms (4,000 to 6,000 m deep) on a commercial scale, in order to secure stable supply of the non-ferrous metallic resource and improve general ocean development techniques. This project, established by the national project system, has been implemented cooperatively by the government, academic and industrial circles since 1981. Described herein are the interim results obtained by the FY 1984. The bases for development of the elementary techniques have been established for the comprehensive ocean tests. Bright prospects have been obtained to achieve the objectives, although there are some problems remaining to be solved. Interfaces between the sub-systems are being reviewed mainly by the persons in charge of the total system. No problem is foreseen in consistency of the individual components. The movement and exploitation functions of the test system are simulated and validated in detail, to develop the total system. It has been found by the simulations that the nodule-collecting machine shows nonlinear tracking characteristics (i.e., movement different from that of the exploitation ship), and unsteady movements (i.e., repeated movements of rapid starting and stopping). (NEDO)

Technical Assessment of Cryo-Compressed Hydrogen Storage Tank Systems for Automotive Applications

Energy Technology Data Exchange (ETDEWEB)

Ahluwalia, Rajesh [Argonne National Lab. (ANL), Argonne, IL (United States); Hua, T. Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Peng, J. -K. [Argonne National Lab. (ANL), Argonne, IL (United States); Lasher, S. [TIAX LLC, Lexington, MA (United States); McKenney, Kurtis [TIAX LLC, Lexington, MA (United States); Sinha, J. [TIAX LLC, Lexington, MA (United States)

2009-12-01

Technical report describing DOE's second assessment report on a third generation (Gen3) system capable of storing hydrogen at cryogenic temperatures within a pressure vessel on-board a vehicle. The report includes an overview of technical progress to date, including the potential to meet DOE onboard storage targets, as well as independent reviews of system cost and energy analyses of the technology paired with delivery costs.

Federal Administrative Court confirms interim action for the Kruemmel power plant site

International Nuclear Information System (INIS)

Anon.

1982-01-01

The interim action concerning the reactor site was confirmed in 1972, the action of voidance because of the possible injuriousness to health was rejected in the first instance. In the appeal OVG Lueneburg had sharpened three clauses concerning the contents of the restrictions and injunctions included in the interim action to the disadvantage of the operator. Responding to a new appeal the BVerwG has eliminated these restrictions and dismissed the following appeals of the plaintiffs. (HP) [de

77 FR 34935 - Foreign-Trade Zone 161; Temporary/Interim Manufacturing Authority; Siemens Energy, Inc., (Wind...

Science.gov (United States)

2012-06-12

... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [Docket T-4-2012] Foreign-Trade Zone 161; Temporary/Interim Manufacturing Authority; Siemens Energy, Inc., (Wind Turbine Nacelles and Hubs); Notice of... temporary/interim manufacturing (T/IM) authority, on behalf of Siemens Energy, Inc., to manufacture wind...

Using ERA-Interim reanalysis for creating datasets of energy-relevant climate variables

Science.gov (United States)

Jones, Philip D.; Harpham, Colin; Troccoli, Alberto; Gschwind, Benoit; Ranchin, Thierry; Wald, Lucien; Goodess, Clare M.; Dorling, Stephen

2017-07-01

The construction of a bias-adjusted dataset of climate variables at the near surface using ERA-Interim reanalysis is presented. A number of different, variable-dependent, bias-adjustment approaches have been proposed. Here we modify the parameters of different distributions (depending on the variable), adjusting ERA-Interim based on gridded station or direct station observations. The variables are air temperature, dewpoint temperature, precipitation (daily only), solar radiation, wind speed, and relative humidity. These are available on either 3 or 6 h timescales over the period 1979-2016. The resulting bias-adjusted dataset is available through the Climate Data Store (CDS) of the Copernicus Climate Change Data Store (C3S) and can be accessed at present from climate.copernicus.eu" target="_blank">ftp://ecem.climate.copernicus.eu. The benefit of performing bias adjustment is demonstrated by comparing initial and bias-adjusted ERA-Interim data against gridded observational fields.

EPA's Revised Interim Financial Assistance Conflict of Interest Policy

Science.gov (United States)

EPA has established the following revised interim policy governing disclosure of actual and potential conflicts of interest (COI Policy) by applicants for, and recipients of, federal financial assistance awards from EPA.

Technical analysis of photovoltaic/wind systems with hydrogen storage

Directory of Open Access Journals (Sweden)

Bakić Vukman V.

2012-01-01

Full Text Available The technical analysis of a hybrid wind-photovoltaic energy system with hydrogen gas storage was studied. The market for the distributed power generation based on renewable energy is increasing, particularly for the standalone mini-grid applications. The main design components of PV/Wind hybrid system are the PV panels, the wind turbine and an alkaline electrolyzer with tank. The technical analysis is based on the transient system simulation program TRNSYS 16. The study is realized using the meteorological data for a Typical Metrological Year (TMY for region of Novi Sad, Belgrade cities and Kopaonik national park in Serbia. The purpose of the study is to design a realistic energy system that maximizes the use of renewable energy and minimizes the use of fossil fuels. The reduction in the CO2 emissions is also analyzed in the paper. [Acknowledgment. This paper is the result of the investigations carried out within the scientific project TR33036 supported by the Ministry of Science of the Republic of Serbia.

Dynamic Socio-technical System Design based on Stakeholder Interaction

Directory of Open Access Journals (Sweden)

Albert Fleischmann

2015-07-01

Full Text Available In order to directly involve stakeholders in socio-technical system design, we argue for streamlining executable process specifications with business process modeling. Due to current agility requirements of organizations, socio-technical system development is considered one of the key activities of members of the organizations. Dynamic process adaptation enable handling the volatility of business operation and IT infrastructure. Subject-oriented process representations are key enablers to dynamic adaptation due to their capability for stakeholders to create directly executable models. In this way stakeholder can be involved in change management pro-actively. Subject-oriented models (i represent all relevant features required for system control and decision making, and (ii are executable on demand. This effectiveness enables organizational change in a creative and efficient way, while establishing innovative design and change management tools. Subject-oriented Business Process Management capabilities are reflected in this realm revealing benefits and potential for further research.

39 CFR 211.4 - Interim personnel regulations.

Science.gov (United States)

2010-07-01

... 39 Postal Service 1 2010-07-01 2010-07-01 false Interim personnel regulations. 211.4 Section 211.4... under the Postal Reorganization Act. (b) Continuation of Personnel Provisions of Former title 39, U.S.C... collective bargaining agreement under the Postal Reorganization Act, all provisions of former title 39, U.S.C...

Guidelines for interim storage of low level waste

International Nuclear Information System (INIS)

Hornibrook, C.; Castagnacci, A.; Clymer, G.; Kelly, J.; Naughton, M.; Saunders, P.; Stoner, P.; Walker, N.; Cazzolli, R.; Dettenmeier, R.; Loucks, L.; Rigsby, M.; Spall, M.; Strum, M.

1992-12-01

This report presents an overview of on-site storage of Low Level Waste while providing guidelines for using the complete Interim On-Site Storage of Low Level Waste report series. Overall, this report provides a methodology for planning and implementing on-site storage

Technical Issues Map for the NHI System Interface and Support Systems Area: 1st Quarter FY 07

International Nuclear Information System (INIS)

Steven R. Sherman

2006-01-01

This document provides a mapping of technical issues associated with development of the Next Generation Nuclear Plant (NGNP) intermediate heat transport loop and nuclear hydrogen plant support systems to the work that has been accomplished or is currently underway. The technical issues are ranked according to priority and by assumed resolution dates. Due to funding limitations, not all high-priority technical issues are under study at the present time, and more resources will need to be dedicated to tackling such issues in the future. This technical issues map is useful for understanding the relative importance of various technical challenges and will be used as a planning tool for future work package planning

Microcomputer Intelligence for Technical Training (MITT): The evolution of an intelligent tutoring system

Science.gov (United States)

Norton, Jeffrey E.; Wiederholt, Bradley J.; Johnson, William B.

1990-01-01

Microcomputer Intelligence for Technical Training (MITT) uses Intelligent Tutoring System (OTS) technology to deliver diagnostic training in a variety of complex technical domains. Over the past six years, MITT technology has been used to develop training systems for nuclear power plant diesel generator diagnosis, Space Shuttle fuel cell diagnosis, and message processing diagnosis for the Minuteman missile. Presented here is an overview of the MITT system, describing the evolution of the MITT software and the benefits of using the MITT system.

Handbook of technical diagnostics fundamentals and application to structures and systems

CERN Document Server

2013-01-01

This book presents concepts, methods and techniques to examine symptoms of faults and failures of structures, systems and components and to monitor functional performance and structural integrity. The book is organized in five parts. Part A introduces the scope and application of technical diagnostics and gives a comprehensive overview of the physics of failure. Part B presents all relevant methods and techniques for diagnostics and monitoring: from stress, strain, vibration analysis, nondestructive evaluation, thermography and industrial radiology to computed tomography and subsurface microstructural analysis. Part C cores the principles and concepts of technical failure analysis, illustrates case studies, and outlines machinery diagnostics with an emphasis on tribological systems. Part D describes the application of structural health monitoring and performance control to plants and the technical infrastructure, including buildings, bridges, pipelines, electric power stations, offshore wind structures, and r...

Frequency and Type of Prosthetic Complications Associated with Interim, Immediately Loaded Full-Arch Prostheses: A 2-Year Retrospective Chart Review.

Science.gov (United States)

Drago, Carl

2016-08-01

The purpose of this report was to retrospectively evaluate implant and immediate full-arch prosthesis survival rates over a 24-month period; patients were consecutively treated with immediate occlusal loading. Dental arch, gender, and implant orientation (vertical vs. tilted) were also noted. All Brånemark System implants (Nobel Active) and interim, all-acrylic resin prostheses placed in patients following an All-on-Four™ protocol, in a single private practice were assessed by retrospective patient chart review. The amount of space provided surgically for implant restorative components and prostheses was determined from measurements of the vertical heights of the interim prostheses in the right/left anterior and posterior segments. These measurements were made in the laboratory. Interim prosthetic repairs (type, frequency, length of time from insertion) were analyzed by type, arch, gender, and implant orientation. Implant survival and insertion torque values were also measured. Inclusion criteria consisted of all Brånemark System implants placed with the All-on-Four protocol from September 1, 2011, until August 31, 2013. Specific dietary instructions were given for the first 7 days immediately postoperatively and for the weeks prior to insertion of the definitive prostheses. One hundred twenty-nine patients, comprising 191 arches (766 implants) from September 1, 2011, until August 31, 2013, were included in the study. One patient experienced implant failure yielding an overall implant survival rate (SR) of 99.5% (762 of 766). Four hundred twenty-six of 430 maxillary implants and 336 of 336 mandibular implants survived for SRs of 99.1% and 100%, respectively. Regarding implant orientation, 415 of 417 tilted implants (SR 99.5%) and 343 of 345 (CSR 95.6%) vertical implants were noted to be clinically stable. Interim, all-acrylic resin prostheses were in place for a mean of 199.2 days; mandibular prostheses were in place for an average of 195.4 days; maxillary

The Homestake Interim Laboratory and Homestake DUSEL

Science.gov (United States)

Lesko, Kevin T.

2011-12-01

The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

The Homestake Interim Laboratory and Homestake DUSEL

International Nuclear Information System (INIS)

Lesko, Kevin T.

2011-01-01

The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

Interim dry cask storage of irradiated Fast Flux Test Facility fuel

International Nuclear Information System (INIS)

Scott, P.L.

1994-09-01

The Fast Flux Test Facility (FFTF), located at the US Department of Energy's (DOE'S) Hanford Site, is the largest, most modern, liquid metal-cooled test reactor in the world. This paper will give an overview of the FFTF Spent Fuel Off load project. Major discussion areas will address the status of the fuel off load project, including an overview of the fuel off load system and detailed discussion on the individual components that make up the dry cask storage portion of this system. These components consist of the Interim Storage Cask (ISC) and Core Component Container (CCC). This paper will also discuss the challenges that have been addressed in the evolution of this project

Interim Feed The Future Population Based Assessment of Cambodia

Data.gov (United States)

US Agency for International Development — This is the interim population based survey of Feed the Future in Cambodia for 2015. The data is split into survey modules. Modules A through C includes location...

Fuel supply shutdown facility interim operational safety requirements

International Nuclear Information System (INIS)

Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

1995-01-01

These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

Study on advanced systematic function of the JNC geological disposal technical information integration system. Research document

International Nuclear Information System (INIS)

Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito Takaya

2004-02-01

In this study, while attaining systematization about the technical know-how mutually utilized between geology environmental field, disposal technology (design) field and safety assessment field, the share function of general information in which the formation of an information share and the use promotion between the technical information management databases built for every field were aimed at as an advancement of the function of JNC Geological Disposal Technical Information Integration System considered, and the system function for realizing considered in integration of technical information. (1) Since the concrete information about geology environment which is gradually updated with progress of stratum disposal research, or increases in reflected suitable for research of design and safety assessment. After arranging the form suitable for systematizing technical information, while arranging the technical information in both the fields of design and safety assessment with the form of two classes based on tasks/works, it systematized planning adjustment about delivery of technical information with geology environmental field. (2) In order to aim at integration of 3-fields technical information of geological disposal, based on the examination result of systematization of technical information, the function of mutual use of the information managed in two or more databases was considered. Moreover, while considering system functions, such as management of the use history of technical information, connection of information use, and a notice of common information, the system operation windows in consideration of the ease of operation was examined. (author)