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Sample records for facility interim operational

  1. Fuel Supply Shutdown Facility Interim Operational Safety Requirements

    Energy Technology Data Exchange (ETDEWEB)

    BENECKE, M.W.

    2000-09-06

    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.

  2. Fuel supply shutdown facility interim operational safety requirements

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-23

    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).

  3. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  4. Operations and Maintenance Concept Plan for the Immobilized High Level Waste (IHLW) Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    JANIN, L.F.

    2000-08-30

    This O&M Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design.

  5. Development of operational criteria for the interim spent fuel storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, M. H.; Kim, J. C.; Kim, D. K.; Cho, D. K.; Bae, K. M. [Kyunghee Univ., Seoul (Korea, Republic of)

    1997-03-15

    The final objective is to develop the technical criteria for the facility operation of the interim spent fuel storage facility. For this purpose, elementary technical issues are evaluated for the wet storage of spent fuels and status of operation in foreign counties are examined. Urgent objective of this study is to provide technical back data for the development of operational criteria. For the back data for the development of operational criteria, domestic technical data for the wet storages are collected as well as standards and criteria related to the spent fuel storage. Operational stutus of spent fuel storages in foreign countries CLAB in Sweden and MRS in the United States are studied. Dry storage concept is also studied in order to find the characteristics of wet storage concept. Also basic technical issues are defined and studied in order to build a draft of operational criteri00.

  6. 340 Waste handling facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    Stordeur, R.T.

    1996-10-04

    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.

  7. 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.

  8. Transuranic storage and assay facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    Porten, D.R., Fluor Daniel Hanford

    1997-02-12

    The Transuranic Waste Storage and Assay Facility (TRUSAF) Interim Safety Basis document provides the authorization basis for the interim operation and restriction on interim operations for the TRUSAF. The TRUSAF ISB demonstrates that the TRUSAF can be operated safely, protecting the workers, the public, and the environment. The previous safety analysis document TRUSAF Hazards Identification and Evaluation (WHC 1987) is superseded by this document.

  9. 40 CFR 270.71 - Operation during interim status.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Operation during interim status. 270... (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Interim Status § 270.71 Operation during interim status. (a) During the interim status period the facility shall not: (1)...

  10. Interim Safety Basis for Fuel Supply Shutdown Facility

    Energy Technology Data Exchange (ETDEWEB)

    BENECKE, M.W.

    2000-09-07

    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.

  11. Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)

    Energy Technology Data Exchange (ETDEWEB)

    COVEY, L.I.

    2000-11-28

    The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, {sup 90}Sr and {sup 137}Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the {sup 137}Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF.

  12. 76 FR 4369 - Interim Deputation Agreements; Interim BIA Adult Detention Facility Guidelines

    Science.gov (United States)

    2011-01-25

    ... Bureau of Indian Affairs Interim Deputation Agreements; Interim BIA Adult Detention Facility Guidelines... publication of the Interim BIA Adult Detention Facility Guidelines and the Interim Model Deputation Agreements... of 2010. Three Interim Model Deputation Agreements will be used: one agreement for tribes in...

  13. Central waste complex interim operational safety requirements

    Energy Technology Data Exchange (ETDEWEB)

    Bendixsen, R.B.; Ames, R.R., Fluor Daniel Hanford

    1997-03-20

    This Interim Operational Safety Requirements document supports the authorization basis for interim operations and identifies restrictions on interim operations for the disposal and storage of solid waste in the Central Waste Complex. The Central Waste Complex Interim Operational Safety Requirements provide the necessary controls on operations in the Central Waste Complex to ensure the radiological and hazardous material exposure will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, 1327 the public and the environment.

  14. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  15. Interim irradiated fuel storage facility for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Lolich, Jose [INVAP SE, Bariloche (Argentina)

    2002-07-01

    In most research reactors irradiated fuel discharged from the reactor is initially stored underwater inside the reactor building for along period of time. This allows for heat dissipation and fission product decay. In most cases this initial storage is done in a irradiated fuel storage facility pool located closed to the reactor core. After a certain cooling time, the fuel discharged should be relocated for long-term interim storage in a Irradiated Fuel Storage (IFS) Facility. IFS facilities are required for the safe storage of irradiated nuclear fuel before it is reprocessed or conditioned for disposal as radioactive waste. The IFS Facility described in this report is not an integral part of an operating nuclear reactor. This facility many be either co-located with nuclear facilities (such as a nuclear reactor or reprocessing plant) or sited independently of other nuclear facilities. (author)

  16. 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.

  17. Flammable gas deflagration consequence calculations for the tankwaste remediation system basis for interim operation

    Energy Technology Data Exchange (ETDEWEB)

    Van Vleet, R.J., Westinghouse Hanford

    1996-09-23

    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.

  18. FB Line Basis for Interim Operation

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, B.

    1998-10-19

    The safety analysis of the FB-Line Facility indicates that the operation of FB-Line to support the current mission does not present undue risk to the facility and co-located workers, general public, or the environment.

  19. 47 CFR 73.404 - Interim hybrid IBOC DAB operation.

    Science.gov (United States)

    2010-10-01

    ... RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The... test operation pursuant to § 73.1620, may commence interim hybrid IBOC DAB operation with digital... No. 99-325. FM stations are permitted to operate with hybrid digital effective radiated power...

  20. Study on the fire-protection-system for interim storage facilities of spent nuclear fuel and transportation ships

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. O; Choi, M. H.; Lee, S. C. and others [Dongbang Electron Industry Corporation, Seoul (Korea, Republic of)

    1993-12-15

    This study consists of : the fire risk and it's fire protection for the storage facilities and transportation equipments of dangerous goods, the fire risk and it's fire protection for the interim storage facilities of spent nuclear fuel, the fire risk and it's fire protection for the dangerous goods transportation ships, the necessary equipment for safety of ships and regulations of fire fighting equipment for ships, technical specification of spent nuclear fuel transportation ships which are operated in foreign countries, draft of fire protection guideline for interim storage facilities of spent nuclear fuel, inspection items of fire fighting equipment, scope of education and training. On the basis of the aforementioned, a draft of fire protection guideline for interim storage facilities of spent nuclear fuel is proposed and the regulations for ship engaged in the a carrage of dangerous goods that should be considered in design and operation stage are proposed.

  1. A review of proposed Glen Canyon Dam interim operating criteria

    Energy Technology Data Exchange (ETDEWEB)

    LaGory, K.; Hlohowskyj, I.; Tomasko, D.; Hayse, J.; Durham, L.

    1992-04-01

    Three sets of interim operating criteria for Glen Canyon Dam on the Colorado River have been proposed for the period of November 1991, to the completion of the record of decision for the Glen Canyon Dam environmental impact statement (about 1993). These criteria set specific limits on dam releases, including maximum and minimum flows, up-ramp and down-ramp rates, and maximum daily fluctuation. Under the proposed interim criteria, all of these parameters would be reduced relative to historical operating criteria to protect downstream natural resources, including sediment deposits, threatened and endangered fishes, trout, the aquatic food base, and riparian plant communities. The scientific bases of the three sets of proposed operating criteria are evaluated in the present report:(1) criteria proposed by the Research/Scientific Group, associated with the Glen Canyon Environmental Studies (GCES); (2) criteria proposed state and federal officials charged with managing downstream resources; and (3) test criteria imposed from July 1991, to November 1991. Data from Phase 1 of the GCES and other sources established that the targeted natural resources are affected by dam operations, but the specific interim criteria chosen were not supported by any existing studies. It is unlikely that irreversible changes to any of the resources would occur over the interim period if historical operating criteria remained in place. It is likely that adoption of any of the sets of proposed interim operating criteria would reduce the levels of sediment transport and erosion below Glen Canyon Dam; however, these interim criteria could result in some adverse effects, including the accumulation of debris at tributary mouths, a shift of new high-water-zone vegetation into more flood-prone areas, and further declines in vegetation in the old high water zone.

  2. Radiation analysis for a generic centralized interim storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, S.G.; Lopez, P. [TRW Environmental Safety Systems, Inc., Vienna, VA (United States); Eble, R.G. [Duke Engineering and Services, Inc., Charlotte, NC (United States)

    1997-12-31

    This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required.

  3. A security vulnerabilities assessment tool for interim storage facilities of low-level radioactive wastes.

    Science.gov (United States)

    Bible, J; Emery, R J; Williams, T; Wang, S

    2006-11-01

    Limited permanent low-level radioactive waste (LLRW) disposal capacity and correspondingly high disposal costs have resulted in the creation of numerous interim storage facilities for either decay-in-storage operations or longer term accumulation efforts. These facilities, which may be near the site of waste generation or in distal locations, often were not originally designed for the purpose of LLRW storage, particularly with regard to security. Facility security has become particularly important in light of the domestic terrorist acts of 2001, wherein LLRW, along with many other sources of radioactivity, became recognized commodities to those wishing to create disruption through the purposeful dissemination of radioactive materials. Since some LLRW materials may be in facilities that may exhibit varying degrees of security control sophistication, a security vulnerabilities assessment tool grounded in accepted criminal justice theory and security practice has been developed. The tool, which includes dedicated sections on general security, target hardening, criminalization benefits, and the presence of guardians, can be used by those not formally schooled in the security profession to assess the level of protection afforded to their respective facilities. The tool equips radiation safety practitioners with the ability to methodically and systematically assess the presence or relative status of various facility security aspects, many of which may not be considered by individuals from outside the security profession. For example, radiation safety professionals might not ordinarily consider facility lighting aspects, which is a staple for the security profession since it is widely known that crime disproportionately occurs more frequently at night or in poorly lit circumstances. Likewise, the means and associated time dimensions for detecting inventory discrepancies may not be commonly considered. The tool provides a simple means for radiation safety professionals to

  4. Tier One Performance Screen Initial Operational Test and Evaluation: 2011 Interim Report

    Science.gov (United States)

    2012-04-01

    Battery (ASVAB) Content, Structure, and Scor ing The ASVAB is a multiple aptitude battery of nine tests administered by the MEPCOM. Most military...Technical Report 1306 Tier One Performance Screen Initial Operational Test and Evaluation: 2011 Interim Report Deirdre J...to) August 2009 to May 2011 4. TITLE AND SUBTITLE Tier One Performance Screen Initial Operational Test and Evaluation: 2011 Interim

  5. Neutron spectrometry at the interim storage facility for spent nuclear fuel

    CERN Document Server

    Králik, M; Studeny, J

    2002-01-01

    Dosimetric characteristics of neutron and photon components of mixed fields around casks for spent nuclear fuel have been determined at various places at the dry interim storage facility. The results obtained with metrological grade instruments were compared with data provided by usual survey meters for both neutrons and photons.

  6. 77 FR 74512 - Interim Policy Leasing for Renewable Energy Data Collection Facility on the Outer Continental...

    Science.gov (United States)

    2012-12-14

    ... Bureau of Ocean Energy Management Interim Policy Leasing for Renewable Energy Data Collection Facility on... leasing are identified as Brunswick NH 17-02 OCS blocks numbered 6074, 6174, and 6126. The proposed lease... of competitive interest from parties interested in leasing any of these nominated areas. The...

  7. 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.

  8. The Interim : until you achieve an operationally responsive ground system

    Science.gov (United States)

    Wendlandt, Bob; Clarke, Kelly; Lei, Jordan; Miyamoto, Charles; Owen-Mankovich, Kyran

    2008-01-01

    Everyone wants to achieve a 'Responsive' Ground Data System (GDS), but that takes time. What do you do in the interim? Our group, called the Integration, Test and Deployment Team (ITD), is a group of responsive engineers whose primary focus is to assist JPL projects to successfully adapt, test, integrate and deploy their ground data system. The team configures and adapts the GDS for a project, so that analysts, engineers and scientist do not need to be experts in the GDS to operate it. The team has developed a human interface to accommodate all types of users. It provides Graphical User Interfaces (GUI's) for those that want GUI's, command line interfaces for those that want control, and selection button interfaces for other users. The cornerstone of a responsive Ground Data System is responsive people. Without individuals who can be aware of a project's changing needs and requirements, how can the GDS become responsive

  9. 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.

  10. 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.

  11. Plutonium uranium extraction (PUREX) end state basis for interim operation (BIO) for surveillance and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    DODD, E.N.

    1999-05-12

    This Basis for Interim Operation (BIO) was developed for the PUREX end state condition following completion of the deactivation project. The deactivation project has removed or stabilized the hazardous materials within the facility structure and equipment to reduce the hazards posed by the facility during the surveillance and maintenance (S and M) period, and to reduce the costs associated with the S and M. This document serves as the authorization basis for the PUREX facility, excluding the storage tunnels, railroad cut, and associated tracks, for the deactivated end state condition during the S and M period. The storage tunnels, and associated systems and areas, are addressed in WHC-SD-HS-SAR-001, Rev. 1, PUREX Final Safety Analysis Report. During S and M, the mission of the facility is to maintain the conditions and equipment in a manner that ensures the safety of the workers, environment, and the public. The S and M phase will continue until the final decontamination and decommissioning (D and D) project and activities are begun. Based on the methodology of DOE-STD-1027-92, Hazards Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports, the final facility hazards category is identified as hazards category This considers the remaining material inventories, form and distribution of the material, and the energies present to initiate events of concern. Given the current facility configuration, conditions, and authorized S and M activities, there are no operational events identified resulting in significant hazard to any of the target receptor groups (e.g., workers, public, environment). The only accident scenarios identified with consequences to the onsite co-located workers were based on external natural phenomena, specifically an earthquake. The dose consequences of these events are within the current risk evaluation guidelines and are consistent with the expectations for a hazards category 2

  12. Basis for Interim Operation for the K-Reactor in Cold Standby

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, B.

    1998-10-19

    The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

  13. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-03-01

    Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

  14. Criteria for designing an interim waste storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Vicente, Roberto, E-mail: rvicente@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The long-lived radioactive wastes with activity above clearance levels generated by radioisotope users in Brazil are collected into centralized waste storage facilities under overview of the National Commission on Nuclear Energy (CNEN). One of these centers is the Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN), in Sao Paulo, which since 1978 also manages the wastes generated by IPEN itself. Present inventory of stored wastes includes about 160 tons of treated wastes, distributed in 1290 steel, 200-liters drums, and 52 steel, 1.6 m{sup 3}-boxes, with an estimated total activity of 0.8 TBq. Radionuclides present in these wastes are fission and activation products, transuranium elements, and isotopes from the uranium and thorium decay series. The capacity and quality of the storage rooms at GRR evolved along the last decades to meet the requirements set forth by the Brazilian regulatory authorities.From a mere outdoor concrete platform over which drums were simply stacked and covered with canvas to the present day building, a great progress was made in the storage method. In this paper we present the results of a study in the criteria that were meant to guide the design of the storage building, many of which were eventually adopted in the final concept, and are now built-in features of the facility. We also present some landmarks in the GRR's activities related to waste management in general and waste storage in particular, until the treated wastes of IPEN found their way into the recently licensed new storage facility. (author)

  15. Facility design, construction, and operation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

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

  16. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Adams, N

    2007-07-08

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to

  17. 76 FR 72006 - Draft Interim Staff Guidance: Evaluations of Uranium Recovery Facility Surveys of Radon and Radon...

    Science.gov (United States)

    2011-11-21

    ... COMMISSION Draft Interim Staff Guidance: Evaluations of Uranium Recovery Facility Surveys of Radon and Radon... Recovery Facility Surveys of Radon and Radon Progeny in Air and Demonstrations of Compliance with 10 CFR 20... that existing guidance does not sufficiently detail how the NRC staff reviews surveys of radon and...

  18. Identifying Potential Areas for Siting Interim Nuclear Waste Facilities Using Map Algebra and Optimization Approaches

    Energy Technology Data Exchange (ETDEWEB)

    Omitaomu, Olufemi A [ORNL; Liu, Cheng [ORNL; Cetiner, Sacit M [ORNL; Belles, Randy [ORNL; Mays, Gary T [ORNL; Tuttle, Mark A [ORNL

    2013-01-01

    The renewed interest in siting new nuclear power plants in the United States has brought to the center stage, the need to site interim facilities for long-term management of spent nuclear fuel (SNF). In this paper, a two-stage approach for identifying potential areas for siting interim SNF facilities is presented. In the first stage, the land area is discretized into grids of uniform size (e.g., 100m x 100m grids). For the continental United States, this process resulted in a data matrix of about 700 million cells. Each cell of the matrix is then characterized as a binary decision variable to indicate whether an exclusion criterion is satisfied or not. A binary data matrix is created for each of the 25 siting criteria considered in this study. Using map algebra approach, cells that satisfy all criteria are clustered and regarded as potential siting areas. In the second stage, an optimization problem is formulated as a p-median problem on a rail network such that the sum of the shortest distance between nuclear power plants with SNF and the potential storage sites from the first stage is minimized. The implications of obtained results for energy policies are presented and discussed.

  19. 2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    Energy Technology Data Exchange (ETDEWEB)

    D. Shanklin

    2006-07-19

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities fro the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003.

  20. 2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    Energy Technology Data Exchange (ETDEWEB)

    D. Shanklin

    2006-07-19

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities fro the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003.

  1. 14 CFR 136.41 - Interim operating authority.

    Science.gov (United States)

    2010-01-01

    ...) AIR CARRIERS AND OPERATORS FOR COMPENSATION OR HIRE: CERTIFICATION AND OPERATIONS COMMERCIAL AIR TOURS... operating authority under this section to a commercial air tour operator for commercial air tour operations over a national park or tribal land for which the operator is an existing commercial air tour...

  2. Air Defense Radar Operations Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Facility consists of laboratories, experimental test equipment including state-of-theart test bed radar, and test ranges. The facilities are used to design, develop,...

  3. Air Defense Radar Operations Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Facility consists of laboratories, experimental test equipment including state-of-theart test bed radar, and test ranges. The facilities are used to design, develop,...

  4. Thermal analysis of the unloading cell of the Spanish centralized interim storage facility (CISF); Analisis termico de la celda de desarga del almacen temporal centralizado (ATC)

    Energy Technology Data Exchange (ETDEWEB)

    Perez Dominguez, J. R.; Perez Vara, R.; Huelamo Martinez, E.

    2016-08-01

    This article deals with the thermal analysis performed for the Untoading Cell of Spain Centralized Interim Storage Facility, CISF (ATC, in Spanish). The analyses are done using computational fluid dynamics (CFD) simulation, with the aim of obtaining the air flow required to remove the residual heat of the elements stored in the cell. Compliance with the admissible heat limits is checked with the results obtained in the various operation and accident modes. The calculation model is flexible enough to allow carrying out a number of sensitivity analyses with the different parameters involved in the process. (Author)

  5. Data Management Facility Operations Plan

    Energy Technology Data Exchange (ETDEWEB)

    Keck, Nicole N

    2014-06-30

    The Data Management Facility (DMF) is the data center that houses several critical Atmospheric Radiation Measurement (ARM) Climate Research Facility services, including first-level data processing for the ARM Mobile Facilities (AMFs), Eastern North Atlantic (ENA), North Slope of Alaska (NSA), Southern Great Plains (SGP), and Tropical Western Pacific (TWP) sites, as well as Value-Added Product (VAP) processing, development systems, and other network services.

  6. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-06-02

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  7. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-04-09

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  8. Operable Unit 3: Proposed Plan/Environmental Assessment for interim remedial action

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    This document presents a Proposed Plan and an Environmental Assessment for an interim remedial action to be undertaken by the US Department of Energy (DOE) within Operable Unit 3 (OU3) at the Fernald Environmental Management Project (FEMP). This proposed plan provides site background information, describes the remedial alternatives being considered, presents a comparative evaluation of the alternatives and a rationnale for the identification of DOE`s preferred alternative, evaluates the potential environmental and public health effects associated with the alternatives, and outlines the public`s role in helping DOE and the EPA to make the final decision on a remedy.

  9. REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISC)

    Energy Technology Data Exchange (ETDEWEB)

    CHASTAIN, S.A.

    2005-10-24

    Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is {le} 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The

  10. 33 CFR 154.1025 - Operating restrictions and interim operating authorization.

    Science.gov (United States)

    2010-07-01

    ..., DEPARTMENT OF HOMELAND SECURITY (CONTINUED) POLLUTION FACILITIES TRANSFERRING OIL OR HAZARDOUS MATERIAL IN... with § 154.1060 of this part. (b) No facility subject to this subpart may handle, store, or transport... under § 154.1015(c) as a significant and substantial harm facility may handle, store, or transport...

  11. An information management system for a spent nuclear fuel interim storage facility.

    Energy Technology Data Exchange (ETDEWEB)

    Finch, Robert J.; Chiu, Hsien-Lang (Taiwan Power Co., Taipei, 10016 Taiwan); Giles, Todd; Horak, Karl Emanuel; Jow, Hong-Nian (Jow International, Kirkland, WA)

    2010-12-01

    We describe an integrated information management system for an independent spent fuel dry-storage installation (ISFSI) that can provide for (1) secure and authenticated data collection, (2) data analysis, (3) dissemination of information to appropriate stakeholders via a secure network, and (4) increased public confidence and support of the facility licensing and operation through increased transparency. This information management system is part of a collaborative project between Sandia National Laboratories, Taiwan Power Co., and the Fuel Cycle Materials Administration of Taiwan's Atomic Energy Council, which is investigating how to implement this concept.

  12. Technical Competencies for the Safe Interim Storage and Management of 233U at U.S. Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, D.O.; Krichinsky, A.M.; Laughlin, S.S.; Van Essen, D.C.; Yong, L.K.

    1999-02-17

    Uranium-233 (with concomitant {sup 232}U) is a man-made fissile isotope of uranium with unique nuclear characteristics which require high-integrity alpha containment biological shielding, and remote handling. The special handling considerations and the fact that much of the {sup 233}U processing and large-scale handling was performed over a decade ago underscore the importance of identifying the people within the DOE complex who are currently working with or have worked with {sup 233}U. The availability of these key personnel is important in ensuring safe interim storage, management and ultimate disposition of {sup 233}U at DOE facilities. Significant programs are ongoing at several DOE sites with actinides. The properties of these actinide materials require many of the same types of facilities and handling expertise as does {sup 233}U.

  13. Operation of JET as a user facility

    Energy Technology Data Exchange (ETDEWEB)

    Kaye, Alan S. E-mail: ask@jet.uk; Cox, M.; Farthing, J.W.; Hitchin, M.; Lomas, P

    2003-09-01

    Since the beginning of 2000, the Joint European Torus (JET) has been operated under the European fusion development agreement (EFDA) as a user facility. The UKAEA as 'operator' maintains and operates the facility and installs enhancements on behalf of EFDA under contract to the European Commission. The experimental programme is proposed and implemented by the 'users', scientists and engineers on secondment from the European fusion laboratories, which also supply equipment for enhancement of the facility. The overall programme is co-ordinated by the close support unit (CSU). During the five experimental campaigns to date, the historical rate of successful pulsing has been largely maintained. One major shutdown has been completed with substantial in-vessel and ex-vessel tasks, and various small enhancements have been installed. The first major enhancement is imminent. The UKAEA is independently responsible for safety and the environmental impact of the project. This paper reviews the requirements and procedures for control of the interface between the operator, the CSU and users, presents performance measures for key aspects, and summarises the experience of the UKAEA in the operation of JET.

  14. PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

    Energy Technology Data Exchange (ETDEWEB)

    MAY TH

    2008-08-12

    The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

  15. Specification ''I'' of the CEFRI concerning the interim job enterprises proposing personnel of A or B category to work in nuclear facilities

    CERN Document Server

    Int. At. Energy Agency Wien

    2002-01-01

    This document aims to specify the organization dispositions which have to bee taken by the interim job enterprises proposing personnel of A or B category to work in nuclear facilities. These dispositions should allow to respect the demands of the CEFRI in matter of formation, medical control and personnel dosimetry. (A.L.B.)

  16. Operational Implementation of the MARSSIM Process at the Wayne Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    Hays, D. C. Jr.; Trujillo, P. A. IV.; Zoller, S. G.

    2002-02-27

    This paper describes the methodologies behind the operational implementation of the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM) process at the Wayne Interim Storage Site (WISS). The United States Army Corps of Engineers (USACE) and Environmental Chemical Corporation (ECC) have implemented the MARSSIM process using various surveys producing raw data. The final remedial status of a survey unit is derived through data reduction, while maintaining a high degree of efficiency in the construction aspects of the remedial action. Data reduction of field measurements is accomplished by merging the data outputs of a Digital Global Positioning System, an exposure rate meter, and laboratory analyses to produce maps which present exposure rates, elevations, survey unit boundaries, direct measurement locations, and sampling locations on a single map. The map serves as a data-posting plot and allows the project team to easily judge the survey unit's remedial status. The operational implementation of the MARSSIM process has been successful in determining the eligibility of survey units for final status surveys at the WISS and also in demonstrating final status radiological and chemical conditions while maintaining an efficient remedial action effort.

  17. Lunar launch and landing facilities and operations

    Science.gov (United States)

    1987-01-01

    The Florida Institute of Technology established an Interdisciplinary Design Team to design a lunar based facility whose primary function involves launch and landing operations for future moon missions. Both manned and unmanned flight operations were considered in the study with particular design emphasis on the utilization (or reutilization) of all materials available on the moon. This resource availability includes man-made materials which might arrive in the form of expendable landing vehicles as well as in situ lunar minerals. From an engineering standpoint, all such materials are considered as to their suitability for constructing new lunar facilities and/or repairing or expanding existing structures. Also considered in this design study was a determination of the feasibility of using naturally occurring lunar materials to provide fuel components to support lunar launch operations. Conventional launch and landing operations similar to those used during the Apollo Program were investigated as well as less conventional techniques such as rail guns and electromagnetic mass drivers. The Advanced Space Design team consisted of students majoring in Physics and Space Science as well as Electrical, Mechanical, Chemical and Ocean Engineering.

  18. Integrated safeguards and facility design and operations

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by insiders requires careful communication and management of safeguards-relevant information on a timely basis. The separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification and careful attention to management of information can result in effective safeguards integration. Whether designing new systems or analyzing existing ones, understanding the interface between facility operations and safeguards is critical to cost-effective integrated safeguards systems that meet modern standards of performance.

  19. First Operational Experience Of The CNGS Facility

    Science.gov (United States)

    Gschwendtner, E.; Pardons, A.; Bruno, L.; Clement, M.; Efthymiopoulos, I.; Elsener, K.; Meddahi, M.; Rangod, S.; Vincke, H.

    2008-02-01

    The CNGS project (CERN Neutrinos to Gran Sasso) aims at directly detecting νμ-ντ oscillation. An intense muon-neutrino beam (1017νμ/day) is generated at CERN and directed towards the Gran Sasso National Laboratory, LNGS, in Italy, where the ντ will be detected in large and complex detectors. An overview of the CNGS beam facility is given. The performance of the primary and secondary beam line during beam commissioning and physics operation is discussed. Modifications on the magnetic focusing lenses (horn and reflector) are described.

  20. Operation of post-irradiation examination facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eun Ka; Park, Kwang Joon; Jeon, Yong Bum [and others] [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    In 1995, the post-irradiation examination (PIE) of nuclear fuels was performed as follows. The relation between burnup and top nozzle spring force of fuel assembly was obtained by measuring the holddown spring force on the Kori-1 reactor fuel assemblies. The resonance ultrasonic test for inspection of defect and moisture in fuel rod was carried out on fuel rods of C15 and J14 assemblies, and the change of fuel rod condition by storing in pool has been analyzed on the intentionally defected fuel rods (ID-C and ID-L) as well as intact fuel rod (1-2) by NDT in ht cell. The oxide layer thickness on cladding surface of J44-L12 fuel rod was measured by NDT method and metallography to reveal the oxidation as a function of temperature in the fuel rod, and the burnup of J44 fuel assembly was measured by chemical analysis. HVAC system and pool water treatment system of the PIE facility were continuously operated for air filtration and water purification. The monitoring of radiation and pool water in PIE facility has been carried out to maintain the facility safety, and electric power supply system was checked and maintained to supply the electric power to the facility normally. The developed measurement techniques of oxide layer thickness on fuel rod cladding and holddown spring force of top nozzle in fuel assembly were applied to examine the nuclear fuels. Besides, a radiation shielding glove box was designed and a hot cell compressor for volume reduction of radioactive materials was fabricated. 19 tabs., 38 figs., 7 refs. (Author) .new.

  1. Interim glycol flowsheet reduction/oxidation (redox) model for the Defense Waste Processing Facility (DWPF)

    Energy Technology Data Exchange (ETDEWEB)

    Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Williams, M. S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Zamecnik, J. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Missimer, D. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-03-08

    Control of the REDuction/OXidation (REDOX) state of glasses containing high concentrations of transition metals, such as High Level Waste (HLW) glasses, is critical in order to eliminate processing difficulties caused by overly reduced or overly oxidized melts. Operation of a HLW melter at Fe+2/ΣFe ratios of between 0.09 and 0.33, a range which is not overly oxidizing or overly reducing, helps retain radionuclides in the melt, i.e. long-lived radioactive 99Tc species in the less volatile reduced Tc4+ state, 104Ru in the melt as reduced Ru+4 state as insoluble RuO2, and hazardous volatile Cr6+ in the less soluble and less volatile Cr+3 state in the glass. The melter REDOX control balances the oxidants and reductants from the feed and from processing additives such as antifoam. Currently, the Defense Waste Processing Facility (DWPF) is running a formic acid-nitric acid (FN) flowsheet where formic acid is the main reductant and nitric acid is the main oxidant. During decomposition formate and formic acid releases H2 gas which requires close control of the melter vapor space flammability. A switch to a nitric acid-glycolic acid (GN) flowsheet is desired as the glycolic acid flowsheet releases considerably less H2 gas upon decomposition. This would greatly simplify DWPF processing. Development of an EE term for glycolic acid in the GN flowsheet is documented in this study.

  2. Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Cummins, G.D.

    1994-06-01

    This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy`s (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS.

  3. A Guide for Planning Facilities for Occupational Preparation Programs in Metallurgy Technology. Interim Report. Research 28.

    Science.gov (United States)

    German, Carl, Jr.

    The major purpose of this guide is to elicit the information necessary for writing educational specifications for facilities to house technical education programs in metallurgy. It is organized in these parts: (1) Part I discusses the major purpose, underlying assumptions, recent instructional trends, and guiding principles utilized in the…

  4. Hazardous Material Storage Facilities and Sites - Commercial Hazardous Waste Operations

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — A Commercial Hazardous Waste Operation is a DEP primary facility type related to the Waste Management Hazardous Waste Program. The sub-facility types related to...

  5. Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

    Energy Technology Data Exchange (ETDEWEB)

    Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

    1997-01-01

    A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs.

  6. Hydrazine Blending and Storage Facility, Interim Response Action, Final Implementation Document for Decommissioning, Phase 1

    Science.gov (United States)

    1991-03-18

    PRIMARY OBJECTIVES OF THE IRA 2. SITE INVENTORY - TANKS, PIPING, BUILDINGS, ASBEST , DEBRIS, DRUMS 3. PLAN OF ACTION - TRANSFER OF UNTREATED WASTEWATER...Response Action (IRA) H at thte Hydrazine Blending and Storage Facility (HBSF) located at Rocky Mountain Arsenal (RMA) in Commerce City , Colorado. It was...LOCATION MAP Commerce CIty , Colorado 1A U) Cl)) zr LU .i I 0< 9< z (’ICM ..w co ai >. r 0) IC., Z C’) ________________0 W jl cor cliB destruction of

  7. Development of Aircraft Impact Scenario on a Concrete Cask in Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Momani, Belal Al; Yoo, Min; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    This paper provides a method for determining the failure criteria in global and local damage responses for the concrete cask under extreme mechanical impact condition. IAEA safety guide No. SSG-15 mentions the hypothetical initiating events of SNF storage. Among the external initiating events, the aircraft strike on a storage cask is considered one of the dominant contributions to the risk during storage phase. Although the probability of aircraft crash on ISF is extremely small, it is important to develop the accident scenario caused by an intentional malicious acts launched towards the storage facility in terms to improve inherent security. Thus, the probabilistic approach to develop aircraft impact scenarios on a storage cask is needed.

  8. IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Rennich, M.J.

    1995-12-01

    Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops` as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems.

  9. Interim reclamation report, Basalt Waste Isolation Project Near Surface Test Facility 1990

    Energy Technology Data Exchange (ETDEWEB)

    Brandt, C.A.; Rickard, W.H. Jr.; Hefty, M.G.; Cadoret, N.A.

    1991-01-01

    This report describes the development of the reclamation project for the Hanford Site Near Surface Test Facility (NSTF), its implementation, and preliminary estimates of its success. The goal of the reclamation project is to return disturbed sites as nearly as practicable to their original conditions using native species. Gable Mountain is dominated by two plant communities: a big sagebrush (Artemisia tridentata) -- Sandberg's bluegrass (Poa sandbergii) community and a stiff sagebrush (Artemisia rigida) -- Sandberg's bluegrass community. Disassembly of the site installations began on March 15, 1988, and the site was returned to original contours by December 12, 1988. Two separate revegetation methods were employed at the NSTF to meet differing site constraints. Vegetative cover and density in the revegetation plots were assessed in April 1989 and again in June 1989 and 1990. It is extremely unlikely that the sand pit, borrow pit, box cuts, generator pad area, or ventilation fan area will reach the reclamation objectives set for these areas within the next 50 years without further intervention. These areas currently support few living plants. Vegetation on revegetated native soils appears to be growing as expected. Vegetation growth on the main waterline is well below the objective. To date, no shrubs have grown on the area, growth of native grasses is well below the objective, and much of the area has been covered with the pit run material, which may not support adequate growth. Without further treatments, the areas without the pit run material will likely revert to a nearly pure cheatgrass condition. 44 refs., 13 figs., 7 tabs.

  10. A study of the operation of selected national research facilities

    Science.gov (United States)

    Eisner, M.

    1974-01-01

    The operation of national research facilities was studied. Conclusions of the study show that a strong resident scientific staff is required for successful facility operation. No unique scheme of scientific management is revealed except for the obvious fact that the management must be responsive to the users needs and requirements. Users groups provide a convenient channel through which these needs and requirements are communicated.

  11. Standing Facilities Versus Open Market Operations: Equivalence Results

    OpenAIRE

    Alessandro Marchesiani; Aleksander Berentsen

    2010-01-01

    In this paper we compare two mechanisms for implementing monetary policy: standing facilities and open market operations. We show that any equilibrium allocation that can be attained with open market operations can be replicated with standing facilities, but that the converse is not true. Furthermore, the set of equilibrium allocations that can be attained with standing facilities is weakly dominated in terms of welfare by the set of equilibrium allocations that can be attained with open mark...

  12. Interim Expertise

    Science.gov (United States)

    Anyaso, Hilary Hurd

    2009-01-01

    The Registry for College and University Presidents places former executives in interim presidential and other senior-level posts and is familiar with the challenges interim executives and institutions encounter in times of leadership transitions. However, the one big advantage interims bring to institutions, says Registry Vice President Kevin J.…

  13. Quality Assurance for Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, C. G.; Kwon, H. I.; Kim, K. H.; Oh, Y. W.; Lee, Y. G.; Ha, J. H.; Lim, N. J.

    2008-12-15

    This report describes QA activities performed within 'Quality Assurance for Nuclear facility project' and results thereof. Efforts were made to maintain and improve quality system of nuclear facilities. Varification activities whether quality system was implemented in compliance with requirements. QA department assisted KOLAS accredited testing and calibration laboratories, ISO 9001 quality system, establishment of QA programs for R and D, and carried out reviews and surveys for development of quality assurance technologies. Major items of this report are as follows : - Development and Improvement of QA Programs - QA Activities - Assessment of Effectiveness and Adequacy for QA Programs

  14. Quality assurance for operation of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, C. G.; Hwang, S. Y.; Kim, K. H.; Ha, J. H.; Kang, J. Y.; Kim, J. S.; Jang, K. J.

    2011-12-15

    This report describes QA activities performed within Quality Assurance for Nuclear facility project and results thereof. Efforts were made to maintain and improve quality system of nuclear facilities. Verification activities whether quality system was implemented in compliance with requirements. QA department assisted KOLAS accredited testing and calibration laboratories, ISO 9001 quality system, establishment of QA programs for R and D, and carried out reviews and surveys for development of quality assurance technologies. Major items of this report are as follows : - Development and Improvement of QA Programs - QA Activities - Assessment of Effectiveness and Adequacy for QA Programs.

  15. Annual Report of Radioactive Waste Facilities Operation in 2013

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; LIU; Fu-guo

    2013-01-01

    301,a section of Department of Radiochemistry,which manages 15 facilities and undertakes the administrative tasks of radioactive waste,is the important guarantee of scientific research production and safety in CIAE.1 The safe operation of the radioactive waste management facilities In 2013,in order to ensure the operation safety,we formulated the inspection regulations,which included regular operation inspection,week safety inspection from the leaders of the section and

  16. National Ignition Facility (NIF) operations procedures plan

    Energy Technology Data Exchange (ETDEWEB)

    Mantrom, D.

    1998-05-06

    The purpose of this Operations Procedures Plan is to establish a standard procedure which outlines how NIF Operations procedures will be developed (i.e , written, edited, reviewed, approved, published, revised) and accessed by the NIF Operations staff who must use procedures in order to accomplish their tasks. In addition, this Plan is designed to provide a guide to the NIF Project staff to assist them in planning and writing procedures. Also, resource and scheduling information is provided.

  17. Spent nuclear fuel project cold vacuum drying facility operations manual

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-05-12

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

  18. Interim Status Groundwater Monitoring Plan for Low-Level Waste Management Areas 1 to 4, RCRA Facilities, Hanford,Washington

    Energy Technology Data Exchange (ETDEWEB)

    Dresel, P Evan

    2004-10-25

    This document describes the monitoring plan to meet the requirements for interim status groundwater monitoring at Hanford Site low-level waste burial grounds as specified by 40 CFR 265, incorporated by reference in WAC 173-303-400. The monitoring will take place at four separate low-level waste management areas in the 200-West and 200-East Areas, in the central part of the site. This plan replaces the previous monitoring plan.

  19. Reliability Considerations for the Operation of Large Accelerator User Facilities

    CERN Document Server

    Willeke, F J

    2016-01-01

    The lecture provides an overview of considerations relevant for achieving highly reliable operation of accelerator based user facilities. The article starts with an overview of statistical reliability formalism which is followed by high reliability design considerations with examples. The article closes with operational aspects of high reliability such as preventive maintenance and spares inventory.

  20. Interim Rationalizability

    OpenAIRE

    Eddie Dekel; Drew Fudenberg; Stephen Morris

    2005-01-01

    This paper proposes the solution concept of interim rationalizability, and shows that all type spaces that have the same hierarchies of beliefs have the same set of interim rationalizable outcomes. This solution concept characterizes common knowledge of rationality in the universal type space.

  1. Interim measure conceptual design for remediation at the former CCC/USDA grain storage facility at Centralia, Kansas : pilot test and remedy implementation.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2007-11-09

    This document presents an Interim Measure Work Plan/Design for the short-term, field-scale pilot testing and subsequent implementation of a non-emergency Interim Measure (IM) at the site of the former grain storage facility operated by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) in Centralia, Kansas. The IM is recommended to mitigate both (1) localized carbon tetrachloride contamination in the vadose zone soils beneath the former facility and (2) present (and potentially future) carbon tetrachloride contamination identified in the shallow groundwater beneath and in the immediate vicinity of the former CCC/USDA facility. Investigations conducted on behalf of the CCC/USDA by Argonne National Laboratory have demonstrated that groundwater at the Centralia site is contaminated with carbon tetrachloride at levels that exceed the Kansas Tier 2 Risk-Based Screening Level (RBSL) and the U.S. Environmental Protection Agency's maximum contaminant level of 5.0 {micro}g/L for this compound. Groundwater sampling and analyses conducted by Argonne under a monitoring program approved by the Kansas Department of Health and Environment (KDHE) indicated that the carbon tetrachloride levels at several locations in the groundwater plume have increased since twice yearly monitoring of the site began in September 2005. The identified groundwater contamination currently poses no unacceptable health risks, in view of the absence of potential human receptors in the vicinity of the former CCC/USDA facility. Carbon tetrachloride contamination has also been identified at Centralia in subsurface soils at concentrations on the order of the Kansas Tier 2 RBSL of 200 {micro}g/kg in soil for the soil-to-groundwater protection pathway. Soils contaminated at this level might pose some risk as a potential source of carbon tetrachloride contamination to groundwater. To mitigate the existing contaminant levels and decrease the potential future concentrations of

  2. Environmental Assessment and Finding of No Significant Impact: Interim Measures for the Mixed Waste Management Facility Groundwater at the Burial Ground Complex at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1999-12-08

    The U. S. Department of Energy (DOE) prepared this environmental assessment (EA) to analyze the potential environmental impacts associated with the proposed interim measures for the Mixed Waste Management Facility (MW) groundwater at the Burial Ground Complex (BGC) at the Savannah River Site (SRS), located near Aiken, South Carolina. DOE proposes to install a small metal sheet pile dam to impound water around and over the BGC groundwater seepline. In addition, a drip irrigation system would be installed. Interim measures will also address the reduction of volatile organic compounds (VOCS) from ''hot-spot'' regions associated with the Southwest Plume Area (SWPA). This action is taken as an interim measure for the MWMF in cooperation with the South Carolina Department of Health and Environmental Control (SCDHEC) to reduce the amount of tritium seeping from the BGC southwest groundwater plume. The proposed action of this EA is being planned and would be implemented concurrent with a groundwater corrective action program under the Resource Conservation and Recovery Act (RCRA). On September 30, 1999, SCDHEC issued a modification to the SRS RCRA Part B permit that adds corrective action requirements for four plumes that are currently emanating from the BGC. One of those plumes is the southwest plume. The RCRA permit requires SRS to submit a corrective action plan (CAP) for the southwest plume by March 2000. The permit requires that the initial phase of the CAP prescribe a remedy that achieves a 70-percent reduction in the annual amount of tritium being released from the southwest plume area to Fourmile Branch, a nearby stream. Approval and actual implementation of the corrective measure in that CAP may take several years. As an interim measure, the actions described in this EA would manage the release of tritium from the southwest plume area until the final actions under the CAP can be implemented. This proposed action is expected to reduce the

  3. Development of a probabilistic safety assessment framework for an interim dry storage facility subjected to an aircraft crash using best-estimate structural analysis

    Energy Technology Data Exchange (ETDEWEB)

    Almomani, Belal; Jang, Dong Chan [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Lee, Sang Hoon [Dept. of Mechanical and Automotive Engineering, Keimyung University, Daegu (Korea, Republic of); Kang, Hyun Gook [Dept. of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute, Troy (United States)

    2017-03-15

    Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose–risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research.

  4. Description and Operation of the A3 Subscale Facility

    Science.gov (United States)

    Saunders, G. P.; Varner, D. G.; Grover, J. B.

    2010-01-01

    The purpose of this paper is to give an overview of the general design and operation of the A3 Subscale test facility. The goal is to provide the reader with a general understanding of what the major facility systems are, where they are located, and how they are used to meet the objectives supporting the design of the A3 altitude rocket test facility. This paper also provides the reader with the background information prior to reading the subsequent papers detailing the design and test results of the various systems described herein.

  5. The GENEPI accelerator operation feedback at the MASURCA reactor facility

    Science.gov (United States)

    Destouches, C.; Fruneau, M.; Belmont, J. L.; Do Pinhal, J.; Albrand, S.; Carreta, J. M.; Chaussonnet, P.; De Conto, J. M.; Fontenille, A.; Fougeras, P.; Garrigue, A.; Guisset, M.; Laurens, J. M.; Loiseaux, J. M.; Marchand, D.; Micoud, R.; Mellier, F.; Perbet, E.; Planet, M.; Ravel, J. C.; Richaud, J. P.

    2006-06-01

    The MUSE-4 experiment, dedicated to the Accelerator Driven System (ADS) development studies, was achieved in the MASURCA nuclear reactor facility from 2000 to 2004. An external neutron source was introduced in a lead buffer zone located at the centre of the reactor core in order to simulate the spallation source. This paper deals with the GENEPI accelerator operation feedback at the MASURCA reactor facility during the MUSE-4 experimental campaign. After a presentation of the MASURCA mock-up facility and of the experimental programme objectives, the different phases of the accelerator design and realization are detailed. Its installation in the MASURCA nuclear facility, achieved in June 2000, is described concerning the technical and administrative topics. Then, the accelerator operation feedback is given concerning maintenance, tritium target management, source monitoring, technical evolutions, etc. The accelerator partial dismantling, achieved in the first part of 2005, is also presented. In addition, the GENEPI contribution to the MUSE-4 programme is presented in terms of experimental results and experimental measurement method improvements. Also, GENEPI 2, an evolution of the GENEPI concept, is described. This accelerator, is coupled to the PEREN facility which is dedicated to the nuclear cross-section measurements. Last, this paper makes a synthesis of the GENEPI operation feedback at the MASURCA facility and proposes recommendations for future projects involving accelerators used in nuclear reactor environment.

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

    Energy Technology Data Exchange (ETDEWEB)

    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. (JGB)

  7. Interim design status and operational report for remote handling fixtures: primary and secondary burners

    Energy Technology Data Exchange (ETDEWEB)

    Burgoyne, R.M.

    1976-12-01

    The HTGR reprocessing flowsheet consists of two basic process elements: (1) spent fuel crushing and burning and (2) solvent extraction. Fundamental to these elements is the design and development of specialized process equipment and support facilities. A major consideration of this design and development program is equipment maintenance: specifically, the design and demonstration of selected remote maintenance capabilities and the integration of these into process equipment design. This report documents the current status of the development of remote handling and maintenance fixtures for the primary and secondary burners.

  8. Man-Vehicle Systems Research Facility - Design and operating characteristics

    Science.gov (United States)

    Shiner, Robert J.; Sullivan, Barry T.

    1992-01-01

    This paper describes the full-mission flight simulation facility at the NASA Ames Research Center. The Man-Vehicle Systems Research Facility (MVSRF) supports aeronautical human factors research and consists of two full-mission flight simulators and an air-traffic-control simulator. The facility is used for a broad range of human factors research in both conventional and advanced aviation systems. The objectives of the research are to improve the understanding of the causes and effects of human errors in aviation operations, and to limit their occurrence. The facility is used to: (1) develop fundamental analytical expressions of the functional performance characteristics of aircraft flight crews; (2) formulate principles and design criteria for aviation environments; (3) evaluate the integration of subsystems in contemporary flight and air traffic control scenarios; and (4) develop training and simulation technologies.

  9. Operation technology of air treatment system in nuclear facilities

    CERN Document Server

    Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

    2001-01-01

    Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

  10. 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

  11. LOTIS facility initial operational capabilities: flexible user interfaces

    Science.gov (United States)

    Hutchison, Sheldon B.; Bell, Raymond M., Jr.; Borota, Stephen A.; Cuzner, Gregor J.; Cochrane, Andrew T.

    2010-10-01

    The Large Optical Test and Integration Site (LOTIS) at the Lockheed Martin Space Systems Company in Sunnyvale, CA, has successfully reached Initial Operational Capability (IOC). LOTIS is designed for the verification and testing of optical systems. The facility consists of a large, temperature stabilized vacuum chamber that also functions as a class 10k cleanroom. Within this chamber and atop an advanced vibration-isolation bench are the 6.5 meter diameter LOTIS Collimator and Scene Generator, LOTIS alignment and support equipment. IOC included completion of the entire facility as well as operation of the LOTIS collimator in air. Wavefront properties of the collimator will be described as well as facility vibration isolation properties and turbulence levels within the collimator test chamber. User-specific test capabilities will also be addressed for two major areas of concern.

  12. The Defense Waste Processing Facility: Two Years of Radioactive Operation

    Energy Technology Data Exchange (ETDEWEB)

    Marra, S.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Gee, J.T.; Sproull, J.F.

    1998-05-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC is currently immobilizing high level radioactive sludge waste in borosilicate glass. The DWPF began vitrification of radioactive waste in May, 1996. Prior to that time, an extensive startup test program was completed with simulated waste. The DWPF is a first of its kind facility. The experience gained and data collected during the startup program and early years of operation can provide valuable information to other similar facilities. This experience involves many areas such as process enhancements, analytical improvements, glass pouring issues, and documentation/data collection and tracking. A summary of this experience and the results of the first two years of operation will be presented.

  13. ARM Operations and Engineering Procedure Mobile Facility Site Startup

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, Jimmy W

    2015-05-01

    This procedure exists to define the key milestones, necessary steps, and process rules required to commission and operate an Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF), with a specific focus toward on-time product delivery to the ARM Data Archive. The overall objective is to have the physical infrastructure, networking and communications, and instrument calibration, grooming, and alignment (CG&A) completed with data products available from the ARM Data Archive by the Operational Start Date milestone.

  14. Largest Experimental Facility for Acetylene Production in Operation

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    @@ Scientists from the CAS Institute of Plasma Physics (IPP) completed in early November, 2004, a 2-megawatt experimental facility for acetylene production by coal plasma pyrolysis. The successful operation of the largest installation of the kind in the world confirms a new method for the large-scale industrialization of acetylene production.

  15. The operation of post-irradiation examination facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eun Ka; Min, Duk Ki; Lee, Young Kil [and others] [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    The operation of post-irradiation examination facility was performed as follow. HVAC and pool water treatment system were continuously operated, and radiation monitoring in PIE facility has been carried out to maintain the facility safely. Inspection of the fuel assembly (F02) transported from Kori Unit 1 was performed in pool, and fuel rods extracted from the fuel assembly (J44) of Kori Unit 2 NPP were examined in hot cell. A part of deteriorated pipe line of drinking water was exchanged for stainless steel pipe to prevent leaking accidents. Halon gas system was also installed in the exhausting blower room for fire fighting. And IAEA inspection camera for safeguard of nuclear materials was fixed at the wall in pool area. Radiation monitoring system were improved to display the area radioactive value at CRT monitor in health physics control room. And automatic check system for battery and emergency diesel generator was developed to measure the voltage and current of them. The performance test of oxide thickness measuring device installed in hot cell for irradiated fuel rod and improvement of the device were performed, and good measuring results using standard sample were obtained. The safeguard inspection of nuclear materials and operation inspection of the facility were carried out through the annual operation inspection, quarterly IAEA inspection and quality assurance auditing. 26 tabs., 43 figs., 14 refs. (Author) .new.

  16. Computational Modeling in Support of National Ignition Facility Operations

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, M J; Sacks, R A; Haynam, C A; Williams, W H

    2001-10-23

    Numerical simulation of the National Ignition Facility (NIF) laser performance and automated control of laser setup process are crucial to the project's success. These functions will be performed by two closely coupled computer codes: the virtual beamline (VBL) and the laser operations performance model (LPOM).

  17. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-06-01

    This Interim Report summarizes the research and development activities of the Superconducting Super Collider project carried out from the completion of the Reference Designs Study (May 1984) to June 1985. It was prepared by the SSC Central Design Group in draft form on the occasion of the DOE Annual Review, June 19--21, 1985. Now largely organized by CDG Divisions, the bulk of each chapter documents the progress and accomplishments to date, while the final section(s) describe plans for future work. Chapter 1, Introduction, provides a basic brief description of the SSC, its physics justification, its origins, and the R&D organization set up to carry out the work. Chapter 2 gives a summary of the main results of the R&D program, the tasks assigned to the four magnet R&D centers, and an overview of the future plans. The reader wishing a quick look at the SSC Phase I effort can skim Chapter 1 and read Chapter 2. Subsequent chapters discuss in more detail the activities on accelerator physics, accelerator systems, magnets and cryostats, injector, detector R&D, conventional facilities, and project planning and management. The magnet chapter (5) documents in text and photographs the impressive progress in successful construction of many model magnets, the development of cryostats with low heat leaks, and the improvement in current-carrying capacity of superconducting strand. Chapter 9 contains the budgets and schedules of the COG Divisions, the overall R&D program, including the laboratories, and also preliminary projections for construction. Appendices provide information on the various panels, task forces and workshops held by the CDG in FY 1985, a bibliography of COG and Laboratory reports on SSC and SSC-related work, and on private industrial involvement in the project.

  18. Operational Readiness Review: Savannah River Replacement Tritium Facility

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-01

    The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members.

  19. Tier One Performance Screen Initial Operational Test and Evaluation: 2012 Interim Report

    Science.gov (United States)

    2013-12-01

    the WPA is part of the TOPS IOT &E, WPA scores will not be considered for enlistment eligibility. The WPA is scheduled for administration at MEPS...Tailored Adaptive Personality Assessment System (TAPAS), for an initial operational test and evaluation ( IOT &E), beginning administration to applicants in...for both selection and classification purposes. 15. SUBJECT TERMS Personnel , Manpower, Selection and classification SECURITY CLASSIFICATION OF

  20. Umatilla Hatchery Satellite Facilities Operation and Maintenance; 1996 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Rowan, Gerald D.

    1997-06-01

    The Confederated Tribes of the Umatilla Indian Reservation (CTUIR) and Oregon Department of Fish and Wildlife (ODFW) are cooperating in a joint effort to enhance steelhead and re-establish salmon runs in the Umatilla River Basin. As an integral part of this program, Bonifer Pond, Minthorn Springs, Imeques C-mem-ini-kem and Thornhollow satellite facilities are operated for acclimation and release of juvenile summer steelhead (Oncorhynchus mykiss), fall and spring chinook salmon (O. tshawytscha) and coho salmon (O. kisutch). Minthorn is also used for holding and spawning adult summer steelhead and Three Mile Dam is used for holding and spawning adult fall chinook and coho salmon. Bonifer, Minthorn, Imeques and Thornhollow facilities are operated for acclimation and release of juvenile salmon and summer steelhead. The main goal of acclimation is to reduce stress from trucking prior to release and improve imprinting of juvenile salmonids in the Umatilla River Basin. Juveniles are transported to the acclimation facilities primarily from Umatilla and Bonneville Hatcheries. This report details activities associated with operation and maintenance of the Bonifer, Minthorn, Imeques, Thornhollow and Three Mile Dam facilities in 1996.

  1. 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

  2. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios. (MOW)

  3. Pre-operational safety appraisal Tritiated Scrap Recovery Facility, Mound facility

    Energy Technology Data Exchange (ETDEWEB)

    Dauby, J.J.; Flanagan, T.M.; Metcalf, L.W.; Rhinehammer, T.B.

    1996-07-01

    The purpose of this report is to identify, assess, and document the hazards which are associated with the proposed operation of the Tritiated Scrap Recovery Facility at Mound Facility. A Pre-operational Safety Appraisal is a requirement as stated in Department of Energy Order 5481.1, Safety Analysis and Review System. The operations to be conducted in the new Tritiated Scrap Waste Recovery Facility are not new, but a continuation of a prime mission of Mound`s i.e. recovery of tritium from waste produced throughout the DOE complex. The new facility is a replacement of an existing process started in the early 1960`s and incorporates numerous design changes to enhance personnel and environmental safety. This report also documents the safety of a one time operation involving the recovery of tritium from material obtained by the Department of Energy from the State of Arizona. This project will involve the processing of 240,000 curies of tritium contained in glass ampoules that were to be used in items such as luminous dial watches. These were manufactured by the now defunct American Atomics Corporation, Tucson, Arizona.

  4. Interim design status and operational report for semiremote handling fixtures: size reduction system

    Energy Technology Data Exchange (ETDEWEB)

    Ballard, A.S.

    1977-02-01

    Crushing of HTGR fuel elements is accomplished by a three-stage crushing system consisting of two overhead eccentric jaw crushers, a double-roll crusher, and an oversize reduction system to ensure complete reduction to the desired size. The crushing system is mounted in a special framework which enables gravity flow, eliminates material transport, and minimizes material holdup. The system has been designated UNIFRAME because of the integrated nature of the equipment. This report addresses the demonstration of semiremote maintenance of the crusher in a nonradioactive environment. Although the crusher maintenance system has some remote handling capability inherent in its design, the scope of this initial program is limited to the handling of selected components and allows for manual assistance in certain circumstances. This mode of operation is designated semiremote maintenance and is intended as an effort to gather experience.

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

    Science.gov (United States)

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

    2017-04-01

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

  6. Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations - Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Ross, Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wilson, Chisom Shawn [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Morrow, Charles [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Osborn, Douglas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gauntt, Randall O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    Efforts are being pursued to develop and qualify a system-level model of a reactor core isolation (RCIC) steam-turbine-driven pump. The model is being developed with the intent of employing it to inform the design of experimental configurations for full-scale RCIC testing. The model is expected to be especially valuable in sizing equipment needed in the testing. An additional intent is to use the model in understanding more fully how RCIC apparently managed to operate far removed from its design envelope in the Fukushima Daiichi Unit 2 accident. RCIC modeling is proceeding along two avenues that are expected to complement each other well. The first avenue is the continued development of the system-level RCIC model that will serve in simulating a full reactor system or full experimental configuration of which a RCIC system is part. The model reasonably represents a RCIC system today, especially given design operating conditions, but lacks specifics that are likely important in representing the off-design conditions a RCIC system might experience in an emergency situation such as a loss of all electrical power. A known specific lacking in the system model, for example, is the efficiency at which a flashing slug of water (as opposed to a concentrated jet of steam) could propel the rotating drive wheel of a RCIC turbine. To address this specific, the second avenue is being pursued wherein computational fluid dynamics (CFD) analyses of such a jet are being carried out. The results of the CFD analyses will thus complement and inform the system modeling. The system modeling will, in turn, complement the CFD analysis by providing the system information needed to impose appropriate boundary conditions on the CFD simulations. The system model will be used to inform the selection of configurations and equipment best suitable of supporting planned RCIC experimental testing. Preliminary investigations with the RCIC model indicate that liquid water ingestion by the turbine

  7. Feasibility study for a transportation operations system cask maintenance facility

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-01-01

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

  8. Embracing Safe Ground Test Facility Operations and Maintenance

    Science.gov (United States)

    Dunn, Steven C.; Green, Donald R.

    2010-01-01

    Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

  9. Operational readiness: an integral part of the facility planning process.

    Science.gov (United States)

    Kidd, LeeAnne; Howe, Rob

    2014-01-01

    Large capital building projects benefit from an operational readiness strategy prior to new facility occupancy. St. Joseph's Healthcare used a structured approach for their readiness planning that included individual work plan meetings, tools for ensuring integration across programs and services and process improvement support to ensure a smooth transition. Over 1100 staff were oriented using a Train-the-Trainer model. Significant effort was required to co-ordinate the customized training, which involved "staffing up" to ensure sufficient resources for backfill. Operational readiness planning places additional demands on managers, requiring support and assistance from dedicated resources both prior to occupancy and several months post-move.

  10. Design and operation of an outdoor microalgae test facility

    Energy Technology Data Exchange (ETDEWEB)

    Weissman, J.C.; Tillett, D.M.; Goebel, R.P. (Microbial Products, Inc., Vacaville, CA (USA))

    1989-10-01

    The objective of the project covered in this report is to establish and operate a facility in the American Southwest to test the concept of producing microalgae on a large scale. This microalgae would then be used as a feedstock for producing liquid fuels. The site chosen for this project was an existing water research station in Roswell, New Mexico; the climate and water resources are representative of those in the Southwest. For this project, researchers tested specific designs, modes of operation, and strains of microalgae; proposed and evaluated modifications to technological concepts; and assessed the progress toward meeting cost objectives.

  11. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  12. SILEX ground segment control facilities and flight operations

    Science.gov (United States)

    Demelenne, Benoit; Tolker-Nielsen, Toni; Guillen, Jean-Claude

    1999-04-01

    The European Space Agency is going to conduct an inter orbit link experiment which will connect a low Earth orbiting satellite and a Geostationary satellite via optical terminals. This experiment has been called SILEX (Semiconductor Inter satellite Link Experiment). Two payloads have been built. One called PASTEL (PASsager de TELecommunication) has been embarked on the French Earth observation satellite SPOT4 which has been launched successfully in March 1998. The future European experimental data relay satellite ARTEMIS (Advanced Relay and TEchnology MISsion), which will route the data to ground, will carry the OPALE terminal (Optical Payload Experiment). The European Space Agency is responsible for the operation of both terminals. Due to the complexity and experimental character of this new optical technology, the development, preparation and validation of the ground segment control facilities required a long series of technical and operational qualification tests. This paper is presenting the operations concept and the early results of the PASTEL in orbit operations.

  13. PIRATE: A Remotely Operable Telescope Facility for Research and Education

    Science.gov (United States)

    Holmes, S.; Kolb, U.; Haswell, C. A.; Burwitz, V.; Lucas, R. J.; Rodriguez, J.; Rolfe, S. M.; Rostron, J.; Barker, J.

    2011-10-01

    We introduce PIRATE, a new remotely operable telescope facility for use in research and education, constructed from off-the-shelf hardware, operated by The Open University. We focus on the PIRATE Mark 1 operational phase, in which PIRATE was equipped with a widely used 0.35 m Schmidt-Cassegrain system (now replaced with a 0.425 m corrected Dall-Kirkham astrograph). Situated at the Observatori Astronòmic de Mallorca, PIRATE is currently used to follow up potential transiting extrasolar planet candidates produced by the SuperWASP North experiment, as well as to hunt for novae in M31 and other nearby galaxies. It is operated by a mixture of commercially available software and proprietary software developed at the Open University. We discuss problems associated with performing precision time-series photometry when using a German Equatorial Mount, investigating the overall performance of such off-the-shelf solutions in both research and teaching applications. We conclude that PIRATE is a cost-effective research facility, and it also provides exciting prospects for undergraduate astronomy. PIRATE has broken new ground in offering practical astronomy education to distance-learning students in their own homes.

  14. The ITER Neutral Beam Test Facility towards SPIDER operation

    Science.gov (United States)

    Toigo, V.; Dal Bello, S.; Gaio, E.; Luchetta, A.; Pasqualotto, R.; Zaccaria, P.; Bigi, M.; Chitarin, G.; Marcuzzi, D.; Pomaro, N.; Serianni, G.; Agostinetti, P.; Agostini, M.; Antoni, V.; Aprile, D.; Baltador, C.; Barbisan, M.; Battistella, M.; Boldrin, M.; Brombin, M.; Dalla Palma, M.; De Lorenzi, A.; Delogu, R.; De Muri, M.; Fellin, F.; Ferro, A.; Gambetta, G.; Grando, L.; Jain, P.; Maistrello, A.; Manduchi, G.; Marconato, N.; Pavei, M.; Peruzzo, S.; Pilan, N.; Pimazzoni, A.; Piovan, R.; Recchia, M.; Rizzolo, A.; Sartori, E.; Siragusa, M.; Spada, E.; Spagnolo, S.; Spolaore, M.; Taliercio, C.; Valente, M.; Veltri, P.; Zamengo, A.; Zaniol, B.; Zanotto, L.; Zaupa, M.; Boilson, D.; Graceffa, J.; Svensson, L.; Schunke, B.; Decamps, H.; Urbani, M.; Kushwah, M.; Chareyre, J.; Singh, M.; Bonicelli, T.; Agarici, G.; Garbuglia, A.; Masiello, A.; Paolucci, F.; Simon, M.; Bailly-Maitre, L.; Bragulat, E.; Gomez, G.; Gutierrez, D.; Mico, G.; Moreno, J.-F.; Pilard, V.; Chakraborty, A.; Baruah, U.; Rotti, C.; Patel, H.; Nagaraju, M. V.; Singh, N. P.; Patel, A.; Dhola, H.; Raval, B.; Fantz, U.; Fröschle, M.; Heinemann, B.; Kraus, W.; Nocentini, R.; Riedl, R.; Schiesko, L.; Wimmer, C.; Wünderlich, D.; Cavenago, M.; Croci, G.; Gorini, G.; Rebai, M.; Muraro, A.; Tardocchi, M.; Hemsworth, R.

    2017-08-01

    SPIDER is one of two projects of the ITER Neutral Beam Test Facility under construction in Padova, Italy, at the Consorzio RFX premises. It will have a 100 keV beam source with a full-size prototype of the radiofrequency ion source for the ITER neutral beam injector (NBI) and also, similar to the ITER diagnostic neutral beam, it is designed to operate with a pulse length of up to 3600 s, featuring an ITER-like magnetic filter field configuration (for high extraction of negative ions) and caesium oven (for high production of negative ions) layout as well as a wide set of diagnostics. These features will allow a reproduction of the ion source operation in ITER, which cannot be done in any other existing test facility. SPIDER realization is well advanced and the first operation is expected at the beginning of 2018, with the mission of achieving the ITER heating and diagnostic NBI ion source requirements and of improving its performance in terms of reliability and availability. This paper mainly focuses on the preparation of the first SPIDER operations—integration and testing of SPIDER components, completion and implementation of diagnostics and control and formulation of operation and research plan, based on a staged strategy.

  15. A Guide for Planning Facilities for Occupational Preparation Programs in Laboratory Animal Science Technology. Interim Report. Research 27.

    Science.gov (United States)

    Colling, Walter E.; Farnsworth, Wilbur M.

    The major purpose of this guide is to elicit the necessary information for the writing of educational specifications for facilities to house career programs in laboratory animal science technology. The guide is also designed to: (1) assist planners in formation of creative solutions to the housing of desired educational programs, (2) prevent…

  16. Five years operating experience at the Fast Flux Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Baumhardt, R. J.; Bechtold, R. A.

    1987-04-01

    The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.

  17. SSBRP User Operations Facility (UOF) Overview and Development Strategy

    Science.gov (United States)

    Picinich, Lou; Stone, Thom; Sun, Charles; Windrem, May; Givens, John J. (Technical Monitor)

    1995-01-01

    This paper will present the Space Station Biological Research Project (SSBRP) User Operations Facility (UOF) architecture and development strategy. A major element of the UOF at NASA Ames Research Center, the Communication and Data System (CDS) will be the primary focus of the discussions. CDS operational, telescience, security, and development objectives will be discussed along with CDS implementation strategy. The implementation strategy discussions will include: Object Oriented Analysis & Design, System & Software Prototyping, and Technology Utilization. A CDS design overview that includes: CDS Context Diagram, CDS Architecture, Object Models, Use Cases, and User Interfaces will also be presented. CDS development brings together "cutting edge" technologies and techniques such as: object oriented development, network security, multimedia networking, web-based data distribution, JAVA, and graphical user interfaces. Use of these "cutting edge" technologies and techniques translates directly to lower development and operations costs.

  18. Report of the Task Group on operation Department of Energy tritium facilities

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    This report discusses the following topics on the operation of DOE Tritium facilities: Environment, Safety, and Health Aspects of Tritium; Management of Operations and Maintenance Functions; Safe Shutdown of Tritium Facilities; Management of the Facility Safety Envelope; Maintenance of Qualified Tritium Handling Personnel; DOE Tritium Management Strategy; Radiological Control Philosophy; Implementation of DOE Requirements; Management of Tritium Residues; Inconsistent Application of Requirements for Measurement of Tritium Effluents; Interdependence of Tritium Facilities; Technical Communication among Facilities; Incorporation of Confinement Technologies into New Facilities; Operation/Management Requirements for New Tritium Facilities; and Safety Management Issues at Department of Energy Tritium Facilities.

  19. Personnel Access Control System Evaluation for National Ignition Facility Operations

    Energy Technology Data Exchange (ETDEWEB)

    Altenbach, T; Brereton, S.; Hermes, G.; Singh, M.

    2001-06-01

    The purpose of this document is to analyze the baseline Access Control System for the National Ignition Facility (NIF), and to assess its effectiveness at controlling access to hazardous locations during full NIF operations. It reviews the various hazards present during a NIF shot sequence, and evaluates the effectiveness of the applicable set of controls at preventing access while the hazards are present. It considers only those hazards that could potentially be lethal. In addition, various types of technologies that might be applicable at NIF are reviewed, as are systems currently in use at other facilities requiring access control for safety reasons. Recommendations on how this system might be modified to reduce risk are made.

  20. Remote operation of Defense Waste Processing Facility sampling stations

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, D E; Gunnels, D L

    1985-01-01

    A full-scale liquid sampling station mockup for the Defense Waste Processing Facility (DWPF) at the Savannah River Laboratory (SRL) demonstrated successful remote operation and replacement of all valves and instruments using master/slave manipulators in a clean atmosphere before similar stations are placed in a radioactive cell. Testing of the sample stations demonstrated the limitations of the manipulators which resulted in minor design changes that were easily accomplished in a clean cell. These same changes would have been difficult and very costly to make in a radioactive environment. 6 figs.

  1. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Favalli, A., E-mail: afavalli@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM (United States); Vo, D. [Los Alamos National Laboratory, Los Alamos, NM (United States); Grogan, B. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Jansson, P. [Uppsala University, Uppsala (Sweden); Liljenfeldt, H. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Mozin, V. [Lawrence Livermore National Laboratory, Livermore, CA (United States); Schwalbach, P. [European Commission, DG Energy, Euratom Safeguards Luxemburg, Luxemburg (Luxembourg); Sjöland, A. [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Tobin, S.J.; Trellue, H. [Los Alamos National Laboratory, Los Alamos, NM (United States); Vaccaro, S. [European Commission, DG Energy, Euratom Safeguards Luxemburg, Luxemburg (Luxembourg)

    2016-06-01

    The purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute {sup 137}Cs count rate and the {sup 154}Eu/{sup 137}Cs, {sup 134}Cs/{sup 137}Cs, {sup 106}Ru/{sup 137}Cs, and {sup 144}Ce/{sup 137}Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

  2. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

    Science.gov (United States)

    Favalli, A.; Vo, D.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S. J.; Trellue, H.; Vaccaro, S.

    2016-06-01

    The purpose of the Next Generation Safeguards Initiative (NGSI)-Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity's behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

  3. Management aspects of Gemini's base facility operations project

    Science.gov (United States)

    Arriagada, Gustavo; Nitta, Atsuko; Adamson, A. J.; Nunez, Arturo; Serio, Andrew; Cordova, Martin

    2016-08-01

    Gemini's Base Facilities Operations (BFO) Project provided the capabilities to perform routine nighttime operations without anyone on the summit. The expected benefits were to achieve money savings and to become an enabler of the future development of remote operations. The project was executed using a tailored version of Prince2 project management methodology. It was schedule driven and managing it demanded flexibility and creativity to produce what was needed, taking into consideration all the constraints present at the time: Time available to implement BFO at Gemini North (GN), two years. The project had to be done in a matrix resources environment. There were only three resources assigned exclusively to BFO. The implementation of new capabilities had to be done without disrupting operations. And we needed to succeed, introducing the new operational model that implied Telescope and instrumentation Operators (Science Operations Specialists - SOS) relying on technology to assess summit conditions. To meet schedule we created a large number of concurrent smaller projects called Work Packages (WP). To be reassured that we would successfully implement BFO, we initially spent a good portion of time and effort, collecting and learning about user's needs. This was done through close interaction with SOSs, Observers, Engineers and Technicians. Once we had a clear understanding of the requirements, we took the approach of implementing the "bare minimum" necessary technology that would meet them and that would be maintainable in the long term. Another key element was the introduction of the "gradual descent" concept. In this, we increasingly provided tools to the SOSs and Observers to prevent them from going outside the control room during nighttime operations, giving them the opportunity of familiarizing themselves with the new tools over a time span of several months. Also, by using these tools at an early stage, Engineers and Technicians had more time for debugging

  4. 78 FR 29393 - University of Missouri-Columbia Facility Operating License No. R-103

    Science.gov (United States)

    2013-05-20

    ... COMMISSION University of Missouri--Columbia Facility Operating License No. R-103 AGENCY: Nuclear Regulatory...) is considering an application for the renewal of Facility Operating License No. R-103 (``Application... application for the renewal of Facility Operating License No. R-103, which, currently authorizes the...

  5. 7 CFR 70.110 - Requirements for sanitation, facilities, and operating procedures in official plants.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Requirements for sanitation, facilities, and operating... Requirements for sanitation, facilities, and operating procedures in official plants. (a) The requirements for sanitation, facilities, and operating procedures in official plants shall be the applicable provisions...

  6. Operation and Maintenance of Water Pollution Control Facilities: A WPCF White Paper.

    Science.gov (United States)

    Hill, William R.; And Others

    1979-01-01

    Presented are the recommendations of the Water Pollution Control Federation for operation and maintenance consideration during the planning design, construction, and operation of wastewater treatment facilities. (CS)

  7. Operation and Maintenance of Water Pollution Control Facilities: A WPCF White Paper.

    Science.gov (United States)

    Hill, William R.; And Others

    1979-01-01

    Presented are the recommendations of the Water Pollution Control Federation for operation and maintenance consideration during the planning design, construction, and operation of wastewater treatment facilities. (CS)

  8. Regulation study for the facility control system design at the Facility Operations Center at TA55

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-16

    NMT-8 is proposing to upgrade the existing Facility Control System (FCS) located within the Facility Operations Center (FOC) at the TA-55 Plutonium Processing and Handling Facility (PPHF). The FCS modifications will upgrade the existing electronics to provide better reliability of system functions. Changes include replacement of the FCS computers and field multiplex units which are used for transmitting systems data. Data collected at the FCS include temperature, pressure, contact closures, etc., and are used for monitoring and/or control of key systems at TA-55. Monitoring is provided for the electrical power system status, PF-4 HVAC air balance status (Static Differential pressure), HVAC fan system status, site chill water return temperature, fire system information, and radioactive constant air monitors alarm information, site compressed air pressure and other key systems used at TA-55. Control output signals are provided for PF-4 HVAC systems, and selected alarms for criticality, fire, loss of pressure in confinement systems. A detailed description of the FCS modifications is provided in Section 2.

  9. 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.

  10. National NIF Diagnostic Program Interim Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Warner, B

    2002-04-25

    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

  11. Augmented reality in the slaughterhouse - A future operation facility?

    Directory of Open Access Journals (Sweden)

    Lars Bager Christensen

    2016-05-01

    Full Text Available The present case study sums up the results of an initial attempt to adapt the emerging technology of Augmented Reality (AR to support routine operations performed in Danish slaughterhouse facilities. Our aim is to reveal the applicability of off-the-shelf components and programming platforms to the trimming and boning process for pork bellies. The AR technology has demonstrated lucrative applications in industrial QA procedures and even farm management applications (Wu, Xiao & Guo, 2013 appear to benefit from applying the technology. With the ever-increasing turnover of labour in the meat industry, we investigate here the application of AR-assisted production procedures as a potential management tool and support tool to assist a novice operator in a specific trimming operation. The case study concerns the trimming and cutting of pork bellies, a widely used and versatile procedure in the Danish pork meat industry. Many similar belly products made from similar raw materials are exported to specific customers and markets. Due to biological variability between pigs, final products are produced with variability in yield, despite the fact that the final product qualities are similar. The best management option is to use the correct raw material for each product, thus generating fewer by-products and increasing the volume/weight of the final product. The application of AR to the cutting operation appears to increase the production yield; however, the operators need training in order to benefit fully from the efficiency and capacity of the application rather than adopting the standard procedure of oral communication of instructions.

  12. 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.

  13. Umatilla Hatchery Satellite Facilities Operation and Maintenance; 1995 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Rowan, Gerald D.

    1996-05-01

    The Confederated Tribes of the Umatilla Indian Reservoir (CTUIR) and Oregon Department of Fish and Wildlife (ODFW) are cooperating in a joint effort to enhance steelhead and re-establish salmon runs in the Umatilla River Basin. As an integral part of this program, Bonifer Pond, Minthorn Springs, Imeques C-mem-ini-kem and Thornhollow facilities are operated for acclimation and release of juvenile summer steelhead (Oncorhynchus mykiss), fall and spring chinook salmon (O. tshawytscha) and coho salmon (O. kisutch). Minthorn is also used for holding and spawning adult summer steelhead, fall chinook and coho salmon. Personnel from the ODFW Eastern Oregon Fish Pathology Laboratory in La Grande took samples of tissues and reproductive fluids from Umatilla River summer steelhead and coho salmon broodstock for monitoring and evaluation purposes. Coded-wire tag recovery information was accessed to determine the contribution of Umatilla river releases to ocean, Columbia River and Umatilla River fisheries.

  14. MagLev Cobra: Test Facilities and Operational Experiments

    Science.gov (United States)

    Sotelo, G. G.; Dias, D. H. J. N.; de Oliveira, R. A. H.; Ferreira, A. C.; De Andrade, R., Jr.; Stephan, R. M.

    2014-05-01

    The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa2Cu3O7-δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

  15. Justification for Continued Operation of the SRS Saltstone Facility (Z-Area)

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, W.A.

    1999-01-20

    Saltstone Production and Disposal Facilities (Z-Area) are a part of the Defense Waste Processing Facilities (DWPF). Z-Area facilities are just one segment of an integrated waste management and disposal system located at the Savannah River Site (SRS). The bases for the Justification of Continuing Operations (JCO) of the Saltstone Production and Disposal Facilities (Z-Area) at SRS are provided.

  16. Transuranic (Tru) waste volume reduction operations at a plutonium facility

    Energy Technology Data Exchange (ETDEWEB)

    Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

    2010-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos

  17. 26 CFR 1.132-7 - Employer-operated eating facilities.

    Science.gov (United States)

    2010-04-01

    ... facility that bears the same proportion to such total labor cost as time spent on the premises bears to total time spent performing services relating to the facility is included in direct operating costs. For... of meals provided to employees at an employer-operated eating facility for employees is excludable...

  18. 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.)

  19. WIPP Remote Handled Waste Facility: Performance Dry Run Operations

    Energy Technology Data Exchange (ETDEWEB)

    Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

    2003-02-24

    The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

  20. Development and operation of a mobile test facility for education

    Science.gov (United States)

    Davis, Christopher T.

    The automotive industry saw a large shift towards vehicle electrification after the turn of the century. It became necessary to ensure that new and existing engineers were qualified to design and calibrate these new systems. To ensure this training, Michigan Tech received a grant to develop a curriculum based around vehicle electrification. As part of this agenda, the Michigan Tech Mobile Laboratory was developed to provide hands-on training for professional engineers and technicians in hybrid electric vehicles and vehicle electrification. The Mobile Lab has since then increased the scope of the delivered curriculum to include other automotive areas and even customizable course content to meet specific needs. This thesis outlines the development of the Mobile Laboratory and its powertrain test facilities. The focus of this thesis is to discuss the different hardware and software systems within the lab and test cells. Detailed instructions on the operation and maintenance of each of the systems are discussed. In addition, this thesis outlines the setup and operation of the necessary equipment for several of the experiments for the on and off campus courses and seminars.

  1. 40 CFR 270.72 - Changes during interim status.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Changes during interim status. 270.72... (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Interim Status § 270.72 Changes during interim status. (a) Except as provided in paragraph (b), the owner or operator of...

  2. 40 CFR 270.70 - Qualifying for interim status.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Qualifying for interim status. 270.70... (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Interim Status § 270.70 Qualifying for interim status. (a) Any person who owns or operates an “existing HWM facility” or a...

  3. 200 Area Interim Storage Area Technical Safety Requirements

    Energy Technology Data Exchange (ETDEWEB)

    CARRELL, R.D.

    2000-03-15

    The 200 Area Interim Storage Area Technical Safety Requirements define administrative controls and design features required to ensure safe operation during receipt and storage of canisters containing spent nuclear fuel. This document is based on the 200 Area Interim Storage Area, Annex D, Final Safety Analysis Report which contains information specific to the 200 Area Interim Storage Area.

  4. Cold Neutron Research Facility begins operating at NIST

    Energy Technology Data Exchange (ETDEWEB)

    Zeman, E.J.

    1991-09-01

    Steady-state neutron beams are generally produced by fission in a nuclear reactor, whereas pulsed beams come from spallation neutron sources. Beams from a reactor have a distribution of wavelengths that is roughly Maxwellian, with a peak wavelength that depends on the temperature of the moderator that surrounds the fuel. Cold neutrons can be selected from the low-energy tail of the distribution, but the flux drops as 1/{lambda}{sup 4}. However, by shifting the whole spectrum to longer wavelengths one can dramatically increase the cold neutron flux. This is achieved by replacing part of the core moderator with a cold moderator, or cold source,' such as liquid deuterium (at about 30 K) or D{sub 2}O ice (at about 40 K). Neutrons lose energy to the moderator through collisions, producing a shifted spectrum from which one can select lower-energy neutrons with a roughly ten-fold improvement in the flux. Neutrons exhibit optical behavior such as refraction and total reflection. Thus one can use neutron guides - analogous to optical fibers - to conduct intense beams of neutrons from the reactor into a large experimental hall, dubbed a guide hall,' where background radiation is low. The Cold Neutron Research Facility was finally funded in 1987 and opened its doors this past June. CNRF is located at the 20-MW NIST research reactor, which began continuous operation in 1969. With some foresight, the designers of the original reactor allowed space for the addition of a cryogenic moderator, which is only now being exploited. NIST will develop 10 experimental stations for use by the research science community. Additional help in financing the facility comes from participating research teams made up of groups from industry, academe and government.

  5. Grande Ronde Endemic Spring Chinook Salmon Supplementation Program : Facility Operation and Maintenance Facilities, Annual Report 2003.

    Energy Technology Data Exchange (ETDEWEB)

    McLean, Michael L.; Seeger, Ryan; Hewitt, Laurie (Confederated Tribes of the Umatilla Indian Reservation, Department of Natural Resources, Pendleton, OR)

    2004-01-01

    Anadromous salmonid stocks have declined in both the Grande Ronde River Basin (Lower Snake River Compensation Plan (LSRCP) Status Review Symposium 1998) and in the entire Snake River Basin (Nehlsen et al. 1991), many to the point of extinction. The Grande Ronde River Basin historically supported large populations of fall and spring chinook (Oncorhynchus tshawytscha), sockeye (O. nerka), and coho (O. kisutch) salmon and steelhead trout (O. mykiss) (Nehlsen et al. 1991). The decline of chinook salmon and steelhead populations and extirpation of coho and sockeye salmon in the Grande Ronde River Basin was, in part, a result of construction and operation of hydroelectric facilities, over fishing, and loss and degradation of critical spawning and rearing habitat in the Columbia and Snake River basins (Nehlsen et al. 1991). Hatcheries were built in Oregon, Washington and Idaho under the Lower Snake River Compensation Plan (LSRCP) to compensate for losses of anadromous salmonids due to the construction and operation of the lower four Snake River dams. Lookingglass Hatchery (LGH) on Lookingglass Creek, a tributary of the Grande Ronde River, was completed under LSRCP in 1982 and has served as the main incubation and rearing site for chinook salmon programs for Grande Ronde and Imnaha rivers in Oregon. Despite these hatchery programs, natural spring chinook populations continued to decline resulting in the National Marine Fisheries Service (NMFS) listing Snake River spring/summer chinook salmon as ''threatened'' under the federal Endangered Species Act (1973) on 22 April 1992. Continuing poor escapement levels and declining population trends indicated that Grande Ronde River basin spring chinook salmon were in imminent danger of extinction. These continuing trends led fisheries co-managers in the basin to initiate the Grande Ronde Endemic Spring Chinook Salmon Supplementation Program (GRESCSSP) in order to prevent extinction and preserve options for use of

  6. Annual Report of Radioactive Waste Facilities Operation in 2015

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; DIAO; Lei; SHEN; Zheng; LI; Wen-ge

    2015-01-01

    301of the Department of Radiochemistry,is in charge of the management of radioactive waste and the safety of the relative facilities to meet the request of the scientific research production.There are 16radioactive waste facilities,including9facilities which are closed and monitored

  7. Medicare program; conditions for payment of power mobility devices, including power wheelchairs and power-operated vehicles. Interim final rule with comment period.

    Science.gov (United States)

    2005-08-26

    This interim final rule conforms our regulations to section 302(a)(2)(E)(iv) of the Medicare Prescription Drug, Improvement, and Modernization Act of 2003 (Pub. L. 108-173). This rule defines the term power mobility devices (PMDs) as power wheelchairs and power operated vehicles (POVs or scooters). It sets forth revised conditions for Medicare payment of PMDs and defines who may prescribe PMDs. This rule also requires a face-to-face examination of the beneficiary by the physician or treating practitioner and a PMD prescription and pertinent parts of the medical record that the durable medical equipment supplier maintains in records and makes available to CMS or its agents upon request. Finally, this rule discusses CMS' policy on documentation that may be requested by CMS or its agents to support a Medicare claim for payment, as well as the elimination for the Certificate of Medical Necessity for PMDs.

  8. Environmental Impact Statement. March 2011. Interim storage, encapsulation and final disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    An Environmental Impact Statement (EIS) shall be prepared and submitted along with applications for permissibility and a licence under the Environmental Code and a licence under the Nuclear Activities Act for new nuclear facilities. This Environmental Impact Statement has been prepared by Svensk Kaernbraenslehantering AB (the Swedish Nuclear Fuel and Waste Management Co, SKB) to be included in the licence applications for continued operation of Clab (central interim storage facility for spent nuclear fuel) in Simpevarp in Oskarshamn Municipality and construction and operation of facilities for encapsulation (integrated with Clab) and final disposal of spent nuclear fuel in Forsmark in Oesthammar Municipality

  9. Developing operating procedures for a low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  10. 77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

    Science.gov (United States)

    2012-05-03

    ... COMMISSION Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY... License No. R- 112, held by Reed College (the licensee), which authorizes continued operation of the Reed... renewed Facility Operating License No. R-112 will expire 20 years from its date of issuance. The...

  11. Quality assurance in the enriched uranium operations NDA facility

    Energy Technology Data Exchange (ETDEWEB)

    May, P.K.; Ceo, R.N. [Oak Ridge Y-12 Plant, TN (United States)

    1997-11-01

    The Nondestructive Analysis (NDA) Facility at the Oak Ridge Y-12 Plant has characterized process wastes for Enriched Uranium Operations since 1978. Since that time, over 50,000 items have been analyzed. Analysis results are used to determine whether or not recovery of uranium from process wastes is economically feasible. Our instrument complement includes one large segmented gamma scanner (SGS), two smaller SGS, two solution assay systems (SAS), and Active Well Coincidence Counter (AWCC). The large SGS is used for analyzing High Efficiency Particulate Air (HEPA) filters ant 208-L drums filled with combustible contaminated waste. The smaller SGS are used to analyze 4-L containers of ash and leached residues. The SAS are used to analyze 125 ml bottles of aqueous or organic waste solutions that may contain uranium. The gamma-based NDA techniques are used to identify which process wastes can be discarded, and which must be recycled. The AWCC is used to analyze high-density materials which are not amenable to gamma-ray analysis. 1 ref., 4 figs.

  12. High Performance Computing Facility Operational Assessment 2015: Oak Ridge Leadership Computing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Barker, Ashley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bernholdt, David E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bland, Arthur S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Gary, Jeff D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Hack, James J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; McNally, Stephen T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Rogers, James H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Smith, Brian E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Straatsma, T. P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Sukumar, Sreenivas Rangan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Thach, Kevin G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Tichenor, Suzy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Vazhkudai, Sudharshan S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Wells, Jack C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility

    2016-03-01

    Oak Ridge National Laboratory’s (ORNL’s) Leadership Computing Facility (OLCF) continues to surpass its operational target goals: supporting users; delivering fast, reliable systems; creating innovative solutions for high-performance computing (HPC) needs; and managing risks, safety, and security aspects associated with operating one of the most powerful computers in the world. The results can be seen in the cutting-edge science delivered by users and the praise from the research community. Calendar year (CY) 2015 was filled with outstanding operational results and accomplishments: a very high rating from users on overall satisfaction that ties the highest-ever mark set in CY 2014; the greatest number of core-hours delivered to research projects; the largest percentage of capability usage since the OLCF began tracking the metric in 2009; and success in delivering on the allocation of 60, 30, and 10% of core hours offered for the INCITE (Innovative and Novel Computational Impact on Theory and Experiment), ALCC (Advanced Scientific Computing Research Leadership Computing Challenge), and Director’s Discretionary programs, respectively. These accomplishments, coupled with the extremely high utilization rate, represent the fulfillment of the promise of Titan: maximum use by maximum-size simulations. The impact of all of these successes and more is reflected in the accomplishments of OLCF users, with publications this year in notable journals Nature, Nature Materials, Nature Chemistry, Nature Physics, Nature Climate Change, ACS Nano, Journal of the American Chemical Society, and Physical Review Letters, as well as many others. The achievements included in the 2015 OLCF Operational Assessment Report reflect first-ever or largest simulations in their communities; for example Titan enabled engineers in Los Angeles and the surrounding region to design and begin building improved critical infrastructure by enabling the highest-resolution Cybershake map for Southern

  13. Umatilla Hatchery Satellite Facilities; Operations and Maintenance, Annual Report 2001.

    Energy Technology Data Exchange (ETDEWEB)

    Rowan, Gerald

    2003-05-01

    The Confederated Tribes of the Umatilla Indian Reservation (CTUIR) and Oregon Department of Fish and Wildlife (ODFW) are cooperating in a joint effort to enhance steelhead and re-establish salmon runs in the Umatilla River Basin. As an integral part of this program, Bonifer Pond, Minthorn Springs, Imeques C-mem-ini-kem, Thornhollow and Pendleton satellite facilities are operated for acclimation and release of juvenile summer steelhead (Oncorhynchus mykiss), fall and spring chinook salmon (O. tshawytscha) and coho salmon (O. kisutch). Minthorn is also used for holding and spawning adult summer steelhead and Three Mile Dam and South Fork Walla Walla facilities are used for holding and spawning chinook salmon. In some years, Three Mile Dam may also be used for holding and spawning coho salmon. In the spring of 2002, summer steelhead were acclimated and released at Bonifer Pond (54,917), Minthorn Springs (47,521), and Pendleton (54,366). Yearling coho (1,621,857) were also acclimated and released at Pendleton. Yearling spring chinook salmon (876,121) were acclimated and released at Imeques C-mem-ini-kem. At Thornhollow, 520,564 yearling fall chinook and 307,194 subyearling fall chinook were acclimated. In addition, 104,908 spring chinook were transported to Imeques C-mem-ini-kem in November for release in the spring of 2003. CTUIR and ODFW personnel monitored the progress of outmigration for juvenile releases at the Westland Canal juvenile facility. Nearly all juveniles released in the spring migrated downstream prior to the trap being opened in early July. A total of 100 unmarked and 10 marked summer steelhead were collected for broodstock at Three Mile Dam from September 21, 2001, through April 2, 2002. An estimated 180,955 green eggs were taken from 36 females and were transferred to Umatilla Hatchery for incubation and rearing. A total of 560 adult and 26 jack spring chinook salmon were collected for broodstock at Three Mile Dam from April 22 through June 12, 2002

  14. The Wallops Flight Facility Rapid Response Range Operations Initiative

    Science.gov (United States)

    Underwood, Bruce E.; Kremer, Steven E.

    2004-01-01

    While the dominant focus on short response missions has appropriately centered on the launch vehicle and spacecraft, often overlooked or afterthought phases of these missions have been launch site operations and the activities of launch range organizations. Throughout the history of organized spaceflight, launch ranges have been the bane of flight programs as the source of expense, schedule delays, and seemingly endless requirements. Launch Ranges provide three basic functions: (1) provide an appropriate geographical location to meet orbital other mission trajectory requirements, (2) provide project services such as processing facilities, launch complexes, tracking and data services, and expendable products, and (3) assure safety and property protection to participating personnel and third-parties. The challenge with which launch site authorities continuously struggle, is the inherent conflict arising from projects whose singular concern is execution of their mission, and the range s need to support numerous simultaneous customers. So, while tasks carried out by a launch range committed to a single mission pale in comparison to efforts of a launch vehicle or spacecraft provider and could normally be carried out in a matter of weeks, major launch sites have dozens of active projects separate sponsoring organizations. Accommodating the numerous tasks associated with each mission, when hardware failures, weather, maintenance requirements, and other factors constantly conspire against the range resource schedulers, make the launch range as significant an impediment to responsive missions as launch vehicles and their cargo. The obvious solution to the launch site challenge was implemented years ago when the Department of Defense simply established dedicated infrastructure and personnel to dedicated missions, namely an Inter Continental Ballistic Missile. This however proves to be prohibitively expensive for all but the most urgent of applications. So the challenge

  15. High Performance Computing Facility Operational Assessment, FY 2011 Oak Ridge Leadership Computing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Baker, Ann E [ORNL; Bland, Arthur S Buddy [ORNL; Hack, James J [ORNL; Barker, Ashley D [ORNL; Boudwin, Kathlyn J. [ORNL; Kendall, Ricky A [ORNL; Messer, Bronson [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL; Wells, Jack C [ORNL; White, Julia C [ORNL

    2011-08-01

    Oak Ridge National Laboratory's Leadership Computing Facility (OLCF) continues to deliver the most powerful resources in the U.S. for open science. At 2.33 petaflops peak performance, the Cray XT Jaguar delivered more than 1.5 billion core hours in calendar year (CY) 2010 to researchers around the world for computational simulations relevant to national and energy security; advancing the frontiers of knowledge in physical sciences and areas of biological, medical, environmental, and computer sciences; and providing world-class research facilities for the nation's science enterprise. Scientific achievements by OLCF users range from collaboration with university experimentalists to produce a working supercapacitor that uses atom-thick sheets of carbon materials to finely determining the resolution requirements for simulations of coal gasifiers and their components, thus laying the foundation for development of commercial-scale gasifiers. OLCF users are pushing the boundaries with software applications sustaining more than one petaflop of performance in the quest to illuminate the fundamental nature of electronic devices. Other teams of researchers are working to resolve predictive capabilities of climate models, to refine and validate genome sequencing, and to explore the most fundamental materials in nature - quarks and gluons - and their unique properties. Details of these scientific endeavors - not possible without access to leadership-class computing resources - are detailed in Section 4 of this report and in the INCITE in Review. Effective operations of the OLCF play a key role in the scientific missions and accomplishments of its users. This Operational Assessment Report (OAR) will delineate the policies, procedures, and innovations implemented by the OLCF to continue delivering a petaflop-scale resource for cutting-edge research. The 2010 operational assessment of the OLCF yielded recommendations that have been addressed (Reference Section 1) and

  16. Facility Operations 1993 fiscal year work plan: WBS 1.3.1

    Energy Technology Data Exchange (ETDEWEB)

    1992-11-01

    The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO{sub 3}) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP).

  17. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed... No. DPR-46, issued to Nebraska Public Power District (the licensee), for operation of the...

  18. 75 FR 11202 - Southern Nuclear Operating Company; Notice of Consideration of Issuance of Amendment to Facility...

    Science.gov (United States)

    2010-03-10

    ... COMMISSION Southern Nuclear Operating Company; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a... significant hazards consideration. Under the Commission's regulations in Title 10 of the Code of...

  19. 9 CFR 354.210 - Minimum standards for sanitation, facilities, and operating procedures in official plants.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Minimum standards for sanitation, facilities, and operating procedures in official plants. 354.210 Section 354.210 Animals and Animal Products... sanitation, facilities, and operating procedures in official plants. The provisions of §§ 354.210 to...

  20. Confined Feeding Operations - CONFINED_FEEDING_OPERATIONS_IDEM_IN: Confined Feeding Operation Facilities in Indiana (Indiana Department of Environmental Management, Point Shapefile)

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — CONFINED_FEEDING_OPERATIONS_IDEM_IN is a point shapefile that contains confined feeding operation facility locations in Indiana, provided by personnel of Indiana...

  1. High Performance Computing Facility Operational Assessment, FY 2010 Oak Ridge Leadership Computing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bland, Arthur S Buddy [ORNL; Hack, James J [ORNL; Baker, Ann E [ORNL; Barker, Ashley D [ORNL; Boudwin, Kathlyn J. [ORNL; Kendall, Ricky A [ORNL; Messer, Bronson [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL; White, Julia C [ORNL

    2010-08-01

    Oak Ridge National Laboratory's (ORNL's) Cray XT5 supercomputer, Jaguar, kicked off the era of petascale scientific computing in 2008 with applications that sustained more than a thousand trillion floating point calculations per second - or 1 petaflop. Jaguar continues to grow even more powerful as it helps researchers broaden the boundaries of knowledge in virtually every domain of computational science, including weather and climate, nuclear energy, geosciences, combustion, bioenergy, fusion, and materials science. Their insights promise to broaden our knowledge in areas that are vitally important to the Department of Energy (DOE) and the nation as a whole, particularly energy assurance and climate change. The science of the 21st century, however, will demand further revolutions in computing, supercomputers capable of a million trillion calculations a second - 1 exaflop - and beyond. These systems will allow investigators to continue attacking global challenges through modeling and simulation and to unravel longstanding scientific questions. Creating such systems will also require new approaches to daunting challenges. High-performance systems of the future will need to be codesigned for scientific and engineering applications with best-in-class communications networks and data-management infrastructures and teams of skilled researchers able to take full advantage of these new resources. The Oak Ridge Leadership Computing Facility (OLCF) provides the nation's most powerful open resource for capability computing, with a sustainable path that will maintain and extend national leadership for DOE's Office of Science (SC). The OLCF has engaged a world-class team to support petascale science and to take a dramatic step forward, fielding new capabilities for high-end science. This report highlights the successful delivery and operation of a petascale system and shows how the OLCF fosters application development teams, developing cutting-edge tools

  2. 34 CFR 395.30 - The location and operation of vending facilities for blind vendors on Federal property.

    Science.gov (United States)

    2010-07-01

    ... 34 Education 2 2010-07-01 2010-07-01 false The location and operation of vending facilities for... § 395.30 The location and operation of vending facilities for blind vendors on Federal property. (a... facilities on any Federal property. (b) Any limitation on the location or operation of a vending facility for...

  3. Impacts of ramping inflexibility of conventional generators on strategic operation of energy storage facilities

    DEFF Research Database (Denmark)

    Nasrolahpour, Ehsan; Kazempour, Jalal; Zareipour, Hamidreza

    2016-01-01

    This paper proposes an approach to assist a pricemaker merchant energy storage facility in making its optimal operation decisions. The facility operates in a pool-based electricity market, where the ramping capability of other resources is limited. Also, wind power resources exist in the system....... The merchant facility seeks to maximize its profit through strategic inter-temporal arbitrage decisions, when taking advantage of those ramp limitations. The market operator, on the other hand, aims at maximizing the social welfare under wind power generation uncertainty. Thus, a stochastic bi......-level optimization model is proposed, taking into account the interactions between the storage facility and the market operator, and the existing market opportunities for the storage facility. The proposed bilevel model is then transformed into a Mathematical Program with Equilibrium Constraints (MPEC) that can...

  4. Reducing Operating Costs by Optimizing Space in Facilities

    Science.gov (United States)

    2012-03-01

    consolidation. Until the S-File can talk to other systems and pull the data this analysis must be accomplished manually . 6) Incorporate space efficiency...Reference Manual . Public Works and Government Services Canada. British Columbia. McGregor, Wes. (2000). Facilities Management and the Business of...floor plans listed in Appendix B. AutoCAD 2010 was the software used. Other software suites may differ slightly in method or terminology. Although

  5. Control System and Operation of the Cryogenic Test Facilities for LHC Series Superconducting Magnets

    CERN Document Server

    Axensalva, J; Lamboy, J P; Tovar-Gonzalez, A; Vullierme, B

    2005-01-01

    Prior to their final preparation before installation in the tunnel, the ~1800 series superconducting magnets of the LHC machine will be entirely tested at reception on modular test facilities using dedicated control systems. The test facilities are operated by teams of high-skilled and trained operators. This paper describes the architecture of the control & supervision system of the cryogenic test facilities as well as the tools and management systems developed to help in real time all involved operation teams in order to reach the required industrial production level.

  6. Simulating potential structural and operational changes for Detroit Dam on the North Santiam River, Oregon-Interim Results

    Science.gov (United States)

    Buccola, Norman L.; Rounds, Stewart A.

    2011-01-01

    Prior to operational changes in 2007, Detroit Dam on the North Santiam River in western Oregon had a well-documented effect on downstream water temperature that was problematic for endangered salmonid fish species. In this U.S. Geological Survey study, done in cooperation with the U.S. Army Corps of Engineers, an existing calibrated CE-QUAL-W2 model of Detroit Lake (the impounded waterbody behind Detroit Dam) was used to determine how changes in dam operation or changes to the structural release points of Detroit Dam might affect downstream water temperatures under a range of historical hydrologic and meteorological conditions.

  7. 77 FR 33782 - License Amendment To Construct and Operate New In Situ Leach Uranium Recovery Facility; Uranium...

    Science.gov (United States)

    2012-06-07

    ... COMMISSION License Amendment To Construct and Operate New In Situ Leach Uranium Recovery Facility; Uranium... referenced. The Ludeman facility In Situ Leach Uranium Recovery Project License Amendment Request is... construct and operate a new in situ leach uranium recovery (ISL) facility at its Ludeman facility...

  8. Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Norm Stanley

    2011-02-01

    This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

  9. Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

    Energy Technology Data Exchange (ETDEWEB)

    1982-09-01

    This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report.

  10. 41 CFR 102-74.70 - Are commercial vendors and nonprofit organizations required to operate vending facilities by...

    Science.gov (United States)

    2010-07-01

    ... and nonprofit organizations required to operate vending facilities by permit or contractual... Management Concession Services § 102-74.70 Are commercial vendors and nonprofit organizations required to operate vending facilities by permit or contractual arrangement? Commercial vendors and...

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

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    2000-02-03

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

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

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-07-02

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

  13. 75 FR 19431 - Union Electric Company; Notice of Consideration of Issuance of Amendment to Facility Operating...

    Science.gov (United States)

    2010-04-14

    ... COMMISSION Union Electric Company; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U... amendment request involves no significant hazards consideration. Under the Commission's ] regulations in...

  14. Facility Safety Plan B360 Complex Biohazardous Operations CMLS-412r0

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, G

    2007-01-08

    This Addendum to the Facility Safety Plan (FSP) 360 Complex describes the safety requirements for the safe conduct of all biohazardous research operations in all buildings within the 360 complex program areas. These requirements include all the responsibilities and authorities of building personnel, operational hazards, and environmental concerns and their controls. In addition, this Addendum prescribes facility-specific training requirements and emergency controls, as well as maintenance and quality assurance requirements for ES&H-related building systems.

  15. Microvibration monitoring: some recent experiences in an operating microelectronics facility

    Science.gov (United States)

    Hassett, Kevin

    1992-02-01

    Major construction work is currently underway at Intel''s Aloha, Oregon, campus. Because of concerns about the effects that construction-generated vibration might have on adjacent ongoing microelectronics manufacturing activities, two important steps were taken. The first of these was to establish guidelines that would be followed by the construction contractor to limit vibration disturbance. The second was to install a computer-based monitoring system that would continuously measure the vibration on the floor of the microelectronics manufacturing facility. In this way, the vibration effects of the construction activities would be monitored and adjusted, by modifying procedures, if necessary. The monitoring program is discussed in this paper. The major characteristics of the monitoring system, the placement of the transducers, and the ways in which the data were managed are described. Some typical data are shown and discussed.

  16. Design data package and operating procedures for MSFC solar simulator test facility

    Science.gov (United States)

    1981-01-01

    Design and operational data for the solar simulator test facility are reviewed. The primary goal of the facility is to evaluate the performance capacibility and worst case failure modes of collectors, which utilize either air or liquid transport media. The facility simulates environmental parameters such as solar radiation intensity, solar spectrum, collimation, uniformity, and solar attitude. The facility also simulates wind conditions of velocity and direction, solar system conditions imposed on the collector, collector fluid inlet temperature, and geometric factors of collector tilt and azimuth angles. Testing the simulator provides collector efficiency data, collector time constant, incident angle modifier data, and stagnation temperature values.

  17. 75 FR 71545 - Changes to NARA Facilities' Hours of Operation

    Science.gov (United States)

    2010-11-24

    ... Personnel Records Center archival research room is located at 9700 Page Ave., St. Louis, MO 63132-5100. The... located at 700 Pennsylvania Avenue, NW., Washington, DC 20408. Hours for the Research Center and the Central Research Room are posted at http://www.archives.gov . The exhibit areas' hours of operation are...

  18. Simulation Modeling of a Facility Layout in Operations Management Classes

    Science.gov (United States)

    Yazici, Hulya Julie

    2006-01-01

    Teaching quantitative courses can be challenging. Similarly, layout modeling and lean production concepts can be difficult to grasp in an introductory OM (operations management) class. This article describes a simulation model developed in PROMODEL to facilitate the learning of layout modeling and lean manufacturing. Simulation allows for the…

  19. Simulation Modeling of a Facility Layout in Operations Management Classes

    Science.gov (United States)

    Yazici, Hulya Julie

    2006-01-01

    Teaching quantitative courses can be challenging. Similarly, layout modeling and lean production concepts can be difficult to grasp in an introductory OM (operations management) class. This article describes a simulation model developed in PROMODEL to facilitate the learning of layout modeling and lean manufacturing. Simulation allows for the…

  20. The Influence of Facility Layout on Operations Explored

    NARCIS (Netherlands)

    Zijlstra, E.; Mobach, M.

    2011-01-01

    Purpose – The purpose of this study is to explore the influence of an office canteen layout on operations, specifically on customer behaviour before checkout, waiting times, and congestion. Design/methodology/approach – The current study was made in the context of discovery and exemplification. The

  1. Guidelines for operator competence - Optimising facility management processes; Leitfaden Betreiberkompetenz. Schritt fuer Schritt Facility Management Prozesse optimieren

    Energy Technology Data Exchange (ETDEWEB)

    Moser, R.

    2005-06-15

    This brochure issued by IFMA (International Facility Management Association) Switzerland and the Swiss Federal Office of Energy (SFOE) presents interactive guidelines for energy management in the area of facility management. These guidelines are based on the results of a project carried out by the International Energy Agency's Annex 40 'Operator competence'. The guidelines provide a step-by-step guide from initial analysis through to successful project completion and answer many questions that may crop up during the process. The focus is placed on energy aspects. Tools and 14 sample process descriptions are provided along with practical examples. Theoretical aspects are also presented and discussed, including models for operator roles and the processes involved. Also, change, risk and knowledge management are examined. Notes and information on possibilities for further education are presented.

  2. A comparative study of worker and general public risks from nuclear facility operation using MACCS2

    Energy Technology Data Exchange (ETDEWEB)

    East, J.M.; O`Kula, K.R.

    1994-10-01

    Over the last five years, the US Department of Energy (DOE) has attempted to establish quantitative risk indices as minimum acceptance criteria for assurance of safe operation of its nuclear facilities. The risk indices serve as aiming points or targets to include consideration of all aspects of operation including normal conditions as well as abnormal, design basis events, and beyond-design basis events. Although initial focus of the application of these safety targets had been on DOE`s reactors, more recent assessments have also considered non-reactor facilities including those encompassing storage and nuclear processing activities. Regardless of the facility`s primary function, accident progression, event tree/fault tree logic models, and probabilistic (dose) consequence assessment model must be implemented to yield a fully integrated analysis of facility operation. The primary tool for probabilistic consequence assessment in the US is the MELCOR Accident Consequence Code System (MACCS). In this study, two version of MACCS are applied to representative source terms developed in the safety analysis associated with a waste processing facility at the Westinghouse Savannah River Company`s (WSRC`s) Savannah River Site (SRS). The MACCS versions are used to estimate population dose and subsequent health effects to workers and the general public from the SRS referenced facility operation. When combined with the frequency of occurrence evaluation, the margin of compliance with the safety targets may be quantified.

  3. Operational facilities of remote control software of ranging measurement equipment

    Science.gov (United States)

    Becceneri, Jose Carlos

    The basic purpose of this paper is to document, in this symposium, the work performed for the construction of Ranging Management Software (RAN), which is one of the functions of the Satellite Control System (SICS) software developed by Instituto Nacional de Pesquisas Espaciais (INPE) to control the Brazilian satellites of MECB (Brazilian Complete Space Mission). This paper shows the RAN basic architecture as well as a set of functions which facilitates both the operation and the ranging system test.

  4. Cooperative Optimal Operation of Wind-Storage Facilities

    DEFF Research Database (Denmark)

    Farashbashi-Astaneh, Seyed-Mostafa; Hu, Weihao; Chen, Zhe

    2014-01-01

    As the penetration of wind power increases in power systems across the world, wind forecast errors become an emerging problem. Storage units are reliable tools to be used in cooperation with wind farms to mitigate imbalance penalties. Nevertheless they are not still economically viable due to huge...... investment cost. We suggest benefitting the storage unit as a regulation service provider beside its normal operation for mitigating wind power imbalances. This idea comes from the fact that storage units have a fast ramping capability which is necessary to meet close to real-time regulation needs...

  5. Cooperative Optimal Operation of Wind-Storage Facilities

    DEFF Research Database (Denmark)

    Farashbashi-Astaneh, Seyed-Mostafa; Hu, Weihao; Chen, Zhe

    2014-01-01

    As the penetration of wind power increases in power systems across the world, wind forecast errors become an emerging problem. Storage units are reliable tools to be used in cooperation with wind farms to mitigate imbalance penalties. Nevertheless they are not still economically viable due to huge...... investment cost. We suggest benefitting the storage unit as a regulation service provider beside its normal operation for mitigating wind power imbalances. This idea comes from the fact that storage units have a fast ramping capability which is necessary to meet close to real-time regulation needs...

  6. 78 FR 16302 - Crystal River Unit 3 Nuclear Generating Plant, Application for Amendment to Facility Operating...

    Science.gov (United States)

    2013-03-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Crystal River Unit 3 Nuclear Generating Plant, Application for Amendment to Facility Operating... Operating License No. DPR-72 for the Crystal River Unit 3 Nuclear Generating Plant (CR-3), located in...

  7. 77 FR 1743 - Facility Operating License Amendment From Florida Power Corporation, Crystal River Nuclear...

    Science.gov (United States)

    2012-01-11

    ... COMMISSION Facility Operating License Amendment From Florida Power Corporation, Crystal River Nuclear... Florida Power Corporation for operation of the Crystal River Nuclear Generating Plant, Unit 3. The proposed amendment would increase the licensed core power level for Crystal River Nuclear Generating Plant...

  8. Improvement in performance and operational experience of 14 UD Pelletron Accelerator Facility, BARC–TIFR

    Indian Academy of Sciences (India)

    P V Bhagwat

    2002-11-01

    14 UD Pelletron Accelerator Facility at Mumbai has been operational since 1989. The project MEHIA (medium energy heavy ion accelerator) started in 1982 and was formally inaugurated on 30th December 1988. Since then the accelerator has been working round the clock. Improvement in accelerator performance and operational experience are described.

  9. Operation of N Reactor and Fuels Fabrication Facilities, Hanford Reservation, Richland, Benton County, Washington: Environmental assessment

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-01

    Environmental data, calculations and analyses show no significant adverse radiological or nonradiological impacts from current or projected future operations resulting from N Reactor, Fuels Fabrication and Spent Fuel Storage Facilities. Nonoccupational radiation exposures resulting from 1978 N Reactor operations are summarized and compared to allowable exposure limits.

  10. RISK ASSESSMENT BY STRUCTURAL ANALYSIS AND VIBRATION MEASUREMENT EQUIPMENT OPERATING AT OIL FACILITIES

    Directory of Open Access Journals (Sweden)

    Marius STAN

    2013-05-01

    Full Text Available Vibration analysis applications in operation is one of the diagnostic methods ofoperation of the facility. Analysis of these types of failures indicated the existence of specificfeatures prints and related equipment vibration spectra. Modeling and identification of theseparticular aspects in the spectrum of vibration machines help to control the operation of oilfacilities built safely.

  11. Operation of N Reactor and Fuels Fabrication Facilities, Hanford Reservation, Richland, Benton County, Washington: Environmental assessment

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-01

    Environmental data, calculations and analyses show no significant adverse radiological or nonradiological impacts from current or projected future operations resulting from N Reactor, Fuels Fabrication and Spent Fuel Storage Facilities. Nonoccupational radiation exposures resulting from 1978 N Reactor operations are summarized and compared to allowable exposure limits.

  12. 77 FR 2766 - Facility Operating License Amendment from Duke Energy Carolinas, LLC., Catawba Nuclear Station...

    Science.gov (United States)

    2012-01-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Facility Operating License Amendment from Duke Energy Carolinas, LLC., Catawba Nuclear Station... and NPF-52 issued to Duke Energy Carolinas, LLC (the licensee), for operation of the Catawba Nuclear...

  13. High Performance Computing Facility Operational Assessment, CY 2011 Oak Ridge Leadership Computing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Baker, Ann E [ORNL; Barker, Ashley D [ORNL; Bland, Arthur S Buddy [ORNL; Boudwin, Kathlyn J. [ORNL; Hack, James J [ORNL; Kendall, Ricky A [ORNL; Messer, Bronson [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL; Wells, Jack C [ORNL; White, Julia C [ORNL; Hudson, Douglas L [ORNL

    2012-02-01

    Oak Ridge National Laboratory's Leadership Computing Facility (OLCF) continues to deliver the most powerful resources in the U.S. for open science. At 2.33 petaflops peak performance, the Cray XT Jaguar delivered more than 1.4 billion core hours in calendar year (CY) 2011 to researchers around the world for computational simulations relevant to national and energy security; advancing the frontiers of knowledge in physical sciences and areas of biological, medical, environmental, and computer sciences; and providing world-class research facilities for the nation's science enterprise. Users reported more than 670 publications this year arising from their use of OLCF resources. Of these we report the 300 in this review that are consistent with guidance provided. Scientific achievements by OLCF users cut across all range scales from atomic to molecular to large-scale structures. At the atomic scale, researchers discovered that the anomalously long half-life of Carbon-14 can be explained by calculating, for the first time, the very complex three-body interactions between all the neutrons and protons in the nucleus. At the molecular scale, researchers combined experimental results from LBL's light source and simulations on Jaguar to discover how DNA replication continues past a damaged site so a mutation can be repaired later. Other researchers combined experimental results from ORNL's Spallation Neutron Source and simulations on Jaguar to reveal the molecular structure of ligno-cellulosic material used in bioethanol production. This year, Jaguar has been used to do billion-cell CFD calculations to develop shock wave compression turbo machinery as a means to meet DOE goals for reducing carbon sequestration costs. General Electric used Jaguar to calculate the unsteady flow through turbo machinery to learn what efficiencies the traditional steady flow assumption is hiding from designers. Even a 1% improvement in turbine design can save the nation

  14. Modelling and operation strategies of DLR's large scale thermocline test facility (TESIS)

    Science.gov (United States)

    Odenthal, Christian; Breidenbach, Nils; Bauer, Thomas

    2017-06-01

    In this work an overview of the TESIS:store thermocline test facility and its current construction status will be given. Based on this, the TESIS:store facility using sensible solid filler material is modelled with a fully transient model, implemented in MATLAB®. Results in terms of the impact of filler site and operation strategies will be presented. While low porosity and small particle diameters for the filler material are beneficial, operation strategy is one key element with potential for optimization. It is shown that plant operators have to ponder between utilization and exergetic efficiency. Different durations of the charging and discharging period enable further potential for optimizations.

  15. Experiments in hand-operated, hypersonic shock tunnel facility

    Science.gov (United States)

    Sudhiesh Kumar, Chintoo; Reddy, K. P. J.

    2016-11-01

    Experiments were conducted using the newly developed table-top, hand-operated hypersonic shock tunnel, otherwise known as the Reddy hypersonic shock tunnel. This novel instrument uses only manual force to generate the shock wave in the shock tube, and is designed to generate a freestream flow of Mach 6.5 in the test section. The flow was characterized using stagnation point pressure measurements made using fast-acting piezoelectric transducers. Schlieren visualization was also carried out to capture the bow shock in front of a hemispherical body placed in the flow. Freestream Mach numbers estimated at various points in the test section showed that for a minimum diameter of 46 mm within the test section, the value did not vary by more than 3 % along any cross-sectional plane. The results of the experiments presented here indicate that the device may be successfully employed for basic hypersonic research activities at the university level.

  16. The Intentional Interim

    Science.gov (United States)

    Nugent, Patricia A.

    2011-01-01

    The author spent years in central-office administration, most recently in an interim position. Some interim administrators simply see themselves as placeholders until the real deal is hired, giving the organization the opportunity to coast. There are others who see themselves as change agents and cannot wait to undo or redo what their predecessor…

  17. Pre-operational environmental monitoring plan for the Device Assembly Facility at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Ferate, F.D.

    1995-01-01

    Nuclear explosives operations have been and may continue to be an important component of the DOE mission at the NTS. This mission has been to conduct the nation`s nuclear testing program in a safe, secure, and efficient manner while assuring full compliance with state and federal regulations, and DOE order`s and directives. These operations have generally included assembly, disassembly or modification, staging, transportation, and tesbng of nuclear explosive devices. They may also include maintenance, repair, retrofit, and surveillance. The Device Assembly Facility (DAF) was constructed to provide a dedicated facility in which to prepare nuclear explosives assemblies for their intended disposition. This facility will provide for combined operations (replacing two separate facilities) and incorporates state-of-the-art safety and security features while minimizing the risks of environmental impacts. The facility has been completed but not yet operated, so the impacts to be considered will b e based on normal operations and not on the impacts of construction activities. The impacts will arise from nuclear explosives operations that require the handling of high explosives in combination with special nuclear materials. Wastes from operation of the earlier device assembly facilities have included grams of epoxies, pints of solvents, and small quantities of waste explosives. These are hazardous (includes radioactive) wastes and are disposed of in accordance with state and federal regulations. Assuming similar operations at the DAF, non-hazardous (includes non-radioactive) solid waste would be transported to a permitted landfill. Waste explosives would be sent to the Area 11 Explosive Ordnance Disposal Unit. Other hazardous waste would be sent to the Area 5 Radioactive Waste.Management Site for shipment or burial.

  18. 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., Bruno; 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...

  19. Operating experience review - Ventilation systems at Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    The Office of Special Projects (DP-35), formerly Office of Self-Assessment (DP-9), analyzed occurrences caused by problems with equipment and material and recommended the following systems for an in-depth study: (1) Selective Alpha Air Monitor (SAAM), (2) Emergency Diesel Generator, (3) Ventilation System, (4) Fire Alarm System. Further, DP-35 conducted an in-depth review of the problems associated with SAAM and with diesel generators, and made several recommendations. This study focusses on ventilation system. The intent was to determine the causes for the events related to these system that were reported in the Occurrence Reporting and Processing System (ORPS), to identify components that failed, and to provide technical information from the commercial and nuclear industries on the design, operation, maintenance, and surveillance related to the system and its components. From these data, sites can develop a comprehensive program of maintenance management, including surveillance, to avoid similar occurrences, and to be in compliance with the following DOE orders.

  20. Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C.; Rokni, Sayed H.; /SLAC; Vylet, Vaclav; /Jefferson Lab

    2009-12-11

    The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power ({approx} 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

  1. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    Energy Technology Data Exchange (ETDEWEB)

    Tyner, C.J.; Birk, S.M.

    1995-09-01

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

  2. Hazard and operability study of the multi-function Waste Tank Facility. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, M.E.

    1995-05-15

    The Multi-Function Waste Tank Facility (MWTF) East site will be constructed on the west side of the 200E area and the MWTF West site will be constructed in the SW quadrant of the 200W site in the Hanford Area. This is a description of facility hazards that site personnel or the general public could potentially be exposed to during operation. A list of preliminary Design Basis Accidents was developed.

  3. Design review report FFTF interim storage cask

    Energy Technology Data Exchange (ETDEWEB)

    Scott, P.L.

    1995-01-03

    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.

  4. New facilities, new challenges: the telescope and instrument operators evolution at ESO

    Science.gov (United States)

    Pino Pavez, Andres; Brillant, Stéphane; Cerda, Susana; Mérand, Antoine; Mieske, Steffen; Smette, Alain; Romero, Cristian M.

    2016-07-01

    Observatories and operational strategies are evolving in connection with the facilities that will be built. For those new facilities, the strategy for dealing with the telescopes, instrumentation, data-flow, reduction process and relationship with the community is more or less handled from its conception. However, for those Observatories already in place, the challenge is to adapt the processes and prepare the existing people for these changes. This talk will show detailed information about current activities, the implemented training plan, the definition of the current operational model, the involvement of the group in projects towards improving operational processes and efficiency, and what new challenges will be involved during the definition of the strategies for the new generation instruments and facilities to be installed.

  5. 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)

  6. 75 FR 2557 - Interim Policy for the Sharing of Information Collected by the Coast Guard Nationwide Automatic...

    Science.gov (United States)

    2010-01-15

    ... SECURITY Coast Guard Interim Policy for the Sharing of Information Collected by the Coast Guard Nationwide.... SUMMARY: The Coast Guard has developed an interim policy for the access and sharing of information... reach the Docket Management Facility by that date. ADDRESSES: This notice and the interim policy...

  7. 76 FR 22802 - Interim Enforcement Policy for Minimum Days Off Requirements

    Science.gov (United States)

    2011-04-25

    ... COMMISSION 10 CFR Part 26 RIN 3150-AI94 Interim Enforcement Policy for Minimum Days Off Requirements AGENCY... for managing worker fatigue at operating nuclear power plants. This interim policy affects licensees... adopt this interim alternative approach has the potential for introducing adverse consequences if...

  8. Gemini Observatory base facility operations: systems engineering process and lessons learned

    Science.gov (United States)

    Serio, Andrew; Cordova, Martin; Arriagada, Gustavo; Adamson, Andy; Close, Madeline; Coulson, Dolores; Nitta, Atsuko; Nunez, Arturo

    2016-08-01

    Gemini North Observatory successfully began nighttime remote operations from the Hilo Base Facility control room in November 2015. The implementation of the Gemini North Base Facility Operations (BFO) products was a great learning experience for many of our employees, including the author of this paper, the BFO Systems Engineer. In this paper we focus on the tailored Systems Engineering processes used for the project, the various software tools used in project support, and finally discuss the lessons learned from the Gemini North implementation. This experience and the lessons learned will be used both to aid our implementation of the Gemini South BFO in 2016, and in future technical projects at Gemini Observatory.

  9. A comparative study of worker and general public risks from nuclear facility operation using MACCS2

    Energy Technology Data Exchange (ETDEWEB)

    East, J.M.; O`Kula, K.R. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1995-12-31

    Over the last five years, the US Department of Energy (DOE) has attempted to establish quantitative risk indices as minimum acceptance criteria for assurance of safe operation of its nuclear facilities. The risk indices serve as aiming points or targets to include consideration of all aspects of operation including normal conditions as well as abnormal, design basis events, and beyond-design basis events. Although initial focus of the application of these safety targets had been on DOE`s reactors, more recent assessments have also considered non-reactor facilities including those encompassing storage and nuclear processing activities. Regardless of the facility`s primary function, accident progression, event tree/fault tree logic models, and probabilistic (dose) consequence assessment model must be implemented to yield a fully integrated analysis of facility operation. The primary tool for probabilistic consequence assessment in the U.S. is the MELCOR Accident Consequence Code System (MACCS). In this study, two version of MACCS are applied to representative source terms developed in the safety analysis associated with a waste processing facility at the Westinghouse Savannah River Company`s (WSRC`s) Savannah River Site (SRS). The MACCS versions are used to estimate population dose and subsequent health effects to workers and the general public from the SRS referenced facility operation. When combined with the frequency of occurrence evaluation, the margin of compliance with the safety targets may be quantified. Additionally, numerical evaluation of the safety targets with the two code versions will serve as an indicator of the impact of the enhancements made to MACCS relative to earlier baseline software.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  11. Fuel Maps for the GEP 6.5LT Engine When Operating on at J/JP-8 Fuel Blends at Ambient and Elevated Temperatures

    Science.gov (United States)

    2015-04-01

    UNCLASSIFIED UNCLASSIFIED FUEL MAPS FOR THE GEP 6.5LT ENGINE WHEN OPERATING ON ATJ/JP-8 FUEL BLENDS AT AMBIENT AND ELEVATED TEMPERATURES...INTERIM REPORT TFLRF No. 464 By Douglas M. Yost Edwin A. Frame U.S. Army TARDEC Fuels and Lubricants Research Facility Southwest... FUEL MAPS FOR THE GEP 6.5LT ENGINE WHEN OPERATING ON ATJ/JP-8 FUEL BLENDS AT AMBIENT AND ELEVATED TEMPERATURES INTERIM REPORT TFLRF No. 464

  12. 77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

    Science.gov (United States)

    2012-11-15

    ... COMMISSION The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R... Operating License No. R-84 (Application), which currently authorizes the Armed Forces Radiobiology Research... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to...

  13. 77 FR 7613 - Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108

    Science.gov (United States)

    2012-02-13

    ... COMMISSION Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108... renewal of Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow... Operating License No. R-108 for the DTRR. The application contains SUNSI. Based on its initial review of the...

  14. Solar production of industrial process hot water: Operation and evaluation of the Campbell Soup hot water solar facility

    Science.gov (United States)

    Kull, J. I.; Neimeyer, W. N.; Youngblood, S. B.

    1980-12-01

    The operation and evaluation of a solar hot water facility is summarized. The period of evaluation was for 12 months from October 1979 through September 1980. The objective of the work was to obtain additional, long term data on the operation and performance of the facility. Minor modifications to the facility were completed. The system was operated for 15 months, and 12 months of detailed data were evaluated. The facility was available for operation and of the time during the last 8 months of evaluation. A detailed description of the solar facility and of the operating experience is given, and a summary of system performance for the 12 month operation/evaluation period is presented. Recommendations for large scale solar facilities based on this project's experience are given, and an environmental impact assessment is provided.

  15. Meeting the challenges of bringing a new base facility operation model to Gemini Observatory

    Science.gov (United States)

    Nitta, Atsuko; Arriagada, Gustavo; Adamson, A. J.; Cordova, Martin; Nunez, Arturo; Serio, Andrew; Kleinman, Scot

    2016-08-01

    The aim of the Gemini Observatory's Base Facilities Project is to provide the capabilities to perform routine night time operations with both telescopes and their instruments from their respective base facilities without anyone present at the summit. Tightening budget constraints prompted this project as both a means to save money and an opportunity to move toward increasing remote operations in the future. We successfully moved Gemini North nighttime operation to our base facility in Hawaii in Nov., 2015. This is the first 8mclass telescope to completely move night time operations to base facility. We are currently working on implementing BFO to Gemini South. Key challenges for this project include: (1) This is a schedule driven project. We have to implement the new capabilities by the end of 2015 for Gemini North and end of 2016 for Gemini South. (2) The resources are limited and shared with operations which has the higher priority than our project. (3) Managing parallel work within the project. (4) Testing, commissioning and introducing new tools to operational systems without adding significant disruptions to nightly operations. (5) Staff buying to the new operational model. (6) The staff involved in the project are spread on two locations separated by 10,000km, seven time zones away from each other. To overcome these challenges, we applied two principles: "Bare Minimum" and "Gradual Descent". As a result, we successfully completed the project ahead of schedule at Gemini North Telescope. I will discuss how we managed the cultural and human aspects of the project through these concepts. The other management aspects will be presented by Gustavo Arriagada [2], the Project Manager of this project. For technical details, please see presentations from Andrew Serio [3] and Martin Cordova [4].

  16. 75 FR 62592 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2010-10-12

    ... amendments to the Renewed Facility Operating Licenses include: (1) The proposed Cyber Security Plan for CCNPP... implement and maintain in effect all provisions of the Nuclear Regulatory Commission-approved Cyber Security... cyber security program. This regulation specifically requires each licensee currently licensed...

  17. CVD Diamond Detector Stability Issues for Operation at the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Schmid, G J; Koch, J A; Moran, M J; Lerche, R A; Izumi, N; Phillips, T W; Glebov, V Y; Sangster, T C; Stoeckl, C

    2003-08-22

    Synthetic diamond crystals produced by the Chemical Vapor Deposition (CVD) technique can serve as fast, radiation hard, neutron sensors for the National Ignition Facility (NIF). Here we explore the stability issues, such as charge trapping and high-flux saturation, that will be relevant to operation at the NIF.

  18. A Study on an appropriate operating system of environmental basic facility service industry

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Hyun Joo [Korea Environment Institute, Seoul (Korea)

    1998-12-01

    The environmental basic facility service industry is designed to have a structural reorganization of general operating system and the efficient and effective participation of private industry and regulation of industry in connection with the general system. 35 refs., 9 figs., 20 tabs.

  19. 76 FR 64388 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses; Involving No...

    Science.gov (United States)

    2011-10-18

    ... . Calvert Cliffs Nuclear Power Plant, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant... No. 1 (DBNPS), Ottawa County, Ohio Docket No. 50-440, Perry Nuclear Power Plant, Unit No. 1 (PNPP... maintenance that is performed on plant equipment. Therefore, operation of the facility in accordance with......

  20. Safety analysis of the Los Alamos critical experiments facility: burst operation of Skua

    Energy Technology Data Exchange (ETDEWEB)

    Orndoff, J.D.; Paxton, H.C.; Wimett, T.F.

    1980-12-01

    Detailed consideration of the Skua burst assembly is provided, thereby supplementing the facility Safety Analysis Report covering the operation of other critical assemblies at the Los Alamos Scientific Laboratory. As with these assemblies the small fission-product inventory, ambient pressure, and moderate temperatures in Skua are amenable to straightforward measures to ensure the protection of the public.

  1. Operation and Performance Measurement on Engines in Sea Level Test Facilities

    Science.gov (United States)

    1984-03-01

    operations which may ho performed in order to imorove a % signal ci, change its existing form into another one for the purpose of electrical comnatibility ...facility that allows realistic gas turbine core engine cyclic testing with fully instrumented components. This corporate funded Low Cycle Fatigue

  2. Environmental Assessment: Construction and Operation of Security Forces & Command Post / Installation Control Center Facilities

    Science.gov (United States)

    2008-01-03

    Operation of Security Forces &Command Post/ICC Facilities January 03, 2008 91 6.0 PERSONS CONTACTED Russell Adams – 78th CEG/CEVQ Larry J. Allen...fPD believes the proposed project will have no adverse effect on Building 300, as defined in 36 CFR Parr 800.5(d)(l). Please note that historic and

  3. 75 FR 19428 - Palisades Nuclear Plant; Notice of Consideration of Issuance of Amendment to Facility Operating...

    Science.gov (United States)

    2010-04-14

    ... COMMISSION Palisades Nuclear Plant; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U... significant hazards consideration. Under the Commission's regulations in Title 10 of the Code of...

  4. 75 FR 70708 - Palisades Nuclear Plant; Notice of Consideration of Issuance of Amendment to Facility Operating...

    Science.gov (United States)

    2010-11-18

    ... COMMISSION Palisades Nuclear Plant; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U... no significant hazards consideration. Under the Commission's regulations in Title 10 of the Code...

  5. 75 FR 76041 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-12-07

    ... implement and maintain a cyber security plan as part of the facility's overall program for physical... plant systems or the manner in which systems are operated. Therefore, the inclusion of the Cyber... assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks...

  6. 42 CFR 412.405 - Preadmission services as inpatient operating costs under the inpatient psychiatric facility...

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 2 2010-10-01 2010-10-01 false Preadmission services as inpatient operating costs under the inpatient psychiatric facility prospective payment system. 412.405 Section 412.405 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES MEDICARE PROGRAM PROSPECTIVE PAYMENT SYSTEMS FOR...

  7. Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

    Energy Technology Data Exchange (ETDEWEB)

    Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

    1991-12-31

    This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}. Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

  8. Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

    Energy Technology Data Exchange (ETDEWEB)

    Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

    1991-12-31

    This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}, Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

  9. Operation reliability analysis of independent power plants of gas-transmission system distant production facilities

    Directory of Open Access Journals (Sweden)

    Piskunov Maksim V.

    2015-01-01

    Full Text Available The new approach was developed to analyze the failure causes in operation of linear facilities independent power supply sources (mini-CHP-plants of gas-transmission system in Eastern part of Russia. Triggering conditions of ceiling operation substance temperature at condenser output were determined with mathematical simulation use of unsteady heat and mass transfer processes in condenser of mini-CHP-plants. Under these conditions the failure probability in operation of independent power supply sources is increased. Influence of environmental factors (in particular, ambient temperature as well as output electric capability values of power plant on mini-CHP-plant operation reliability was analyzed. Values of mean time to failure and power plant failure density during operation in different regions of Eastern Siberia and Far East of Russia were received with use of numerical simulation results of heat and mass transfer processes at operation substance condensation.

  10. A decision support system for quantitative measurement of operational efficiency in a blood collection facility.

    Science.gov (United States)

    Kros, John F; Yim Pang, Robyn

    2004-04-01

    A decision support system (DSS) is presented that allows users to input, analyze, and output data derived from blood banking operations. The DSS developed is a hybrid system that is both data and model driven. The system provides information, models, and data manipulation tools to assist users in the quantitative measurement of the operational efficiency in a blood collection facility. A relational database was developed to address the four major variables, which impact the cost per unit of blood being collected. Using visual basic, a user interface and mathematical model were developed establishing the relationships to analyze cost per unit of collected blood. Using inputs from users and historical financial data, the DSS calculates the cost per unit as each of the major variables is altered. Real life situations by the mobile operations team at a blood collection facility were used to test the DSS.

  11. Operational readiness review for the Waste Experimental Reduction Facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    An Operational Readiness Review (ORR) at the Idaho National Engineering Laboratory`s (INEL`s) Waste Experimental Reduction Facility (WERF) was conducted by EG&G Idaho, Inc., to verify the readiness of WERF to resume operations following a shutdown and modification period of more than two years. It is the conclusion of the ORR Team that, pending satisfactory resolution of all pre-startup findings, WERF has achieved readiness to resume unrestricted operations within the approved safety basis. ORR appraisal forms are included in this report.

  12. Conjunctive operation of river facilities for integrated water resources management in Korea

    Science.gov (United States)

    Kim, Hwirin; Jang, Cheolhee; Kim, Sung

    2016-10-01

    With the increasing trend of water-related disasters such as floods and droughts resulting from climate change, the integrated management of water resources is gaining importance recently. Korea has worked towards preventing disasters caused by floods and droughts, managing water resources efficiently through the coordinated operation of river facilities such as dams, weirs, and agricultural reservoirs. This has been pursued to enable everyone to enjoy the benefits inherent to the utilization of water resources, by preserving functional rivers, improving their utility and reducing the degradation of water quality caused by floods and droughts. At the same time, coordinated activities are being conducted in multi-purpose dams, hydro-power dams, weirs, agricultural reservoirs and water use facilities (featuring a daily water intake of over 100 000 m3 day-1) with the purpose of monitoring the management of such facilities. This is being done to ensure the protection of public interest without acting as an obstacle to sound water management practices. During Flood Season, each facilities contain flood control capacity by limited operating level which determined by the Regulation Council in advance. Dam flood discharge decisions are approved through the flood forecasting and management of Flood Control Office due to minimize flood damage for both upstream and downstream. The operational plan is implemented through the council's predetermination while dry season for adequate quantity and distribution of water.

  13. Conjunctive operation of river facilities for integrated water resources management in Korea

    Directory of Open Access Journals (Sweden)

    H. Kim

    2016-10-01

    Full Text Available With the increasing trend of water-related disasters such as floods and droughts resulting from climate change, the integrated management of water resources is gaining importance recently. Korea has worked towards preventing disasters caused by floods and droughts, managing water resources efficiently through the coordinated operation of river facilities such as dams, weirs, and agricultural reservoirs. This has been pursued to enable everyone to enjoy the benefits inherent to the utilization of water resources, by preserving functional rivers, improving their utility and reducing the degradation of water quality caused by floods and droughts. At the same time, coordinated activities are being conducted in multi-purpose dams, hydro-power dams, weirs, agricultural reservoirs and water use facilities (featuring a daily water intake of over 100 000 m3 day−1 with the purpose of monitoring the management of such facilities. This is being done to ensure the protection of public interest without acting as an obstacle to sound water management practices. During Flood Season, each facilities contain flood control capacity by limited operating level which determined by the Regulation Council in advance. Dam flood discharge decisions are approved through the flood forecasting and management of Flood Control Office due to minimize flood damage for both upstream and downstream. The operational plan is implemented through the council's predetermination while dry season for adequate quantity and distribution of water.

  14. Operating experience of the tile carrier transfer facility during the JET remote tile exchange

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, P.; Patel, B.; Davies, N.; Middleton, R.; Mills, S.; Palmer, J.; Pedrick, L.; Wilson, D.W. [JET Joint Undertaking, Abingdon, Oxon (United Kingdom); Hurd, F. [NET Team, Garching (Germany)

    1998-07-01

    During the Remote Tile Exchange shutdown at JET, the purpose built Tile Carrier Transfer Facility (TCTF) has been successfully used for the remote removal and storage of activated, tritiated and beryllium contaminated torus components. The short boom, end effector and tine arrangement was also used during the installation of the new Gas Box Divertor. Tritium levels required the use of techniques and practices which were successful in confining contamination and allowed the declassification of work areas. A holding area and posting facilities enabled ancillary equipment / tool logistics to be managed efficiently. This article presents and describes all the equipment used and reports the operational experience. (authors)

  15. 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...

  16. 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...

  17. Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; O' Kelly, D S

    2006-05-08

    A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to

  18. Environmental assessment for device assembly facility operations, Nevada Test Site, Nye County, Nevada. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The U.S. Department of Energy, Nevada Operations Office (DOE/NV), has prepared an environmental assessment (EA), (DOE/EA-0971), to evaluate the impacts of consolidating all nuclear explosive operations at the newly constructed Device Assembly Facility (DAF) in Area 6 of the Nevada Test Site. These operations generally include assembly, disassembly or modification, staging, transportation, testing, maintenance, repair, retrofit, and surveillance. Such operations have previously been conducted at the Nevada Test Site in older facilities located in Area 27. The DAF will provide enhanced capabilities in a state-of-the-art facility for the safe, secure, and efficient handling of high explosives in combination with special nuclear materials (plutonium and highly enriched uranium). Based on the information and analyses in the EA, DOE has determined that the proposed action would not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (42 U.S.C. 4321 et seq.). Therefore, an environmental impact statement is not required, and DOE is issuing this finding of no significant impact.

  19. Radiation dose evaluation based on exposure scenario during the operation of radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Jeong Hyoun; Kim Chang Lak; Choi, Heui Joo; Park, Joo Wan [Korea Electric Power Corporation, Nuclear Environment Technology Institute, Taejon (Korea, Republic of)

    1999-07-01

    Radiation dose to worker in disposal facility was calculated by using point kernel MICROSHIELD V5.02 computer code based on exposure scenarios. An conceptual design model for disposal vaults in disposal facility was used for object of shielding calculation model. Selected radionuclides and their activities among radioactive wastes from nuclear power plants were assumed as radiation sources for the exposure calculation. Annual radiation doses to crane workers and to people working on disposal vaults were calculated according to exposure time and distance from the sources with conservative operation scenarios. The scenarios used for this study were based on assumption for representing disposal activities in a future Korean near surface disposal facility. Calculated exposure rates to worker during normal disposal work were very low comparing with annual allowable limit for radiation worker.

  20. Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

  1. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1-December 31, 2016

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, Jimmy [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-01-01

    Individual datastreams from instrumentation at the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research observatories (sites) are collected and routed to the ARM Data Center (ADC). The Data Management Facility (DMF), a component of the ADC, executes datastream processing in near-real time. Processed data are then delivered approximately daily to the ARM Data Archive, also a component of the ADC, where they are made freely available to the research community. For each instrument, ARM calculates the ratio of the actual number of processed data records received daily at the ARM Data Archive to the expected number of data records. DOE requires national user facilities to report time-based operating data.

  2. Audit of the radioactive liquid waste treatment facility operations at the Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-19

    Los Alamos National Laboratory (Los Alamos) generates radioactive and liquid wastes that must be treated before being discharged to the environment. Presently, the liquid wastes are treated in the Radioactive Liquid Waste Treatment Facility (Treatment Facility), which is over 30 years old and in need of repair or replacement. However, there are various ways to satisfy the treatment need. The objective of the audit was to determine whether Los Alamos cost effectively managed its Treatment Facility operations. The audit determined that Los Alamos` treatment costs were significantly higher when compared to similar costs incurred by the private sector. This situation occurred because Los Alamos did not perform a complete analysis of privatization or prepare a {open_quotes}make-or-buy{close_quotes} plan for its treatment operations, although a {open_quotes}make-or-buy{close_quotes} plan requirement was incorporated into the contract in 1996. As a result, Los Alamos may be spending $2.15 million more than necessary each year and could needlessly spend $10.75 million over the next five years to treat its radioactive liquid waste. In addition, Los Alamos has proposed to spend $13 million for a new treatment facility that may not be needed if privatization proves to be a cost effective alternative. We recommended that the Manager, Albuquerque Operations Office (Albuquerque), (1) require Los Alamos to prepare a {open_quotes}make-or-buy{close_quotes} plan for its radioactive liquid waste treatment operations, (2) review the plan for approval, and (3) direct Los Alamos to select the most cost effective method of operations while also considering other factors such as mission support, reliability, and long-term program needs. Albuquerque concurred with the recommendations.

  3. Manual for operation of the multipurpose thermalhydraulic test facility TOPFLOW (Transient Two Phase Flow Test Facility); Betriebshandbuch fuer die Mehrzweck-Thermohydraulikversuchsanlage TOPFLOW

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M.; Carl, H.; Schuetz, H.; Pietruske, H.; Lenk, S. [SAAS Systemanalyse und Automatisierungsservice GmbH, Possendorf (Germany)

    2004-07-01

    The Forschungszentrum Rossendorf (FZR) e. V. is constructing a new large-scale test facility, TOPFLOW, for thermalhydraulic single effect tests. The acronym stands for transient two phase flow test facility. It will mainly be used for the investigation of generic and applied steady state and transient two phase flow phenomena and the development and validation of models of computational fluid dynamic (CFD) codes. The manual of the test facility must always be available for the staff in the control room and is restricted condition during operation of personnel and also reconstruction of the facility. (orig./GL)

  4. Interim directive ID 2001-5 : public safety and sour gas policy implementation recommendations 54, 60, and 61 : site-specific emergency response plans for sour gas operations, emergency planning zones, and reduced planning zones

    Energy Technology Data Exchange (ETDEWEB)

    McCrank, N. [Alberta Energy and Utilities Board, Calgary, AB (Canada)

    2001-08-01

    A report of findings and recommendations was presented to the Alberta Energy and Utilities Board (EUB) in December 2000 by the Provincial Advisory Committee on Public Safety and Sour Gas (Advisory Committee). Emergency planning zones (EPZs) and emergency response plans (ERPs) for sour gas operations and how they translate into EUB practices and requirements are topics that were identified in the recommendations. A full review of current emergency preparedness requirements, including the methodology for the determination of EPZs, will be undertaken by the EUB to address these recommendations. The outcome of the update of information concerning health effects of hydrogen sulfide and sulphur dioxide, as well as the review of the current use of dispersion models and probabilistic risk assessment is expected to greatly affect the review on emergency preparedness. The comprehensive review of ERP requirements and determination of EPZs, including reduced EPZs, will take place upon completion of the updated health information, which is expected to take approximately 18 to 24 months. Effective immediately, this interim directive provides additional clarification on the administration of these existing requirements by the EUB, and the document includes new requirements to be used in the interim. This document was prepared in response to Recommendations 54, 60, and 61. It should be noted that the current emergency response planning and preparedness requirements in place remain valid until they are replaced or rescinded. 4 figs.

  5. Operation of the 25 kW NASA Lewis Solar Regenerative Fuel Cell Testbed Facility

    Energy Technology Data Exchange (ETDEWEB)

    Voecks, G.E.; Rohatgi, N.K.; Moore, S.H. [Jet Propulsion Lab., Pasadena, CA (United States)] [and others

    1996-12-31

    Assembly of the NASA Lewis Research Center Solar Regenerative Fuel Cell Testbed Facility has recently been completed and system testing is in progress. This facility includes the integration of 50 kW photovoltaic solar cell arrays, a 25 kW proton exchange membrane (PEM) electrolysis unit, four 5 kW PEM fuel cells, high pressure hydrogen and oxygen storage vessels, high purity water storage containers, and computer monitoring, control and data acquisition. The purpose of this facility is multi-faceted, but was originally intended to serve as a testbed for evaluating a closed-loop powerplant for future NASA extended life support operations, such as a Lunar outpost, and also as a terrestrial powerplant example for remote or continuous back-up support operations. The fuel cell and electrolyzer subsystems design and assembly were conducted by the Jet Propulsion Laboratory (JPL), the photovoltaic arrays and electrical interconnect to the electrolyzer were provided by the US Navy/China Lake Naval Weapons Center, and testing and operations are being carried out by JPL.

  6. Numerical simulations of the first operational conditions of the negative ion test facility SPIDER

    Energy Technology Data Exchange (ETDEWEB)

    Serianni, G., E-mail: gianluigi.serianni@igi.cnr.it; Agostinetti, P.; Antoni, V.; Baltador, C.; Chitarin, G.; Marconato, N.; Pasqualotto, R.; Sartori, E.; Toigo, V.; Veltri, P. [Consorzio RFX (CNR, ENEA, INFN, UNIPD, Acciaierie Venete SpA), Corso Stati Uniti 4, 35127 Padova (Italy); Cavenago, M. [INFN-LNL, Viale dell’Università n. 2, 35020 Legnaro (Italy)

    2016-02-15

    In view of the realization of the negative ion beam injectors for ITER, a test facility, named SPIDER, is under construction in Padova (Italy) to study and optimize production and extraction of negative ions. The present paper is devoted to the analysis of the expected first operations of SPIDER in terms of single-beamlet and multiple-beamlet simulations of the hydrogen beam optics in various operational conditions. The effectiveness of the methods adopted to compensate for the magnetic deflection of the particles is also assessed. Indications for a sequence of the experimental activities are obtained.

  7. The century storage facility. Why we have to give thoughts to the castor halls; Die Jahrhundert-Lager. Warum wir uns dringend Gedanken ueber die Castor-Hallen machen muessen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-01-15

    The authors discuss the situation of the German interim storage facilities for high-level nuclear waste. The Castor casks are supposed to be licensed as storage casks for 40 years. It is already foreseeable that after 40 years a final repository will not be available. This means that the Castor casks and the interim storage halls will have to be operated at least for the 21st century without valid licensing.

  8. 40 CFR Appendix III to Part 265 - EPA Interim Primary Drinking Water Standards

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false EPA Interim Primary Drinking Water..., STORAGE, AND DISPOSAL FACILITIES Pt. 265, App. III Appendix III to Part 265—EPA Interim Primary Drinking Water Standards Parameter Maximum level (mg/l) Arsenic 0.05 Barium 1.0 Cadmium 0.01 Chromium...

  9. Systematic Method for Evaluating Extraction and Injection Flow Rates for 100-KR-4 and 100-HR-3 Groundwater Operable Unit Pump-and-Treat Interim Actions for Hydraulic Containment

    Energy Technology Data Exchange (ETDEWEB)

    Spiliotopoulos, Alexandros A.

    2013-03-20

    This document describes a systematic method to develop flow rate recommendations for Pump-and-Treat (P&T) extraction and injection wells in 100-KR-4 and 100-HR-3 Groundwater Operable Units (OU) of the Hanford Site. Flow rate recommendations are developed as part of ongoing performance monitoring and remedy optimization of the P&T interim actions to develop hydraulic contairnnent of the dissolved chromium plume in groundwater and protect the Columbia River from further discharges of groundwater from inland. This document details the methodology and data required to infer the influence of individual wells near the shoreline on hydraulic containment and river protection and develop flow rate recommendations to improve system performance and mitigate potential shortcomings of the system configuration in place.

  10. Automatic Management Systems for the Operation of the Cryogenic Test Facilities for LHC Series Superconducting Magnets

    CERN Document Server

    Tovar-Gonzalez, A; Herblin, L; Lamboy, J P; Vullierme, B

    2006-01-01

    Prior to their final preparation before installation in the tunnel, the ~1800 series superconducting magnets of the LHC machine shall be entirely tested at reception on modular test facilities. The operation 24 hours per day of the cryogenic test facilities is conducted in turn by 3-operator teams, assisted in real time by the use of the Test Bench Priorities Handling System, a process control application enforcing the optimum use of cryogenic utilities and of the "Tasks Tracking System", a web-based e-traveller application handling 12 parallel 38-task test sequences. This paper describes how such computer-based management systems can be used to optimize operation of concurrent test benches within technical boundary conditions given by the cryogenic capacity, and how they can be used to study the efficiency of the automatic steering of all individual cryogenic sub-systems. Finally, this paper presents the overall performance of the cryomagnet test station for the first complete year of operation at high produ...

  11. National Ignition Facility start-up/operations engineering and special equipment construction health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    Huddleston, P C

    1998-05-08

    This document sets forth the responsibilities, interfaces, guidelines, rules, policy, and regulations for all workers involved in the S/O and SE construction, installation, and acceptance testing. This document is enforced from the first day that S/O and SE workers set foot on the NIF construction site until the end of the Project at Critical Decision 4. This document is applicable only to site activities, which are defined as those that occur within the perimeter of the fenced-off NIF construction zone and the Target Chamber Assembly Area (Helipad). The associated Special Equipment laydown and construction support areas listed in Appendix B are not under this plan; their safety provisions are discussed in the Appendix. Prototype and other support activities, such as the Amplifier Laboratory and Frame Assembly Unit assembly area, are not included in this plan. After completion of the Operational Readiness Review, the Facility Safety Procedure, Operational Safety Requirements, and Operational Safety Procedures are the governing safety documents for the operating facility. The S/O and SE project elements are required to implement measures that create a universal awareness of and promote safe job practices at the site. This includes all Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory, Sandia National Laboratories, University of Rochester, supplement labor organization, and subcontractor employees; visitors; and guests serving the S/O and SE effort.

  12. National Ignition Facility start-up/operations engineering and special equipment construction health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    Huddleston, P C

    1998-05-08

    This document sets forth the responsibilities, interfaces, guidelines, rules, policy, and regulations for all workers involved in the S/O and SE construction, installation, and acceptance testing. This document is enforced from the first day that S/O and SE workers set foot on the NIF construction site until the end of the Project at Critical Decision 4. This document is applicable only to site activities, which are defined as those that occur within the perimeter of the fenced-off NIF construction zone and the Target Chamber Assembly Area (Helipad). The associated Special Equipment laydown and construction support areas listed in Appendix B are not under this plan; their safety provisions are discussed in the Appendix. Prototype and other support activities, such as the Amplifier Laboratory and Frame Assembly Unit assembly area, are not included in this plan. After completion of the Operational Readiness Review, the Facility Safety Procedure, Operational Safety Requirements, and Operational Safety Procedures are the governing safety documents for the operating facility. The S/O and SE project elements are required to implement measures that create a universal awareness of and promote safe job practices at the site. This includes all Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory, Sandia National Laboratories, University of Rochester, supplement labor organization, and subcontractor employees; visitors; and guests serving the S/O and SE effort.

  13. Intel International Interim Report

    Science.gov (United States)

    Martin, Wendy; Mandinach, Ellen; Kanaya, Tomoe; Culp, Katie McMillan

    2004-01-01

    This interim report presents preliminary data and observations from evaluations of Intel Teach to the Future being conducted around the world, and recommendations for building and refining this evaluation portfolio to ensure that findings will be instructive at the local, national and international level. The data presented here reflect the…

  14. Operational safety analysis of the Olkiluoto encapsulation plant and disposal facility; Olkiluodon kapselointi- ja loppusijoituslaitoksen kaeyttoeturvallisuusanalyysi

    Energy Technology Data Exchange (ETDEWEB)

    Rossi, J.; Suolanen, V. [VTT Technical Research Centre of Finland, Espoo (Finland)

    2012-11-15

    Radiation doses for workers of the facility, for inhabitants in the environment and for terrestrial ecosystem possibly caused by the encapsulation and disposal facilities to be built at Olkiluoto during its operation were considered in the study. The study covers both the normal operation of the plant and some hypothetical incidents and accidents. Release through the ventilation stack is assumed to be filtered both in normal operation and in hypothetical abnormal fault and accident cases. In addition the results for unfiltered releases are also presented. This research is limited to the deterministic analysis. During about 30 operation years of our four nuclear power plant units there have been found 58 broken fuel pins. Roughly estimating there has been one fuel leakage per year in a facility (includes two units). Based on this and adopting a conservative approach, it is estimated that one fuel pin per year could leak in normal operation during encapsulation process. The release magnitude in incidents and accidents is based on the event chains, which lead to loss of fuel pin tightness followed by a discharge of radionuclides into the handling space and to some degree to the atmosphere through the ventilation stack equipped with redundant filters. The most exposed group of inhabitants is conservatively assumed to live at the distance of 200 meters from the encapsulation and disposal plant and it will receive the largest doses in most dispersion conditions. The dose value to a member of the most exposed group was calculated on the basis of the weather data in such a way that greater dose than obtained here is caused only in 0.5 percent of dispersion conditions. The results obtained indicate that during normal operation the doses to workers remain small and the dose to the member of the most exposed group is less than 0.001 mSv per year. In the case of hypothetical fault and accident releases the offsite doses do not exceed either the limit values set by the safety

  15. Estimates of power deposited via cesium/barium beta and gamma radiation captured in components of a Hanford cesium chloride capsule and by components of overpacked capsules placed in an interim dry storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Roetman, V.E., Westinghouse Hanford

    1996-12-23

    The deposition of power in Hanford cesium chloride capsules and in the components of design concepts for overpacking and interim storage were determined as requested (Randklev, 1996a). The power deposition results from the selective capture of gamma and beta radiation coming from the decay of the 137CS isotope in the CsCl contained in the capsules. The following three cases were analyzed: (a) a single CsCl capsule, (b) an overpack containing eight CsCl capsules, and (c) an infinite square array of such overpacks as placed in tubes of a interim dry storage facility. The power deposition was expressed as watts per gram for each of the respective physical design components in these three cases. Per the analyses request and guidance (Randklev 1996a), the primary analysis objective was to characterize, for each case, the power deposition across the radial cross-section at the expected axial position of maximum deposition. As requested, this primary part of the analysis work was done using choices for component dimension and material properties that would reasonably characterize the maximum deposition profile across the salt (CsCl) and the inner capsule barrier of the double walled metal capsule system used to construct the Hanford capsules. The secondary objective was to further evaluate the deposition behavior relative to the influence of axial position. The guidance (Randklev 1996a) also requested 1797 an analysis case that involved a lag-storage pit in a hot-cell, in which a cylindrical metal basket from a transportation cask would be used to position several capsules in the lag-storage pit. Although the basic model for the lag storage concept evaluation was essentially completed by the end of FY-96, the analysis was not run because of the need to prioritize and limit the work scope due to funding limitations for FY-97. The specific purpose for performing the subject set of analyses (Randklev 1996a) is to obtain power deposition values (i.e., per the decay of T37cs

  16. 78 FR 72897 - Draft Guidance for Industry on Interim Product Reporting for Human Drug Compounding Outsourcing...

    Science.gov (United States)

    2013-12-04

    ... Human Drug Compounding Outsourcing Facilities Under Section 503B of the Federal Food, Drug, and Cosmetic... entitled ``Interim Product Reporting for Human Drug Compounding Outsourcing Facilities Under Section 503B... register as outsourcing facilities (outsourcing facilities). DATES: Although you can comment on...

  17. First operation of the medical research facility at the NSLS for coronary angiography

    Energy Technology Data Exchange (ETDEWEB)

    Thomlinson, W.; Gmuer, N.; Chapman, D.; Garrett, R.; Lazarz, N.; Moulin, H. (Brookhaven National Lab., Upton, NY (United States)); Thompson, A.C. (Lawrence Berkeley Lab., CA (United States)); Zeman, H.D. (Dept. of Biomedical Engineering, University of Tennessee, Memphis, Tennessee, 38163 (US)); Brown, G.S. (Stanford Univ., CA (United States). Stanford Synchrotron Radiation Lab.); Morrison, J.; Reiser, P

    1991-01-01

    The Synchrotron Medical Research Facility (SMERF) at the National Synchrotron Light Source has been completed and is operational for human coronary angiography experiments. The imaging system and hardware have been brought to SMERF from the Stanford Synchrotron Radiation Laboratory where prior studies were carried out. SMERF consists of a suite of rooms at the end of the high field superconducting wiggler X17 beamline and is classified as an Ambulatory health Care Facility. Since October of 1990 the coronary arteries of five patients have been imaged. Continuously improving image quality has shown that a large part of both the right coronary artery and the left anterior descending coronary artery can be imaged following a venous injection of contrast agent. 16 refs., 4 figs.

  18. DOE High Performance Computing Operational Review (HPCOR): Enabling Data-Driven Scientific Discovery at HPC Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, Richard; Allcock, William; Beggio, Chris; Campbell, Stuart; Cherry, Andrew; Cholia, Shreyas; Dart, Eli; England, Clay; Fahey, Tim; Foertter, Fernanda; Goldstone, Robin; Hick, Jason; Karelitz, David; Kelly, Kaki; Monroe, Laura; Prabhat,; Skinner, David; White, Julia

    2014-10-17

    U.S. Department of Energy (DOE) High Performance Computing (HPC) facilities are on the verge of a paradigm shift in the way they deliver systems and services to science and engineering teams. Research projects are producing a wide variety of data at unprecedented scale and level of complexity, with community-specific services that are part of the data collection and analysis workflow. On June 18-19, 2014 representatives from six DOE HPC centers met in Oakland, CA at the DOE High Performance Operational Review (HPCOR) to discuss how they can best provide facilities and services to enable large-scale data-driven scientific discovery at the DOE national laboratories. The report contains findings from that review.

  19. Optimization of the Operation of Green Buildings applying the Facility Management

    Science.gov (United States)

    Somorová, Viera

    2014-06-01

    Nowadays, in the field of civil engineering there exists an upward trend towards environmental sustainability. It relates mainly to the achievement of energy efficiency and also to the emission reduction throughout the whole life cycle of the building, i.e. in the course of its implementation, use and liquidation. These requirements are fulfilled, to a large extent, by green buildings. The characteristic feature of green buildings are primarily highly-sophisticated technical and technological equipments which are installed therein. The sophisticated systems of technological equipments need also the sophisticated management. From this point of view the facility management has all prerequisites to meet this requirement. The paper is aimed to define the facility management as an effective method which enables the optimization of the management of supporting activities by creating conditions for the optimum operation of green buildings viewed from the aspect of the environmental conditions

  20. Cryogenic magnet tests for the LHC process operation using web-based tools and facilities

    CERN Document Server

    Hemelsoet, G H; Chohan, V; Veyrunes, E

    2005-01-01

    For the Large Hadron Collider under construction at CERN, an essential requirement is the acceptance test of its 1706 Cryo-magnets in cryogenic conditions in a purpose-built facility at CERN. Several teams ensure the proper operation of the infrastructure on a round the clock basis. The cold test part is one of the key elements amongst many other essential activities requiring magnet transport and connections/disconnections, cryogenic preparation and pumping, cooling down to 1.9 K as well warm up before disconnection & removal. All these operations involve multi-tasking and usage of 12 test benches with nominal turn-round time per dipole magnet of 120 hours. It also involves multiple teams of industrial contractors, a support contract for cryogenics operation, CERN staff in magnet testing Operation, aided by a large external collaboration of visiting staff for round the clock operation. This paper gives a flavour of the operation and exposes the software tools that were necessary, designed and developed t...

  1. Environmental assessment: Proposed construction of Refuge operational facilities, water management facilities, wildlife oriented interpretation/recreation development, road and water management facilities rehabilitation, and implementation of a vegetation control plan

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — The proposed action consists of the construction of facilities for refuge operation, water management, and wildlife-oriented interpretation and recreation; the...

  2. 7 CFR 56.76 - Minimum facility and operating requirements for shell egg grading and packing plants.

    Science.gov (United States)

    2010-01-01

    ... egg grading and packing plants. 56.76 Section 56.76 Agriculture Regulations of the Department of... Facility Requirements § 56.76 Minimum facility and operating requirements for shell egg grading and packing.... (2) The outside premises adjacent to grading, packing, cooler, and storage rooms must be...

  3. Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

    Energy Technology Data Exchange (ETDEWEB)

    Pettersson, Stig [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Forsgren, Ebbe [SwedPower AB, Stockholm (Sweden); Lange, Fritz [Lange Art AB, Stockholm (Sweden)

    2002-04-01

    This report documents a proposal for the design of the deep repository for spent nuclear fuel. The proposal is based on the principles that were formulated in the original KBS-3 study, but has been supplemented by investigations and experience to reflect current knowledge. The purpose of the report is to provide an integrated picture of the deep repository, as a basis for SKB's other work, e.g. environmental impact assessments, transport systems, safety issues and alternative locations, and to provide a co-ordinated account of the conditions and requirements concerning all of the necessary functions in the deep repository in order to have a well functioning facility. In addition, it should be possible to use the report as: a tool in the task of achieving a co-ordinated, safe and accepted design for the facility, a basis for further planning and costing, a basis for adaptation to geographic and other conditions for the particular location, a basis for information material, both within SKB and for interested parties outside, such as public authorities, municipalities and the general public. The capacity of the deep repository has been chosen on the basis of 40 years of operation of the Swedish nuclear power reactors, which will produce approximately 9,000 tons of uranium, equivalent to approximately 4,500 canisters. The design outlined is based on theoretical analyses of functions, safety requirements, procedures etc. that can be identified during the various phases of the construction and operation of the repository. In addition, preliminary organisation and staffing plans have been drawn up, for use as the basis for planning the necessary buildings. The report gives a vision of the overall layout and function of the facility, and a proposal for the design of all individual parts of the repository. The relationships between the various parts of the repository are described, both above and below ground, as is the interplay between the part above ground and part

  4. 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.

  5. Operational Circular nr 5 - October 2000 USE OF CERN COMPUTING FACILITIES

    CERN Multimedia

    Division HR

    2000-01-01

    New rules covering the use of CERN Computing facilities have been drawn up. All users of CERN’s computing facilites are subject to these rules, as well as to the subsidiary rules of use. The Computing Rules explicitly address your responsibility for taking reasonable precautions to protect computing equipment and accounts. In particular, passwords must not be easily guessed or obtained by others. Given the difficulty to completely separate work and personal use of computing facilities, the rules define under which conditions limited personal use is tolerated. For example, limited personal use of e-mail, news groups or web browsing is tolerated in your private time, provided CERN resources and your official duties are not adversely affected. The full conditions governing use of CERN’s computing facilities are contained in Operational Circular N° 5, which you are requested to read. Full details are available at : http://www.cern.ch/ComputingRules Copies of the circular are also available in the Divis...

  6. The Langley thermal protection system test facility: A description including design operating boundaries

    Science.gov (United States)

    Klich, G. F.

    1976-01-01

    A description of the Langley thermal protection system test facility is presented. This facility was designed to provide realistic environments and times for testing thermal protection systems proposed for use on high speed vehicles such as the space shuttle. Products from the combustion of methane-air-oxygen mixtures, having a maximum total enthalpy of 10.3 MJ/kg, are used as a test medium. Test panels with maximum dimensions of 61 cm x 91.4 cm are mounted in the side wall of the test region. Static pressures in the test region can range from .005 to .1 atm and calculated equilibrium temperatures of test panels range from 700 K to 1700 K. Test times can be as long as 1800 sec. Some experimental data obtained while using combustion products of methane-air mixtures are compared with theory, and calibration of the facility is being continued to verify calculated values of parameters which are within the design operating boundaries.

  7. Potential soil contaminant levels of polychlorinated dibenzodioxins and dibenzofurans at industrial facilities employing heat transfer operations

    Energy Technology Data Exchange (ETDEWEB)

    Korte, N.E.; Muhr, C.A.; Greene, D.W.

    1992-04-01

    Certain manufacturing facilities formerly used large quantities of polychlorinated biphenyl (PCB) fluids in heat transfer operations. At many of these locations, operations have also involved PCB-containing electrical equipment. Commonly, over many years of plant operations, spills and leaks have resulted in PCB soil contamination. Dioxins and furans have been associated with PCB contamination in both the technical and popular press. Consequently, the need for analyses for dioxins and furans must be evaluated at locations where soils are contaminated with PCBs. This report presents an evaluation of potential dioxin and furan soil contamination based on heat transfer operations and spills from electrical equipment. The following five scenarios were examined for dioxin and furan contamination: (1) impurities in heat transfer fluids, (2) formation during heat transfer operations, (3) pyrolysis of heat transfer fluids, (4) impurities in dielectric fluids, and (5) pyrolysis of dielectric fluids. The potential contamination with dioxins and furans was calculated and compared with a 20 ppb guideline that has been used by the Centers for Disease Control for dioxin in subsoil. The results demonstrated that dioxins are formed only under pyrolytic conditions and only from the trichlorobenzenes present in dielectric fluids. Furans are found as impurities in PCB fluids but, as with dioxins, are not formed in significant quantities except during pyrolysis. Fortunately, pyrolytic conditions involving PCB fluids and soil contamination are unlikely; therefore, analyses for dioxin and furan contamination in soils will rarely be needed.

  8. 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.

  9. Design and Integrate Improved Systems for Nuclear Facility Ventilation and Exhaust Operations

    Energy Technology Data Exchange (ETDEWEB)

    Moore, Murray E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-04-15

    Objective: The objective of this R&D project would complete the development of three new systems and integrate them into a single experimental effort. However, each of the three systems has stand-alone applicability across the DOE complex. At US DOE nuclear facilities, indoor air is filtered and ventilated for human occupancy, and exhaust air to the outdoor environment must be regulated and monitored. At least three technical standards address these functions, and the Los Alamos National Laboratory would complete an experimental facility to answer at least three questions: (1) Can the drag coefficient of a new Los Alamos air mixer be reduced for better operation in nuclear facility exhaust stacks? (2) Is it possible to verify the accuracy of a new dilution method for HEPA filter test facilities? (3) Is there a performance-based air flow metric (volumetric flow or mass flow) for operating HEPA filters? In summary, the three new systems are: a mixer, a diluter and a performance-based metric, respectively. The results of this project would be applicable to at least four technical standards: ANSI N13.1 Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities; ASTM F1471 Standard Test Method for Air Cleaning Performance of a High-Efficiency Particulate Air Filter System, ASME N511: In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems, and ASME AG-1: Code On Nuclear Air And Gas Treatment. All of the three proposed new systems must be combined into a single experimental device (i.e. to develop a new function of the Los Alamos aerosol wind tunnel). Technical Approach: The Radiation Protection RP-SVS group at Los Alamos has an aerosol wind tunnel that was originally (2006) designed to evaluate small air samplers (cf. US EPA 40 CFR 53.42). In 2009, the tunnel was modified for exhaust stack verifications per the ANSI N13.1 standard. In 2010, modifications were started on the

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-09-01

    At Sandia National Laboratories in New Mexico (SNL/NM), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/NM applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule. These design standards generally apply to all disciplines on all SNL/NM projects. Architectural and engineering design must be both functional and cost-effective. Facility design must be tailored to fit its intended function, while emphasizing low-maintenance, energy-efficient, and energy-conscious design. Design facilities that can be maintained easily, with readily accessible equipment areas, low maintenance, and quality systems. To promote an orderly and efficient appearance, architectural features of new facilities must complement and enhance the existing architecture at the site. As an Architectural and Engineering (A/E) professional, you must advise the Project Manager when this approach is prohibitively expensive. You are encouraged to use professional judgment and ingenuity to produce a coordinated interdisciplinary design that is cost-effective, easily contractible or buildable, high-performing, aesthetically pleasing, and compliant with applicable building codes. Close coordination and development of civil, landscape, structural, architectural, fire

  11. Gravity Plant Physiology Facility (GPPF) Team in the Spacelab Payload Operations Control Center (SL

    Science.gov (United States)

    1992-01-01

    The primary payload for Space Shuttle Mission STS-42, launched January 22, 1992, was the International Microgravity Laboratory-1 (IML-1), a pressurized manned Spacelab module. The goal of IML-1 was to explore in depth the complex effects of weightlessness of living organisms and materials processing. Around-the-clock research was performed on the human nervous system's adaptation to low gravity and effects of microgravity on other life forms such as shrimp eggs, lentil seedlings, fruit fly eggs, and bacteria. Materials processing experiments were also conducted, including crystal growth from a variety of substances such as enzymes, mercury iodide, and a virus. The Huntsville Operations Support Center (HOSC) Spacelab Payload Operations Control Center (SL POCC) at the Marshall Space Flight Center (MSFC) was the air/ground communication channel used between the astronauts and ground control teams during the Spacelab missions. Featured is the Gravity Plant Physiology Facility (GPPF) team in the SL POCC during the IML-1 mission.

  12. Gravity Plant Physiology Facility (GPPF) Team in the Spacelab Payload Operations Control Center (SL

    Science.gov (United States)

    1992-01-01

    The primary payload for Space Shuttle Mission STS-42, launched January 22, 1992, was the International Microgravity Laboratory-1 (IML-1), a pressurized manned Spacelab module. The goal of IML-1 was to explore in depth the complex effects of weightlessness of living organisms and materials processing. Around-the-clock research was performed on the human nervous system's adaptation to low gravity and effects of microgravity on other life forms such as shrimp eggs, lentil seedlings, fruit fly eggs, and bacteria. Materials processing experiments were also conducted, including crystal growth from a variety of substances such as enzymes, mercury iodide, and a virus. The Huntsville Operations Support Center (HOSC) Spacelab Payload Operations Control Center (SL POCC) at the Marshall Space Flight Center (MSFC) was the air/ground communication channel used between the astronauts and ground control teams during the Spacelab missions. Featured is the Gravity Plant Physiology Facility (GPPF) team in the SL POCC during the IML-1 mission.

  13. Critical Point Facility (CPE) Group in the Spacelab Payload Operations Control Center (SL POCC)

    Science.gov (United States)

    1992-01-01

    The primary payload for Space Shuttle Mission STS-42, launched January 22, 1992, was the International Microgravity Laboratory-1 (IML-1), a pressurized manned Spacelab module. The goal of IML-1 was to explore in depth the complex effects of weightlessness of living organisms and materials processing. Around-the-clock research was performed on the human nervous system's adaptation to low gravity and effects of microgravity on other life forms such as shrimp eggs, lentil seedlings, fruit fly eggs, and bacteria. Materials processing experiments were also conducted, including crystal growth from a variety of substances such as enzymes, mercury iodide, and a virus. The Huntsville Operations Support Center (HOSC) Spacelab Payload Operations Control Center (SL POCC) at the Marshall Space Flight Center (MSFC) was the air/ground communication channel used between the astronauts and ground control teams during the Spacelab missions. Featured is the Critical Point Facility (CPE) group in the SL POCC during STS-42, IML-1 mission.

  14. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

  15. The optimum operating conditions of the phased double-rotor facility at the ET-RR-1 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Naguib, K.; Habib, N.; Wahba, M.; Kilany, M.; Adib, M. [National Research Centre, Cairo (Egypt). Reactor and Neutron Physics Dept.

    1997-02-07

    A pulsed neutron polyenergetic thermal beam at ET-RR-1 is produced by a phased double-rotor facility. One of the rotors has two diametrically opposite curved slots, while the second is designed to operate as a rotating collimator. The dimensions of the phased rotating collimator are selected to match the curved slot rotor. The calculated collimator transmissions at different operating conditions are found to be in good agreement with the experimental ones. The optimum operating conditions of the double-rotor facility are deduced. The calculations were carried out using a computer program RCOL. The RCOL was designed in FORTRAN-77 to operate on PCs. (author).

  16. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    Energy Technology Data Exchange (ETDEWEB)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  17. Preliminary CFD Assessment of an Experimental Test Facility Operating with Heavy Liquid Metals

    Directory of Open Access Journals (Sweden)

    Matteo Lizzoli

    2017-01-01

    Full Text Available The CFD analysis of a Venturi nozzle operating in LBE (key component of the CIRCE facility, owned by ENEA is presented in this paper. CIRCE is a facility developed to investigate in detail the fluid-dynamic behavior of ADS and/or LFR reactor plants. The initial CFD simulations have been developed hand in hand with the comparison with experimental data: the test results were used to confirm the reliability of the CFD model, which, in turn, was used to improve the interpretation of the experimental data. The Venturi nozzle is modeled with a 3D CFD code (STAR-CCM+. Later on, the CFD model has been used to assess the performance of the component in conditions different from the ones tested in CIRCE: the performance of the Venturi is presented, in terms of pressure drops, for various operating conditions. Finally, the CFD analysis has been focused on the evaluation of the effects of the injection of an inert gas in the flow of the liquid coolant on the performance of the Venturi nozzle.

  18. Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

  19. PIRATE: A Remotely-Operable Telescope Facility for Research and Education

    CERN Document Server

    Holmes, S; Haswell, C A; Burwitz, V; Lucas, R J; Rodriguez, J; Rolfe, S M; Rostron, J; Barker, J

    2011-01-01

    We introduce PIRATE, a new remotely-operable telescope facility for use in research and education, constructed from 'off-the-shelf' hardware, operated by The Open University. We focus on the PIRATE Mark 1 operational phase where PIRATE was equipped with a widely- used 0.35m Schmidt-Cassegrain system (now replaced with a 0.425m corrected Dall Kirkham astrograph). Situated at the Observatori Astronomic de Mallorca, PIRATE is currently used to follow up potential transiting extrasolar planet candidates produced by the SuperWASP North experiment, as well as to hunt for novae in M31 and other nearby galaxies. It is operated by a mixture of commercially available software and proprietary software developed at the Open University. We discuss problems associated with performing precision time series photometry when using a German Equatorial Mount, investigating the overall performance of such 'off-the-shelf' solutions in both research and teaching applications. We conclude that PIRATE is a cost-effective research fac...

  20. Results of operation and current safety performance of nuclear facilities located in the Russian Federation

    Science.gov (United States)

    Kuznetsov, V. M.; Khvostova, M. S.

    2016-12-01

    After the NPP radiation accidents in Russia and Japan, a safety statu of Russian nuclear power plants causes concern. A repeated life time extension of power unit reactor plants, designed at the dawn of the nuclear power engineering in the Soviet Union, power augmentation of the plants to 104-109%, operation of power units in a daily power mode in the range of 100-70-100%, the use of untypical for NPP remixed nuclear fuel without a careful study of the results of its application (at least after two operating periods of the research nuclear installations), the aging of operating personnel, and many other management actions of the State Corporation "Rosatom", should attract the attention of the Federal Service for Ecological, Technical and Atomic Supervision (RosTekhNadzor), but this doesn't happen. The paper considers safety issues of nuclear power plants operating in the Russian Federation. The authors collected statistical information on violations in NPP operation over the past 25 years, which shows that even after repeated relaxation over this period of time of safety regulation requirements in nuclear industry and highly expensive NPP modernization, the latter have not become more safe, and the statistics confirms this. At a lower utilization factor high-power pressure-tube reactors RBMK-1000, compared to light water reactors VVER-440 and 1000, have a greater number of violations and that after annual overhauls. A number of direct and root causes of NPP mulfunctions is still high and remains stable for decades. The paper reveals bottlenecks in ensuring nuclear and radiation safety of nuclear facilities. Main outstanding issues on the storage of spent nuclear fuel are defined. Information on emissions and discharges of radioactive substances, as well as fullness of storages of solid and liquid radioactive waste, located at the NPP sites are presented. Russian NPPs stress test results are submitted, as well as data on the coming removal from operation of NPP

  1. GIS based location optimization for mobile produced water treatment facilities in shale gas operations

    Science.gov (United States)

    Kitwadkar, Amol Hanmant

    Over 60% of the nation's total energy is supplied by oil and natural gas together and this demand for energy will continue to grow in the future (Radler et al. 2012). The growing demand is pushing the exploration and exploitation of onshore oil and natural gas reservoirs. Hydraulic fracturing has proven to not only create jobs and achieve economic growth, but also has proven to exert a lot of stress on natural resources---such as water. As water is one of the most important factors in the world of hydraulic fracturing, proper fluids management during the development of a field of operation is perhaps the key element to address a lot of these issues. Almost 30% of the water used during hydraulic fracturing comes out of the well in the form of flowback water during the first month after the well is fractured (Bai et. al. 2012). Handling this large amount of water coming out of the newly fractured wells is one of the major issues as the volume of the water after this period drops off and remains constant for a long time (Bai et. al. 2012) and permanent facilities can be constructed to take care of the water over a longer period. This paper illustrates development of a GIS based tool for optimizing the location of a mobile produced water treatment facility while development is still occurring. A methodology was developed based on a multi criteria decision analysis (MCDA) to optimize the location of the mobile treatment facilities. The criteria for MCDA include well density, ease of access (from roads considering truck hauls) and piping minimization if piping is used and water volume produced. The area of study is 72 square miles east of Greeley, CO in the Wattenberg Field in northeastern Colorado that will be developed for oil and gas production starting in the year 2014. A quarterly analysis is done so that we can observe the effect of future development plans and current circumstances on the location as we move from quarter to quarter. This will help the operators to

  2. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

  3. Grande Ronde Endemic Spring Chinook Salmon Supplementation Program; Satellite Facilities Operation and Maintenance, 2005 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    McLean, Michael L.; Seeger, Ryan; Hewitt, Laurie (Confederated Tribes of the Umatilla Indian Reservation, Department of Natural Resources, Pendleton, OR)

    2006-01-01

    prompting an early release. The total mortality for the acclimation period was 49 (0.05 %). The total number of fish released from the acclimation facility during the late period was 105,369. Maintenance and repair activities were conducted at the acclimation facilities in 2005. Facility maintenance work consisted of snow removal, installation of drainage lines, removal of gravel from intake area, installation of new gate at the CCAF, and complete overhaul of 2 travel trailers. The Catherine Creek Adult Capture Facility (CCACF) was put into operation on 11 February 2005. The first adult summer steelhead was captured on 4 March. A total of 190 adult summer steelhead were trapped and released from 4 March to 16 May 2005. Peak arrival at the trap was the week of 8 April. The first adult spring Chinook salmon was captured at CCACF on 6 May 2005. A total of 226 spring Chinook salmon were trapped from 6 May to 8 July 2005. There were 56 adults and 4 jacks unmarked and 136 adult and 30 jack marked spring Chinook salmon trapped. Peak arrival at the trap was the week of 10 June for the unmarked and marked fish. None of the captive broodstock returns were collected for broodstock. Broodstock was collected systematically over the entire return from 31 May to 6 July 2005. Ten of the 34 broodstock collected and transported from CCACF to LGH were unmarked fish trapped. About 18% of the naturally produced adult males and females trapped were taken to LGH for broodstock. One jack was collected for every 5 adult males that were taken to LGH. A total of 30 age 4 and 5 and 4 age 3 fish were transported to LGH for broodstock. The hatchery component of the broodstock was 66.7%. Five weekly spawning surveys were conducted below the weir on Catherine Creek beginning 30 June 2005. During these surveys no live or dead fish were observed. The trap was removed from Catherine Creek on 3 August 2005. Temperatures at the CCACF ranged from -0.1 C on 14 February to 23.7 C on 21 July. The hourly

  4. Comparison of cask and drywell storage concepts for a monitored retrievable storage/interim storage system

    Energy Technology Data Exchange (ETDEWEB)

    Rasmussen, D.E.

    1982-12-01

    The Department of Energy, through its Richland Operations Office is evaluating the feasibility, timing, and cost of providing a federal capability for storing the spent fuel, high-level wastes, and transuranic wastes that DOE may be obligated by law to manage until permanent waste disposal facilities are available. Three concepts utilizing a monitored retrievable storage/interim storage (MRS/IS) facility have been developed and analyzed. The first concept, co-location with a reprocessing plant, has been developed by staff of Allied General Nuclear Services. the second concept, a stand-alone facility, has been developed by staff of the General Atomic Company. The third concept, co-location with a deep geologic repository, has been developed by the Pacific Northwest Laboratory with the assistance of the Westinghouse Hanford Company and Kaiser Engineers. The objectives of this study are: to develop preconceptual designs for MRS/IS facilities: to examine various issues such as transportation of wastes, licensing of the facilities, and environmental concerns associated with operation of such facilities; and to estimate the life-cycle costs of the facilities when operated in response to a set of scenarios that define the quantities and types of waste requiring storage in specific time periods, generally spanning the years 1989 to 2037. Three scenarios are examined to develop estimates of life-cycle costs for the MRS/IS facilities. In the first scenario, the reprocessing plant is placed in service in 1989 and HLW canisters are stored until a repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at intervals as needed to meet the demand. In the second scenario, the reprocessing plants are delayed in starting operations by 10 years, but the repositories open on schedule. In the third scenario, the repositories are delayed 10 years, but the reprocessing plants open on schedule.

  5. 105-H Reactor Interim Safe Storage Project Final Report

    Energy Technology Data Exchange (ETDEWEB)

    E.G. Ison

    2008-11-08

    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&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.

  6. 76 FR 11291 - University of New Mexico AGN-201M Reactor Notice of Issuance of Renewed Facility Operating...

    Science.gov (United States)

    2011-03-01

    ... COMMISSION University of New Mexico AGN-201M Reactor Notice of Issuance of Renewed Facility Operating License... No. R-102, held by the University of New Mexico (the licensee), which authorizes continued operation of the University of New Mexico AGN-201M Reactor (UNMR), located in Albuquerque, Bernalillo...

  7. Wastewater Facilities Operation and Management. Instructor Guide. Working for Clean Water: An Information Program for Advisory Groups.

    Science.gov (United States)

    Long, David A.

    Local communities must be willing to spend funds to assure the proper operation and management of wastewater treatment facilities. Designed for citizen advisory groups, the one-hour learning session described in this instructor's manual covers problem areas, federal requirements, and responsibilities for wastewater plant operations and management.…

  8. Pilot plant operation of the Uranium Chip Oxidation Facility at the Y-12 Plant

    Energy Technology Data Exchange (ETDEWEB)

    Childs, Y.C.

    1987-01-16

    Due to changing environmental regulations, the current practice of depleted uranium chip (machine turning) disposal via shallow land burial has become environmentally objectionable. The chips are pyrophoric and oxidize rapidly when exposed to air; therefore, long-term storage of the uranium chips presents a major fire hazard. The Oak Ridge Y-12 Plant Development Division was contacted to devise a disposal method that would eliminate chip burial and minimize storage space requirements. The proposed method of accomplishing this task was oxidizing the uranium chips to uranium oxide (U/sub 3/O/sub 8/) under controlled conditions. Pilot plant operation of the Uranium Chip Oxidation Facility (UCOF) was initiated on May 20, 1985, by the Y-12 Development Division. The purpose of this initial development testing was to evaluate the equipment, determine operating parameters, and provide on-the-job training for Waste Treatment Operations (WTO) personnel. Startup of the UCOF began with the check-out of the equipment using only the No. 1 oxidizer. Following the verification stage, the oxidizer was loaded with an initial charge of cold uranium oxide (U/sub 3/O/sub 8/) in preparation for test burning. Results of the test are given.

  9. Innovative pollution prevention program at Air Force owned Raytheon operated facility incorporating Russian technology

    Energy Technology Data Exchange (ETDEWEB)

    Stallings, J.H.; Cepeda-Calderon, S.

    1999-07-01

    Air Force Plant 44 in Tucson, Arizona is owned by the Air Force and operated by Raytheon Missile Systems Company. A joint Air Force/Raytheon Pollution Prevention Team operates at AFP 44 with the ultimate goal to minimize or eliminate the use of hazardous substances. The team works together to uncover new technologies and methods that will replace chemicals used in the plant's missile manufacturing facilities. The program maximizes pollution prevention by first eliminating hazardous material use, then chemical recycling, next hazardous waste reduction and finally wastewater treatment and recycling. From fiscal years 1994 through 1997, nine pollution prevention projects have been implemented, totaling $2.6 million, with a payback averaging less than two years. A unique wastewater treatment method has been demonstrated as part of this program. This is electroflotation, a Russian technology which removes dispersed particles from liquid with gas bubbles obtained during water electrolysis. A unit was built in the US which successfully removed organic emulsions from wastewater. Operational units are planned for the removal of waste from waterfall paint booths. The pollution prevention joint team continues to be very active with two projects underway in FY 98 and two more funded for FY 99.

  10. Initial closed operation of the CELSS Test Facility Engineering Development Unit

    Science.gov (United States)

    Kliss, M.; Blackwell, C.; Zografos, A.; Drews, M.; MacElroy, R.; McKenna, R.; Heyenga, A. G.

    2003-01-01

    As part of the NASA Advanced Life Support Flight Program, a Controlled Ecological Life Support System (CELSS) Test Facility Engineering Development Unit has been constructed and is undergoing initial operational testing at NASA Ames Research Center. The Engineering Development Unit (EDU) is a tightly closed, stringently controlled, ground-based testbed which provides a broad range of environmental conditions under which a variety of CELSS higher plant crops can be grown. Although the EDU was developed primarily to provide near-term engineering data and a realistic determination of the subsystem and system requirements necessary for the fabrication of a comparable flight unit, the EDU has also provided a means to evaluate plant crop productivity and physiology under controlled conditions. This paper describes the initial closed operational testing of the EDU, with emphasis on the hardware performance capabilities. Measured performance data during a 28-day closed operation period are compared with the specified functional requirements, and an example of inferring crop growth parameters from the test data is presented. Plans for future science and technology testing are also discussed. Published by Elsevier Science Ltd on behalf of COSPAR.

  11. Analysis of 2016 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Aluzzi, F. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-03-16

    Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, N.Y. and the Kesselring Site Operations (KSO) facility near Ballston Spa, N.Y. are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the U.S. Environmental Protection Agency (EPA), which regulates both sites. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted to process the meteorological tower data for the 2016 calendar year from both on-site meteorological towers.

  12. Analysis of 2015 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Aluzzi, F. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-02-19

    Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, N.Y. and the Kesselring Site Operations (KSO) facility near Ballston Spa, N.Y. are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the U.S. Environmental Protection Agency (EPA), which regulates both sites. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted to process the meteorological tower data for the 2015 calendar year from both on-site meteorological towers.

  13. Treatment of defective fuel rods for interim storage

    Energy Technology Data Exchange (ETDEWEB)

    Muenchow, K.; Hummel, W. [AREVA NP GmbH, Erlangen (Germany)

    2013-07-01

    In this paper we look exclusively at the treatment of defective fuel rods for long-term dry interim storage at the nuclear power plant, in order to avoid off-site transports. AREVA has developed a technique that allows verifiably adequate drying of the defective fuel rods and reconstructs the barrier for retaining radioactive materials. This is done by individually encapsulating the defective fuel rods and achieving gas-tightness by seal welding. This guarantees the retention of radioactive materials during the storage period of at least 40 years in a transport and storage flask in an interim storage facility at site. (orig.)

  14. Interim Assessments: A User's Guide

    Science.gov (United States)

    Marshall, Kim

    2008-01-01

    Interim assessments are hot in American schools. Also called benchmark or periodic tests, these assessments are given every four to nine weeks to check on students' progress. Although interim assessments are an important tool for school improvement, they are easy to misuse. In the author's work coaching principals in a number of districts, he has…

  15. Guidance: Interim Municipal Settlement Policy

    Science.gov (United States)

    Interim guidance and fact sheets regarding settlements involving municipalities or municipal waste under Section 122 CERCLA as amended by SARA. Interim policy sets forth the criteria by which EPA generally determines whether to exercise enforcement discretion to pursue MSW generators and transporters as PRPs.

  16. Installation and first operation of the International Fusion Materials Irradiation Facility injector at the Rokkasho site

    Energy Technology Data Exchange (ETDEWEB)

    Gobin, Raphael, E-mail: rjgobin@cea.fr; Bogard, Daniel; Bolzon, Benoit; Bourdelle, Gilles; Chauvin, Nicolas; Chel, Stéphane; Girardot, Patrick; Gomes, Adelino; Guiho, Patrice; Harrault, Francis; Loiseau, Denis; Lussignol, Yves; Misiara, Nicolas; Roger, Arnaud; Senée, Franck; Valette, Matthieu [Commissariat à l’Energie Atomique et aux Energies Alternatives, CEA/Saclay, DSM/IRFU, 91191 Gif/Yvette (France); Cara, Philippe; Duglué, Daniel; Gex, Dominique [Fusion for Energy, BFD Department, Garching (Germany); Okumura, Yoshikazu [IFMIF/EVEDA Project Team, Obuchi-Omotedate, 2-166, Rokkasho, Aomori (Japan); and others

    2016-02-15

    The International Fusion Materials Irradiation Facility (IFMIF) linear IFMIF prototype accelerator injector dedicated to high intensity deuteron beam production has been designed, built, and tested at CEA/Saclay between 2008 and 2012. After the completion of the acceptance tests at Saclay, the injector has been fully sent to Japan. The re-assembly of the injector has been performed between March and May 2014. Then after the check-out phase, the production of the first proton beam occurred in November 2014. Hydrogen and deuteron beam commissioning is now in progress after having proceeded with the final tests on the entire injector equipment including high power diagnostics. This article reports the different phases of the injector installation pointing out the safety and security needs, as well as the first beam production results in Japan and chopper tests. Detailed operation and commissioning results (with H{sup +} and D{sup +} 100 keV beams) are reported in a second article.

  17. Dental emergency rates at two expeditionary medical support facilities supporting operations enduring and Iraqi Freedom.

    Science.gov (United States)

    Dunn, William J; Langsten, Robert E; Flores, Salvador; Fandell, Jay E

    2004-07-01

    This study reports dental emergency rates and distribution of causes of dental emergencies at two expeditionary medical support facilities supporting operations Enduring Freedom/ Iraqi Freedom. A retrospective cohort analysis of 9948 soldiers deployed to Prince Sultan Air Base, Kingdom of Saudi Arabia, and 1467 soldiers at Baghdad International Airport, Iraq, was accomplished from a phased deployment from January 2003 to September 2003. Procedures were divided into 11 categories: endodontic, extraction of teeth other than third molars, extraction of third molar teeth, restoration of teeth (caries), restoration of broken teeth (not caries), orthodontic bracket/wire problem, sensitive teeth, temperomandibular pain, periodontal, oral pathology, and prosthodontic. The dental emergency rates for Prince Sultan Air Base and Baghdad International Airport were 153 and 145 dental emergencies per 1000 soldiers per year, respectively. Most of the emergencies were because of dental caries. Pain from third molars was the second most common reason for visiting the dental clinic.

  18. First Operating Experiences of Beam Position Monitors in the TESLA Test Facility Linac

    Science.gov (United States)

    Lorenz, R.; Sachwitz, M.; Schreiber, H. J.; Tonisch, F.; Castellano, M.; Patteri, P.; Tazzioli, F.; Catani, L.

    1997-05-01

    Different types of monitors where installed in the TESLA Test Facility Linac to measure the beam position. At each superconducting quadrupole, the transverse beam position will be measured with a resolution of better than 10 μm, using a cylindrical cavity excited in the TM_110-mode by an off-center beam. In addition, two 'warm' cavities working at room temperature were built for the Injector I and the Bunch Compressor. The amplitude of the TM_110-mode and its phase are measured in a homodyne receiver. For the experimental area, stripline monitors having a resolution of better than 100 μm were built, tested and installed. The averaged position of the whole bunch train of Injector I is measured in a narrowband receiver using the amplitude-to-phase conversion. This paper summarizes the designs, cold tests and first operating experiences of both monitor types.

  19. Transient validation of RELAP5 model with the DISS facility in once through operation mode

    Science.gov (United States)

    Serrano-Aguilera, J. J.; Valenzuela, L.

    2016-05-01

    Thermal-hydraulic code RELAP5 has been used to model a Solar Direct Steam Generation (DSG) system. Experimental data from the DISS facility located at Plataforma Solar de Almería is compared to the numerical results of the RELAP5 model in order to validate it. Both the model and the experimental set-up are in once through operation mode where no injection or active control is regarded. Time dependent boundary conditions are taken into account. This work is a preliminary study of further research that will be carried out in order to achieve a thorough validation of RELAP5 models in the context of DSG in line-focus solar collectors.

  20. 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.

  1. PROJECT W-551 SUMMARY INFORMATION FOR EARLY LAW INTERIM PRETREATMENT SYSTEM SELECTION

    Energy Technology Data Exchange (ETDEWEB)

    AR, TEDESCHI

    2008-08-11

    This report provides summary data for use by the decision board to assess and select the final 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-fonnaldebyde resin. This document provides a summary of comparative data against prior weighted criteria to support technology selection. Supporting details and background for this summary are documented in the separate report, RPP-RPT-37741.

  2. 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.

  3. Deployment, Commissioning and Operation of Plasma Electrode Pockels Cells in the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, P A; Ollis, C W; Hinz, A; Robb, C; Primdahl, K A; Watson, J J; O' Brien, M D; Funkhouser, W G; Biltoft, P J; Shelton, R T; Tapley, W C; DeHope, W J

    2003-12-01

    Large aperture Plasma Electrode Pockels Cells (PEPCs) are an enabling technology in the National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory. The Pockels cells allow the NIF laser to take advantage of multipass main amplifier architecture, thus reducing costs and physical size of the facility. Each Pockels cell comprises four 40-cm x 40-cm apertures arranged in a 4 x 1 array. The combination of the Pockels cell and a thin-film polarizer, also configured in a 4 x 1 array, forms an optical switch that is key to achieving the required multi-pass operation. The operation of the PEPC is a follows: Before the arrival of the laser pulse, optically transparent, low-density helium plasmas are initiated to serve as electrodes for the KDP crystals mounted in the Pockels cell. During beam propagation through the main laser cavity a longitudinal electric field is impressed on the electro-optic crystals. The polarization of the propagating beams is rotated by 90{sup o} on each of two passes, thereby allowing the beam to be trapped in the main laser amplifier cavity for a total of four passes before being switched out into the cavity spatial filter. The physics aspects of the PEPC are well documented. Consequently, this paper will emphasize the PEPC subsystem in the context of its role and relevance within the broader NIF laser system, provide a view of the complexity of the subsystem and give an overview of PEPC's interactions with other elements of NIF, including interfaces to the Beamline Infrastructure, the NIF Timing Subsystem, and the Integrated Computer Control System (ICCS); along with dependence on the Optics Production, Transport and Handling (T&H), and Assembly, Integration and Refurbishment (AIR) and Operations organizations. Further, we will discuss implementation details related to the functional blocks and individual components that comprise PEPC, with particular emphasis on the unique constraints placed on the elements and the

  4. The development and operation of the international solar-terrestrial physics central data handling facility

    Science.gov (United States)

    Lehtonen, Kenneth

    1994-01-01

    The National Aeronautics and Space Administration (NASA) Goddard Space Flight Center (GSFC) International Solar-Terrestrial Physics (ISTP) Program is committed to the development of a comprehensive, multi-mission ground data system which will support a variety of national and international scientific missions in an effort to study the flow of energy from the sun through the Earth-space environment, known as the geospace. A major component of the ISTP ground data system is an ISTP-dedicated Central Data Handling Facility (CDHF). Acquisition, development, and operation of the ISTP CDHF were delegated by the ISTP Project Office within the Flight Projects Directorate to the Information Processing Division (IPD) within the Mission Operations and Data Systems Directorate (MO&DSD). The ISTP CDHF supports the receipt, storage, and electronic access of the full complement of ISTP Level-zero science data; serves as the linchpin for the centralized processing and long-term storage of all key parameters generated either by the ISTP CDHF itself or received from external, ISTP Program approved sources; and provides the required networking and 'science-friendly' interfaces for the ISTP investigators. Once connected to the ISTP CDHF, the online catalog of key parameters can be browsed from their remote processing facilities for the immediate electronic receipt of selected key parameters using the NASA Science Internet (NSI), managed by NASA's Ames Research Center. The purpose of this paper is twofold: (1) to describe how the ISTP CDHF was successfully implemented and operated to support initially the Japanese Geomagnetic Tail (GEOTAIL) mission and correlative science investigations, and (2) to describe how the ISTP CDHF has been enhanced to support ongoing as well as future ISTP missions. Emphasis will be placed on how various project management approaches were undertaken that proved to be highly effective in delivering an operational ISTP CDHF to the Project on schedule and

  5. Solar production of industrial process hot water: operation and evaluation of the Campbell Soup hot water solar facility. Final report, September 1, 1979-December 10, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Kull, J. I.; Niemeyer, W. N.; Youngblood, S. B.

    1980-12-01

    The operation and evaluation of a solar hot water facility designed by Acurex Corporation and installed (November 1977) at the Campbell Soup Company Sacramento, California canning plant is summarized. The period of evaluation was for 12 months from October 1979 through September 1980. The objective of the work was to obtain additional, long term data on the operation and performance of the facility. Minor modifications to the facility were completed. The system was operated for 15 months, and 12 months of detailed data were evaluated. The facility was available for operation 99% of the time during the last 8 months of evaluation. A detailed description of the solar facility and of the operating experience is given, and a summary of system performance for the 12 month operation/evaluation period is presented. Recommendations for large-scale solar facilities based on this project's experience are given, and an environmental impact assessment for the Campbell Soup solar facility is provided. (WHK)

  6. Effectiveness Monitoring Report, MWMF Tritium Phytoremediation Interim Measures.

    Energy Technology Data Exchange (ETDEWEB)

    Hitchcock, Dan; Blake, John, I.

    2003-02-10

    This report describes and presents the results of monitoring activities during irrigation operations for the calendar year 2001 of the MWMF Interim Measures Tritium Phytoremediation Project. The purpose of this effectiveness monitoring report is to provide the information on instrument performance, analysis of CY2001 measurements, and critical relationships needed to manage irrigation operations, estimate efficiency and validate the water and tritium balance model.

  7. Recommended management practices for operation and closure of shallow injection wells at DOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    The Safe Drinking Water Act established the Underground Injection Control (UIC) program to ensure that underground injection of wastes does not endanger an underground source of drinking water. Under UIC regulations, an injection well is a hole in the ground, deeper than it is wide, that receives wastes or other fluid substances. Types of injection wells range from deep cased wells to shallow sumps, drywells, and drainfields. The report describes the five classes of UIC wells and summarizes relevant regulations for each class of wells and for the UIC program. The main focus of the report is Class IV and V shallow injection wells. Class IV wells are prohibited and should be closed when they are identified. Class V wells are generally authorized by rule, but EPA or a delegated state may require a permit for a Class V well. This report provides recommendations on sound operating and closure practices for shallow injection wells. In addition the report contains copies of several relevant EPA documents that provide additional information on well operation and closure. Another appendix contains information on the UIC programs in 21 states in which there are DOE facilities discharging to injection wells. The appendix includes the name of the responsible regulatory agency and contact person, a summary of differences between the state`s regulations and Federal regulations, and any closure guidelines for Class IV and V wells.

  8. 33 CFR 385.38 - Interim goals.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Interim goals. 385.38 Section 385... System and Water Availability Consistent With the Goals and Purpose of the Plan § 385.38 Interim goals... Interim Goals Agreement establishing interim goals to facilitate inter-agency planning, monitoring,...

  9. 40 CFR 262.212 - Making the hazardous waste determination at an on-site interim status or permitted treatment...

    Science.gov (United States)

    2010-07-01

    ....212 Making the hazardous waste determination at an on-site interim status or permitted treatment... hazardous waste permit or interim status as soon as it arrives in the on-site treatment, storage or disposal... permitted treatment, storage or disposal facility. (e) If the unwanted material is a hazardous waste, the...

  10. 40 CFR 257.3-5 - Application to land used for the production of food-chain crops (interim final).

    Science.gov (United States)

    2010-07-01

    ... possible health hazard. (b) Polychlorinated Biphenyls (PCBs). Solid waste containing concentrations of PCBs... production of food-chain crops (interim final). 257.3-5 Section 257.3-5 Protection of Environment... Application to land used for the production of food-chain crops (interim final). (a) Cadmium. A facility or...

  11. Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.

  12. Effects of Interim Assessments on the Achievement Gap: Evidence from an Experiment

    Science.gov (United States)

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

    2015-01-01

    Motivated by the passage of the No Child Left Behind (NCLB) Act, all states operate accountability systems that measure and report school and student performance annually. The purpose of this study is to examine the effects of interim assessments on the achievement gap. The authors examine the impact of interim assessments throughout the…

  13. NDRC Released the Interim Measures on Voluntary Emission Reductions of GHG Trading and Management

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    National Development and Reform Commission issued the Interim Measures on Voluntary Emission Reduction of GHG Trading and Management (hereafter referred to as" Interim Measures") on June, 13th, 2012, which is formulated to encourage project-based voluntary emission reductions and ensure the proper operation of trading activities.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-06-01

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

  15. Operational climate monitoring from space: the EUMETSAT satellite application facility on climate monitoring (CM-SAF

    Directory of Open Access Journals (Sweden)

    J. Schulz

    2008-05-01

    Full Text Available The Satellite Application Facility on Climate Monitoring (CM-SAF aims at the provision of satellite-derived geophysical parameter data sets suitable for climate monitoring. CM-SAF provides climatologies for Essential Climate Variables (ECV, as required by the Global Climate Observing System implementation plan in support of the UNFCCC. Several cloud parameters, surface albedo, radiation fluxes at the top of the atmosphere and at the surface as well as atmospheric temperature and humidity products form a sound basis for climate monitoring of the atmosphere. The products are categorized in monitoring data sets obtained in near real time and data sets based on carefully intercalibrated radiances. The CM-SAF products are derived from several instruments on-board operational satellites in geostationary and polar orbit, i.e., the Meteosat and NOAA satellites, respectively. The existing data sets will be continued using data from the instruments on-board the new EUMETSAT Meteorological Operational satellite (MetOP. The products have mostly been validated against several ground-based data sets both in situ and remotely sensed. The accomplished accuracy for products derived in near real time is sufficient to monitor variability on diurnal and seasonal scales. Products based on intercalibrated radiance data can also be used for climate variability analysis up to inter-annual scale. A central goal of the recently started Continuous Development and Operations Phase of the CM-SAF (2007–2012 is to further improve all CM-SAF data sets to a quality level that allows for studies of inter-annual variability.

  16. Air emission points for facilities in Iowa with operating permits for Title V of the Federal Clean Air Act_considered MAJOR permits

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Air emission points for facilities in Iowa with operating permits for Title V of the Federal Clean Air Act, considered "major" permits. Also includes emission points...

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

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    2000-11-18

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

  18. Future proton and mixed-field irradiation facilities with slow extraction for LHC operation phase and for LHC upgrades

    CERN Document Server

    Assmann, Ralph Wolfgang; Brugger, Markus; Efthymiopoulos, Ilias; Feldbaumer, Eduard; Garrido, Mar Capeans; Glaser, Maurice; Kramer, Daniel; Linssen, Lucie; Losito, Roberto; Moll, Michael; Rembser, Christoph; Silari, Marco; Thurel, Yves; Tsesmelis, Emmanuel; Vincke, Helmut; CERN. Geneva. The LHC experiments Committee; LHCC

    2010-01-01

    In the present proposal we present the need for improved proton and mixed-field irradiation facilities with slow beam extraction at CERN. Strong needs are expressed by both the detector and accelerator communities and concern the LHC operation era as well as the upgrades of machine and experiments. The current facilities and test areas have a number of limitations and drawbacks. Preliminary studies indicate that there are possibilities for a coherent and cost-effective approach towards improved facilities for the future. The aim of this document is to inform the LHCC and seek its recognition for the need of such facilities. In addition we would appreciate the support of the LHCC for pursuing further implementation studies at a PS East Hall location.

  19. Operation of a fast diamond γ-ray detector at the HIγS facility

    Energy Technology Data Exchange (ETDEWEB)

    Williams, T.; N' Diaye, C.; Breton, D.; Cassou, K.; Dupraz, K.; Favier, P.; Jehanno, D.; Kubytskyi, V.; Liu, X.; Maalmi, J.; Martens, A.; Peinaud, Y.; Stocchi, A.; Zomer, F. [LAL, Univ Paris-Sud, CNRS/IN2P3, Université Paris-Saclay, Orsay (France); Griesmayer, E.; Kavrigin, P. [Vienna University of Technology (Austria); Ahmed, M.W. [Triangle Universities Nuclear Laboratory, Durham, NC 27708 (United States); Physics Department, Duke University, Durham, NC 27708 (United States); Department of Mathematics and Physics, North Carolina Central University, Durham, NC 27707 (United States); Sikora, M.; Weller, H.R. [Triangle Universities Nuclear Laboratory, Durham, NC 27708 (United States); Physics Department, Duke University, Durham, NC 27708 (United States)

    2016-09-11

    Operations of a diamond sensor placed in a high average-intensity beam of photons with energies of a few MeV are reported. Data was taken at the HIγS facility of TUNL in parasitic mode while nuclear-physics experiments were taking place. The energies of the photons during data taking were 2, 3 and 7 MeV with circular and linear polarisations of the photon beam. The collected charge appears to be constant at these energies, which is consistent with simulations. A dedicated run with bunches of photons separated by 16 ns shows that they are unambiguously distinguished. This is possible thanks to a FWHM of the pulses measured to be about 6 ns. The results indicate that the tested apparatus fulfils the requirements for a fast monitoring detector for the ELI-NP source currently under construction, which motivates this work, and demonstrates for the first time the capabilities of such detectors in high average-intensity photon beams.

  20. Progress of the ELISE test facility: results of caesium operation with low RF power

    Science.gov (United States)

    Franzen, P.; Fantz, U.; Wünderlich, D.; Heinemann, B.; Riedl, R.; Kraus, W.; Fröschle, M.; Ruf, B.; Nocentini, R.; the NNBI Team

    2015-05-01

    The Max-Planck-Institut für Plasmaphysik test facility ELISE is an important intermediate step towards the in-time realization of the ITER neutral beam injection system (NBI). ELISE is equipped with a large radio-frequency (RF) driven negative hydrogen ion source (1 × 0.9 m2) of half the size of the ITER NBI source. The paper reports on the main results of the very first operation of the source with caesium, but with low RF power, both for hydrogen and deuterium, with pulse lengths of up to 500 s. The results are rather encouraging for the achievement of the required ITER NBI parameters, especially in hydrogen, where large current densities with respect to the low RF power could be achieved at a ratio of co-extracted electrons to extracted ions of 0.5-0.6 at the relevant source pressure of 0.3 Pa. The required magnetic filter field was significantly lower than expected from the experience with the prototype RF source. Similar large extracted ion currents could be achieved also in deuterium, but with larger amounts of co-extracted electrons. Here, the required ratio of co-extracted electrons to extracted ions of one could be achieved only in short pulses.

  1. Dental emergency rates at an expeditionary medical support facility supporting Operation Enduring Freedom.

    Science.gov (United States)

    Dunn, William Jackson

    2004-05-01

    The purpose of this study was to report the dental emergency rate and the distribution of cause of dental emergencies at an Expeditionary Medical Support +25 medical facility during a 6-month deployment in support of Operation Enduring Freedom. A retrospective cohort analysis of 1,972 soldiers stationed at Seeb Air Base, Sultanate of Oman, was accomplished from a phased deployment from March to September 2002. Procedures were divided into 11 categories: endodontic, extraction of teeth other than third molars, extraction of third molar teeth, restoration of teeth (caries), restoration of broken teeth (not caries), orthodontic bracket/wire problem, sensitive teeth, temperomandibular pain, periodontal, oral pathology, and prosthodontic. One hundred thirty-five dental emergency visits were recorded, corresponding to a rate of 137 dental emergencies per 1,000 soldiers per year. Most of the emergencies (34.8%) were due to caries. Pain from third molars was the second most common reason for visiting the dental clinic (19.3%).

  2. Characterization of the radiation environment at the UNLV accelerator facility during operation of the Varian M6 linac

    Science.gov (United States)

    Hodges, M.; Barzilov, A.; Chen, Y.; Lowe, D.

    2016-10-01

    The bremsstrahlung photon flux from the UNLV particle accelerator (Varian M6 model) was determined using MCNP5 code for 3 MeV and 6 MeV incident electrons. Human biological equivalent dose rates due to accelerator operation were evaluated using the photon flux with the flux-to-dose conversion factors. Dose rates were computed for the accelerator facility for M6 linac use under different operating conditions. The results showed that the use of collimators and linac internal shielding significantly reduced the dose rates throughout the facility. It was shown that the walls of the facility, in addition to the earthen berm enveloping the building, provide equivalent shielding to reduce dose rates outside to below the 2 mrem/h limit.

  3. Department of Energy’s ARM Climate Research Facility External Data Center Operations Plan Located At Brookhaven National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Cialella, A. [Brookhaven National Lab. (BNL), Upton, NY (United States); Gregory, L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Lazar, K. [Brookhaven National Lab. (BNL), Upton, NY (United States); Liang, M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Ma, L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Tilp, A. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wagener, R. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-05-01

    The External Data Center (XDC) Operations Plan describes the activities performed to manage the XDC, located at Brookhaven National Laboratory (BNL), for the Department of Energy’s Atmospheric Radiation Measurement (ARM) Climate Research Facility. It includes all ARM infrastructure activities performed by the Data Management and Software Engineering Group (DMSE) at BNL. This plan establishes a baseline of expectation within the ARM Operations Management for the group managing the XDC.

  4. 76 FR 62868 - Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76

    Science.gov (United States)

    2011-10-11

    ... COMMISSION Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76... No. R- 76. ADDRESSES: You can access publicly available documents related to this notice using the... License No. R-76, held by the Washington State University (WSU, the licensee), which authorizes...

  5. 26 CFR 1.132-7T - Treatment of employer-operated eating facilities-1985 through 1988 (temporary).

    Science.gov (United States)

    2010-04-01

    ... proportion as time spent on the premises bears to total time is included in direct operating costs. For... (temporary). (a) In general—(1) General rule. The value of meals provided to employees at an employer... meals furnished at the facility are provided during, or immediately before or after, the employee's...

  6. How School Facilities Managers and Business Officials Are Reducing Operating Costs and Saving Money. Energy-Smart Building Choices.

    Science.gov (United States)

    Department of Energy, Washington, DC.

    This guide addresses contributions that school facility administrators and business officials can make in an effort to reduce operating costs and free up money for capital improvements. The guide explores opportunities available to utilize energy-saving strategies at any stage in a building's life, from its initial design phase through renovation.…

  7. Simulation of mass storage systems operating in a large data processing facility

    Science.gov (United States)

    Holmes, R.

    1972-01-01

    A mass storage simulation program was written to aid system designers in the design of a data processing facility. It acts as a tool for measuring the overall effect on the facility of on-line mass storage systems, and it provides the means of measuring and comparing the performance of competing mass storage systems. The performance of the simulation program is demonstrated.

  8. General certification procedure of enterprises and interim job enterprises; Procedure generale de certification des entreprises et entreprises de travail temporaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    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.)

  9. Hanford environment as related to radioactive waste burial grounds and transuranium waste storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D.J.; Isaacson, R.E.

    1977-06-01

    A detailed characterization of the existing environment at Hanford was provided by the U.S. Energy Research and Development Administration (ERDA) in the Final Environmental Statement, Waste Management Operations, Hanford Reservation, Richland, Washington, December 1975. Abbreviated discussions from that document are presented together with current data, as they pertain to radioactive waste burial grounds and interim transuranic (TRU) waste storage facilities. The discussions and data are presented in sections on geology, hydrology, ecology, and natural phenomena. (JRD)

  10. Interim Sanitary Landfill Groundwater Monitoring Report (1998 Annual Report)

    Energy Technology Data Exchange (ETDEWEB)

    Wells, D.

    1999-03-18

    The SRS Interim Sanitary Landfill opened in Mid-1992 and operated until 1998 under Domestic Waste Permit No. 025500-1120. Several contaminants have been detected in the groundwater beneath the unit.The well sampling and analyses were conducted in accordance with Procedure 3Q5, Hydrogeologic Data Collection.

  11. Single Shell Tank (SST) Interim Stabilization Project Plan

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-05-22

    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.

  12. New Pump and Treat Facility Remedial Action Work Plan for Test Area North (TAN) Final Groundwater Remediation, Operable Unit 1-07B

    Energy Technology Data Exchange (ETDEWEB)

    L. O. Nelson

    2003-09-01

    This operations and maintenance plan supports the New Pump and Treat Facility (NPTF) remedial action work plan and identifies the approach and requirements for the operations and maintenance activities specific to the final medical zone treatment remedy. The NPTF provides the treatment system necessary to remediate the medical zone portion of the OU 1-07B contaminated groundwater plume. Design and construction of the New Pump and Treat Facility is addressed in the NPTF remedial action work plan. The scope of this operation and maintenance plan includes facility operations and maintenance, remedy five-year reviews, and the final operations and maintenance report for the NPTF.

  13. 75 FR 30372 - Foreign-Trade Zone 196 Temporary/Interim Manufacturing Authority ATC Logistics & Electronics...

    Science.gov (United States)

    2010-06-01

    ... & Electronics (Cell Phone Kitting and Distribution); Notice of Approval On March 30, 2010, the Executive... & Electronics, operator of Site 2, FTZ 196, requesting temporary/interim manufacturing (T/IM) authority...

  14. LANDFILLS AS BIOREACTORS: RESEARH AT THE OUTER LOOP LANDFILL, LOUISVILLE, KENTUCKY; FIRST INTERIM REPORT

    Science.gov (United States)

    Interim report resulting from a cooperative research and development agreement (CRADA) between US EP A's Officeof Research and Development - National Risk Management Research Laboratory and a n ongoing field demonstrationof municipal waste landfills being operated as bioreact...

  15. 78 FR 56752 - Interim Staff Guidance Specific Environmental Guidance for Integral Pressurized Water Reactors...

    Science.gov (United States)

    2013-09-13

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Interim Staff Guidance Specific Environmental Guidance for Integral Pressurized Water Reactors... and operate integral pressurized water reactors (iPWR). This guidance applies to environmental reviews...

  16. Scoping Calculations for Potential Groundwater Impacts from Operation of the APT Facility at SRS

    Energy Technology Data Exchange (ETDEWEB)

    Thibault, J.J.

    1999-10-07

    The purpose of this study was to determine the potential travel times and paths of the postulated activated groundwater beneath the facility and to examine the fate and transport of this activated groundwater.

  17. Straighttalk. The ideal master facility plan begins with business strategy and integrates operational improvement.

    Science.gov (United States)

    Powder, Scott; Brown, Richard E; Haupert, John M; Smith, Ryder

    2007-04-02

    Given the scarcity of capital to meet ever-growing demands for healthcare services, master facility planning has become more important than ever. Executives must align their master facility plans with their overall business strategy, incorporating the best in care- and service-delivery models. In this installment of Straight Talk, executives from two health systems--Advocate Health Care in Oak Brook, Ill. and Parkland Health & Hospital System in Dallas--discuss master facility planning. Modern Healthcare and PricewaterhouseCoopers present Straight Talk. The session on master facility planning was held on March 8, 2007 at Modern Healthcare's Chicago Headquarters. Charles Lauer, former vice president of publishing and editorial director at Modern Healthcare, was the moderator.

  18. CERCLA interim action at the Par Pond unit: A case study

    Energy Technology Data Exchange (ETDEWEB)

    Hickey, H.M. [Westinghouse Savannah River Co., Aiken, SC (United States); Matthews, S.S.; Neal, L.W. [Rust Environment and Infrastructure, Inc., Greenville, SC (United States); Weiss, W.R. [Rust Environment and Infrastructure, Inc., Aiken, SC (United States)

    1993-11-01

    The Par Pond unit designated under CERCLA consists of sediments within a Savannah River Site (SRS) cooling water reservoir. The sediments are contaminated with radionuclides and nonradioactive constituents from nuclear production reactor operations. The mercury in Par Pond is believed to have originated from the Savannah River. Because of Par Pond Dam safety Issues, the water level of the reservoir was drawn down, exposing more than 1300 acres of contaminated sediments and triggering the need for CERCLA interim remedial action. This paper presents the interim action approach taken with Par Pond as a case study. The approach considered the complexity of the Par Pond ecosystem, the large size of Par Pond, the volume of contaminated sediments, and the institutional controls existing at SRS. The Environmental Protection Agency (EPA) considers units with large volumes of low-concentration wastes, as is the case with Par Pond, to be {open_quotes}special sites.{close_quotes} Accordingly, EPA guidance establishes that the range of alternatives developed focus primarily on containment options and other remedial approaches that mitigate potential risks associated with the {open_quotes}special site.{close_quotes} The remedial alternatives, according to EPA, are not to be prohibitively expensive or difficult to implement. This case study also is representative of the types of issues that will need to be addressed within the Department of Energy (DOE) complex as nuclear facilities are transitioned to inactive status and corrective/remedial actions are warranted.

  19. Evaluating the relative impacts of operational and financial factors on the competitiveness of an algal biofuel production facility.

    Science.gov (United States)

    Hise, Adam M; Characklis, Gregory W; Kern, Jordan; Gerlach, Robin; Viamajala, Sridhar; Gardner, Robert D; Vadlamani, Agasteswar

    2016-11-01

    Algal biofuels are becoming more economically competitive due to technological advances and government subsidies offering tax benefits and lower cost financing. These factors are linked, however, as the value of technical advances is affected by modeling assumptions regarding the growth conditions, process design, and financing of the production facility into which novel techniques are incorporated. Two such techniques, related to algal growth and dewatering, are evaluated in representative operating and financing scenarios using an integrated techno-economic model. Results suggest that these techniques can be valuable under specified conditions, but also that investment subsidies influence cost competitive facility design by incentivizing development of more capital intensive facilities (e.g., favoring hydrothermal liquefaction over transesterification-based facilities). Evaluating novel techniques under a variety of operational and financial scenarios highlights the set of site-specific conditions in which technical advances are most valuable, while also demonstrating the influence of subsidies linked to capital intensity. Copyright © 2016 Elsevier Ltd. All rights reserved.

  20. The planning, construction, and operation of a radioactive waste storage facility for an Australian state radiation regulatory authority

    Energy Technology Data Exchange (ETDEWEB)

    Wallace, J.D.; Kleinschmidt, R.; Veevers, P. [Radiation Health, Queensland (Australia)

    1995-12-31

    Radiation regulatory authorities have a responsibility for the management of radioactive waste. This, more often than not, includes the collection and safe storage of radioactive sources in disused radiation devices and devices seized by the regulatory authority following an accident, abandonment or unauthorised use. The public aversion to all things radioactive, regardless of the safety controls, together with the Not In My Back Yard (NIMBY) syndrome combine to make the establishment of a radioactive materials store a near impossible task, despite the fact that such a facility is a fundamental tool for regulatory authorities to provide for the radiation safety of the public. In Queensland the successful completion and operational use of such a storage facility has taken a total of 8 years of concerted effort by the staff of the regulatory authority, the expenditure of over $2 million (AUS) not including regulatory staff costs and the cost of construction of an earlier separate facility. This paper is a summary of the major developments in the planning, construction and eventual operation of the facility including technical and administrative details, together with the lessons learned from the perspective of the overall project.

  1. Initial operation of a solar heating and cooling system in a full-scale solar building test facility

    Science.gov (United States)

    Knoll, R. H.; Miao, D.; Hamlet, I. L.; Jensen, R. N.

    1976-01-01

    The Solar Building Test Facility (SBTF) located at Hampton, Virginia became operational in early summer of 1976. This facility is a joint effort by NASA-Lewis and NASA-Langley to advance the technology for heating and cooling of office buildings with solar energy. Its purposes are to (1) test system components which include high-performing collectors, (2) test performance of complete solar heating and cooling system, (3) investigate component interactions and (4) investigate durability, maintenance and reliability of components. The SBTF consists of a 50,000 square foot office building modified to accept solar heated water for operation of an absorption air conditioner and for the baseboard heating system. A 12,666 square foot solar collector field with a 30,000 gallon storage tank provides the solar heated water. A description of the system and the collectors selected is given here, along with the objectives, test approach, expected system performance and some preliminary results.

  2. The status of LILW disposal facility construction in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min-Seok; Chung, Myung-Sub; Park, Kyu-Wan [Korea Radioactive Waste Management Corporation (KRMC), 89, Bukseong-ro, Gyeongju-si,, Gyeongsangbuk-do (Korea, Republic of)

    2013-07-01

    In this paper, we discuss the experiences during the construction of the first LILW disposal facility in South Korea. In December 2005, the South Korean Government designated Gyeongju-city as a host city of Low- and Intermediate-Level Radioactive Waste(LILW) disposal site through local referendums held in regions whose local governments had applied to host disposal facility in accordance with the site selection procedures. The LILW disposal facility is being constructed in Bongilri, Yangbuk-myeon, Gyeongju. The official name of the disposal facility is called 'Wolsong Low and Intermediate Level Radioactive Waste Disposal Center (LILW Disposal Center)'. It can dispose of 800,000 drums of radioactive wastes in a site of 2,100,000 square meters. At the first stage, LILW repository of underground silo type with disposal capacity of 100,000 drums is under construction expected to be completed by June of 2014. The Wolsong Low and Intermediate Level Radioactive Waste Disposal Center consists of surface facilities and underground facilities. The surface facilities include a reception and inspection facility, an interim storage facility, a radioactive waste treatment building, and supporting facilities such as main control center, equipment and maintenance shop. The underground facilities consist of a construction tunnel for transport of construction equipment and materials, an operation tunnel for transport of radioactive waste, an entrance shaft for workers, and six silos for final disposal of radioactive waste. As of Dec. 2012, the overall project progress rate is 93.8%. (authors)

  3. Operation, Maintenance and Evaluation of the Bonifer and Minthorn Springs Juvenile Release and Adult Collection Facilities, 1988 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Lofy, Peter T.

    1989-12-01

    The Confederated Tribes of the Umatilla Indian Reservation and Oregon Department of Fish and Wildlife are cooperating in a joint effort to increase steelhead and re-establish salmon runs in the Umatilla River Basin. As part of this program, Bonifer and Minthorn Acclimation Facilities are operated for holding adult steelhead and acclimation and release of juvenile steelhead and salmon. This report details the projects and maintenance done during 1988.

  4. Government Owned-Contractor Operated Munitions Facilities: Are They Appropriate in the Age of Strict Environmental Compliance and Liability?

    Science.gov (United States)

    1990-04-01

    Hancock v. Train, 426 U.S. 167 (1976). In Hancock, one of the installations which was the subject of the decision was the Paducah Gaseous Diffusion ...IMMUNITY FOR GOCO MUNITIONS FACILITIES VI. CONCLUSION 66 VI. ENDNOTES 68 ii I. INTRODUCTION (W]e find in these contracts [at GOCO munitions plants ] a...world. The essence of this policy called for private, rather than public, operation of war production plants . . . . We relied upon that system as the

  5. 15 CFR 904.322 - Interim action.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Interim action. 904.322 Section 904... Sanctions and Denials Permit Sanction for Violations § 904.322 Interim action. (a) To protect marine...) The Judge will order interim action under paragraph (a) of this section, only after finding that...

  6. 15 CFR 908.5 - Interim reports.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Interim reports. 908.5 Section 908.5... SUBMITTING REPORTS ON WEATHER MODIFICATION ACTIVITIES § 908.5 Interim reports. (a) Any person engaged in a... Administrator, not later than 45 days thereafter, an interim report setting forth as of such date...

  7. 32 CFR 776.82 - Interim suspension.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Interim suspension. 776.82 Section 776.82... Complaint Processing Procedures § 776.82 Interim suspension. (a) Where the Rules Counsel determines there is... interim suspension, pending completion of a professional responsibility investigation. The...

  8. 22 CFR 127.8 - Interim suspension.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Interim suspension. 127.8 Section 127.8 Foreign... Interim suspension. (a) The Managing Director of the Directorate of Defense Trade Controls or the Director of the Office of Defense Trade Controls Compliance is authorized to order the interim suspension...

  9. 29 CFR 1614.505 - Interim relief.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 4 2010-07-01 2010-07-01 false Interim relief. 1614.505 Section 1614.505 Labor Regulations... OPPORTUNITY Remedies and Enforcement § 1614.505 Interim relief. (a)(1) When the agency appeals and the case... interim relief. (2) Service under the temporary or conditional restoration provisions of paragraph (a)(1...

  10. 24 CFR 7.44 - Interim relief.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Interim relief. 7.44 Section 7.44... § 7.44 Interim relief. (a) When the Department appeals and the case involves removal, separation, or... outcome of the Department appeal. The employee may decline the offer of interim relief. (b) Service under...

  11. 12 CFR 268.505 - Interim relief.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 3 2010-01-01 2010-01-01 false Interim relief. 268.505 Section 268.505 Banks... REGARDING EQUAL OPPORTUNITY Remedies and Enforcement § 268.505 Interim relief. (a)(1) When the Board appeals... offer of interim relief. (2) Service under the temporary or conditional restoration provisions of...

  12. Operation And Maintenance In Facilities Management Practices: A Gap Analysis In Malaysia

    Directory of Open Access Journals (Sweden)

    Zawawi Zuraihana Ahmad

    2016-01-01

    Full Text Available Facilities management in Malaysia has started as early as 1990s during the development of mega projects such as Putrajaya in 1999 [8, 9]. During this period, Malaysia was introduced to an integrated property management and maintenance services known as facilities management. However, its implementation according to the standard practice is still being disputed. The purpose of facilities management standard practices is to provide the facility management profession with a leading reference on facilities management activities and standards. Therefore, the determination of how far the gap in FM current practice is essential to help our FM industry. Thus, the aim of this study is to establish the gap between the current practices and the standard practices and also how far the gap should be satisfied. A set of questionnaire was designed upon literature and previous research done to gather the required information. The study is subjected to FM organizations in private sectors and only the personnel at management level are assessed. There were certified that most of the practices that assessed by means of gap analysis had an acceptable result which the gap between the current practices and the standard practices are not too far.

  13. Operational Phase Life Cycle Assessment of Select NASA Ground Test Facilities

    Science.gov (United States)

    Sydnor, George H.; Marshall, Timothy J.; McGinnis, Sean

    2011-01-01

    NASA's Aeronautics Test Program (ATP) is responsible for many large, high-energy ground test facilities that accomplish the nation s most advanced aerospace research. In order to accomplish these national objectives, significant energy and resources are consumed. A select group of facilities was analyzed using life-cycle assessment (LCA) to determine carbon footprint and environmental impacts. Most of these impacts stem from electricity and natural gas consumption, used directly at the facility and to generate support processes such as compressed air and steam. Other activities were analyzed but determined to be smaller in scale and frequency with relatively negligible environmental impacts. More specialized facilities use R-134a, R-14, jet fuels, or nitrogen gas, and these unique inputs can have a considerable effect on a facility s overall environmental impact. The results of this LCA will be useful to ATP and NASA as the nation looks to identify its top energy consumers and NASA looks to maximize research output and minimize environmental impact. Keywords: NASA, Aeronautics, Wind tunnel, Keyword 4, Keyword 5

  14. Research on the application of PPP model in the Chinese construction and operation of new energy vehicle charging facilities

    Science.gov (United States)

    Zhu, Liping

    2017-05-01

    New energy car charging equipment is the development and popularization of new energy vehicles. It has the nature of quasi-public goods. Due to the large number of construction projects, wide distribution, big investment, it needs huge sums of money. PPP mode is a new financing model and has the inherent driving force to lead the idea the technology and the system innovation. The government and the social subject cooperate on the basis of the spirit of contract thus achieve benefit sharing. This mode effectively improve the operation of new energy vehicle charging facilities operating efficiency

  15. Conceptual waste package interim product specifications and data requirements for disposal of borosilicate glass defense high-level waste forms in salt geologic repositories

    Energy Technology Data Exchange (ETDEWEB)

    1983-06-01

    The conceptual waste package interim product specifications and data requirements presented are applicable specifically to the normal borosilicate glass product of the Defense Waste Processing Facility (DWPF). They provide preliminary numerical values for the defense high-level waste form parameters and properties identified in the waste form performance specification for geologic isolation in salt repositories. Subject areas treated include containment and isolation, operational period safety, criticality control, waste form/production canister identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available.

  16. Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

    Energy Technology Data Exchange (ETDEWEB)

    1987-09-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs.

  17. Start of operation of the barrel measuring facility II-01. Implementation into operational processes; Inbetriebnahme der Fassmessanlage FAME II-01. Einbindung in die betrieblichen Ablaeufe

    Energy Technology Data Exchange (ETDEWEB)

    Buesing, B. [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany); Escher, M. [Wissenschaftlich-Technische Ingenieurberatung GmbH (WTI), Juelich (Germany)

    2013-07-01

    For the operation of the barrel measuring facility (FAME) II-01 a variety requirements to the measuring techniques were defined and tested in the frame of start-up. The used mechanical engineering and measuring technique complies with the state-of-the-art. Using the barrel measuring facility quality assured determinations of the dose rate and the nuclide-specific activity inventory were performed. For the evaluation of the gamma spectrometric measurements of FAME II-01 appropriately qualified personnel is available. The implementation of the facility in combination with the connection to the data base system PIK-AS and AVK it guaranteed that important data are available in real-time for the measuring process and the subsequent work steps. Besides this it is guaranteed that using the import/export functions relevant data are reviewed, supplemented and exchanged between the systems without transfer errors. The determined data of the dose rate and gamma spectrometric measurements allow an activity determination of the waste package with quality assurance and close to reality. Conservative assumptions in the frame of activity calculations for the later final disposal can be reduced. The automated operation of FAME allows also the reduction of radiation exposure of the personnel.

  18. Operational Philosophy for the Advanced Test Reactor National Scientific User Facility

    Energy Technology Data Exchange (ETDEWEB)

    J. Benson; J. Cole; J. Jackson; F. Marshall; D. Ogden; J. Rempe; M. C. Thelen

    2013-02-01

    In 2007, the Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF). At its core, the ATR NSUF Program combines access to a portion of the available ATR radiation capability, the associated required examination and analysis facilities at the Idaho National Laboratory (INL), and INL staff expertise with novel ideas provided by external contributors (universities, laboratories, and industry). These collaborations define the cutting edge of nuclear technology research in high-temperature and radiation environments, contribute to improved industry performance of current and future light-water reactors (LWRs), and stimulate cooperative research between user groups conducting basic and applied research. To make possible the broadest access to key national capability, the ATR NSUF formed a partnership program that also makes available access to critical facilities outside of the INL. Finally, the ATR NSUF has established a sample library that allows access to pre-irradiated samples as needed by national research teams.

  19. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report July 1–September 30, 2012

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2012-10-10

    Individual datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research sites are collected and routed to the Data Management Facility (DMF) for processing in near-real-time. Instrument and processed data are then delivered approximately daily to the ARM Data Archive, where they are made freely available to the research community. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Data Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year (FY) dating back to 1998.

  20. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1–December 31, 2012

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2013-01-11

    Individual datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research sites are collected and routed to the Data Management Facility (DMF) for processing in near-real-time. Instrument and processed data are then delivered approximately daily to the ARM Data Archive, where they are made freely available to the research community. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Data Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year dating back to 1998.

  1. 77 FR 137 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2012-01-03

    ... the fuel rods do not experience transition boiling during normal operation and AOOs if the SLMCPR... during normal operation and AOOs if the proposed SLMCPR limits are not violated. The proposed SLMCPR...

  2. Prediction and measurement of entrained flow coal gasification processes. Interim report, September 8, 1981-September 7, 1983

    Energy Technology Data Exchange (ETDEWEB)

    Hedman, P.O.; Smoot, L.D.; Fletcher, T.H.; Smith, P.J.; Blackham, A.U.

    1984-01-31

    This volume reports interim experimental and theoretical results of the first two years of a three year study of entrained coal gasification with steam and oxygen. The gasifier facility and testing methods were revised and improved. The gasifier was also modified for high pressure operation. Six successful check-out tests at elevated pressure were performed (55, 75, 100, 130, 170, and 215 psig), and 8 successful mapping tests were performed with the Utah bituminous coal at an elevated pressure of 137.5 psig. Also, mapping tests were performed at atmospheric pressure with a Utah bituminous coal (9 tests) and with a Wyoming subbituminous coal (14 tests). The LDV system was used on the cold-flow facility to make additional nonreactive jets mixing measurements (local mean and turbulent velocity) that could be used to help validate the two-dimensional code. The previously completed two-dimensional entrained coal gasification code, PCGC-2, was evaluated through rigorous comparison with cold-flow, pulverized coal combustion, and entrained coal gasification data. Data from this laboratory were primarily used but data from other laboratories were used when available. A complete set of the data used has been compiled into a Data Book which is included as a supplemental volume of this interim report. A revised user's manual for the two-dimensional code has been prepared and is also included as a part of this interim report. Three technical papers based on the results of this study were published or prepared. 107 references, 57 figures, 35 tables.

  3. An Integrated Approach to Measuring Emissions from Confined Animal Feeding Operations at the Whole Facility Scale

    OpenAIRE

    Bingham, G. E.; Hatfiels, J.; J. H. Prueger; Wilkerson, T. D.; Zavyalov, V. V.; Pfeiffer, R. L.; Hipps, L.; R. Martin; Silva., P; Eichinger, W.

    2006-01-01

    Agricultural operations produce a variety of particulates and gases that influence air quality. Agriculture, through wind erosion, tillage and harvest operations, burning, diesel-powered machinery and animal production operations, is a source of particulate matter that can enter human lungs and cause pulmonary problems. Animal production operations can be a source of gaseous emissions such as ammonia, odor-causing volatile organic compounds, hydrogen sulfide, greenhouse gases (methane, nitrou...

  4. 76 FR 50759 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-08-16

    ... during plant transients or anticipated operational occurrences (AOOs). The proposed SLMCPR value for... AOOs. Operational limits will be established based on the proposed SLMCPR to ensure that the SLMCPR is... of the fuel rods do not experience transition boiling during normal operation and AOOs) is met. Since...

  5. 78 FR 47785 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-08-06

    ... changes to the operation of any systems or components in normal or accident or transient operating... systems or plant operations. The proposed change is consistent with the safety analysis assumptions and... the PRFO transient provides additional margin to the Minimum Critical Power Ratio Safety Limit and...

  6. 76 FR 5614 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-02-01

    ... Plan provides a significant enhancement to cyber security where no requirement existed before. The... and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not... during normal operation and during abnormal operational transients, at least 99.9% of all fuel rods...

  7. 75 FR 70032 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-11-16

    ... identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that the facility's digital computer and communications systems and networks are protected from cyber attacks. The implementation and incorporation of the Cyber Security...

  8. 41 CFR 101-5.105 - Operation of the centralized facility.

    Science.gov (United States)

    2010-07-01

    ... justification in terms of economy and efficiency. Centralized services provided pursuant to the regulation may... centralized facility. 101-5.105 Section 101-5.105 Public Contracts and Property Management Federal Property Management Regulations System FEDERAL PROPERTY MANAGEMENT REGULATIONS GENERAL 5-CENTRALIZED SERVICES IN...

  9. Heat transfer results and operational characteristics of the NASA Lewis Research Center hot section cascade test facility

    Science.gov (United States)

    Gladden, H. J.; Yeh, F. C.; Fronek, D. L.

    1985-01-01

    The NASA Lewis Research Center gas turbine hot section test facility has been developed to provide a real-engine environment with well known boundary conditions for the aerothermal performance evaluation/verification of computer design codes. The initial aerothermal research data obtained are presented and the operational characteristics of the facility are discussed. This facility is capable of testing at temperatures and pressures up to 1600 K and 18 atm which corresponds to a vane exit Reynolds number range of 0.5 x 1 million to 2.5 x 1 million based on vane chord. The component cooling air temperature can be independently modulated between 330 and 700 K providing gas-to-coolant temperature ratios similar to current engine application. Research instrumentation of the test components provide conventional pressure and temperature measurements as well as metal temperatures measured by IR-photography. The primary data acquisition mode is steady state through a 704 channel multiplexer/digitizer. The test facility was configured as an annular cascade of full coverage film cooled vanes for the initial series of research tests.

  10. KONTEC 2013. 11{sup th} international symposium on 'Conditioning of radioactive operational and decommissioning waste' and 11{sup th} BMBF status report on 'Decommissioning and demolition of nuclear facilities'; KONTEC 2013. 11. internationales Symposium 'Konditionierung radioaktiver Betriebs- und Stilllegungsabfaelle' einschliesslich 11. Statusbericht des BMBF 'Stilllegung und Rueckbau kerntechnischer Anlagen'. Veranstaltungsbericht

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2013-06-15

    KONTEC 2013 was held in Dresden on 13 to 15 March 2013. The 11{sup th} event organized under this heading dealt with the subjects of 'Conditioning of Radioactive Operational and Decommissioning Waste' and 'Decommissioning and Demolition of Nuclear Facilities' including the R and D Status Report by the Federal Ministry of Education and Research (BMBF) on the same subject. The conference was attended by an international audience from 19 countries. The program included plenary sessions on these 4 key topics: - Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning. - Decommissioning and Dismantling of Nuclear Facilities. - Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes. - Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). These sessions were accompanied by poster sessions and short presentations under the heading of 'Kontec Direct.' The best presentations of the categories Plenary Session Presentation, Poster Presentation and Kontec-Direct have been awarded. In detail, 'Dismantling of Russian nuclear powered submarines' by Detlef Mietann, 'Requalification of 'Old Packages' for the Konrad Repository Described for the Model Case of Packages from Storage Annex A and Repackaging of Containers Holding Compacts in Hall 2 of the GNS Plant' by Martina Koessler, Sebastian Schwall and Pascal Budriks, and 'Electrochemical process development for cleaning organic, C-14-labelled waste solutions' by Hans-Juergen Friedrich. (orig.)

  11. Primer for the Interim Chair

    Science.gov (United States)

    Soltys, Stephen M.

    2011-01-01

    Objective: Being successful in the role of an Interim Chair requires an approach to transitional leadership that is different from that of individuals filling the Chair role permanently. This article reviews pertinent literature on the topic. Method: The author reviewed the literature, cited pertinent articles, and supplemented with personal…

  12. Report on the long-term interim storage of spent fuels and vitrified wastes; Gutachten zur Langzeitzwischenlagerung abgebrannter Brennelemente und verglaster Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-12-03

    Long-term interim storage for several hundred years is an option on the management of high-level radioactive wastes. The decision on final disposal is postponed. Worldwide the long-term interim storage is not part of the disposal concept - a geologic final repository is the ultimate aim. Using today's technology the interim storage over several hundred years is supposed to be uncritical. Aging management is the most important challenge - the renewal of the facilities would have to be expected. Possible social change and their impact on the interim storage problem has not been considered.

  13. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1–December 31, 2011

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2012-01-09

    Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent approximately daily to the ARM Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year (FY) dating back to 1998.

  14. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report January 1–March 31, 2012

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2012-04-13

    Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent approximately daily to the ARM Data Archive, where they are made available to the research community. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year (FY) dating back to 1998.

  15. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report: October 1 - December 31, 2010

    Energy Technology Data Exchange (ETDEWEB)

    Sisterson, DL

    2011-03-02

    Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent approximately daily to the ARM Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year (FY) dating back to 1998.

  16. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report July 1–September 30, 2011

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2011-10-10

    Individual raw datastreams from instrumentation at the Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent approximately daily to the ARM Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of processed data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual datastream, site, and month for the current year and (2) site and fiscal year (FY) dating back to 1998.

  17. Operational Performance and Improvements to the RF Power Sources for the Compact Linear Collider Test Facility (CTF3) at CERN

    CERN Document Server

    McMonagle, Gerard

    2006-01-01

    The CERN CTF3 facility is being used to test and demonstrate key technical issues for the CLIC (Compact Linear Collider) study. Pulsed RF power sources are essential elements in this test facility. Klystrons at S-band (29998.55 GHz), in conjunction with pulse compression systems, are used to power the Drive Beam Accelerator (DBA) to achieve an electron beam energy of 150 MeV. The L-Band RF system, includes broadband Travelling Wave Tubes (TWTs) for beam bunching with 'phase coded' sub pulses in the injector and a narrow band high power L-Band klystron powering the transverse 1.5GHz RF deflector in the Delay Loop immediately after the DBA. This paper describes these different systems and discusses their operational performance.

  18. Operational performance and improvements to the rf power sources for the Compact Linear Collider Test Facility (CTF3) at CERN

    CERN Document Server

    McMonagle, Gerard

    2006-01-01

    The CERN CTF3 facility is being used to test and demonstrate key technical issues for the CLIC (Compact Linear Collider) study. Pulsed RF power sources are essential elements in this test facility. Klystrons at S-band (29998.55 GHz), in conjunction with pulse compression systems, are used to power the Drive Beam Accelerator (DBA) to achieve an electron beam energy of 150 MeV. The L-Band RF system, includes broadband Travelling Wave Tubes (TWTs) for beam bunching with 'phase coded' sub pulses in the injector and a narrow band high power L-Band klystron powering the transverse 1.5 GHz RF deflector in the Delay Loop immediately after the DBA. This paper describes these different systems and discusses their operational performance.

  19. Technical documentation in support of the project-specific analysis for construction and operation of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, M.A.; Vinikour, W. [Argonne National Lab., IL (United States). Environmental Assessment Div.; Allison, T. [Argonne National Lab., IL (United States). Decision and Information Sciences Div.] [and others

    1996-09-01

    This document provides information that supports or supplements the data and impact analyses presented in the National Ignition Facility (NIF) Project-Specific Analysis (PSA). The purposes of NIF are to achieve fusion ignition in the laboratory for the first time with inertial confinement fusion (ICF) technology and to conduct high- energy-density experiments ins support of national security and civilian application. NIF is an important element in the DOE`s science-based SSM Program, a key mission of which is to ensure the reliability of the nation`s enduring stockpile of nuclear weapons. NIF would also advance the knowledge of basic and applied high-energy- density science and bring the nation a large step closer to developing fusion energy for civilian use. The NIF PSA includes evaluations of the potential environmental impacts of constructing and operating the facility at one of five candidate site and for two design options.

  20. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI).

  1. Crew Factors in Flight Operations XII: A Survey of Sleep Quantity and Quality in On-Board Crew Rest Facilities

    Science.gov (United States)

    Rosekind, Mark R.; Gregory, Kevin B.; Co, Elizabeth L.; Miller, Donna L.; Dinges, David F.

    2000-01-01

    Many aircraft operated on long-haul commercial airline flights are equipped with on-board crew rest facilities, or bunks, to allow crewmembers to rest during the flight. The primary objectives of this study were to gather data on how the bunks were used, the quantity and quality of sleep obtained by flight crewmembers in the facilities, and the factors that affected their sleep. A retrospective survey comprising 54 questions of varied format addressed demographics, home sleep habits, and bunk sleep habits. Crewmembers from three airlines with long-haul fleets carrying augmented crews consisting of B747-100/200, B747-400, and MD-11 aircraft equipped with bunks returned a total of 1404 completed surveys (a 37% response rate). Crewmembers from the three carriers were comparable demographically, although one carrier had older, more experienced flight crewmembers. Each group, on average, rated themselves as "good" or "very good" sleepers at home, and all groups obtained about the same average amount of sleep each night. Most were able to sleep in the bunks, and about two thirds indicated that these rest opportunities benefited their subsequent flight deck alertness and performance. Comfort, environment, and physiology (e.g., being ready for sleep) were identified as factors that most promoted sleep. Factors cited as interfering with sleep included random noise, thoughts, heat, and the need to use the bathroom. These factors, in turn, suggest potential improvements to bunk facilities and their use. Ratings of the three aircraft types suggested differences among facilities. Bunks in the MD-11 were rated significantly better than either of the B747 types, and the B747-400 bunks received better ratings than did the older, B747-100/200 facilities.

  2. Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill

    Energy Technology Data Exchange (ETDEWEB)

    Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

    1989-07-01

    Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs.

  3. 75 FR 23808 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-05-04

    ... storage location at a given time,'' was one basis for the exemption from the criticality alarm system... involves no significant changes to the operation of any systems or components in normal or accident..., ``Criticality accident requirements,'' of Title 10 of the Code of Federal Regulations (10 CFR). The Operating...

  4. A Manual of Simplified Laboratory Methods for Operators of Wastewater Treatment Facilities.

    Science.gov (United States)

    Westerhold, Arnold F., Ed.; Bennett, Ernest C., Ed.

    This manual is designed to provide the small wastewater treatment plant operator, as well as the new or inexperienced operator, with simplified methods for laboratory analysis of water and wastewater. It is emphasized that this manual is not a replacement for standard methods but a guide for plants with insufficient equipment to perform analyses…

  5. Depth of Blanket. Operational Control Tests for Wastewater Treatment Facilities. Instructor's Manual [and] Student Workbook.

    Science.gov (United States)

    Arasmith, E. E.

    The determination of the thickness of a sludge blanket in primary and secondary clarifiers and in gravity thickness is important in making operational control decisions. Knowing the thickness and concentration will allow the operator to determine sludge volume and detention time. Designed for individuals who have completed National Pollutant…

  6. 77 FR 22808 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-04-17

    ... different type of equipment will be installed) or changes in methods governing normal plant operation. The... governing normal plant operation. In addition, the changes do not impose any new or different requirements...-related system performs its function. The change revises license renewal commitments and aging...

  7. Operation REDWING

    Science.gov (United States)

    1956-07-31

    only 16mm cinemascope films would be available after 1 August 1956t Act- tion was taken to modify the screens of the Terrace and Starlite theaters...approximately 900, was in operation throughout the interim and operational period. The Starlite Theater, which seats approximately 600, opened in

  8. Safety analysis, 200 Area, Savannah River Plant: Separations area operations. Building 221-H, B-Line, Scrap Recovery Facility (Supplement 2A): Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-07-01

    The now HB-Line is located an top of the 221-H Building on the fifth and sixth levels and is designed to replace the aging existing HB-Line production facility. The new HB-Line consists of three separate facilities: the Scrap Recovery Facility, Neptunium Facility, and Plutonium Oxide Facility. The Scrap Recovery Facility is designed to routinely generate nitrate solutions of {sup 235}U{sup 239}Pu and Pu-238 fromscrap for purification by anion exchange or by solvent extraction in the canyon. The now facility incorporates improvements in: (1) engineered controls for nuclear criticality, (2) cabinet integrity and engineered barriers to contain contamination and minimize personnel exposure to airborne contamination, (3) shielding and remote operations to decrease radiation exposure, and (4) equipment and ventilation design to provide flexibility and improved process performance.

  9. Environmental Assessment for the proposed modification and continued operation of the DIII-D facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The EA evaluates the proposed action of modifying the DIII-D fusion facility and conducting related research activities at the GA San Diego site over 1995-1999 under DOE contract number DE-ACO3-89ER51114. The proposed action is need to advance magnetic fusion research for future generation fusion devices such as ITER and TPX. It was determined that the proposed action is not a major action significantly affecting the quality of the human environment according to NEPA; therefore a finding of no significant impact is made and an environmental impact statement is not required.

  10. Studies and research concerning BNFP: life of project operating expenses for away-from-reactor (AFR) spent fuel storage facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Shallo, F. A.

    1979-09-01

    Life of Project operating expenses for a licensed Away-From-Reactor (AFR) Spent Fuel Storage Facility are developed in this report. A comprehensive business management structure is established and the functions and responsibilities for the facility organization are described. Contractual provisions for spent fuel storage services are evaluated.

  11. RCRA (Resource Conservation and Recovery Act) personnel training guidance manual for owners or operators of hazardous-waste-management facilities. Draft report

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    The manual provides guidance to an audience consisting of owners or operators of hazardous waste-management facilities and also regulatory personnel responsible for facility permitting. Information is provided concerning general training strategies and program design, types of training, training modules pertinent to hazardous-waste management, suggested training module elements, and sources of information.

  12. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

  13. 76 FR 58303 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-09-20

    ... Power Station, Unit No. 1 (DBNPS) Technical Specifications (TS) 5.5.8, ``Steam Generator (SG) Program... requirement specific to the OM holding a senior reactor operator (SRO) license. The revised BSEP, Units 1...

  14. 78 FR 31978 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-05-28

    ... affect the plant itself. Changing the ISV Plan does not affect prevention and mitigation of abnormal events, e.g., accidents, anticipated operational occurrences, earthquakes, floods and turbine missiles...

  15. Air Quality Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research FacilityFacilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

  16. Pulsed laser facilities operating from UV to IR at the Gas Laser Lab of the Lebedev Institute

    Science.gov (United States)

    Ionin, Andrei; Kholin, Igor; Vasil'Ev, Boris; Zvorykin, Vladimir

    2003-05-01

    Pulsed laser facilities developed at the Gas Lasers Lab of the Lebedev Physics Institute and their applications for different laser-matter interactions are discussed. The lasers operating from UV to mid-IR spectral region are as follows: e-beam pumped KrF laser (λ= 0.248 μm) with output energy 100 J; e-beam sustained discharge CO2(10.6 μm) and fundamental band CO (5-6 μm) lasers with output energy up to ~1 kJ; overtone CO laser (2.5-4.2 μm) with output energy ~ 50 J and N2O laser (10.9 μm) with output energy of 100 J; optically pumped NH3 laser (11-14 μm). Special attention is paid to an e-beam sustained discharge Ar-Xe laser (1.73 μm ~ 100 J) as a potential candidate for a laser-propulsion facility. The high energy laser facilities are used for interaction of laser radiation with polymer materials, metals, graphite, rocks, etc.

  17. Grande Ronde Endemic Spring Chinook Salmon Supplementation Program : Facility Operations and Maintenance, 2004 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    McLean, Michael L.; Seeger, Ryan; Hewitt, Laurie (Confederated Tribes of the Umatilla Indian Reservation, Department of Natural Resources, Pendleton, OR)

    2005-02-01

    There were 2 acclimation periods at the Catherine Creek Acclimation Facility (CCAF) in 2004. During the early acclimation period, 92,475 smolts were delivered from Lookingglass Hatchery (LGH) on 8 March. This group was comprised entirely of progeny from the captive broodstock program. The size of the fish at delivery was 23.1 fish/lb. Volitional releases began 15 March 2004 and ended 22 March with an estimated total (based on PIT tag detections of 1,475) of 8,785 fish leaving the raceways. This was 9.5% of the total fish delivered. Fish remaining in the raceways after volitional release were forced out. Hourly detections of PIT-tagged fish showed that most of the fish left between 1200 and 2000 hours which was similar to the hourly temperature profile. The size of the fish just before the volitional release was 23.1 and the size of the fish remaining just before the forced release was 23.5 fish/lb. The total mortality for the acclimation period was 62 (0.07 %). The total number of fish released from the acclimation facility during the early period was 92,413. During the second acclimation period 70,977 smolts were delivered from LGH on 24 March. This group was comprised entirely of progeny from the conventional broodstock program. The size of the fish at delivery was 23.4 fish/lb. Volitional releases began 30 March 2004 and ended 12 April with an estimated total (based on PIT tag detections of 3,632) of 49,147 fish leaving the raceways. This was 69.2% of the total fish delivered. Fish remaining in the raceways after volitional release were forced out. Hourly detections of PIT-tagged fish showed that most of the fish left between 1200 and 2000 hours which was similar to the hourly temperature profile. The size of the fish just before the volitional release was 23.4 and the size of the fish remaining just before the forced release was 23.9 fish/lb. The total mortality for the acclimation period was 18 (0.03 %). The total number of fish released from the acclimation

  18. Interim storage of power reactor spent nuclear fuel (SNF) and its potential application to SNF separations and closed fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Levy, Salomon, E-mail: slevy112@aol.com

    2009-10-15

    Interim, centralized, engineered (dry cask) storage facilities for USA light water power reactor spent nuclear fuel (SNF) should be implemented to complement and to offer much needed flexibility while the Nuclear Regulatory Commission is funded to complete its evaluation of the Yucca Mountain License and to subject it to public hearings. The interim sites should use the credo reproduced in Table 1 [Bunn, M., 2001. Interim Storage of Spent Nuclear Fuel. Harvard University and University of Tokyo] and involve both the industry and government. The sites will help settle the 50 pending lawsuits against the government and the $11 billion of potential additional liabilities for SNF delay damages if Yucca Mountain does not being operation in 2020 [DOE, 2008a. Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Stations (December)]. Under the developing consensus to proceed with closed fuel cycles, it will be necessary to develop SNF separation facilities with stringent requirements upon separation processes and upon generation of only highly resistant waste forms. The location of such facilities at the interim storage sites would offer great benefits to those sites and assure their long term viability by returning them to their original status. The switch from once-through to closed fuel cycle will require extensive time and development work as illustrated in 'The Path to Sustainable Nuclear Energy' [DOE, 2005. The Path to Sustainable Nuclear Energy. Basic and Applied Research Opportunities for Advanced Fuel Cycles. DOE (September)]. A carefully crafted long term program, funded for at least 5 years, managed by a strong joint government-industry team, and subjected to regular independent reviews should be considered to assure the program stability and success. The new uncertainty about Yucca Mountain role raises two key issues: (a) what to do with the weapons and other high level government

  19. Are interim management statements redundant?

    OpenAIRE

    Schleicher, T.; Walker, Martin

    2015-01-01

    In 2004 the Transparency Directive increased the reporting frequency by mandating the Interim Management Statement (IMS). However, only nine years later, the EU announced that it was making quarterly reporting voluntary again arguing that IMSs are redundant as they are unlikely to contain any additional information not already required by the Market Abuse Directive (MAD). The current paper tests this argument empirically. For that it collects data on trading statements from a post-MAD pre-IMS...

  20. Interim safety basis compliance matrix for Trenches 31 and 34

    Energy Technology Data Exchange (ETDEWEB)

    Ames, R.R.

    1994-12-30

    The tables provided in this document identify the specific requirements and basis for the administrative controls established in the Westinghouse Hanford Company (WHC) Solid Waste Burial Ground (SWBG) Interim Safety Basis (ISB) for operation of the Project W-025, Mixed Waste Lined Landfill (Trenches 31 and 34). The tables document the necessary controls and implementing procedures to ensure compliance with the requirements of the ISB. These requirements provide a basis for future Unreviewed Safety Questions (USQ) screening of applicable procedure changes, proposed physical modifications, tests, experiments, and occurrences. Table 1 provides the SWBG interim Operational Safety Requirements administrative controls matrix. The specific assumptions and commitments used in the safety analysis documents applicable to disposal of mixed wastes in Trenches 31 and 34 are provided in Table 2. Table 3 is provided to document the potential engineered and administrative mitigating features identified in the Preliminary Hazard Analysis (PHA) for disposal of mixed waste.

  1. Fifteen Years of Operation at NASA's National Transonic Facility with the World's Largest Adjustable Speed Drive

    Science.gov (United States)

    Sydnor, George H.; Bhatia, Ram; Krattiger, Hansueli; Mylius, Justus; Schafer, D.

    2012-01-01

    In September 1995, a project was initiated to replace the existing drive line at NASA's most unique transonic wind tunnel, the National Transonic Facility (NTF), with a single 101 MW synchronous motor driven by a Load Commutated Inverter (LCI). This Adjustable Speed Drive (ASD) system also included a custom four-winding transformer, harmonic filter, exciter, switch gear, control system, and feeder cable. The complete system requirements and design details have previously been presented and published [1], as well as the commissioning and acceptance test results [2]. The NTF was returned to service in December 1997 with the new drive system powering the fan. Today, this installation still represents the world s largest horizontal single motor/drive combination. This paper describes some significant events that occurred with the drive system during the first 15 years of service. These noteworthy issues are analyzed and root causes presented. Improvements that have substantially increased the long term viability of the system are given.

  2. The first operation and combustion characteristics of 1MW{sub th} test facility

    Energy Technology Data Exchange (ETDEWEB)

    Jang, G.H.; Chang, I.G.; Jeong, S.Y.; Seon, C.Y.; Yang, G.M. [R and D Center, Hanjung, Changwon (Korea)

    1998-11-01

    In this study, the effects of air staging with different parameter variations were investigated on their NOx emission and burnout of fuel. For this purpose, a pulverized coal combustion test facility with 1MW{sub th} was available. The burner of combustor was externally air staging burner(EASE) type made by IFRF. The pulverized high bituminous(Blair athol) coal from Australia was used as fuel, and the particle size less than 80 {mu}m was 83.4%. Overall excess air ratio was 1.2. From the study, the amount of core air did not affect their NOx reduction. With fuel rich condition in primary zone, the NOx emission was improved. But it was not possible to achieve a sufficient burnout when NOx emission was less than 500 ppm. (author). 8 refs., 8 figs., 2 tabs.

  3. Radiation technology facilities operating at the italian ENEA-Casaccia research center

    Energy Technology Data Exchange (ETDEWEB)

    Tata, A.; Festinesi, A.; Rosa, R. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Innovazione

    1998-04-01

    The ENEA Casaccia Research Center, 20 km far from Rome, is the main Italian technological research Center, with more than 2000 scientists involved in several advanced research fields (materials, energy, environment, etc.). Within the frame of radiation technology, three main facilities are in service at full power at the Casaccia research Center: a 1 MW TRIGA Mark II reactor (RC-1); a 5 kW fast source reactor (TAPIRO); a 3.7 x 10{sup 15} Bq Cobalt-60 irradiation plant (CALLIOPE). Main R-D programmes carried out regard medical radioisotopes and radio trackers production, neutron radiography, neutron activation analysis, radiation damage analysis, neutron diffractometry, foodstuffs treatment, crosslinking processes, wastes (hazardous, chemical, hospital) processing. The paper provides a features description of utilized facilities and reports main present carried out projects. [Italiano] Il Centro Ricerca ENEA della casaccia, situato a 20 km circa da Roma, e` il maggiore centro di ricerca tecnologica italiano, con oltre 2000 ricercatori impegnati in numerosi campi di ricerca avanzata (materiali, energia, ambiente, etc.). Nell`ambito delle tecnologie di irraggiamento, sono presenti e pienamente funzionanti presso il C.R. Casaccia tre principali impianti: un reattore termico TRIGA mark II da 1 MW (RC-1); un reattore-sorgente veloce da 5 kW (TAPIRO); un impianto di irraggiamento a Cobalto-60 da 3.7. x 10{sup 15} Bq (CALLIOPE). I principali programmi R-D condotti riguardano la produzione di radioisotopi e radiotraccianti di utilizzo in campo medico, la radiografia neutronica, l`analisi per attivazione neutronica, l`analisi del danno da radiazioni, la diffrattometria neutronica, il trattamento di derrate alimentari, i processi di reticolazione polimerica, il trattamento di rifiuti (tossico-nocivi, chimici, ospedaliri). Il presente lavoro fornisce una descrizione tecnica degli impianti, nonche` indicazioni sui principali programmo condotti attualmente presso tali impienti.

  4. Big Oaks National Wildlife Refuge : Interim Plans : 2000

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This interim plan for Big Oaks National Wildlife Refuge cover an interim comprehensive conservation plan, a hunting and fishing plan and an interim compatibility...

  5. A dynamic programming model for optimal planning of aquifer storage and recovery facility operations

    Science.gov (United States)

    Uddameri, V.

    2007-01-01

    Aquifer storage recovery (ASR) is an innovative technology with the potential to augment dwindling water resources in regions experiencing rapid growth and development. Planning and design of ASR systems requires quantifying how much water should be stored and appropriate times for storage and withdrawals within a planning period. A monthly scale planning model has been developed in this study to derive optimal (least cost) long-term policies for operating ASR systems and is solved using a recursive deterministic dynamic programming approach. The outputs of the model include annual costs of operation, the amount of water to be imported each month as well as the schedule for storage and extraction. A case study modeled after a proposed ASR system for Mustang Island and Padre Island service areas of the city of Corpus Christi is used to illustrate the utility of the developed model. The results indicate that for the assumed baseline demands, the ASR system is to be kept operational for a period of 4 months starting from May through August. Model sensitivity analysis indicated that increased seasonal shortages can be met using ASR with little additional costs. For the assumed cost structure, a 16% shortage increased the costs by 1.6%. However, the operation time of ASR increased from 4 to 8 months. The developed dynamic programming model is a useful tool to assess the feasibility of evaluating the use of ASR systems during regional-scale water resources planning endeavors.

  6. 78 FR 67402 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-11-12

    ... change reflects an organizational change to transition from an operating plant to a permanently defueled... change during the 30-day comment period such that failure to act in a timely way would result, for... (iii) the filing has been submitted in a timely fashion based on the availability of the...

  7. 76 FR 76193 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-12-06

    ... Tube Failure (PWR).'' The primary loop components (e.g., reactor vessel, reactor internals, control rod... verify that appropriate nuclear and thermal hydraulic margins to safety are maintained. Therefore, the... SLMCPRs contained in TS 2.1, ``Safety Limits,'' for two recirculation loop operation and...

  8. 76 FR 52699 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-08-23

    ... information. With respect to copyrighted works, except for limited excerpts that serve the purpose of the... meeting the alternate shutdown capability. A thermal-hydraulic analysis will demonstrate that these... of safety? Response: No. Thermal-hydraulic analysis demonstrates that the proposed operations to...

  9. 77 FR 67679 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-13

    ... affect the prevention and mitigation of any abnormal events, e.g., accidents, anticipated operational occurrences, earthquakes, floods and turbine missiles, or their safety or design analyses. The probabilistic... Tier 2 change. The changes do not affect the prevention and mitigation of any abnormal events, e.g...

  10. Capillary Suction Time. Operational Control Tests for Wastewater Treatment Facilities. Instructor's Manual [and] Student Workbook.

    Science.gov (United States)

    Wooley, John F.

    Capillary suction time is time required for the liquid phase of a treated sludge to travel through 1 centimeter of media (blotter or filter paper). Designed for individuals who have completed National Pollutant Discharge Elimination System (NPDES) level 1 laboratory training skills, this module provides waste water treatment plant operators with…

  11. 75 FR 30440 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-06-01

    ... in a condition that reduces the probability of an inadvertent transient or the need for a plant... allow a one-time replacement of the 2C 125-volt direct current (VDC) battery while Salem Unit 2 is at... existing 2C 125VDC battery, a temporary, TS operable battery will provide the same function as the...

  12. 75 FR 77906 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-12-14

    ... osmosis system during normal plant operation to remove silica from borated water storage tank and the... being proposed which will introduce any physical changes to the existing plant design. The proposed... Plants.'' Basis for proposed no significant hazards consideration determination: As required by 10 CFR...

  13. 76 FR 77565 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-12-13

    ... not be able to offer assistance in using unlisted software. If a participant is electronically... conditions for operation are determined. The safety analysis acceptance criteria are not impacted by this... an initiating event within the assumed acceptance limits. The proposed changes do not affect...

  14. 76 FR 1462 - Notice Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2011-01-10

    ... analysis acceptance criteria continue to be met. Power level is not an initiator of any transient or... . Entergy Operations, Inc., System Energy Resources, Inc., South Mississippi Electric Power Association, and... licensed thermal power (CLTP) of 3,898 megawatts thermal (MWt) to 4,408 MWt. Evaluations and analyses...

  15. 75 FR 1655 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-01-12

    ... Testing Program,'' contains references to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI as the source of requirements for the inservice testing (IST) of ASME Code... incorporated references to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM...

  16. 77 FR 60146 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-10-02

    ... Amendment No. 151 for FNP Unit 2 which added Note 3 to Surveillance Requirement (SR) 3.4.11.1 and created... entirely from the FNP Unit 2 TS. This change is administrative in nature, because Cycle 16 for FNP Unit 2 has been completed; FNP Unit 2 is currently operating in Cycle 22. Therefore, SR 3.4.11.1 Note 3...

  17. 77 FR 40647 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-07-10

    ... following a design basis LOCA. Each train has a service water pump discharge crossover valve installed which... revised to govern system operation and use of the crossover design feature to mitigate a LOSW event. The use of the NSWS pump discharge crossover valves within their design limitations and...

  18. Rise Time. Operational Control Tests for Wastewater Treatment Facilities. Instructor's Manual [and] Student Workbook.

    Science.gov (United States)

    Carnegie, John W.

    The rise time test (along with the settleometer procedure) is used to monitor sludge behavior in the secondary clarifier of an activated sludge system. The test monitors the effect of the nitrification/denitrification process and aids the operator in determining optimum clarifier sludge detention time and, to some extent, optimum degree of…

  19. [Working conditions and professional risk for operational personnel of energy facilities].

    Science.gov (United States)

    Amirov, N Kh; Ilyukhin, N E; Rusin, M N; Krasnoshchekova, V N

    2013-01-01

    Features of working conditions and a state of health of operation personnel of the network companies of power industry were studied for the purpose of justification and introduction of preventive actions for the decrease in influence of factors of professional risk.

  20. 76 FR 39136 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-07-05

    .... The resulting bending action constrains the tubes in the tubesheet thereby restricting primary- to...) Program,'' to exclude a portion of the tubes below the top of the steam generator tubesheet from periodic steam generator tube inspections during Refueling Outage 14 and the subsequent operating cycle. The...

  1. 76 FR 70768 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-11-15

    ... of these failure modes is small, based on the operating history of similar equipment at other plants... annulus for online work. Without use of the SB dome penetration hatches, materials would travel through the auxiliary building (AB), to the annulus access door, and be hoisted up the annual access...

  2. 78 FR 22563 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-04-16

    ... been in place since the beginning of plant operation. The revised curves are based on a later edition..., any hearing will take place after issuance. The Commission expects that the need to take this action... general requirements: (1) The name, address, and telephone number of the requestor or petitioner; (2) the...

  3. 75 FR 51490 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-08-20

    ... Cyber Security Plan directly impacts the physical configuration or function of plant structures, systems... Northwest's overall program for physical protection of CGS . Inclusion of the CGS Cyber Security Plan in the... manner in which systems are operated, maintained, modified, tested, or inspected. The JAF Cyber...

  4. 77 FR 55864 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-09-11

    ... previously available; and (iii) the filing has been submitted in a timely fashion based on the availability.... Equipment that could be affected by PRNM system has been evaluated. No new operating mode, safety-related equipment lineup, accident scenario, or system interaction mode was identified. Therefore, the upgraded...

  5. 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.

  6. 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.

  7. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 2: Solid waste retrieval facilities -- Phase 1, detail design drawings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 2 provides the complete set of the Detail Design drawings along with a listing of the drawings. Once approved by WHC, these drawings will be issued and baselined for the Title 3 construction effort.

  8. 76 FR 30184 - Outer Continental Shelf (OCS) Renewable Energy Program Interim Policy Leasing for Marine...

    Science.gov (United States)

    2011-05-24

    ... Energy Program Interim Policy Leasing for Marine Hydrokinetic Technology Testing Offshore Florida AGENCY... public in the leasing decision for an offshore technology testing facility located on the OCS, in... resources and socioeconomic conditions that could result from leasing and the technology testing...

  9. Interim-status groundwater monitoring plan for the 216-B-63 trench

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-02-09

    This document outlines the groundwater monitoring plan, under RCRA regulations in 40 CFR 265 Subpart F and WAC173-300-400, for the 216-B-63 Trench. This interim status facility is being sampled under detection monitoring criteria and this plan provides current program conditions and requirements.

  10. 78 FR 67442 - Congestion Mitigation and Air Quality Improvement Program Interim Guidance

    Science.gov (United States)

    2013-11-12

    .... Bicycle and Pedestrian Facilities Programs The Interim Guidance explains that CMAQ eligibility is available to programs authorized in the bicycle and pedestrian programs governed by 23 CFR Part 652, with an... scope of CMAQ eligibility for electric vehicle charging stations and natural gas vehicle refueling...

  11. List of currently classified documents relative to Hanford Production Facilities Operations originated on the Hanford Site between 1961 and 1972

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    The United States Department of Energy (DOE) has declared that all Hanford plutonium production- and operations-related information generated between 1944 and 1972 is declassified. Any documents found and deemed useful for meeting Hanford Environmental Dose Reconstruction (HEDR) objectives may be declassified with or without deletions in accordance with DOE guidance by Authorized Derivative Declassifiers. The September 1992, letter report, Declassifications Requested by the Technical Steering Panel of Hanford Documents Produced 1944--1960, (PNWD-2024 HEDR UC-707), provides an important milestone toward achieving a complete listing of documents that may be useful to the HEDR Project. The attached listing of approximately 7,000 currently classified Hanford-originated documents relative to Hanford Production Facilities Operations between 1961 and 1972 fulfills TSP Directive 89-3. This list does not include such titles as the Irradiation Processing Department, Chemical Processing Department, and Hanford Laboratory Operations monthly reports generated after 1960 which have been previously declassified with minor deletions and made publicly available. Also Kaiser Engineers Hanford (KEH) Document Control determined that no KEH documents generated between January 1, 1961 and December 31, 1972 are currently classified. Titles which address work for others have not been included because Hanford Site contractors currently having custodial responsibility for these documents do not have the authority to determine whether other than their own staff have on file an appropriate need-to-know. Furthermore, these documents do not normally contain information relative to Hanford Site operations.

  12. E-Area Performance Assessment Interim Measures Assessment FY2005

    Energy Technology Data Exchange (ETDEWEB)

    Stallings, M

    2006-01-31

    After major changes to the limits for various disposal units of the E-Area Low Level Waste Facility (ELLWF) last year, no major changes have been made during FY2005. A Special Analysis was completed which removes the air pathway {sup 14}C limit from the Intermediate Level Vault (ILV). This analysis will allow the disposal of reactor moderator deionizers which previously had no pathway to disposal. Several studies have also been completed providing groundwater transport input for future special analyses. During the past year, since Slit Trenches No.1 and No.2 were nearing volumetric capacity, they were operationally closed under a preliminary closure analysis. This analysis was performed using as-disposed conditions and data and showed that concrete rubble from the demolition of 232-F was acceptable for disposal in the STs even though the latest special analysis for the STs had reduced the tritium limits so that the inventory in the rubble exceeded limits. A number of special studies are planned during the next years; perhaps the largest of these will be revision of the Performance Assessment (PA) for the ELLWF. The revision will be accomplished by incorporating special analyses performed since the last PA revision as well as revising analyses to include new data. Projected impacts on disposal limits of more recent studies have been estimated. No interim measures will be applied during this year. However, it is being recommended that tritium disposals to the Components-in-Grout (CIG) Trenches be suspended until a limited Special Analysis (SA) currently in progress is completed. This SA will give recommendations for optimum placement of tritiated D-Area tower waste. Further recommendations for tritiated waste placement in the CIG Trenches will be given in the upcoming PA revision.

  13. Accidental nuclear excursion recuplex operation 234-5 facility: Final medical report

    Energy Technology Data Exchange (ETDEWEB)

    Fuqua, P. A.

    1962-04-07

    The April 7, 1962 criticality accident involving human exposures was the first to have occurred in any production facility at Hanford. The accidental nuclear excursion did not result in any mechanical damage or spread of contamination. Three employees received over-exposure to gamma and neutron radiation. None were fatally exposed and in each case the over-exposure was recognized promptly. Following an initial period of medical observation and testing, the men were released to work. They continued to be followed clinically. Clinical studies performed were hematological procedures including leukocyte chromosome aberrations, morphologically aberrant blood cells, bone marrow evaluations, blood chemistry determinations, amino acid excretion studies, seminal fluid, urinary gonadotropins and estrogen excretion studies, testicular biopsies and crystalline lens examinations. These studies, along with a brief description of the accident and of the dosimetry, are summarized in this report by those participating in the studies. In view of the dose ranges received in these cases, both the negative and positive findings are considered to be of unusual interest due to the lack of knowledge of effects following human exposures at these levels.

  14. The elbe accelerator facility starts operation with the superconducting rf gun

    CERN Document Server

    Xiang, R; Buettig, H; Janssen, D; Justus, M; Lehnert, U; Michel, P; Murcek, P; Schneider, C; Schurig, R; Staufenbiel, F; Teichert, J; Kamps, T; Rudolph, J; Schenk, M; Klemz, G; Will, I

    2010-01-01

    As the first superconducting rf photo-injector (SRF gun) in practice, the FZD 3+1/2 cell SRF gun is successfully connected to the superconducting linac ELBE. This setting will improve the beam quality for ELBE users. It is the first example for an accelerator facility fully based on superconducting RF technology. For high average power FEL and ERL sources, the combination of SRF linac and SRF gun provides a new chance to produce beams of high average current and low emittance with relative low power consumption. The main parameters achieved from the present SRF gun are the final electron energy of 3 MeV, 16 μA average current, and rms transverse normalized emittances of 3 mm mrad at 77 pC bunch charge. A modified 3+1/2 cell niobium cavity has been fabricated and tested, which will increase the rf gradient in the gun and thus better the beam parameters further. In this paper the status of the integration of the SRF gun with the ELBE linac will be presented, and the latest results of the beam experiments will ...

  15. The Earthscope USArray Array Network Facility (ANF): Metadata, Network and Data Monitoring, Quality Assurance During the Second Year of Operations

    Science.gov (United States)

    Eakins, J. A.; Vernon, F. L.; Martynov, V.; Newman, R. L.; Cox, T. A.; Lindquist, K. L.; Hindley, A.; Foley, S.

    2005-12-01

    The Array Network Facility (ANF) for the Earthscope USArray Transportable Array seismic network is responsible for: the delivery of all Transportable Array stations (400 at full deployment) and telemetered Flexible Array stations (up to 200) to the IRIS Data Management Center; station command and control; verification and distribution of metadata; providing useful remotely accessible world wide web interfaces for personnel at the Array Operations Facility (AOF) to access state of health information; and quality control for all data. To meet these goals, we use the Antelope software package to facilitate data collection and transfer, generation and merging of the metadata, real-time monitoring of dataloggers, generation of station noise spectra, and analyst review of individual events. Recently, an Antelope extension to the PHP scripting language has been implemented which facilitates the dynamic presentation of the real-time data to local web pages. Metadata transfers have been simplified by the use of orb transfer technologies at the ANF and receiver end points. Web services are being investigated as a means to make a potentially complicated set of operations easy to follow and reproduce for each newly installed or decommissioned station. As part of the quality control process, daily analyst review has highlighted areas where neither the regional network bulletins nor the USGS global bulletin have published solutions. Currently four regional networks (Anza, BDSN, SCSN, and UNR) contribute data to the Transportable Array with additional contributors expected. The first 100 stations (42 new Earthscope stations) were operational by September 2005 with all but one of the California stations installed. By year's end, weather permitting, the total number of stations deployed is expected to be around 145. Visit http://anf.ucsd.edu for more information on the project and current status.

  16. Utilizing the US Lab Nadir Research Window for Remote Sensing Operations with The Window Observational Research Facility (WORF)

    Science.gov (United States)

    Turner, Richard; Barley, Bryan; Gilbert, Paul A. (Technical Monitor)

    2002-01-01

    The Window Observational Research Facility (WORF) is an ISPR-based rack facility designed to take advantage of the high optical quality US Lab Nadir research window. The WORF is based on the ISS Expedite the Processing of Experiments to Space Station (EXPRESS) rack mechanical structure and electronic systems. The WORF has a unique payload volume located at the center of the rack that provides access to the window. The interior dimensions of the payload volume are 34-in. (86.36 cm) wide by 33-in. (83.82 cm) high by 23-in. (58.42 cm) deep. This facility supports the deployment of payloads such as 9 in. aerial photography cameras and 12 in. diameter optical equipment. The WORF coupled with the optical quality of the United States Lab window support the deployment of various payload disciplines. The WORF provides payloads with power, data command and control, air cooling, water cooling, and video processing. The WORF's payload mounting surfaces and interfaces include the interior payload mounting shelf and the interior and exterior aircraft-like seat tracks. The payload mounting shelf is limited to a maximum mass of 136 kg (299 pounds). The WORF can accommodate large payloads such as the commonly used Leica-Heerbrug RC-30 aerial photography camera (whose dimensions are 53.3 cm (21-in.) wide by 50.8 cm (20-in.) deep by 76.2 cm (30-in.) long). The performance characteristics of the WORF allow it to support an array of payload disciplines. The WORF provides a maximum of 3 Kw at 28 Vdc and has a maximum data rate of 10 Mbps. The WORF's unique payload volume is designed to be light-tight, down to 2.8 x 10(exp -11) Watts/cm2/steradian, and have low-reflective surfaces. This specially designed WORF interior supports payload investigations that observe low-light-level phenomenon such as aurora. Although the WORF rack does not employ any active rack isolation (i.e., vibration dampening) technology, the rack provides a very stable environment for payload operations (on the order

  17. High level waste interim storge architecture selection - decision report

    Energy Technology Data Exchange (ETDEWEB)

    Calmus, R.B.

    1996-09-27

    The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford Site tank waste treatment and immobilization services using privatized facilities (RL 1996a). This plan contains a two-phased approach. Phase I is a proof-of-principle/connnercial demonstration- scale effort and Phase II is a fiill-scale production effort. In accordance with the planned approach, interim storage and disposal of various products from privatized facilities are to be DOE fumished. The high-level waste (BLW) interim storage options, or alternative architectures, were identified and evaluated to provide the framework from which to select the most viable method of Phase I BLW interim storage (Calmus 1996). This evaluation, hereafter referred to as the Alternative Architecture Evaluation, was performed to established performance and risk criteria (technical merit, cost, schedule, etc.). Based on evaluation results, preliminary architectures and path forward reconunendations were provided for consideration in the architecture decision- maldng process. The decision-making process used for selection of a Phase I solidified BLW interim storage architecture was conducted in accordance with an approved Decision Plan (see the attachment). This decision process was based on TSEP-07,Decision Management Procedure (WHC 1995). The established decision process entailed a Decision Board, consisting of Westinghouse Hanford Company (VY`HC) management staff, and included appointment of a VTHC Decision Maker. The Alternative Architecture Evaluation results and preliminary recommendations were presented to the Decision Board members for their consideration in the decision-making process. The Alternative Architecture Evaluation was prepared and issued before issuance of @C-IP- 123 1, Alternatives Generation and Analysis Procedure (WI-IC 1996a), but was deemed by the Board to fully meet the intent of WHC-IP-1231. The Decision Board members concurred with the bulk of the Alternative Architecture

  18. US PRACTICE FOR INTERIM WET STORAGE OF RRSNF

    Energy Technology Data Exchange (ETDEWEB)

    Vinson, D.

    2010-08-05

    Aluminum research reactor spent nuclear fuel is currently being stored or is anticipated to be returned to the United States and stored at Department of Energy storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper summarizes the current practices to provide for continued safe interim wet storage in the U.S. Aluminum fuel stored in poor quality water is subject to aggressive corrosion attack and therefore water chemistry control systems are essential to maintain water quality. Fuel with minor breaches are safely stored directly in the basin. Fuel pieces and heavily damaged fuel is safely stored in isolation canisters.

  19. A history of startup and operations of the 234-5 facility during the year 1949

    Energy Technology Data Exchange (ETDEWEB)

    Bell, R.S.

    1950-02-09

    It is desired at this time to present in summary form a factual history of the Building 234-5 operations, encompassing not only the immediate pre-start-up period from April to July, 1949, but including the major obstacles encountered in the succeeding interval to the end of 1949. This report is intended to serve not only as a review of 234-5 operations during this period but also as a documentary evidence of the difficulties experienced and the manner in which they impeded the start-up. This report presupposes a certain familiarity with the background of the 234-5 Building. To one unacquainted with the scope of this project, or for those desiring a background review, reference should be made to Document HM-253, ``234-5 Building Program Review``, by D.D. Streid, dated April 22, 1949. It must be realized that any attempt to discuss in detail all the circumstances and difficulties contributing to the start-up period would be disconcerting to the reader, and would very likely be repetitive. Therefore, although it is far from the writer`s intent that a cursory review will suffice, the presentation will be as nearly as practicable, chronological and comparative. For the sake of clarity it will be necessary to present several items topically.

  20. AGR-1 Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Machael Abbott

    2009-08-01

    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.

  1. Commissioning and initial operation of the Isotope Production Facility at the Los Alamos Neutron Science Center (LANSCE).

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, K. F. (Kenneth F.); Alvestad, H. W. (Henry W.); Barkley, W. C. (Walter C.); Barlow, D. B. (David B.); Barr, D. S. (Dean S.); Bennett, L. S. (Langdon S.); Bitteker, L. J. (Leo J.); Bjorklund, E. A. (Eric A.); Boedeker, W.; Borden, M. J. (Michael J.); Cardon, R.; Carr, G. (Gary); Casados, J. L. (Jeffrey L.); Cohen, Stanley; Cordova, J. F. (Justo J.; Faucett, John Allen,; Fresquez, M. (Matthew); Gallegos, F. R. (Floyd R.); Gilpatrick, J. D. (John Douglas); Gonzales, F. (Fermin); Gorman, F. W. (Frederick W.); Gulley, M. S. (Mark S.); Hall, M. J. (Michael J.); Hayden, D. J. (David J.); Heaton, R. C. (Richard C.); Henderson, D. B. (Dale B.); Ireland, D. B. (David B.); Jacobson, E. G. (Edward G.); Johns, G. D. (Glen D.); Kersteins, D. M. (Debora M.); Maestas, A. J. (Alfred J.); Martinez, A. M. (Alexandra M.); Martinez, D. G. (Derwin G.); Martinez, G.; Martinez, J.; Martinez, M. P. (Martin P.); Merl, R. B. (Robert B.); Merrill, J. B. (John B.); Meyer, B. J. (Bruce J.); Meyer, R., Sr.; Milder, M.; Morgan, E.; Nortier, M.; O' Hara, J. F. (James F.); Olivas, F. R. (Felix R.); Oothoudt, Michael; Pence, T. D. (Tim D.); Perets, Mikhaʾel ben Yosef; Peterson, E.; Pillai, C. (Chandra); Romero, F.; Rose, C.; Rybarcyk, L. J. (Lawrence J.); Sanchez, G. (Gary); Sandoval, J. B. (Jacob B.); Schaller, S. (Stuart); Shelley, F. E. (Fred E.); Shurter, R. B. (Robert B.); Sommer, Walter F.; Stettler, M. W. (Matthew W.); Stockton, J. L. (Jerry L.); Sturrock, J. C. (James C.); Tomei, T. L. (Tony L.); Valdez, F.; Vigil, V. P. (Victor P.); Walstrom, P. L. (Peter L.); Wanco, P. M. (Peter M.); Wilmarth, J.

    2004-01-01

    The recently completed 100-MeV H{sup +} Isotope Production Facility (IPF) at the LANSCE will provide radioisotopes for medical research and diagnosis, for basic research and for commercial use. A change to the LANSCE accelerator facility allowed for the installation of the IPF. Three components make up the LANSCE accelerator: an injector that accelerates the H{sup +} beam to 750-KeV, a drift-tube linac (DTL) that increases the beam energy to 100-MeV, and a side-coupled cavity linac (SCCL) that accelerates the beam to 800-MeV. The transition region, a space between the DTL and the SCCL, was modified to permit the insertion of a kicker magnet (23{sup o} kick angle) for the purpose of extracting a portion of the 100-MeV H{sup +} beam. A new beam line was installed to transport the extracted H{sup +} beam to the radioisotope production target chamber. This paper will describe the commissioning and initial operating experiences of IPF.

  2. Optimizing Facility Configurations and Operating Conditions for Improved Performance in the NASA Ames 24 Inch Shock Tube

    Science.gov (United States)

    Bogdanoff, David W.; Cruden, Brett A.

    2016-01-01

    The Ames Electric Arc Shock Tube (EAST) is a shock tube wherein the driver gas can be heated by an electric arc discharge. The electrical energy is stored in a 1.2 MJ capacitor bank. Four inch and 24 inch diameter driven tubes are available. The facility is described and the need for testing in the 24 inch tube to better simulate low density NASA mission profiles is discussed. Three test entries, 53, 53B and 59, are discussed. Tests are done with air or Mars gas (95.7% CO2/2.7% N2/1.6% Ar) at pressures of 0.01 to 0.14 Torr. Velocities spanned 6.3-9.2 km/s, with a nominal center of 7 km/s. Many facility configurations are studied in an effort to improve data quality. Various driver and driven tube configurations and the use of a buffer section between the driver and the driven tube are studied. Diagnostics include test times, time histories of the shock light pulses and tilts of the shock wave off the plane normal to the tube axis. The report will detail the results of the various trials, give the best configuration/operating conditions found to date and provide recommendations for further improvements. Finally, diaphragm performance is discussed.

  3. Developing a Signature Based Safeguards Approach for the Electrorefiner and Salt Cleanup Unit Operations in Pyroprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, Chantell Lynne-Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-01-27

    Traditional nuclear materials accounting does not work well for safeguards when applied to pyroprocessing. Alternate methods such as Signature Based Safeguards (SBS) are being investigated. The goal of SBS is real-time/near-real-time detection of anomalous events in the pyroprocessing facility as they could indicate loss of special nuclear material. In high-throughput reprocessing facilities, metric tons of separated material are processed that must be accounted for. Even with very low uncertainties of accountancy measurements (<0.1%) the uncertainty of the material balances is still greater than the desired level. Novel contributions of this work are as follows: (1) significant enhancement of SBS development for the salt cleanup process by creating a new gas sparging process model, selecting sensors to monitor normal operation, identifying safeguards-significant off-normal scenarios, and simulating those off-normal events and generating sensor output; (2) further enhancement of SBS development for the electrorefiner by simulating off-normal events caused by changes in salt concentration and identifying which conditions lead to Pu and Cm not tracking throughout the rest of the system; and (3) new contribution in applying statistical techniques to analyze the signatures gained from these two models to help draw real-time conclusions on anomalous events.

  4. Operation and commissioning of IFMIF (International Fusion Materials Irradiation Facility) LIPAc injector

    Energy Technology Data Exchange (ETDEWEB)

    Okumura, Y., E-mail: okumura.yoshikazu@jaea.go.jp, E-mail: rjgobin@cea.fr; Knaster, J.; Ayala, J.-M.; Marqueta, A.; Perez, M.; Pruneri, G.; Scantamburlo, F. [IFMIF/EVEDA Project Team, Obuchi-Omotedate, 039-3212 Rokkasho, Aomori (Japan); Gobin, R., E-mail: okumura.yoshikazu@jaea.go.jp, E-mail: rjgobin@cea.fr; Bolzon, B.; Chauvin, N.; Chel, S.; Harrault, F.; Senée, F.; Valette, M. [Commissariat à l’Energie Atomique et aux Energies Alternatives, CEA/Saclay, DSM/IRFU, 91191 Gif/Yvette (France); Heidinger, R.; Cara, P.; Gex, D.; Phillips, G. [F4E, Fusion for Energy, BFD Department, D-85748 Garching (Germany); Ichimiya, R.; Ihara, A. [JAEA, Division of Rokkasho BA Project, Obuchi-Omotedate, 039-3212 Rokkasho, Aomori (Japan); and others

    2016-02-15

    The objective of linear IFMIF prototype accelerator is to demonstrate 125 mA/CW deuterium ion beam acceleration up to 9 MeV. The injector has been developed in CEA Saclay and already demonstrated 140 mA/100 keV deuterium beam [R. Gobin et al., Rev. Sci. Instrum. 85, 02A918 (2014)]. The injector was disassembled and delivered to the International Fusion Energy Research Center in Rokkasho, Japan. After reassembling the injector, commissioning has started in 2014. Up to now, 100 keV/120 mA/CW hydrogen and 100 keV/90 mA/CW deuterium ion beams have been produced stably from a 10 mm diameter extraction aperture with a low beam emittance of 0.21 π mm mrad (rms, normalized). Neutron production by D-D reaction up to 2.4 × 10{sup 9} n/s has been observed in the deuterium operation.

  5. Research on common methods for evaluating the operation effect of integrated wastewater treatment facilities of iron and steel enterprises

    Science.gov (United States)

    Bingsheng, Xu

    2017-04-01

    Considering the large quantities of wastewater generated from iron and steel enterprises in China, this paper is aimed to research the common methods applied for evaluating the integrated wastewater treatment effect of iron and steel enterprises. Based on survey results on environmental protection performance, technological economy, resource & energy consumption, services and management, an indicator system for evaluating the operation effect of integrated wastewater treatment facilities is set up. By discussing the standards and industrial policies in and out of China, 27 key secondary indicators are further defined on the basis of investigation on main equipment and key processes for wastewater treatment, so as to determine the method for setting key quantitative and qualitative indicators for evaluation indicator system. It is also expected to satisfy the basic requirements of reasonable resource allocation, environmental protection and sustainable economic development, further improve the integrated wastewater treatment effect of iron and steel enterprises, and reduce the emission of hazardous substances and environmental impact.

  6. 45 CFR 1623.6 - Interim funding.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this...

  7. Locating Interim Assessments within Teachers' Assessment Practice

    Science.gov (United States)

    Riggan, Matthew; Olah, Leslie Nabors

    2011-01-01

    Promising research on the teaching and learning impact of classroom-embedded formative assessment has spawned interest in a broader array of assessment tools and practices, including interim assessment. Although researchers have begun to explore the impact of interim assessments in the classroom, like other assessment tools and practices, they…

  8. 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)

  9. An Assessment of the Electric Power Quality and Electrical Installation Impacts on Medical Electrical Equipment Operations at Health Care Facilities

    Directory of Open Access Journals (Sweden)

    Mário C.G. Ramos

    2009-01-01

    Full Text Available Problem statement: Medical electrical equipments at health care facilities presented malfunction and wrong medical information due to poor electric power quality and to inadequate electrical Installations. Some equipment such as X-ray, computerized axial tomography and magnetic resonance imaging are considered as polluting ones due to their high amount of harmonics and voltage transients produced on the electrical power supply when in operation, while other equipments, connected to the same power supply, are considered sensitive or victim ones, presenting failure or producing wrong. Approach: The effects on some sensitive medical electrical equipment were verified in a controlled environment at energy quality technological center of the technical school of the University of Sao Paulo. A heart monitor, pulmonary ventilator and pulse oxymeter equipment types were submitted to a controlled voltage supply with high harmonic content and voltage sags. The test methodology used simulated conditions based on Brazilian NBR standards, ANSI/IEEE Std. 519, IEC 60601 and IEC 61000-4-11 standards. Results: The results of the polluting equipment current consumption measurements as well as the three sensitive equipments tested were presented and discussed. The pulmonary ventilator presented problems that range from stoppage to expiratory valve blockage and alarm system failures. The pulse oxymeter presented display malfunctions and it was extremely sensitive to voltage sags. The heart monitor maintained steady operation in all test cases. Conclusion/Recommendations: In spite of several existing recommendations and standards for testing medical electrical equipments, there is a lack of standard related to test cases considering the effects of high harmonic and voltage sags. The quality of electrical installation in health care facilities needs to be improved to reduce risks to the patients and to provide better health treatment.

  10. Laser performance operations model (LPOM): The computational system that automates the setup and performance analysis of the National Ignition Facility

    Science.gov (United States)

    Shaw, Michael; House, Ronald

    2015-02-01

    The National Ignition Facility (NIF) is a stadium-sized facility containing a 192-beam, 1.8 MJ, 500-TW, 351-nm laser system together with a 10-m diameter target chamber with room for many target diagnostics. NIF is the world's largest laser experimental system, providing a national center to study inertial confinement fusion and the physics of matter at extreme energy densities and pressures. A computational system, the Laser Performance Operations Model (LPOM) has been developed that automates the laser setup process, and accurately predict laser energetics. LPOM uses diagnostic feedback from previous NIF shots to maintain accurate energetics models (gains and losses), as well as links to operational databases to provide `as currently installed' optical layouts for each of the 192 NIF beamlines. LPOM deploys a fully integrated laser physics model, the Virtual Beamline (VBL), in its predictive calculations in order to meet the accuracy requirements of NIF experiments, and to provide the ability to determine the damage risk to optical elements throughout the laser chain. LPOM determines the settings of the injection laser system required to achieve the desired laser output, provides equipment protection, and determines the diagnostic setup. Additionally, LPOM provides real-time post shot data analysis and reporting for each NIF shot. The LPOM computation system is designed as a multi-host computational cluster (with 200 compute nodes, providing the capability to run full NIF simulations fully parallel) to meet the demands of both the controls systems within a shot cycle, and the NIF user community outside of a shot cycle.

  11. B Plant interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    Chalk, S.E.

    1996-09-01

    This interim safety basis (ISB-008) replaces the B Plant Safety Analysis Report, WHC-SD-WM-SAR-013, Rev. 2 (WHC 1993a). ISB-008 uses existing accident analyses, modified existing accident analyses, and new accident analyses to prove that B Plant remains within the safety envelope for transition, deactivation, standby, and shutdown activities. The analyses in ISB-008 are in accordance with the most current requirements for analytical approach, risk determination, and configuration management. This document and supporting accident analyses replace previous design-basis documents.

  12. Standard guide for mechanical drive systems for remote operation in hot cell facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 Intent: 1.1.1 The intent of this standard is to provide general guidelines for the design, selection, quality assurance, installation, operation, and maintenance of mechanical drive systems used in remote hot cell environments. The term mechanical drive systems used herein, encompasses all individual components used for imparting motion to equipment systems, subsystems, assemblies, and other components. It also includes complete positioning systems and individual units that provide motive power and any position indicators necessary to monitor the motion. 1.2 Applicability: 1.2.1 This standard is intended to be applicable to equipment used under one or more of the following conditions: 1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment. 1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded. 1.2.1.3 The ...

  13. Urgent recommendation. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Nakano, Masayuki [International Affairs and Safeguards Division, Atomic Energy Bureau, Science and Technology Agency, Tokyo (Japan)

    2000-12-01

    The Investigation Committee for Critical Accident at Uranium Processing Plant was founded immediately after the accident to investigate the cause of the accident and to establish measures to prevent the similar accident. On September 30, 1999 around 10:35, the Japan's first criticality accident occurred at JCO Co. Ltd. Uranium processing plant (auxiliary conversion plant) located at Tokai-mura Ibaraki-ken. The criticality continued on and off for approximately 20 hours after the first instantaneous criticality. The accident led the recommendation of tentative evacuation and sheltering indoors for residents living in the neighborhood. The serious exposure to neutrons happened to three workers. The dominant effect is dose due to neutrons and gamma rays from the precipitation tank. When the accident took place, three workers dissolved sequentially about 2.4 kg uranium powder with 18.8 % enrichment in the 10-litter bucket with nitric acid. The procedure of homogenization of uranium nitrate was supposed to be controlled using the shape-limited narrow storage column. Actually, however, the thick and large precipitation tank was used. As a result, about 16.6 kg of uranium was fed into the tank, which presumably caused criticality. The first notification by JCO was delayed and the following communication was not smooth. This led to the delay of correct understanding of the situation and made the initial proper response difficult, then followed by insufficient communication between the nation, prefecture, and local authority. Urgent recommendations were made on the following items; (1) Safety measures to be taken at the accident site, (2) health cares for residents and others, (3) Comprehensive safety securing at nuclear operators such as Establishment of the effective audit system, Safety education for employees and Qualification and licensing system, Safety related documents, etc. (4) Reconstruction of the government's safety regulations such as How safety

  14. Explanation of Significant Differences for the Record of Decision for Interim Actions in Zone 1, East Tennessee Technology Park, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Jacobs

    2011-02-01

    Zone 1 is a 1400-acre area outside the fence of the main plant at The East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The Record of Decision for Interim Actions in Zone, ETTP (Zone 1 Interim ROD) (DOE 2002) identifies the remedial actions for contaminated soil, buried waste, and subsurface infrastructure necessary to protect human health and to limit further contamination of groundwater. Since the Zone 1 Interim Record of Decision (ROD) was signed, new information has been obtained that requires the remedy to be modified as follows: (1) Change the end use in Contractor's Spoil Area (CSA) from unrestricted industrial to recreational; (2) Remove Exposure Units (EU5) ZI-50, 51, and 52 from the scope of the Zone I Interim ROD; (3) Change the end use of the duct bank corridor from unrestricted industrial to restricted industrial; and (4) Remove restriction for the disturbance of soils below 10 feet in Exposure Unit (EU) Z1-04. In accordance with 40 Code of Federal Regulations (CFR) 300.435, these scope modifications are a 'significant' change to the Zone 1 Interim ROD. In accordance with CERCLA Sect. 117 (c) and 40 CFR 300.435 (c)(2)(i), such a significant change is documented with an Explanation of Significant Differences (ESD). The purpose of this ESD is to make the changes listed above. This ESD is part of the Administrative Record file, and it, and other information supporting the selected remedy, can be found at the DOE Information Center, 475 Oak Ridge Turnpike, Oak Ridge, Tennessee 37830, from 8:00 a.m. to 5:00 p.m., Monday through Friday. The ORR is located in Roane and Anderson counties, within and adjacent to the corporate city limits of Oak Ridge, Tennessee. ETTP is located in Roane County near the northwest corner of the ORR. ETTP began operation during World War II as part of the Manhattan Project. The original mission of ETTP was to produce enriched uranium for use in atomic weapons. The plant produced enriched uranium from

  15. Fatal and Non-Fatal Electrocution Injuries at U.S. Marine Corps Forward Medical Facilities During Operation Enduring Freedom and Operation Iraqi Freedom.

    Science.gov (United States)

    Williams, Bradley; Deaton, Travis; Galarneau, Mike; Dye, Judy; Zieber, Tara; Auten, Jonathan

    2017-09-01

    Death from electrocution is rare and generally an accidental occurrence. In contrast to civilian patterns of electrocution injury, the military work environment suffers from a greater percentage of fatal high-voltage electrocutions. This study compared U.S. and international electrocution case fatality rates to rates among deployed military personnel presenting for care at expeditionary medical care facilities. We also sought to identify potential risk factors for fatal electrocution injury among deployed military personnel. A retrospective analysis was performed on electrocution injuries presenting to U.S. Marine Corps forward deployed medical facilities in Iraq and Afghanistan between January 2004 and December 2012. Descriptive statistics were used to describe the study population and compare fatal and nonfatal electrocutions. Fatality rates were reported in cases per 1,000,000 people per year. A total of 38 patients were identified; all were males with a mean (SD) age of 25.3 (5.3) years. Most electrocutions occurred on base (68%), whereas a smaller number (21%) occurred while conducting operations outside of the base. A majority of fatal cases (80%) occurred while outside of base on foot or vehicle mounted patrol. The rate of fatal electrocutions among U.S. Marine Corps personnel during this period was 37 per 1,000,000 people per year, 7-fold higher than the international electrocution fatality rate of 5.4 per 1,000,000 people per year and nearly three-fold above the U.S. utility and construction worker's fatality rate of 14 per 1,000,000 people per year. Electrocution injuries occurring during foot or vehicle mounted patrols seem to account for findings of higher case fatality rates among deployed military personnel than those found in international or high risk civilian occupational settings. Basic life support training for medical and nonmedical military personnel is critical to optimizing care delivered at the scene of these injuries. Reprint & Copyright

  16. Major ionic compositions of fine particulate matter in an animal feeding operation facility and its vicinity.

    Science.gov (United States)

    Li, Qian-feng; Wang-Li, Lingjuan; Liu, Zifei; Jayanty, R K M; Shah, Sanjay B; Bloomfield, Peter

    2014-11-01

    Animal feeding operations (AFOs) produce particulate matter (PM) and gaseous pollutants. Investigation of the chemical composition of PM2.5 inside and in the local vicinity of AFOs can help to understand the impact of the AFO emissions on ambient secondary PM formation. This study was conducted on a commercial egg production farm in North Carolina. Samples of PM2.5 were collected from five stations, with one located in an egg production house and the otherfour located in the vicinity ofthe farm alongfour wind directions. The major ions of NH4+, Na+, K+, SO4(2-), Cl-, and NO3- were analyzed using ion chromatography (IC). In the house, the mostly abundant ions were SO4(2-), Cl-, and K+. At ambient stations, SO4(2-), and NH4+ were the two most abundant ions. In the house, NH4+, SO4(2-), and NO3- accounted for only 10% of the PM2.5 mass; at ambient locations, NH4+, SO4(2-), and NO3- accounted for 36-41% of the PM2.5 mass. In the house, NH4+ had small seasonal variations indicating that gas- phase NH3. was not the only major force driving its gas-particle partitioning. At the ambient stations, NH4+ had the highest concentrations in summer In the house, K+, Na+, and Cl- were highly correlated with each other In ambient locations, SO4(2-) and NH4+ had a strong correlation, whereas in the house, SO4(2-) and NH4+ had a very weak correlation. Ambient temperature and solar radiation were positively correlated with NH4+ and SO4(2-). This study suggests that secondary PM formation inside the animal house was not an important source of PM2.5. In the vicinity, NH3 emissions had greater impact on PM2.5 formation.

  17. Experimental Report for Thermal Hydraulic Behavior During Startup, Power Change and MCP Transient Operation by using the High Temperature/High Pressure Test Facility(VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ki Yong; Park, Hyun Sik; Cho, Seok; Lee, Sung Jae; Choi, Nam Hyun; Min, Kyong Ho; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2005-07-15

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes experimental test results for performance test items, including heatup, power change, MCP transient, and natural circulation operations by using the VISTA facility.

  18. Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

  19. Design, fabrication and operation of a biomass fermentation facility. First quarterly report, October 1-December 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    O' Neil, D.J.; Colcord, A.R.; Bery, M.K.; Day, S.W.; Roberts, R.S.; El-Barbary, I.A.; Havlicek, S.C.; Anders, M.E.; Sondhi, D.

    1978-01-01

    The objective of this project is to design, fabricate, and operate a fermentation facility which will demonstrate on a pilot-scale level (3 oven-dry tons (ODT) per day of feedstock) the economic and technical feasibility of producing anhydrous ethyl alcohol from lignocellulosic biomass residues (wood, corn stover, and wheat straw principally). The resultant process development unit (PDU) will be flexibly designed so as to evaluate current and projected unit operations, materials of construction, chemical and enzymatic systems which offer the potential of significant technological and economic breakthroughs in alcohol production from biomass. The principal focus of the project is to generate fuels from biomass. As such, in addition to alcohol which can be used as a transportation fuel, by-products are to be directed where possible to fuel applications. The project consists of two parts: (1) conceptual design, and (2) detailed engineering design. The first quarter's activities have focused on a critical review of several aspects of the conceptual design of the 3 ODT/day PDU, viz.: (1) biomass cost, availability, and characterization; (2) pretreatment processes for lignocellulosic residues; (3) hydrolytic processes (enzymatic and acidic); (4) fermentation processes; (5) alcohol recovery systems; (6) by-product streams utilization; and (7) process economics.

  20. Accidental nuclear excursion Recuplex operation 234-5 facility. Final report: Date of incident: April 7, 1962

    Energy Technology Data Exchange (ETDEWEB)

    1962-08-01

    On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing the men were released to return to work. In compliance with AEC Manual Chapter 0703, an AEC-HAPO committee composed of two AEC employees and five General Electric employees was appointed by the Manger, HOO, with the concurrence of the General Manager, HAPO, to conduct an investigation of the incident. The committee`s purpose was to determine the cause, nature, and extent of the incident, and recommend action to be taken by others to minimize or preclude future incidents of this magnitude. A study of operating practices and operating conditions that appeared to exist prior to, during, and subsequent to the accident was made by the committee. The committee believes that this report provides sufficient information to answer questions which may arise as a result of the criticality incident except those relating to its cause.

  1. Belgian class II nuclear facilities such as irradiators and accelerators. Regulatory Body attention points and operating experience feedback

    Energy Technology Data Exchange (ETDEWEB)

    Minne, Etienne; Peters, Christelle; Mommaert, Chantal; Kennes, Christian; Cortenbosch, Geert; Schmitz, Frederic; Haesendonck, Michel van [Bel V, Brussels (Belgium); Carlier, Pascal; Schrayen, Virginie; Wertelaers, An [Federal Agency for Nuclear Control, Brussels (Belgium)

    2016-11-15

    The aim of this paper is to present the Regulatory Body attention points and the operating experience feedback from Belgian ''class IIA'' facilities such as industrial and research irradiators, bulk radionuclides producers and conditioners. Reinforcement of the nuclear safety and radiation protection has been promoted by the Federal Agency for Nuclear Control (FANC) since 2009. This paper is clearly a continuation of the former paper [1] presenting the evolution in the regulatory framework relative to the creation of Bel V, the subsidiary of the FANC, and to the new ''class IIA'' covering heavy installations such as those mentioned above. Some lessons learnt are extracted from the operating experience feedback based on the events declared to the authorities. Even though a real willingness to meet the new safety requirements is observed among the ''class IIA'' licensees, promoting the safety culture, the nuclear safety and radiation protection remains an endless challenge for the Regulatory Body.

  2. Second session: operating European facilities and their programs; Session 2: Les installations Europeennes actuelles et leurs programmes

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Porracchia, A.; Fougeras, P.; Morey, J.M. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Reacteurs; Loubiere, S.; Durande-Ayme, P. [CEA Saclay, Nuclear Energy Div., Reactors and Nuclear Services Deptment, 91 - Gif-sur-Yvette (France); Guidez, J.; Goux, D. [CEA Valrho, Dir. de l' Energie Nucleaire, DEN, 30 - Marcoule (France); Dupraz, R.; Brand, B. [FRAMATOME, AREVA-FANP, 69 - Lyon (France); Blanc, J.Y. [CEA Saclay, 91 - Gif sur Yvette (France); Perthuis, S. de [FRAMATOME ANP, 92 - Paris-La-Defence (France); Le Rouzic, J.F. [Electricite de France (EDF), 92 - Clamart (France)

    2005-07-01

    Most European nuclear post-irradiation examination facilities are ageing and the optimization of the remaining infrastructures may lead to connect them through a network implying consistent staff competence between countries and efficient nuclear material transport means. The second article describes the 3 very-low power research reactors operating in France: Minerve, Masurca and Eole. The Osiris reactor is presented in the third article, the author focuses on the devices available in Osiris to perform irradiation in light water reactor conditions and in high temperature reactor conditions and on the associated programs. Phenix reactor located on the Marcoule site had been performing from 1974 to 1990 the necessary technological qualifications required by the fast reactor system. An important upgrading program, led from 1994 to 2003, has allowed the reactor to begin a second life. Its investigation program encompasses research work on the transmutation of actinides and fission products and on new nuclear fuels and materials required for the future fourth generation of reactors. In Europe about 20 hot laboratories offer services to perform examination and qualification required by their national civil nuclear programs. Most are state-owned and show a large range of activities: nuclear fuels, materials, reprocessing, radio-nuclides, and radio-active sources. The last article reviews the main test loops operating in France and in neighboring countries. About 30 installations are reported and classified according to their activity fields : critical heat flux, hydro-mechanics, device testing, accidental situations, helium and severe reactor accidents. (A.C.)

  3. Spacelab data processing facility (SLDPF) Quality Assurance (QA)/Data Accounting (DA) expert systems: Transition from prototypes to operational systems

    Science.gov (United States)

    Basile, Lisa

    1988-01-01

    The SLDPF is responsible for the capture, quality monitoring processing, accounting, and shipment of Spacelab and/or Attached Shuttle Payloads (ASP) telemetry data to various user facilities. Expert systems will aid in the performance of the quality assurance and data accounting functions of the two SLDPF functional elements: the Spacelab Input Processing System (SIPS) and the Spacelab Output Processing System (SOPS). Prototypes were developed for each as independent efforts. The SIPS Knowledge System Prototype (KSP) used the commercial shell OPS5+ on an IBM PC/AT; the SOPS Expert System Prototype used the expert system shell CLIPS implemented on a Macintosh personal computer. Both prototypes emulate the duties of the respective QA/DA analysts based upon analyst input and predetermined mission criteria parameters, and recommended instructions and decisions governing the reprocessing, release, or holding for further analysis of data. These prototypes demonstrated feasibility and high potential for operational systems. Increase in productivity, decrease of tedium, consistency, concise historial records, and a training tool for new analyses were the principal advantages. An operational configuration, taking advantage of the SLDPF network capabilities, is under development with the expert systems being installed on SUN workstations. This new configuration in conjunction with the potential of the expert systems will enhance the efficiency, in both time and quality, of the SLDPF's release of Spacelab/AST data products.

  4. Tennessee Valley region study: potential year 2000 radiological dose to population resulting from nuclear facility operations. [Includes glossary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-06-01

    A companion report, DOE/ET-0064/1, presents a geographic, cultural, and demographic profile of the Tennessee Valley Region study area. This report describes the calculations of radionuclide release and transport and of the resultant dose to the regional population, assuming a projected installed capacity of 220,000 MW in the year 2000, of which 144,000 MW would be nuclear. All elements of the fuel cycle were assumed to be in operation. The radiological dose was calculated as a one-year dose based on ingestion of 35 different food types as well as for nine non-food pathways, and was reported as dose to the total body and for six specific organs for each of four age groups (infant, child, teen, and adult). Results indicate that the average individual would receive an incremental dose of 7 x 10/sup -4/ millirems in the year 2000 from the operation of nuclear facilities within and adjacent to the region, five orders of magnitude smaller than the dose from naturally occurring radiation in the area. The major contributor to dose was found to be tritium, and the most significant pathways were immersion in air, inhalation of air, transpiration of tritium (absorption through the skin), and exposure radionuclide-containing soil. 60 references.

  5. Succesvol interim-management : Meesterschap in een tijdelijke context

    NARCIS (Netherlands)

    Schaveling, J.

    2010-01-01

    Als flexibele optie om het management van organisaties aan te vullen, past interim-management helemaal in deze tijd. Maar wat maakt een interim-managementopdracht succesvol? ‘Succesvol interim-management’ is een studie naar de succesfactoren van interim-management. In de literatuur worden verschille

  6. 40 CFR 270.73 - Termination of interim status.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Termination of interim status. 270.73... (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Interim Status § 270.73 Termination of interim status. Interim status terminates when: (a) Final administrative disposition of...

  7. Scoren met interim-management : De weg naar tevreden opdrachtgevers

    NARCIS (Netherlands)

    Schaveling, J.

    2010-01-01

    Tegenwoordig kijkt niemand in organisaties meer op van de aanwezigheid van interim-managers. Interim-management biedt dé flexibiliteit om het management van organisaties aan te vullen. Maar wat maakt interim-managementopdrachten succesvol? Daarover gaat 'Scoren met interim-management: de weg naar te

  8. 33 CFR 1.05-45 - Interim rule.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Interim rule. 1.05-45 Section 1... PROVISIONS Rulemaking § 1.05-45 Interim rule. (a) An interim rule may be issued when it is in the public... example, an interim rule may be issued in instances when normal procedures for notice and comment prior...

  9. Design, operation, and monitoring capability of an experimental artificial-recharge facility at East Meadow, Long Island, New York

    Science.gov (United States)

    Schneider, B.J.; Oaksford, E.T.

    1986-01-01

    Artificial recharge with tertiary-treated sewage is being tested at East Meadow to evaluate the physical and chemical effects on the groundwater system. The recharge facility contains 11 recharge basins and 5 injection wells and is designed to accept 4 million gallons of reclaimed water per day. Of the 11 basins, 7 are recently constructed and will accept 0.5 million gallons per day each. An observation manhole (12-foot inside diameter and extending 16 feet below the basin floor) was installed in each of two basins to enable monitoring and sampling of percolating reclaimed water in the unsaturated zone with instruments such as tensiometers, gravity lysimeters, thermocouples, and soil-gas samplers. Five shallow (100-feet deep) injection wells will each return 0.5 million gallons per day to the groundwater reservoir. Three types of injection-well design are being tested; the differences are in the type of gravel pack around the well screen. When clogging at the well screen occurs, redevelopment should restore the injection capability. Flow to the basins and wells is regulated by automatic flow controllers in which a desired flow rate is maintained by electronic sensors. Basins can also operate in a constant-head mode in which a specified head is maintained in the basin automatically. An observation-well network consisting of 2-inch- and 6-inch-diameter wells was installed within a 1-square-mile area at the recharge facility to monitor aquifer response and recharge. During 48 days of operation within a 17-week period (October 1982 through January 1983), 88.5 million gallons of reclaimed water was applied to the shallow water table aquifer through the recharge basins. A 4.29-foot-high groundwater mound developed during a 14-day test; some water level increase associated with the mound was detected 1,000 ft from the basins. Preliminary water quality data from wells affected by reclaimed water show evidence that mechanisms of mixing, dilution, and dispersion are

  10. GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

    Energy Technology Data Exchange (ETDEWEB)

    Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

    2015-07-01

    International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

  11. KC-135 Operations Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The KC-135 Low-G Flight Research aircraft (a predecessor of the Boeing 707) is used to fly parabolas to create 20-25 seconds of weightlessness so that the astronauts...

  12. KC-135 Operations Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The KC-135 Low-G Flight Research aircraft (a predecessor of the Boeing 707) is used to fly parabolas to create 20-25 seconds of weightlessness so that the astronauts...

  13. Performance Confirmation Strategies for the Waste Isolation Pilot Plant - A Historical Perspective from an Operating Disposal Facility - 12248

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, Steve [John Hart and Associate for Sandia National Laboratories, Carlsbad, New Mexico 88220 (United States)

    2012-07-01

    Performance confirmation is an important element of the Waste Isolation Pilot Plant (WIPP) program. Performance confirmation was first used during the early WIPP site characterization phase to focus experimental activities that address the development of probabilistic repository performance models and to address stakeholder assurance needs. The program is currently used to analyze the conditions of the repository and its surroundings to ensure that the basis for the repository's long-term radioactive waste containment predictions is valid. This basis is related to the parameters, assumptions, conceptual and numerical models that are used to predict or validate the potential radioactive waste containment performance of the system. The concept of performance confirmation for the WIPP is one that has evolved since the first repository work was initiated decades ago and plays an important role in assuring adequate repository performance both now and in the long-term. The WIPP mission has progressed from a pilot project to an operational disposal facility and will progress to eventual site closure when disposal operations are completed. Performance confirmation is an important part of each of these progressions. The concept of disposing radioactive waste in a geologic repository today involves a complete understanding of many technical, political, regulatory, societal and economic elements. Many of these elements overlap and solving all relevant issues necessary to site, operate and decommission a disposal facility should be done with knowledge of each element's requirements and impacts. Performance confirmation is one tool that can help to coordinate many of these elements into a program that actively investigates what is thought to be adequately understood about the system and what information is lacking. A performance confirmation program is used to determine ways to challenge and verify those areas that are thought to be understood and to find ways to

  14. Evidence for photoneutron production in the lead shielding of a dedicated intra-operative electron only facility.

    Science.gov (United States)

    Biggs, P J

    1998-01-01

    A dedicated electron-only intra-operative suite has just been completed at the Massachusetts General Hospital. This suite is located on the 3rd floor with the shielding consisting entirely of lead and borated polyethylene, except for concrete in the floor and ceiling to support the lead and on the finished floor. The radiation protection barriers for this facility were calculated on the basis of a maximum permissible dose of 10 microSv wk(-1) for photons and 10 microSv wk(-1) for neutrons, based on a quality factor of 10 (this factor is specified in the regulations of the Commonwealth of Massachusetts). This even split was predicated on the basis that, except for the primary beam, the neutron leakage from the machine was generally about the same as for x rays. The initial survey showed that the neutron dose equivalent outside all barriers, except below the floor, was within the calculated values, neutron dose equivalent measured directly below the floor was found to be 35 microSv wk(-1) for the highest electron energy, a difference of > 25 microSv wk(-1). The neutron dose equivalent, for neutrons produced by bremsstrahlung photon interactions in the lead and based on a 3% photon background in the electron beam, was calculated to be 25 microSv wk(-1), in good agreement with this difference.

  15. Environmental assessment for the proposed construction and operation of a Genome Sequencing Facility in Building 64 at Lawrence Berkeley Laboratory, Berkeley, California

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This document is an Environmental Assessment (EA) for a proposed project to modify 14,900 square feet of an existing building (Building 64) at Lawrence Berkeley Laboratory (LBL) to operate as a Genome Sequencing Facility. This EA addresses the potential environmental impacts from the proposed modifications to Building 64 and operation of the Genome Sequencing Facility. The proposed action is to modify Building 64 to provide space and equipment allowing LBL to demonstrate that the Directed DNA Sequencing Strategy can be scaled up from the current level of 750,000 base pairs per year to a facility that produces over 6,000,000 base pairs per year, while still retaining its efficiency.

  16. Russian River Interim Action Management Plan

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — An interim action plan is presented to guide the 1979 management of the Kenai National Moose Range's portion of the lower Russian River and its confluence with the...

  17. Interim Policy for Evaluation of Stereoisomeric Pesticides

    Science.gov (United States)

    An interim approach for determining data requirements for non-racemic mixtures of stereoisomeric pesticides. These data are needed in order to assess the risk posed to ecosystems and drinking water sources by these mixtures.

  18. DOE UST interim subsurface barrier technologies workshop

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  19. A Guide for Developing Standard Operating Job Procedures for the Activated Sludge - Aeration & Sedimentation Process Wastewater Treatment Facility. SOJP No. 5.

    Science.gov (United States)

    Mason, George J.

    This guide for developing standard operating job procedures for wastewater treatment facilities is devoted to the activated sludge aeration and sedimentation process. This process is for conversion of nonsettleable and nonfloatable materials in wastewater to settleable, floculated biological groups and separation of the settleable solids from the…

  20. A Guide for Developing Standard Operating Job Procedures for the Activated Sludge - Aeration & Sedimentation Process Wastewater Treatment Facility. SOJP No. 5.

    Science.gov (United States)

    Mason, George J.

    This guide for developing standard operating job procedures for wastewater treatment facilities is devoted to the activated sludge aeration and sedimentation process. This process is for conversion of nonsettleable and nonfloatable materials in wastewater to settleable, floculated biological groups and separation of the settleable solids from the…

  1. Issues related to the construction and operation of a geological disposal facility for nuclear fuel waste in crystalline rock - the Canadian experience

    Energy Technology Data Exchange (ETDEWEB)

    Allan, C.J.; Baumgartner, P.; Ohta, M.M.; Simmons, G.R.; Whitaker, S.H. [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs

    1997-12-31

    This paper covers the overview of the Canadian nuclear fuel waste management program, the general approach to the siting, design, construction, operation and closure of a geological disposal facility, the implementing disposal, and the public involvement in implementing geological disposal of nuclear fuel waste. And two appendices are included. 45 refs., 5 tabs., 10 figs.

  2. School Operations and Maintenance: Best Practices For Controlling Energy Costs. A Guidebook for K-12 School System Business Officers and Facilities Managers

    Science.gov (United States)

    US Department of Energy, 2004

    2004-01-01

    Operations and maintenance (O&M) offers not only strategies for maintaining facilities, but also opportunities for reducing energy costs and increasing energy efficiency at existing schools, regardless of age. This Guidebook provides detailed and practical guidance on how K-12 school districts can plan and implement enhancements to their current…

  3. Unit cell modeling in support of interim performance assessment for low level tank waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kline, N.W., Westinghouse Hanford

    1996-08-01

    A unit cell model is used to simulate the base analysis case and related sensitivity cases for the interim performance assessment of low level tank waste disposal. Simulation case results are summarized in terms of fractional contaminant release rates to the vadose zone and to the water table at the unconfined aquifer. Results suggest that the crushed glass water conditioning layer at the top of the facility and the chemical retardation pad at the bottom of the facility can be important components of the facility. Results also suggest that the release rates to the water table are dominated by the release rate from the waste form.

  4. Dosimetry at an interim storage for spent nuclear fuel.

    Science.gov (United States)

    Králík, M; Kulich, V; Studeny, J; Pokorny, P

    2007-01-01

    The Czech nuclear power plant Dukovany started its operation in 1985. All fuel spent from 1985 up to the end of 2005 is stored at a dry interim storage, which was designed for 60 CASTOR-440/84 casks. Each of these casks can accommodate 84 fuel assemblies from VVER 440 reactors. Neutron-photon mixed fields around the casks were characterized in terms of ambient dose equivalent measured by standard area dosemeters. Except this, neutron spectra were measured by means of a Bonner sphere spectrometer, and the measured spectra were used to derive the corresponding ambient dose equivalent due to neutrons.

  5. New Pump and Treat Facility Remedial Action Work Plan For Test Area North Final Groundwater Remediation, Operable Unit 1-07B

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, L. O.

    2007-06-12

    This remedial action work plan identifies the approach and requirements for implementing the medial zone remedial action for Test Area North, Operable Unit 1-07B, at the Idaho National Laboratory. This plan details the management approach for the construction and operation of the New Pump and Treat Facility (NPTF). As identified in the remediatial design/remedial action scope of work, a separate remedial design/remedial action work plan will be prepared for each remedial component of the Operable Unit 1-07B remedial action.

  6. CALCULATION OF OPERATING PARAMETERS OF HIGH-VOLTAGE POWER TAKE-OFF SYSTEM FOR THE PHOTOVOLTAIC FACILITY

    Directory of Open Access Journals (Sweden)

    R.V. Zaitsev

    2016-09-01

    Full Text Available Purpose. To ensure maximum production of electric power by photovoltaic vacilities, in addition to using highly efficient photovoltaic modules equipped with solar radiation concentrators must use a highly effective power take-off system. This paper is inscribed to solving the problem of a highly efficient and economic power take-off system development. Methodology. To solving the problem, we implemented three stages. On the first stage examines the dependence of electrical power from the intensity of the incident solar radiation. Based on this, the second stage is calculated the DC-DC converter resonant circuit and its working parameters, and developed circuit diagram of DC-DC converter. On the third stage, we carry out an analysis of power take-off system with step up DC-DC converter working. Results. In this paper, we carry out the analysis of working efficiency for photovoltaic facility power take-off system with step-up boost converter. The result of such analysis show that the efficiency of such system in a wide range of photovoltaic energy module illumination power is at 0.92, whereas the efficiency of classic power take-off systems does not exceed 0.70. Achieved results allow designing a circuit scheme of a controlled bridge resonant step-up converter with digital control. Proposed scheme will ensure reliable operation, fast and accurate location point of maximum power and conversion efficiency up to 0.96. Originality. Novelty of proposed power take-off system solution constitute in implementation of circuit with DC-DC converters, which as it shown by results of carrying out modeling is the most effective. Practical value. Practical implementation of proposed power take-off system design will allow reducing losses in connective wires and increasing the efficiency of such a system up to 92.5% in wide range of photovoltaic energy modules illumination.

  7. Calculation of the operation mode of the emergency condenser (EC) of the INKA test facility with ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Wilschuetz, H.G. [E.ON Kernkraft GmbH, Hannover (Germany); Leyer, S. [AREVA NP GmbH, Offenbach (Germany); Kruessenberg, A.K.; Schaefer, F. [FZD Forschungszentrum Dresden-Rossendorf e.V. (Germany)

    2010-05-15

    On 4{sup th} of April 2008 AREVA and E.ON signed a cooperation agreement. An essential part of this is the Final Basic Design Contract SWR 1000. On 28{sup th} of November 2008 AREVA and E.ON have signed a Memorandum of Understanding to develop a commercially viable product and to focus on the successful deployment of the SWR 1000 in a collaborative manner. Meanwhile a rebranding was conducted: the new name of this evolutionary boiling water reactor of the Generation III+ is KERENATM trademark. It is the common intention of AREVA and E.ON to complete the basic design until the end of 2010 so as to reach a design ready for bid and ready for licensing for a construction primarily in a European country. The KERENA trademark is not a completely new plant concept, it is a proven further developed design, based on Gundremmingen NPP and the whole accumulated German BWR operating experience. The design shall fulfill the following major safety items: - further reduction of core damage frequency, - control of postulated core melt accident by in-vessel melt retention without emergency response actions, - introduction of passive safety systems (principle of diversity and redundancy), and - long grace periods for manual intervention (> 3 days). Especially for the newly introduced passive safety systems, which are described in detail, not only an experimental testing and validation is needed, but also thermal-hydraulic system codes have to be qualified, to be able to consider the mostly gravity driven 3D-flow phenomena correctly. Since in some countries the code ATHLET is well established, it is useful to prove its capabilities or to enhance the capabilities, if necessary. Therefore the FZD (Forschungszentrum Dresden-Rossendorf) is performing a model development and calculations for code validation of the test results from INKA (INtegral test facility in KArlstein, Germany). This paves the way for licensing procedures later on. (orig.)

  8. The Copernicus S5P Mission Performance Centre / Validation Data Analysis Facility for TROPOMI operational atmospheric data products

    Science.gov (United States)

    Compernolle, Steven; Lambert, Jean-Christopher; Langerock, Bavo; Granville, José; Hubert, Daan; Keppens, Arno; Rasson, Olivier; De Mazière, Martine; Fjæraa, Ann Mari; Niemeijer, Sander

    2017-04-01

    Sentinel-5 Precursor (S5P), to be launched in 2017 as the first atmospheric composition satellite of the Copernicus programme, carries as payload the TROPOspheric Monitoring Instrument (TROPOMI) developed by The Netherlands in close cooperation with ESA. Designed to measure Earth radiance and solar irradiance in the ultraviolet, visible and near infrared, TROPOMI will provide Copernicus with observational data on atmospheric composition at unprecedented geographical resolution. The S5P Mission Performance Center (MPC) provides an operational service-based solution for various QA/QC tasks, including the validation of S5P Level-2 data products and the support to algorithm evolution. Those two tasks are to be accomplished by the MPC Validation Data Analysis Facility (VDAF), one MPC component developed and operated at BIRA-IASB with support from S[&]T and NILU. The routine validation to be ensured by VDAF is complemented by a list of validation AO projects carried out by ESA's S5P Validation Team (S5PVT), with whom interaction is essential. Here we will introduce the general architecture of VDAF, its relation to the other MPC components, the generic and specific validation strategies applied for each of the official TROPOMI data products, and the expected output of the system. The S5P data products to be validated by VDAF are diverse: O3 (vertical profile, total column, tropospheric column), NO2 (total and tropospheric column), HCHO (tropospheric column), SO2 (column), CO (column), CH4 (column), aerosol layer height and clouds (fractional cover, cloud-top pressure and optical thickness). Starting from a generic validation protocol meeting community-agreed standards, a set of specific validation settings is associated with each data product, as well as the appropriate set of Fiducial Reference Measurements (FRM) to which it will be compared. VDAF collects FRMs from ESA's Validation Data Centre (EVDC) and from other sources (e.g., WMO's GAW, NDACC and TCCON). Data

  9. Fire Hazard Analysis for the Cold Vacuum Drying facility (CVD) Facility

    CERN Document Server

    Singh, G

    2000-01-01

    The CVDF is a nonreactor nuclear facility that will process the Spent Nuclear Fuels (SNF) presently stored in the 105-KE and 105-KW SNF storage basins. Multi-canister overpacks (MCOs) will be loaded (filled) with K Basin fuel transported to the CVDF. The MCOs will be processed at the CVDF to remove free water from the fuel cells (packages). Following processing at the CVDF, the MCOs will be transported to the CSB for interim storage until a long-term storage solution can be implemented. This operation is expected to start in November 2000. A Fire Hazard Analysis (FHA) is required for all new facilities and all nonreactor nuclear facilities, in accordance with U.S. Department of Energy (DOE) Order 5480.7A, Fire Protection. This FHA has been prepared in accordance with DOE 5480.7A and HNF-PRO-350, Fire Hazard Analysis Requirements. Additionally, requirements or criteria contained in DOE, Richland Operations Office (RL) RL Implementing Directive (RLID) 5480.7, Fire Protection, or other DOE documentation are cite...

  10. 76 FR 9743 - Foreign-Trade Zone Subzone 22- Chicago, IL, Temporary/Interim Manufacturing Authority, Baxter...

    Science.gov (United States)

    2011-02-22

    ... Authority, Baxter Healthcare Corporation (Pharmaceutical and Biological Product Manufacturing), Notice of.../ interim manufacturing (T/IM) authority, on behalf of Baxter Healthcare Corporation (Baxter) to manufacture... FTZ Board Orders 1347 (69 FR 52857, 8/30/04) and 1480 (71 FR 55422, 9/22/06). The Baxter facility and...

  11. 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.

  12. 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.

  13. 78 FR 13695 - Information Collection: Renewable Energy and Alternate Uses of Existing Facilities on the Outer...

    Science.gov (United States)

    2013-02-28

    ... Verification 100 3 CVA design 300 Agent (CVA) conducts interim reports. independent assessment of the facility... reports if required, in format specified. 100 3 CVA final 300 reports. 705(a)(3); 708; 709; 710; 712.. CVA conducts 100 3 CVA interim 300 independent reports. assessments/ inspections on the fabrication and...

  14. Study of New Youth Initiatives in Apprenticeship. Interim Report. Volume 2: Site Visit Reports.

    Science.gov (United States)

    CSR, Inc., Washington, DC.

    This second volume of the interim report provides detailed case study reports on each of the eight Youth Apprenticeship Projects. (Volume 1, an overview of data from the site visits, is available separately as CE 032 791.) Discussion areas covered in each site visit report are local context/operational environment, administrative information,…

  15. 40 CFR 80.156 - Liability for violations of the interim detergent program controls and prohibitions.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Liability for violations of the interim detergent program controls and prohibitions. 80.156 Section 80.156 Protection of Environment... operating under such refiner's corporate, trade, or brand name or that of any of its marketing...

  16. 40 CFR 265.383 - Interim status thermal treatment devices burning particular hazardous waste.

    Science.gov (United States)

    2010-07-01

    ... status thermal treatment devices burning particular hazardous waste. (a) Owners or operators of thermal treatment devices subject to this subpart may burn EPA Hazardous Wastes FO20, FO21, FO22, FO23, FO26, or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Interim status thermal...

  17. Advantages on dry interim storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

    2006-07-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  18. Methods Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  19. Hanford Generic Interim Safety Basis

    Energy Technology Data Exchange (ETDEWEB)

    Lavender, J.C.

    1994-09-09

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  20. Groundwater monitoring plan for the Hanford Site 216-B-3 pond RCRA facility

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, D.B.; Chou, C.J.

    1998-06-01

    The 216-B-3 pond system was a series of ponds for disposal of liquid effluent from past Hanford production facilities. In operation since 1945, the B Pond system has been a RCRA facility since 1986, with Resource Conservation and Recovery Act (RCRA) interim-status groundwater monitoring in place since 1988. In 1994, discharges were diverted from the main pond, where the greatest potential for contamination was thought to reside, to the 3C expansion pond. In 1997, all discharges to the pond system were discontinued. In 1990, the B Pond system was elevated from detection groundwater monitoring to an assessment-level status because total organic halogens and total organic carbon were found to exceed critical means in two wells. Subsequent groundwater quality assessment failed to find any specific hazardous waste contaminant that could have accounted for the exceedances, which were largely isolated in occurrence. Thus, it was recommended that the facility be returned to detection-level monitoring.