WorldWideScience

Sample records for application facility baf

  1. Colloidal synthesis of BaF2 nanoparticles and their application as fillers in polymer nanocomposites

    Science.gov (United States)

    Sathyamurthy, Srivatsan; Tuncer, Enis; More, Karren L.; Gu, Baohua; Sauers, Isidor; Paranthaman, M. Parans

    2012-03-01

    Nanoparticles of pure and Eu-doped BaF2 have been prepared through sol-gel colloidal synthesis. In addition, BaF2-filled PMMA polymer nanocomposites were fabricated and dielectric properties were measured. The as-synthesized pure and Eu-doped BaF2 nanoparticles were analyzed by both X-ray diffraction and transmission electron microscopy and consisted of crystalline BaF2 particles with an average diameter of 13.6 nm with a standard deviation of about ±2.4 nm. The photoluminescence properties of the pure and Eu-doped (2%, 4% and 8%) nanoparticles showed characteristic emission of Eu3+ (5D0→7F J ( J=1-4) transitions). We also measured significantly enhanced dielectric breakdown strength of up to 30% for BaF2 nanocomposites over the unfilled PMMA polymer. This study thus offers some promise of sol-gel synthesis of nanocomposite dielectrics with great potential for use as electrical insulation materials in cryogenic high-voltage applications.

  2. Colloidal synthesis of BaF2 nanoparticles and their application as fillers in polymer nanocomposites

    Energy Technology Data Exchange (ETDEWEB)

    Sathyamurthy, Srivatsan [ORNL; Tuncer, Enis [ORNL; More, Karren Leslie [ORNL; Gu, Baohua [ORNL; Sauers, Isidor [ORNL; Paranthaman, Mariappan Parans [ORNL

    2012-01-01

    Nanoparticles of pure and Eu-doped BaF2 have been prepared through sol-gel colloidal synthesis. In addition, BaF2 filled PMMA polymer nanocomposites were fabricated and dielectric properties were measured. The as-synthesized pure and Eu-doped BaF2 nanoparticles were analyzed by both X-ray diffraction and transmission electron microscopy and consisted of crystalline BaF2 particles with an average diameter of 13.6 nm with a standard deviation of about 2.4 nm. The photoluminescence properties of the pure and Eu-doped (2%, 4% and 8%) nanoparticles showed characteristic emission of Eu3+ (5D0 7FJ (J=1-4) transitions). We also measured significantly enhanced dielectric breakdown strength of up to 30% for BaF2 nanocomposites over the unfilled PMMA polymer. This study thus offers some promise of sol-gel synthesis of nanocomposite dielectrics with great potential for use as electrical insulation materials in cryogenic high voltage applications.

  3. Development of a BaF2 scintillation spectrometer for evaluation of photon energy spectra in workplaces around nuclear facilities

    International Nuclear Information System (INIS)

    Urabe, Itsumasa; Yoshimoto, Taka-aki; Kobayashi, Katsuhei; Akiyoshi, Tsunekazu; Tsujimoto, Tadashi; Nakashima, Yoshiyuki; Oda, Keiji.

    1997-01-01

    A BaF 2 scintillation spectrometer has been constructed for the determination of photon energy spectra in workplaces around nuclear facilities. Energy absorption spectra by the BaF 2 detector were calculated with the EGS4 Monte Carlo code in the energy region from 0.1 to 100 MeV and a response matrix of the spectrometer was obtained from the energy absorption spectra, of which the energy resolutions were modified to fit to the experimental results. With the irradiation experiments using neutron-capture gamma rays and those from radioactive sources, it became clear that photon energy spectra can be evaluated within an error of about 10% in the energy region 0.1 MeV to a few tens of megaelectronvolts. (author)

  4. Applications of microtron facility

    International Nuclear Information System (INIS)

    Sanjeev, Ganesh

    2013-01-01

    An 8 MeV Microtron accelerator installed and commissioned in Mangalore University to strengthen research activities in the area of Radiation Physics and allied sciences is also being used extensively for coordinated research programs in basic and applied areas of science and technology involving researchers from national laboratories and sister universities of the region. The electron accelerator with its versatile features extends energetic electrons, intense photons and neutrons of moderate flux to cater to the needs of the users of the facility. A brief view of this 'first of its kind' facility in the country and the R and D programs with some sample results is presented. (author)

  5. Ho3+/Yb3+ co-doped TeO2-BaF2-Y2O3 glasses for ∼1.2 μm laser applications

    Science.gov (United States)

    Wang, Shunbin; Li, Chengzhi; Yao, Chuanfei; Jia, Shijie; Jia, Zhixu; Qin, Guanshi; Qin, Weiping

    2017-02-01

    Intense ∼1.2 μm fluorescence is observed in Ho3+/Yb3+ co-doped TeO2-BaF2-Y2O3 glasses under 915 nm laser diode excitation. The 1.2 μm emission can be ascribed to the transition 5I6→5I8 of Ho3+. With the introducing of BaF2, the content of OH in the glasses drops markedly, and the 1.2 μm emission intensity increases gradually as increasing the concentration percentage of BaF2. Furthermore, microstructured fibers based on the TeO2-BaF2-Y2O3 glasses are fabricated by using a rod-in-tube method, and a relative positive gain of ∼9.42 dB at 1175.3 nm is obtained in a 5 cm long fiber.

  6. IEEE 1394 CAMERA IMAGING SYSTEM FOR BROOKHAVENS BOOSTER APPLICATION FACILITY BEAM DIAGNOSTICS

    International Nuclear Information System (INIS)

    BROWN, K.A.; FRAK, B.; GASSNER, D.; HOFF, L.; OLSEN, R.H.; SATOGATA, T.; TEPIKIAN, S.

    2002-01-01

    Brookhaven's Booster Applications Facility (BAF) will deliver resonant extracted heavy ion beams from the AGS Booster to short-exposure fixed-target experiments located at the end of the BAF beam line. The facility is designed to deliver a wide range of heavy ion species over a range of intensities from 10 3 to over 10 8 ions/pulse, and over a range of energies from 0.1 to 3.0 GeV/nucleon. With these constraints we have designed instrumentation packages which can deliver the maximum amount of dynamic range at a reasonable cost. Through the use of high quality optics systems and neutral density light filters we will achieve 4 to 5 orders of magnitude in light collection. By using digital IEEE1394 camera systems we are able to eliminate the frame-grabber stage in processing and directly transfer data at maximum rates of 400 Mb/set. In this note we give a detailed description of the system design and discuss the parameters used to develop the system specifications. We will also discuss the IEEE1394 camera software interface and the high-level user interface

  7. BNL ACCELERATOR-BASED RADIOBIOLOGY FACILITIES

    International Nuclear Information System (INIS)

    LOWENSTEIN, D.I.

    2000-01-01

    For the past several years, the Alternating Gradient Synchrotron (AGS) at Brookhaven National Laboratory (USA) has provided ions of iron, silicon and gold, at energies from 600 MeV/nucleon to 10 GeV/nucleon, for the US National Aeronautics and Space Administration (NASA) radiobiology research program. NASA has recently funded the construction of a new dedicated ion facility, the Booster Applications Facility (BAF). The Booster synchrotron will supply ion beams ranging from protons to gold, in an energy range from 40--3,000 MeV/nucleon with maximum beam intensities of 10 10 to 10 11 ions per pulse. The BAF Project is described and the future AGS and BAF operation plans are presented

  8. Application of robotics in nuclear facilities

    International Nuclear Information System (INIS)

    Byrd, J.S.; Fisher, J.J.

    1986-01-01

    Industrial robots and other robotic systems have been successfully applied at the Savannah River nuclear site. These applications, new robotic systems presently under development, general techniques for the employment of robots in nuclear facilities, and future systems are discussed

  9. Production of sorption functional media (SFM) from clinoptilolite tailings and its performance investigation in a biological aerated filter (BAF) reactor

    International Nuclear Information System (INIS)

    Feng, Yan; Qi, Jingyao; Chi, Liying; Wang, Dong; Wang, Zhaoyang; Li, Ke; Li, Xin

    2013-01-01

    Highlights: ► Sorption functional media (SFM) were prepared using zeolite tailings. ► Two upflow BAFs were applied to treat municipal wastewater. ► SFM BAF brought a relative superiority to haydite reactor. ► SFM BAF has a stronger adaptability to low temperature (6–11°C) for NH 3 -N removal. ► The application provided a promising way in zeolite tailings utilization. -- Abstract: The few reuse and large stockpile of zeolite tailings led to a series of social and environmental problems. This study investigated the possibility of using the zeolite tailings as one of principal raw materials to prepare sorption functional media (SFM) by a high temperature sintering process. The SFM was used to serve as a biomedium in a biological aerated filter (BAF) reactor for domestic wastewater treatment, and its purification performance was examined. The physical, chemical and sorption properties of SFM were also determined. The microstructure of the SFM was analyzed by scanning electron microscopy (SEM). Results revealed that: (1) zeolite tailings could be used to produce the SFM under the optimal sintering parameters; (2) the sorption and desorption isotherm of ammonia nitrogen on SFM could be well described by the Langmuir formula; (3) in terms of removing organic matter, ammonia nitrogen, turbidity and colourity, the performance of the biofilter with SFM was superior to that with haydite; and (4) SFM BAF has a stronger adaptability to low temperature (6–11 °C) for NH 3 -N removal compared to haydite BAF. Therefore, the SFM produced from the zeolite tailings was suitable to serve as the biomedium in the domestic wastewater treatment

  10. Hanford facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-01-01

    This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains ''umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit

  11. Grout Treatment Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) is an existing treatment, storage, and/or disposal (TSD) unit located in the 200 East Area and the adjacent 600 Area of the Hanford Site. The GTF mixes dry cementitious solids with liquid mixed waste (containing both dangerous and radioactive constituents) produced by Hanford Site operations. The GTF consists of the following: The 241-AP-02D and 241-AP-04D waste pump pits and transfer piping; Dry Materials Facility (DMF); Grout Disposal Facility (GDF), consisting of the disposal vault and support and monitoring equipment; and Grout Processing Facility (GPF) and Westinghouse Hanford Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The Grout Treatment Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this TSD unit, including the current revision, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings

  12. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Coenenberg, J.G.

    1997-08-15

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  13. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    International Nuclear Information System (INIS)

    Coenenberg, J.G.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, 'operating' treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  14. Scintillation and radiation damage of doped BaF2 crystals

    International Nuclear Information System (INIS)

    Gong Zufang; Xu Zizong; Chang Jin

    1992-01-01

    The emission spectra and the radiation damage of BaF 2 crystals doped Ce and Dy have been studied. The results indicate that the doped BaF 2 crystals have the intrinsic spectra of impurity besides the intrinsic spectra of BaF 2 crystals. The crystals colored and the transmissions decrease with the concentration of impurity in BaF 2 crystals after radiation by γ-ray of 60 Co. The doped Ce BaF 2 irradiated by ultraviolet has faster recover of transmissions but for doped Dy the effect is not obvious. The radiation resistance is not good as pure BaF 2 crystals

  15. WIPP's Hazardous Waste Facility Permit Renewal Application

    International Nuclear Information System (INIS)

    Most, W.A.; Kehrman, R.F.

    2009-01-01

    Hazardous waste permits issued by the New Mexico Environment Department (NMED) have a maximum term of 10-years from the permit's effective date. The permit condition in the Waste Isolation Pilot Plant's (WIPP) Hazardous Waste Facility Permit (HWFP) governing renewal applications, directs the Permittees to submit a permit application 180 days prior to expiration of the Permit. On October 27, 1999, the Secretary of the NMED issued to the United States Department of Energy (DOE), the owner and operator of WIPP, and to Washington TRU Solutions LLC (WTS), the Management and Operating Contractor and the cooperator of WIPP, a HWFP to manage, store, and dispose hazardous waste at WIPP. The DOE and WTS are collectively known as the Permittees. The HWFP is effective for a fixed term not to exceed ten years from the effective date of the Permit. The Permittees may renew the HWFP by submitting a new permit application at least 180 calendar days before the expiration date, of the HWFP. The Permittees are not proposing any substantial changes in the Renewal Application. First, the Permittees are seeking the authority to dispose of Contact-Handled and Remote-Handled TRU mixed waste in Panel 8. Panels 4 through 7 have been approved in the WIPP Hazardous Waste Facility Permit as it currently exists. No other change to the facility or to the manner in which hazardous waste is characterized, managed, stored, or disposed is being requested. Second, the Permittees also seek to include the Mine Ventilation Rate Monitoring Plan, as Attachment Q in the HWFP. This Plan has existed as a separate document since May 2000. The NMED has requested that the Plan be submitted as part of the Renewal Application. The Permittees have been operating to the Mine Ventilation Rate Monitoring Plan since the Plan was submitted. Third, some information submitted in the original WIPP RCRA Part B Application has been updated, such as demographic information. The Permittees will submit this information in the

  16. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations

  17. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 2 appendices covering engineering drawings and operating procedures

  18. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constitutents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 2 Appendices covering engineering drawings and operating procedures

  19. Grout Treatment Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 14 Appendices. Topics include Engineering Drawings, Maps, Roads, Toxicity Testing, and Pilot-Scale Testing

  20. Cardiac-enriched BAF chromatin-remodeling complex subunit Baf60c regulates gene expression programs essential for heart development and function

    Directory of Open Access Journals (Sweden)

    Xin Sun

    2018-01-01

    Full Text Available How chromatin-remodeling complexes modulate gene networks to control organ-specific properties is not well understood. For example, Baf60c (Smarcd3 encodes a cardiac-enriched subunit of the SWI/SNF-like BAF chromatin complex, but its role in heart development is not fully understood. We found that constitutive loss of Baf60c leads to embryonic cardiac hypoplasia and pronounced cardiac dysfunction. Conditional deletion of Baf60c in cardiomyocytes resulted in postnatal dilated cardiomyopathy with impaired contractile function. Baf60c regulates a gene expression program that includes genes encoding contractile proteins, modulators of sarcomere function, and cardiac metabolic genes. Many of the genes deregulated in Baf60c null embryos are targets of the MEF2/SRF co-factor Myocardin (MYOCD. In a yeast two-hybrid screen, we identified MYOCD as a BAF60c interacting factor; we showed that BAF60c and MYOCD directly and functionally interact. We conclude that Baf60c is essential for coordinating a program of gene expression that regulates the fundamental functional properties of cardiomyocytes.

  1. Neutron radiographic techniques, facilities and applications

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1984-08-01

    This is a collection of three papers, written for presentation on two international conferences. The first paper: ''Neutron radiography. Techniques and facilities'', written by J.P. Barton of N-Ray Engineering Co. La Jolla, CA., USA and J.C. Domanus was presented at the International Symposium on the Use and Development of Low and Medium Flux Research Reactors at the Massachusets Institute of Technology, Cambridge, Mass., USA, 16-19 October 1983. The second paper: ''Neutron radiography with the DR-1 reactor at Risoe National Laboratory'', written by J.C. Domanus, was presented at the same Symposium. The third paper: ''Defects in nuclear fuel revealed by neutron radiography'', written by J.C. Domanus is accepted for presentation on 18 October 1984 to the 3rd European Conference on Nondestructive Testing, Florence, Italy, 15-18 October 1984. While the first paper describes the principles of neutron radiographic techniques and facilities, the second one describes an example of such facility and the third gives an example of application of neutron radiography in the field of nuclear fuel. (author)

  2. Synchrotron radiation facilities for chemical applications

    International Nuclear Information System (INIS)

    Hatano, Yoshihiko

    1995-01-01

    Synchrotron radiation (SR) research is of great importance in understanding radiation chemistry, physics, and biology. It is also clearly recognized in the international chemical community that chemical applications of SR are greatly advanced and divided into 1) Molecular Spectroscopy and Dynamics Studies-Gases, Surfaces, and Condensed Matter- , 2) Radiation Chemistry and Photochemistry, 3) X-ray Structural and XAFS Studies-Crystals, Surfaces, and Liquids- , 4) Analytical Chemistry, and 5) Synthesis or R and D of New Materials. In this paper, a survey is given of recent advances in the application of SR to the chemistry of excitation and ionization of molecules, i.e., SR chemistry, in the wavelength region between near-ultraviolet and hard X-rays. The topics will be chosen from those obtained at some leading SR facilities. (J.P.N.)

  3. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A

    International Nuclear Information System (INIS)

    Bowman, R.C.

    1994-04-01

    This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification

  4. Protection of Facilities and Risk Assessment Application

    OpenAIRE

    Nađ, Ivan; Mihaljević, Branko; Mihalinčić, Martina

    2014-01-01

    The state of security on a specific area imposes the necessity for constant analysis of the existing system of protection of key state facilities, especially facilities of special significance for the defence. The facilities of special significance for the defence are an important part of the daily life, and enable smooth functioning of the economy and all other state activities. The protection of facilities of special significance for the defence is considered to be a system of obligatory me...

  5. The role of BAF (mSWI/SNF) complexes in mammalian neural development.

    Science.gov (United States)

    Son, Esther Y; Crabtree, Gerald R

    2014-09-01

    The BAF (mammalian SWI/SNF) complexes are a family of multi-subunit ATP-dependent chromatin remodelers that use ATP hydrolysis to alter chromatin structure. Distinct BAF complex compositions are possible through combinatorial assembly of homologous subunit families and can serve non-redundant functions. In mammalian neural development, developmental stage-specific BAF assemblies are found in embryonic stem cells, neural progenitors and postmitotic neurons. In particular, the neural progenitor-specific BAF complexes are essential for controlling the kinetics and mode of neural progenitor cell division, while neuronal BAF function is necessary for the maturation of postmitotic neuronal phenotypes as well as long-term memory formation. The microRNA-mediated mechanism for transitioning from npBAF to nBAF complexes is instructive for the neuronal fate and can even convert fibroblasts into neurons. The high frequency of BAF subunit mutations in neurological disorders underscores the rate-determining role of BAF complexes in neural development, homeostasis, and plasticity. © 2014 Wiley Periodicals, Inc.

  6. Liquid effluent retention facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-06-01

    This appendix to the Liquid Effluent Retention Facility Dangerous Waste Permit Application contains pumps, piping, leak detection systems, geomembranes, leachate collection systems, earthworks and floating cover systems

  7. Survey of EPA facilities for solar thermal energy applications

    Science.gov (United States)

    Nelson, E. V.; Overly, P. T.; Bell, D. M.

    1980-01-01

    A study was done to assess the feasibility of applying solar thermal energy systems to EPA facilities. A survey was conducted to determine those EPA facilities where solar energy could best be used. These systems were optimized for each specific application and the system/facility combinations were ranked on the basis of greatest cost effectiveness.

  8. Facility overview for commercial application of selected Rocky Flats facilities

    International Nuclear Information System (INIS)

    1996-11-01

    The purpose of this Facility Overview is to support the Rocky Flats Local Impacts Initiative's Request for Interest, to solicit interest from commercial corporations for utilizing buildings 865 and 883, and the equipment contained within each building, for a commercial venture. In the following sections, this document describes the Rocky Flats Site, the buildings available for lease, the equipment within these buildings, the site services available to a tenant, the human resources available to support operations in buildings 865 and 883, and the environmental condition of the buildings and property. In addition, a brief description is provided of the work performed to date to explore the potential products that might be manufactured in Buildings 865 and 883, and the markets for these products

  9. Non-Federal Facilities National Application -

    Data.gov (United States)

    Department of Transportation — Navigation and Administrative tool to monitor Air Traffic Facilities from inception to commissioning. Ability to track field inspections and analysis. It influences...

  10. 75 FR 41877 - Insured Healthcare Facilities 232 Loan Application

    Science.gov (United States)

    2010-07-19

    ... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5376-N-65] Insured Healthcare Facilities 232 Loan Application AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY... Proposal: Insured Healthcare Facilities 232 Loan Application. OMB Approval Number: 2502-New. Form Numbers...

  11. 75 FR 16821 - Insured Healthcare Facilities 232 Loan Application

    Science.gov (United States)

    2010-04-02

    ... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5376-N-23] Insured Healthcare Facilities 232 Loan Application AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY...: Title of Proposal: Insured Healthcare Facilities 232 Loan Application. OMB Approval Number: 2502-New...

  12. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

  13. BAF200 is required for heart morphogenesis and coronary artery development.

    Directory of Open Access Journals (Sweden)

    Lingjuan He

    Full Text Available ATP-dependent SWI/SNF chromatin remodeling complexes utilize ATP hydrolysis to non-covalently change nucleosome-DNA interactions and are essential in stem cell development, organogenesis, and tumorigenesis. Biochemical studies show that SWI/SNF in mammalian cells can be divided into two subcomplexes BAF and PBAF based on the subunit composition. ARID2 or BAF200 has been defined as an intrinsic subunit of PBAF complex. However, the function of BAF200 in vivo is not clear. To dissect the possible role of BAF200 in regulating embryogenesis and organ development, we generated BAF200 mutant mice and found they were embryonic lethal. BAF200 mutant embryos exhibited multiple cardiac defects including thin myocardium, ventricular septum defect, common atrioventricular valve, and double outlet right ventricle around E14.5. Moreover, we also detected reduced intramyocardial coronary arteries in BAF200 mutants, suggesting that BAF200 is required for proper migration and differentiation of subepicardial venous cells into arterial endothelial cells. Our work revealed that PBAF complex plays a critical role in heart morphogenesis and coronary artery angiogenesis.

  14. Mutation of neuron-specific chromatin remodeling subunit BAF53b : rescue of plasticity and memory by manipulating actin remodeling

    NARCIS (Netherlands)

    Vogel Ciernia, Annie; Kramár, Enikö A; Matheos, Dina P; Havekes, Robbert; Hemstedt, Thekla J; Magnan, Christophe N; Sakata, Keith; Tran, Ashley; Azzawi, Soraya; Lopez, Alberto; Dang, Richard; Wang, Weisheng; Trieu, Brian; Tong, Joyce; Barrett, Ruth M; Post, Rebecca J; Baldi, Pierre; Abel, Ted; Lynch, Gary; Wood, Marcelo A

    Recent human exome-sequencing studies have implicated polymorphic Brg1-associated factor (BAF) complexes (mammalian SWI/SNF chromatin remodeling complexes) in several intellectual disabilities and cognitive disorders, including autism. However, it remains unclear how mutations in BAF complexes

  15. Radiation damage in BaF2 crystals

    International Nuclear Information System (INIS)

    Woody, C.L.; Kierstead, J.A.; Levy, P.W.; Stoll, S.

    1991-01-01

    The effects of radiation damage and recovery have been studied in BaF 2 crystals exposed to 60 Co radiation. The change in optical transmission and scintillation light output have been measured as a function of dose up to 4.7 x 10 6 rad. Although some crystals exhibit a small change in transmission, a greater change in scintillation light output is observed. Several 25 cm long crystals whichhave been irradiated show large changes in both transmission and light output. Recovery from radiation damage has been studied as a function of time and exposure to UV light. A long lived radiation induced phosphorescence has been observed in all irradiated samples which is distinct from the standard fast and slow scintillation emissions. The emission spectrum of the phosphorescence has been measured and shown a peakat ∼330 nm, near the region of the slow scintillation component. Results are given on the dependence of the decay time of the phosphorescence with dose

  16. Application of Facility Management in Brownfield Conversion

    Directory of Open Access Journals (Sweden)

    Wernerová Eva

    2016-12-01

    Full Text Available The subject of this paper covers two issues, namely the issue of brownfields and their conversion and the issue of Facility Management, which offers the possibility of applying its principles and tools for extending the benefit of the construction works as a tool for active access to care for the property. This paper aims to link these two topics and to identify the possibility of applying Facility Management in the conversation process of revitalization of brownfields so that subsequent commissioning eliminates the risk of future costly operation and relapse of the revitalized building into the category of brownfields.

  17. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

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

    International Nuclear Information System (INIS)

    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

  19. 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.

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

    African Journals Online (AJOL)

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

  1. The proposed irradiation facility and applications

    International Nuclear Information System (INIS)

    Singson, C.C.; Navarro, Q.O.

    As early as 1972, the Philippine Atomic Energy Commission proposed the setting up of a radiation facility for the sterilization of medical products. A result of a market survey with the assistance of an IAEA expert was conducted to determine the market potential for such venture. With the Food Terminal, Inc. (FTI) a government agro-industrial fair which explored the economic benefits of project, encouraging results have been obtained with finances from FAO and IAEA. The proposed pilot plant will serve as a multi purpose facility for the sterilization of medical and laboratory products, irradiation of food and agricultural produce and manufacture of wood plastic compositions for the textile and furniture industries. With the benefits derived from the said project, it is hoped that its early installation be pushed through. (author)

  2. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Vault design, run-on/run-off control design, and asphalt compatibility with 90-degree celsius double-shell slurry feed

  3. Experimental Study on the Treatment of low C/N ratio disposal of sewage with BAF

    Science.gov (United States)

    Wang, W. J.; Ma, T.; Cheng, W.

    2010-03-01

    The Biological Aerated Filter (BAF) is a simple, high-efficient, low-consumptive for new biological membrane method correspond to the situation of china, will be one of the main technical measures to solve the progressive deterioration of water environment problem faced china especially medium and small towns. This paper focuses on the experimental study and mechanism analysis in which the up flow, cocurrent gas-water, single-stage BAF was adopted on treatment domestic wastewater, the results showed that BAF has good performance in treating domestic sewage, and it had steady treatment effect with different pollution loads.

  4. Booster Applications Facility report, Phase 2

    Energy Technology Data Exchange (ETDEWEB)

    Thieberger, P. (ed.)

    1991-06-01

    This report summarizes studies and planning performed by Brookhaven National Laboratory (BNL) personnel at the request of NASA for the design, construction and operation of experimental areas and facilities for utilization of ion beams from the BNL Booster synchrotron particle accelerator. These facilities would be primarily utilized to simulate space radiation for radiobiological research, shielding studies and detector calibrations. The feasibility of such a project has been established, preliminary designs and cost estimates have been developed and a formal proposal can be submitted pending DOE concurrence. The main body of this report consists of the material presented by BNL during the meeting with a NASA appointed Panel on December 10 and 11, 1990. The individual speakers have provided brief summaries of their talks and explanations of their figures. In addition there are two appendices. One, contains detailed discussion of the shared mode of operation and the corresponding beam compatibility tables. The second appendix contains cost estimate details. An executive summary on budgets and schedules has been added, containing possible phased construction and outfitting scenarios and the corresponding expense and commitment profiles as well as new operational cost estimates. Material contained in the executive summary reflects the correction of some errors and new studies performed in response to the NASA Panel suggestions.

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

    African Journals Online (AJOL)

    Information Impact | Jorunal of Information and Knowledge Management

    Findings also revealed that inadequate training of staff on ICT application to technical services; poor electricity supply and insufficient fund were some of the challenges plaguing the application of ICT facilities to technical unit of the library. The study recommends that there should be adequate straining of staff, provision of ...

  6. Absorption Spectra of BaF2 Sm2O3, Sm, Gd, and Ho Plasmas

    Science.gov (United States)

    Martin, Michael; Bastiani-Ceccotti, Serena

    2009-11-01

    Knowledge of the opacities of high Z element plasmas is important in indirect drive ICF and the study of stellar evolution. There are few experimental measurements of this quantity, and its theoretical determination is difficult due to the number of possible bound electron configurations. This study aims to better the theoretical understanding of this parameter by looking at the 3d-4f transitions of BaF2, Sm2O3, Sm, Gd, and Ho plasmas at the LULI2000 facility. The plasmas are produced by radiative heating and are cold, 15 -- 40 eV, and relatively dense, ˜ .01gm/cm^3 A plasma is produced by a .5 ns laser pulse irradiating a gold hohlraum and then probed by an x-ray source created by a gold foil irradiated by a 10 ps laser pulse. The transmission is found with simultaneous source and absorption measurements by an x-ray spectrometer in the 8 - 20 å range We will compare the results with statistical atomic structure codes. From this experiment we will gain further insight into the spectral broadening of neighboring Z elements due to changing plasma temperature and into mixture thermodynamics. This is a first step towards an experimental study of astrophysical domains.

  7. The BAH domain of BAF180 is required for PCNA ubiquitination

    Energy Technology Data Exchange (ETDEWEB)

    Niimi, Atsuko [Department of Genome Dynamics, Research Institute of Environmental Medicine, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8601 (Japan); Hopkins, Suzanna R; Downs, Jessica A [Genome Damage and Stability Centre, University of Sussex, Falmer, Brighton BN1 9RQ (United Kingdom); Masutani, Chikahide, E-mail: masutani@riem.nagoya-u.ac.jp [Department of Genome Dynamics, Research Institute of Environmental Medicine, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8601 (Japan)

    2015-09-15

    Highlights: • The expression of BAF180 promotes UV-induced PCNA ubiquitination during S phase. • The BAH domains of BAF180 alone are sufficient to promote PCNA ubiquitination. • The BAH domains are not assembled into the PBAF in the absence of the C-terminus. - Abstract: Monoubiquitination of proliferating cell nuclear antigen (PCNA) is a critical regulator of post replication repair (PRR). The depletion of BAF180, a unique subunit of the PBAF chromatin remodeling complex in human cells results in reduced PCNA ubiquitination leading to less efficient fork progression following DNA damage, but little is known about the mechanism. Here, we report that the expression of exogenous BAF180 in cells promotes PCNA ubiquitination during S-phase after UV irradiation and it persists for many hours. No correlation was observed between the protein level of ubiquitin-specific protease 1 (USP1) and ubiquitinated PCNA in BAF180 expressing cells. Analysis of cells expressing BAF180 deletion mutants showed that the bromo-adjacent homology (BAH) domains are responsible for this effect. Surprisingly, a deletion construct encoding only the BAH domain region is able to increase the level of ubiquitinated PCNA, even though it is unable to be assembled into the PBAF complex. These results suggest that the ATPase-dependent chromatin remodeling activity of PBAF is not necessary, but instead the BAH domains are sufficient to promote PCNA ubiquitination.

  8. Chromatin Remodeling BAF (SWI/SNF Complexes in Neural Development and Disorders

    Directory of Open Access Journals (Sweden)

    Godwin Sokpor

    2017-08-01

    Full Text Available The ATP-dependent BRG1/BRM associated factor (BAF chromatin remodeling complexes are crucial in regulating gene expression by controlling chromatin dynamics. Over the last decade, it has become increasingly clear that during neural development in mammals, distinct ontogenetic stage-specific BAF complexes derived from combinatorial assembly of their subunits are formed in neural progenitors and post-mitotic neural cells. Proper functioning of the BAF complexes plays critical roles in neural development, including the establishment and maintenance of neural fates and functionality. Indeed, recent human exome sequencing and genome-wide association studies have revealed that mutations in BAF complex subunits are linked to neurodevelopmental disorders such as Coffin-Siris syndrome, Nicolaides-Baraitser syndrome, Kleefstra's syndrome spectrum, Hirschsprung's disease, autism spectrum disorder, and schizophrenia. In this review, we focus on the latest insights into the functions of BAF complexes during neural development and the plausible mechanistic basis of how mutations in known BAF subunits are associated with certain neurodevelopmental disorders.

  9. Chromatin Remodeling BAF (SWI/SNF) Complexes in Neural Development and Disorders

    Science.gov (United States)

    Sokpor, Godwin; Xie, Yuanbin; Rosenbusch, Joachim; Tuoc, Tran

    2017-01-01

    The ATP-dependent BRG1/BRM associated factor (BAF) chromatin remodeling complexes are crucial in regulating gene expression by controlling chromatin dynamics. Over the last decade, it has become increasingly clear that during neural development in mammals, distinct ontogenetic stage-specific BAF complexes derived from combinatorial assembly of their subunits are formed in neural progenitors and post-mitotic neural cells. Proper functioning of the BAF complexes plays critical roles in neural development, including the establishment and maintenance of neural fates and functionality. Indeed, recent human exome sequencing and genome-wide association studies have revealed that mutations in BAF complex subunits are linked to neurodevelopmental disorders such as Coffin-Siris syndrome, Nicolaides-Baraitser syndrome, Kleefstra's syndrome spectrum, Hirschsprung's disease, autism spectrum disorder, and schizophrenia. In this review, we focus on the latest insights into the functions of BAF complexes during neural development and the plausible mechanistic basis of how mutations in known BAF subunits are associated with certain neurodevelopmental disorders. PMID:28824374

  10. Chromatin Remodeling BAF (SWI/SNF) Complexes in Neural Development and Disorders.

    Science.gov (United States)

    Sokpor, Godwin; Xie, Yuanbin; Rosenbusch, Joachim; Tuoc, Tran

    2017-01-01

    The ATP-dependent BRG1/BRM associated factor (BAF) chromatin remodeling complexes are crucial in regulating gene expression by controlling chromatin dynamics. Over the last decade, it has become increasingly clear that during neural development in mammals, distinct ontogenetic stage-specific BAF complexes derived from combinatorial assembly of their subunits are formed in neural progenitors and post-mitotic neural cells. Proper functioning of the BAF complexes plays critical roles in neural development, including the establishment and maintenance of neural fates and functionality. Indeed, recent human exome sequencing and genome-wide association studies have revealed that mutations in BAF complex subunits are linked to neurodevelopmental disorders such as Coffin-Siris syndrome, Nicolaides-Baraitser syndrome, Kleefstra's syndrome spectrum, Hirschsprung's disease, autism spectrum disorder, and schizophrenia. In this review, we focus on the latest insights into the functions of BAF complexes during neural development and the plausible mechanistic basis of how mutations in known BAF subunits are associated with certain neurodevelopmental disorders.

  11. New nuclear facilities and their analytical applications in China

    International Nuclear Information System (INIS)

    Zhang, Z.Y.; He, X.; Ma, Y.H.; Ding, Y.Y.; Chai, Z.F.

    2014-01-01

    Nuclear analytical techniques are a family of modern analytical methods that are based on nuclear reactions, nuclear effects, nuclear radiations, nuclear spectroscopy, nuclear parameters, and nuclear facilities. Because of their combined characteristics of sensitivity and selectivity, they are widely used in projects ranging from life sciences to deep-space exploration. In this review article, new nuclear facilities and their analytical applications in China are selectively reviewed, covering the following aspects: large scientific facilities, national demands, and key scientific issues with the emphasis on the new achievements. (orig.)

  12. Hanford facility dangerous waste permit application, 242-A evaporator

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, 'operating' treatment, storage, and/or disposal units, such as the 242-A Evaporator (this document, DOE/RL-90-42)

  13. Accelerator-TEM interface facility and application

    International Nuclear Information System (INIS)

    Liu Chuansheng; Li Ming; He Jun; Yang Zheng; Zhou Lin; Wang Zesong; Guo Liping; Jiang Changzhong; Yang Shibo; Fu Dejun; Fan Xiangjun; Liu Jiarui; Lee J C

    2010-01-01

    An accelerator-TEM interface facility has been established at Wuhan University in 2008. The system consists of an H800 TEM linked to a 200 kV ion implanter and a 2 x 1.7 MV tandem accelerator. Nitrogen ions at 115 keV were successfully transported from the implanter into the TEM chamber through the interface system, and the ion currents measured at the entrance of the TEM column were between 20 and 180 nA. Structural evolution caused by ion irradiation in Si, GaAs, nanocrystal Ag was observed in situ. The in situ observation showed that the critical implantation dose for amorphization of Si is 10 14 cm -2 . The nuclear material C276 samples implanted with 115 keV Ar + was also studied, and dislocation loops sized at 3-12 nm were clearly observed after implantation to doses of over 1 x 10 15 cm -2 . The density of the loops increased with the dose. Evolution to polycrystalline and amorphous structures were observed at 5 x l0 15 cm -2 and 3 x 10 16 cm -2 , respectively. An in situ RBS/C chamber was installed on the transport line of the accelerator-TEM interface system. This enables in situ measurement of composition and location of the implanted species in lattice of the samples. In addition, a 50 kV low-energy gaseous ion generator was installed close to the TEM chamber, which facilitates in situ TEM observation of helium bubbles formed in helium-implanted materials. (authors)

  14. Accelerator-tem interface facility and application

    International Nuclear Information System (INIS)

    Li Ming; He Jun; Yang Zheng; Zhou Lin; Liu Chuansheng; Guo Liping; Jiang Changzhong; Yang Shibo; Fu Dejun; Fan Xiangjun; Liu Jiarui; Lee, J.C.

    2010-01-01

    An accelerator-TEM interface facility has been established at Wuhan University. The system consists of an H800 TEM linked to a 200 kV ion implanter and a 2 x 1.7 MV tandetron accelerator. Measures were taken to isolate the TEM from mechanical vibration transmitted from the ion beam lines and good resolution was maintained with the TEM machine when operated under high zoom modes during the ion implantation. Nitrogen ions at 115 keV were successfully transported from the implanter into the TEM chamber through the interface system, and the ion currents measured at the entrance of the TEM column were between 20 and 180 nA. Structural evolution caused by ion irradiation in Si, GaAs, nanocrystal Ag were observed in situ. The TEM sample could be tilted by 52 degree and for low energy ion irradiation, real time observation was realized. The in situ observation showed that the critical implant dose for amorphization of Si is 2 x 10 14 cm -2 and it became fully amorphized at 3 x 10 15 cm -2 . Amorphization of GaAs started at 1 x 10 14 cm -2 , whereas for nanocrystal Ag, the starting dose was 6 x 10 14 cm -2 . The nuclear material C276 samples implanted with 115 keV Ar+ was also studied and dislocation loops with sizes of 3-12 nm were clearly observed after implantation to doses higher than 1 x 10 15 cm -2 . The density of the loops increased with the increase in the implant dose and evolution to polycrystalline and amorphous structures were observed at 5 x 10 15 cm -2 and 3 x 10 16 cm -2 , respectively. An in situ RBS/C chamber has been installed on the transport line of the accelerator-TEM interface system. This makes it possible to in situ measure composition and location of impurities in the lattice of the implanted samples. In addition, a 50 kV low-energy gaseous ion generator was installed close to the TEM chamber, which facilitates in situ TEM observation of helium bubbles formed in materials by helium implantation. (authors)

  15. Idaho National Engineering Laboratory irradiation facilities and their applications

    International Nuclear Information System (INIS)

    Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

    1986-05-01

    Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

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

    International Nuclear Information System (INIS)

    Hays, C.B.

    1998-01-01

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

  17. Optical characterization of Tm3+ doped Bi2O3-GeO2-Ga2O3 glasses in absence and presence of BaF2

    Science.gov (United States)

    Han, Kexuan; Zhang, Peng; Wang, Shunbin; Guo, Yanyan; Zhou, Dechun; Yu, Fengxia

    2016-01-01

    In this paper, Two new Bi2O3-GeO2-Ga2O3 glasses (one presence of BaF2) doped with 1mol% Tm2O3 were prepared by melt-quenching technique. Differential thermal analysis (DTA), the absorption, Raman, IR spectra and fluorescence spectra were measured. The Judd–Ofelt intensity parameters, emission cross section, absorption cross section, and gain coefficient of Tm3+ ions were comparatively investigated. After the BaF2 introduced, the glass showed a better thermal stability, lower phonon energy and weaker OH− absorption coefficient, meanwhile, a larger ~1.8 μm emission cross section σem (7.56 × 10−21 cm2) and a longer fluorescence lifetime τmea (2.25 ms) corresponding to the Tm3+: 4F3 → 3H6 transition were obtained, which is due to the addition of fluoride in glass could reduce the quenching rate of hydroxyls and raise the cross-relaxation (3H6 + 3H4 → 3F4 + 3F4) rate. Our results suggest that the Tm3+ doped Bi2O3-GeO2-Ga2O3 glass with BaF2 might be potential to the application in efficient ~1.8 μm lasers system. PMID:27506152

  18. Optical characterization of Tm(3+) doped Bi2O3-GeO2-Ga2O3 glasses in absence and presence of BaF2.

    Science.gov (United States)

    Han, Kexuan; Zhang, Peng; Wang, Shunbin; Guo, Yanyan; Zhou, Dechun; Yu, Fengxia

    2016-08-10

    In this paper, Two new Bi2O3-GeO2-Ga2O3 glasses (one presence of BaF2) doped with 1mol% Tm2O3 were prepared by melt-quenching technique. Differential thermal analysis (DTA), the absorption, Raman, IR spectra and fluorescence spectra were measured. The Judd-Ofelt intensity parameters, emission cross section, absorption cross section, and gain coefficient of Tm(3+) ions were comparatively investigated. After the BaF2 introduced, the glass showed a better thermal stability, lower phonon energy and weaker OH(-) absorption coefficient, meanwhile, a larger ~1.8 μm emission cross section σem (7.56 × 10(-21) cm(2)) and a longer fluorescence lifetime τmea (2.25 ms) corresponding to the Tm(3+): (4)F3 → (3)H6 transition were obtained, which is due to the addition of fluoride in glass could reduce the quenching rate of hydroxyls and raise the cross-relaxation ((3)H6 + (3)H4 → (3)F4 + (3)F4) rate. Our results suggest that the Tm(3+) doped Bi2O3-GeO2-Ga2O3 glass with BaF2 might be potential to the application in efficient ~1.8 μm lasers system.

  19. An Application of Business Process Management to Health Care Facilities.

    Science.gov (United States)

    Hassan, Mohsen M D

    The purpose of this article is to help health care facility managers and personnel identify significant elements of their facilities to address, and steps and actions to follow, when applying business process management to them. The ABPMP (Association of Business Process Management Professionals) life-cycle model of business process management is adopted, and steps from Lean, business process reengineering, and Six Sigma, and actions from operations management are presented to implement it. Managers of health care facilities can find in business process management a more comprehensive approach to improving their facilities than Lean, Six Sigma, business process reengineering, and ad hoc approaches that does not conflict with them because many of their elements can be included under its umbrella. Furthermore, the suggested application of business process management can guide and relieve them from selecting among these approaches, as well as provide them with specific steps and actions that they can follow. This article fills a gap in the literature by presenting a much needed comprehensive application of business process management to health care facilities that has specific steps and actions for implementation.

  20. PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

    Directory of Open Access Journals (Sweden)

    Virpi Kouhia

    2012-01-01

    Full Text Available This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.

  1. PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

    International Nuclear Information System (INIS)

    Virpi Kouhia, V.; Purhonen, H.; Riikonen, V.; Puustinen, M.; Kyrki-Rajamaki, R.; Vihavainen, J.

    2012-01-01

    This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.

  2. Treatment of heavy oil wastewater by UASB-BAFs using the combination of yeast and bacteria.

    Science.gov (United States)

    Zou, Xiao-Ling

    2015-01-01

    A novel system integrating an upflow anaerobic sludge blanket (UASB) reactor and a two-stage biological aerated filter (BAF) system was investigated as advanced treatment of heavy oil wastewater with large amounts of dissolved recalcitrant organic substances and low levels of nitrogen and phosphorus nutrients. #1 BAF, inoculated with two yeast strains (Candida tropicalis and Rhodotorula dairenensis), was installed in the upper reaches of #2 BAF inoculated with activated sludge. During the 180-day study period, the chemical oxygen demand (COD), ammonia nitrogen (NH3-N), oil and polyaromatic hydrocarbons (PAHs) in the wastewater were removed by 90.2%, 90.8%, 86.5% and 89.4%, respectively. Although the wastewater qualities fluctuated and the hydraulic retention time continuously decreased, the effluent quality index met the national discharge standard steadily. The UASB process greatly improved the biodegradability of the wastewater, while #1 BAF played an important role not only in degrading COD but also in removing oil and high molecular weight PAHs. This work demonstrates that the hybrid UASB-BAFs system containing yeast-bacteria consortium has the potential to be used in bioremediation of high-strength oily wastewater.

  3. Hanford Facility Dangerous Waste Permit Application, 222-S Laboratory Complex

    International Nuclear Information System (INIS)

    WILLIAMS, J.F.

    2000-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the 222-S Laboratory Complex (this document, DOE/RL-91-27). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the 222-S Laboratory Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this 222-S Laboratory Complex permit application documentation is current as of August 2000

  4. Application of essential facility doctrine to transmission grid; Sodenmo eno essential facility no hori no tekiyo

    Energy Technology Data Exchange (ETDEWEB)

    Maruyama, M. [Central Research Institute of Electric Power Industry, Tokyo (Japan)

    1997-06-01

    This paper arranges the essential facility doctrine in America and describes it according to each judgment example how the doctrine is applied on the access of electricity supply companies to transmission grids. By applying the result to the situation of Japan, the point at issue occurring in the range of the Anti-Monopoly Law was arranged and investigated when third parties (power generating manufacturers) access the transmission grids of electricity supply companies in the form of wholesale or self transmission in the electricity supply industry of Japan. In the judgment example of America, a transmission grid can be considered as essential facility. The refusal of essential facility application is judged to be illegal only when it aims at keeping and expanding the leading market share without a fair reason. The application of essential facility can be refused when the transmission line is insufficient in capacity, when no necessary technical conditions are satisfied during use, or when the cost generated during use cannot be collected. 18 refs., 7 figs., 2 tabs.

  5. The performance of BAF using natural zeolite as filter media under conditions of low temperature and ammonium shock load

    International Nuclear Information System (INIS)

    He Shengbing; Xue Gang; Kong Hainan

    2007-01-01

    Natural zeolite and expanded clay were used as filter media for biological aerated filter (BAF) to treat municipal wastewater in parallel in whole three test stages. The stage one test results revealed that zeolite BAF and expanded clay BAF have COD and NH 3 -N removals in the range of 84.63-93.11%, 85.74-96.26%, 82.34-93.71%, and 85.06-93.2%, respectively, under the conditions of water temperature of 20-25 deg. C and hydraulic load of 2-3 m 3 /(m 2 h). At the following stage two, the influent NH 3 -N concentration was increased to about double value of the stage one, and it was investigated that the effluent NH 3 -N of expanded clay BAF increased significantly and then gradually restored to normal condition in 2 weeks, while the effluent NH 3 -N of zeolite BAF kept stable. At stage three, the low reactor temperature has also different effects on these two BAFs, under conditions of water temperature of 7-10 deg. C, hydraulic load of 2-3 m 3 /(m 2 h), zeolite BAF and expanded clay BAF have COD and NH 3 -N removals in the range of 74.5-88.47% (average of 81.57%), 71.73-88.49% (average of 81.06%), 71.91-87.76% (average of 80.49%), and 38.41-77.17% (average of 65.42%), respectively. Three stages test results indicated that the zeolite BAF has a stronger adaptability to NH 3 -N shock load and low temperature compared to expanded clay BAF. In addition, the detection of the amounts of heterobacteria and nitrobacteria of two biological aerated filters in three stages also showed the zeolite filter media was more suitable to the attached growth of nitrobacteria, which is helpful to the improvement of nitrification performance in zeolite BAF

  6. The Arabidopsis SWI/SNF protein BAF60 mediates seedling growth control by modulating DNA accessibility

    KAUST Repository

    Jégu, Teddy

    2017-06-15

    Plant adaptive responses to changing environments involve complex molecular interplays between intrinsic and external signals. Whilst much is known on the signaling components mediating diurnal, light, and temperature controls on plant development, their influence on chromatin-based transcriptional controls remains poorly explored.In this study we show that a SWI/SNF chromatin remodeler subunit, BAF60, represses seedling growth by modulating DNA accessibility of hypocotyl cell size regulatory genes. BAF60 binds nucleosome-free regions of multiple G box-containing genes, opposing in cis the promoting effect of the photomorphogenic and thermomorphogenic regulator Phytochrome Interacting Factor 4 (PIF4) on hypocotyl elongation. Furthermore, BAF60 expression level is regulated in response to light and daily rhythms.These results unveil a short path between a chromatin remodeler and a signaling component to fine-tune plant morphogenesis in response to environmental conditions.

  7. The Arabidopsis SWI/SNF protein BAF60 mediates seedling growth control by modulating DNA accessibility

    KAUST Repository

    Jé gu, Teddy; Veluchamy, Alaguraj; Ramirez Prado, Juan Sebastian; Rizzi-Paillet, Charley; Perez, Magalie; Lhomme, Anaï s; Latrasse, David; Coleno, Emeline; Vicaire, Serge; Legras, Sté phanie; Jost, Bernard; Rougé e, Martin; Barneche, Fredy; Bergounioux, Catherine; Crespi, Martin; Mahfouz, Magdy M.; Hirt, Heribert; Raynaud, Cé cile; Benhamed, Moussa

    2017-01-01

    Plant adaptive responses to changing environments involve complex molecular interplays between intrinsic and external signals. Whilst much is known on the signaling components mediating diurnal, light, and temperature controls on plant development, their influence on chromatin-based transcriptional controls remains poorly explored.In this study we show that a SWI/SNF chromatin remodeler subunit, BAF60, represses seedling growth by modulating DNA accessibility of hypocotyl cell size regulatory genes. BAF60 binds nucleosome-free regions of multiple G box-containing genes, opposing in cis the promoting effect of the photomorphogenic and thermomorphogenic regulator Phytochrome Interacting Factor 4 (PIF4) on hypocotyl elongation. Furthermore, BAF60 expression level is regulated in response to light and daily rhythms.These results unveil a short path between a chromatin remodeler and a signaling component to fine-tune plant morphogenesis in response to environmental conditions.

  8. Software data acquisition system for the ''Chateau de Cristal'' multicounter 74 BaF2

    International Nuclear Information System (INIS)

    Adzama, G.

    1985-01-01

    The ''Chateau de Cristal'' is a 74 BaF2 detector assembly. Other detectors such as Ge (up to 12) and particle detectors can be added to this multidetector. The data acquisition system hardware and software are implemented in 3 VME crates. The operating system is handled by 68000 Motorola microprocessors. This work is dedicated to the initialization and control tasks of the multidetector. Handling of high voltage power supply for the 74 BaF2 detectors via a RS 232 C serial port, CAMAC initialization for the ADC 4300 Lecroy and DFC modules, data exchange between the 3 VME crates and automatic energy calibration for the BaF2 detectors. All the software is written in 68000 Motorola assembly language [fr

  9. The Transrapid test facility between system development and system application

    Energy Technology Data Exchange (ETDEWEB)

    Baur, L [MVP GmbH, Muenchen (Germany)

    1996-12-31

    In the development of a new rail technology, such as the magnetic levitation, there is - in contrast to the further development of the railway technology - not the possibility to use existing routes for the technical verification of the system technology until the application. Instead of this there are two possibilities: Cost-effective preliminary development on test beds and small test facilities up to a development stage which justifies the (relatively serious) risk of realising a service route early and to conclude the system trials and verification there; cost-intensive construction of a large-scale test facility which permits an application-related verification of all important system functions and thus creates the technical pre-requisites for a low-risk system application; The presentation deals with the technical requirements of the system at the test facility the challenges and chances linked to its realisation and adjustment to the rapidly progressing state-of-the-art and which this way opens up for a minimisation of the technical application risk. (orig./HW)

  10. The application of SQUG to non-reactor facilities

    International Nuclear Information System (INIS)

    Hoskins, R.S.

    1993-01-01

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

  11. BAF is a cytosolic DNA sensor that leads to exogenous DNA avoiding autophagy.

    Science.gov (United States)

    Kobayashi, Shouhei; Koujin, Takako; Kojidani, Tomoko; Osakada, Hiroko; Mori, Chie; Hiraoka, Yasushi; Haraguchi, Tokuko

    2015-06-02

    Knowledge of the mechanisms by which a cell detects exogenous DNA is important for controlling pathogen infection, because most pathogens entail the presence of exogenous DNA in the cytosol, as well as for understanding the cell's response to artificially transfected DNA. The cellular response to pathogen invasion has been well studied. However, spatiotemporal information of the cellular response immediately after exogenous double-stranded DNA (dsDNA) appears in the cytosol is lacking, in part because of difficulties in monitoring when exogenous dsDNA enters the cytosol of the cell. We have recently developed a method to monitor endosome breakdown around exogenous materials using transfection reagent-coated polystyrene beads incorporated into living human cells as the objective for microscopic observations. In the present study, using dsDNA-coated polystyrene beads (DNA-beads) incorporated into living cells, we show that barrier-to-autointegration factor (BAF) bound to exogenous dsDNA immediately after its appearance in the cytosol at endosome breakdown. The BAF(+) DNA-beads then assembled a nuclear envelope (NE)-like membrane and avoided autophagy that targeted the remnants of the endosome membranes. Knockdown of BAF caused a significant decrease in the assembly of NE-like membranes and increased the formation of autophagic membranes around the DNA-beads, suggesting that BAF-mediated assembly of NE-like membranes was required for the DNA-beads to evade autophagy. Importantly, BAF-bound beads without dsDNA also assembled NE-like membranes and avoided autophagy. We propose a new role for BAF: remodeling intracellular membranes upon detection of dsDNA in mammalian cells.

  12. Fluorine dynamics in BaF2 superionic conductors investigated by NMR

    OpenAIRE

    Gumann, Patryk

    2008-01-01

    In this work the dynamics of fluorine in solid-state electrolytes having BaF2-structure was investigated using three different NMR-methods: field cycling relaxometry, lineshape analysis, and static field gradient NMR. For this purpose a pure BaF2 crystal, as well as crystals doped with trivalent impurities (LaF3), were studied as a function of temperature. The main goal of this investigation was to utilize the structure information provided by neutron scattering and MAS NMR data in order to s...

  13. Applications of inventory difference tool at Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    Hench, K.W.; Longmire, V.; Yarbro, T.F.; Zardecki, A.

    1998-01-01

    A prototype computer program reads the inventory entries directly from the Microsoft Access database. Based on historical data, the program then displays temporal trends and constructs a library of rules that encapsulate the system behavior. The analysis of inventory data is illustrated using a combination of realistic and simulated facility examples. Potential payoffs of this methodology include a reduction in time and resources needed to perform statistical tests and a broad applicability to DOE needs such as treaty verification

  14. Seismic Isolation Studies and Applications for Nuclear Facilities

    International Nuclear Information System (INIS)

    Choun, Young Sun

    2005-01-01

    Seismic isolation, which is being used worldwide for buildings, is a well-known technology to protect structures from destructive earthquakes. In spite of the many potential advantages of a seismic isolation, however, the applications of a seismic isolation to nuclear facilities have been very limited because of a lack of sufficient knowledge about the isolation practices. The most important advantage of seismic isolation applications in nuclear power plants is that the safety and reliability of the plants can be remarkably improved through the standardization of the structures and equipment regardless of the seismic conditions of the sites. The standardization of structures and equipment will reduce the capital cost and design/construction schedule for future plants. Also, a seismic isolation can facilitate decoupling of the design and development for equipment, piping, and components due to the use of the generic in-structure response spectra associated with the standardized plant. Moreover, a seismic isolation will improve the plant safety margin against the design basis earthquake (DBE) as well as a beyond design basis seismic event due to its superior seismic performance. A number of seismic isolation systems have been developed and tested since 1970s, and some of them have been applied to conventional structures in several countries of high seismicity. In the nuclear field, there have been many studies on the applicability of such seismic isolation systems, but the application of a seismic isolation is very limited. Currently, there are some discussions on the application of seismic isolation systems to nuclear facilities between the nuclear industries and the regulatory agencies in the U.S.. In the future, a seismic isolation for nuclear facilities will be one of the important issues in the nuclear industry. This paper summarizes the past studies and applications of a seismic isolation in the nuclear industry

  15. Mutation of Neuron-Specific Chromatin Remodeling Subunit BAF53b: Rescue of Plasticity and Memory by Manipulating Actin Remodeling

    Science.gov (United States)

    Ciernia, Annie Vogel; Kramár, Enikö A.; Matheos, Dina P.; Havekes, Robbert; Hemstedt, Thekla J.; Magnan, Christophe N.; Sakata, Keith; Tran, Ashley; Azzawi, Soraya; Lopez, Alberto; Dang, Richard; Wang, Weisheng; Trieu, Brian; Tong, Joyce; Barrett, Ruth M.; Post, Rebecca J.; Baldi, Pierre; Abel, Ted; Lynch, Gary; Wood, Marcelo A.

    2017-01-01

    Recent human exome-sequencing studies have implicated polymorphic Brg1-associated factor (BAF) complexes (mammalian SWI/SNF chromatin remodeling complexes) in several intellectual disabilities and cognitive disorders, including autism. However, it remains unclear how mutations in BAF complexes result in impaired cognitive function. Post-mitotic…

  16. Hanford Facility dangerous waste permit application, general information

    International Nuclear Information System (INIS)

    1993-05-01

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

  17. Hanford facility dangerous waste permit application, PUREX storage tunnels

    International Nuclear Information System (INIS)

    Price, S.M.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997

  18. Remote machine engineering applications for nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Toto, G.; Wyle, H.R.

    1983-01-01

    Decontamination and decommissioning of a nuclear facility require the application of techniques that protect the worker and the enviroment from radiological contamination and radiation. Remotely operated portable robotic arms, machines, and devices can be applied. The use of advanced systems should enhance the productivity, safety, and cost facets of the efforts; remote automatic tooling and systems may be used on any job where job hazard and other factors justify application. Many problems based on costs, enviromental impact, health, waste generation, and political issues may be mitigated by use of remotely operated machines. The work that man can not do or should not do will have to be done by machines

  19. License application approach for the California LLRW disposal facility

    International Nuclear Information System (INIS)

    Gaynor, R.K.; Romano, S.A.; Hanrahan, T.P.

    1990-01-01

    US Ecology, Inc. is the State of California's license designee to site, develop and operate a low-level radioactive waste (LLRW) disposal facility to serve member states of the Southwestern Compact. US Ecology identified a proposed site in the Ward Valley of southeastern California in March 1988. Following proposed site selection, US Ecology undertook studies required to prepare a license application. US Ecology's license application for this desert site was deemed complete for detailed regulatory review by the California Department of Health Services (DHS) in December 1989. By mutual agreement, disposal of mixed waste is not proposed pending the State of California's decision on appropriate management of this small LLRW subset

  20. Software application for a total management of a radioactive facility

    International Nuclear Information System (INIS)

    Mirpuri, E.; Escudero, R.; Macias, M.T.; Perez, J.; Sanchez, A.; Usera, F.

    2008-01-01

    The use of radiological material and/or equipment that generate ionizing radiation is widely extended in biological research. In every laboratory there are a large variety of methods, operations, techniques, equipment, radioisotopes and users related to the work with ionizing radiation. In order to control the radioactive material, users and the whole facility a large number of documents, databases and information is necessary to be created by the manager of the Radioactivity Facility. This kind of information is characterized by a constant and persistent manipulation and includes information of great importance such as the general management of the radioactive material and waste management, exposed workers vigilance, controlled areas access, laboratory and equipment reservations, radiological inspections, etc. These activities are often complicated by the fact that the main manager of the radioactive facility is also in charge of bio-safety and working prevention issues so the documents to generate and manipulate and the procedures to develop are multiplied. A procedure to access and manage all these files is highly recommended in order to optimize the general management of the facility, avoiding loss of information, automating all the activities and allowing data necessary for control easily accessible. In this work we present a software application for a total management of the facility. This software has been developed by the collaboration of six of the most important research centers from Spain in coordination with the company 'Appize soluciones'. This is a flexible and versatile application that adapts to any specific need of every research center, providing the appropriate reports and checklist that speed up to general management and increase the ease of writing the official documents, including the Operations Book. (author)

  1. Applicability study of optical fiber distribution sensing to nuclear facilities

    International Nuclear Information System (INIS)

    Takada, Eiji; Kimura, Atsushi; Nakazawa, Masaharu; Kakuta, Tsunemi

    1999-01-01

    Optical fibers have advantages like flexible configuration, intrinsic immunity for electromagnetic fields etc., and they have been used for signal transmission and as optical fiber sensors (OFSs). By some of these sensor techniques, continuous or discrete distribution of physical parameters can be measured. Here, in order to discuss the applicability of these OFSs to nuclear facilities, irradiation experiments to optical fibers were carried out using the fast neutron source reactor 'YAYOI' and a 60 Co γ source. It has been shown that, under irradiation with fast neutrons, the radiation induced loss increase almost linearly with the neutron fluence. On the other hand, when irradiated with 60 Co γ rays, the loss shows a saturation tendency. As an example of the OFSs, applicability of the Raman distributed temperature sensor (RDTS) to the monitoring of nuclear facilities has been examined. Two correction techniques for radiation induced errors have been developed and for the demonstration of their feasibility, measurements were carried out along the primary piping system of the experimental fast reactor: JOYO. During the continuous measurements with the total dose of more than 10 7 [R], the radiation induced errors showed a saturating tendency and the feasibility of the loss correction technique was demonstrated. Although the time response of the system should be improved, the RDTS can be expected as a noble temperature monitor in nuclear facilities. (author)

  2. Coffin-Siris syndrome and the BAF complex: genotype-phenotype study in 63 patients

    NARCIS (Netherlands)

    Santen, Gijs W. E.; Aten, Emmelien; Vulto-van Silfhout, Anneke T.; Pottinger, Caroline; van Bon, Bregje W. M.; van Minderhout, Ivonne J. H. M.; Snowdowne, Ronelle; van der Lans, Christian A. C.; Boogaard, Merel; Linssen, Margot M. L.; Vijfhuizen, Linda; van der Wielen, Michiel J. R.; Vollebregt, M. J. Ellen; Breuning, Martijn H.; Kriek, Marjolein; van Haeringen, Arie; den Dunnen, Johan T.; Hoischen, Alexander; Clayton-Smith, Jill; de Vries, Bert B. A.; Hennekam, Raoul C. M.; van Belzen, Martine J.; Almureikhi, Mariam; Baban, Anwar; Barbosa, Mafalda; Ben-Omran, Tawfeg; Berry, Katherine; Bigoni, Stefania; Boute, Odile; Brueton, Louise; van der Burgt, Ineke; Canham, Natalie; Chandler, Kate E.; Chrzanowska, Krystyna; Collins, Amanda L.; de Toni, Teresa; Dean, John; den Hollander, Nicolette S.; Flore, Leigh Anne; Fryer, Alan; Gardham, Alice; Graham, John M.; Harrison, Victoria; Horn, Denise; Jongmans, Marjolijn C.; Josifova, Dragana; Kant, Sarina G.; Kapoor, Seema; Kingston, Helen; Maas, Saskia M.

    2013-01-01

    De novo germline variants in several components of the SWI/SNF-like BAF complex can cause Coffin-Siris syndrome (CSS), Nicolaides-Baraitser syndrome (NCBRS), and nonsyndromic intellectual disability. We screened 63 patients with a clinical diagnosis of CSS for these genes (ARID1A, ARID1B, SMARCA2,

  3. A BaF2-BGO detector for high-energy gamma rays

    International Nuclear Information System (INIS)

    Bargholtz, C.; Ritzen, B.; Tegner, P.E.

    1989-01-01

    A scintillation detector has been developed for gamma rays with energy between a few hundred keV and approximately 100 MeV. The detector comprises a BaF 2 and a BGO crystal giving it good timing properties and a reasonably good energy resolution in combination with compact size. (orig.)

  4. A BaF2 crystal array for high energy-ray measurements

    Indian Academy of Sciences (India)

    Abstract. We shall discuss about the scientific motivation and construction of a 7 × 7 BaF2 crystal array at Variable Energy Cyclotron Centre, Calcutta. This detector would be used to measure high energy -ray photons from GDR decay and proton–neutron bremsstrahlung reactions at the present 88'' cyclotron and upcoming ...

  5. 616 Nonradioactive Dangerous Waste Storage Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-10-01

    The 616 Nonradioactive Dangerous Waste Storage Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this storage unit, including the Part A included with this document, is provided at the beginning of the Part A Section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings. The 616 Nonradioactive Dangerous Waste Storage Facility Dangerous Waste Permit Application (Revision 0) was submitted to the Washington State Department of Ecology and the US Environmental Protection Agency on July 31, 1989. Revision 1, addressing Washington State Department of Ecology review comments made on Revision 0 dated November 21, 1989, and March 23, 1990, was submitted on June 22, 1990. This submittal, Revision 2, addresses Washington State Department of Ecology review comments made on Revision 1, dated June 22, 1990, August 30, 1990, December 18, 1990, and July 8, 1991

  6. Application of PSA techniques to synchrotron radiation source facilities

    International Nuclear Information System (INIS)

    Sanyasi Rao, V.V.S.; Vinod, G.; Vaze, K.K.; Sarkar, P.K.

    2011-01-01

    Synchrotron radiation sources are increasingly being used in research and medical applications. Various instances of overexposure in these facilities have been reported in literature. These instances have lead to the investigation of the risks associated with them with a view to minimise the risks and thereby increasing the level of safety. In nuclear industry, Probabilistic Safety Assessment (PSA) methods are widely used to assess the risk from nuclear power plants. PSA presents a systematic methodology to evaluate the likelihood of various accident scenarios and their possible consequences using fault/event tree techniques. It is proposed to extend similar approach to analyse the risk associated with synchrotron radiation sources. First step for such an analysis is establishing the failure criteria, considering the regulatory stipulations on acceptable limits of dose due to ionization radiation from normal as well as beam loss scenarios. Some possible scenarios considered in this study are (1) excessive Bremsstrahlung in the ring due to loss of vacuum, (2) Target failure due to excessively focused beam (3) mis-directed/mis-steered beam (4) beam loss and sky shine. Hazard analysis needs to cover the beam transfer line, storage ring and experimental beam line areas. Various safety provisions are in place to minimize the hazards from these facilities such as access control interlock systems, radiation shielding for storage ring and beam lines and safety shutters (for beam lines). Experimental beam line area is the most vulnerable locations that need to be critically analysed. There are multiple beam lines, that have different safety provisions and consequences from postulated beam strikes will also be different and this increases the complexity of analysis. Similar studies conducted for such experimental facilities have identified that the radiation safety interlock system, used to control access to areas inside ring and the hutches of beamline facilities has an

  7. Various applications using the SLOWPOKE-2 facility at RMC

    International Nuclear Information System (INIS)

    Bennett, L.G.I.; Nielsen, K.S.

    2011-01-01

    History will record that the reactor pool at the SLOWPOKE-2 Facility at RMC was one of the first SLOWPOKE pools to be constructed (mid 1970s), even though the reactor itself was the last SLOWPOKE reactor to be installed and commissioned (1985). The unique and very useful feature of the reactor pool is that it is uncovered, allowing for applications in addition to the NAA and radioisotope production applications initially advertised. Because the installation of a tangential neutron beam tube (NBT) had been planned from the beginning, an outer irradiation site inside the reactor container was replaced by a thermal column. Next, a positioning system was added to accept large objects such as flight control surfaces from DND's CF-18 fighter aircraft. Imaging of these surfaces using film is being phased out with the introduction of digital imaging. Very recently a tomography stage was designed and built and is now integrated into the neutron imaging system. Also in the open pool are three pulley and rope 'elevators', two of which allow for large samples to be exposed to various kinds of radiation directly outside of the reactor container. The third elevator is located against the west pool wall, which allows for sample exposure to radiation without any neutron contribution. At the time of negotiating the purchase of the reactor, a teaching package consisting of an in-pool borated ion chamber and an outlet thermocouple was ordered. Automatic irradiation and counting systems in the form of cyclic, pseudo-cyclic, and long counting options were added to the original manual irradiation option. This past summer (2010), a delayed neutron counting system (DNCS) was built and installed in the SLOWPOKE-2 Facility at RMC. Examples will be given for the above-mentioned applications.

  8. Various applications using the SLOWPOKE-2 facility at RMC

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, L.G.I.; Nielsen, K.S. [Royal Military College of Canada, Kingston, ON (Canada)

    2011-07-01

    History will record that the reactor pool at the SLOWPOKE-2 Facility at RMC was one of the first SLOWPOKE pools to be constructed (mid 1970s), even though the reactor itself was the last SLOWPOKE reactor to be installed and commissioned (1985). The unique and very useful feature of the reactor pool is that it is uncovered, allowing for applications in addition to the NAA and radioisotope production applications initially advertised. Because the installation of a tangential neutron beam tube (NBT) had been planned from the beginning, an outer irradiation site inside the reactor container was replaced by a thermal column. Next, a positioning system was added to accept large objects such as flight control surfaces from DND's CF-18 fighter aircraft. Imaging of these surfaces using film is being phased out with the introduction of digital imaging. Very recently a tomography stage was designed and built and is now integrated into the neutron imaging system. Also in the open pool are three pulley and rope 'elevators', two of which allow for large samples to be exposed to various kinds of radiation directly outside of the reactor container. The third elevator is located against the west pool wall, which allows for sample exposure to radiation without any neutron contribution. At the time of negotiating the purchase of the reactor, a teaching package consisting of an in-pool borated ion chamber and an outlet thermocouple was ordered. Automatic irradiation and counting systems in the form of cyclic, pseudo-cyclic, and long counting options were added to the original manual irradiation option. This past summer (2010), a delayed neutron counting system (DNCS) was built and installed in the SLOWPOKE-2 Facility at RMC. Examples will be given for the above-mentioned applications.

  9. Scintillation response of BaF2 and YAlO3:Ce (YAP:Ce) to energetic ions

    International Nuclear Information System (INIS)

    Slunga, E.; Cederwall, B.; Ideguchi, E.; Kerek, A.; Klamra, W.; Marel, J. van der; Novak, D.; Norlin, L.-O.

    2001-01-01

    The scintillation response of BaF 2 and YAP:Ce to protons, α particles, 16 O and 28 Si ions in the 5-30 MeV range has been investigated. The ratio between the fast and slow parts of the scintillator signal for BaF 2 has been used to separate protons, α particles and heavier ions, and the dependence of this ratio on the particle energy has been studied. The time constants and intensities of the two components of the YAP:Ce signal were measured, as were the time constant and intensity of the weak component of the slow part of the BaF 2 signal. Furthermore, the dependence of the light yield on the particle energy has been investigated for both BaF 2 and YAP:Ce

  10. Scintillation response of BaF sub 2 and YAlO sub 3 Ce) to energetic ions

    CERN Document Server

    Slunga, E; Ideguchi, E; Kérek, A; Klamra, W; Marel, J V D; Novák, D; Norlin, L O

    2001-01-01

    The scintillation response of BaF sub 2 and YAP:Ce to protons, alpha particles, sup 1 sup 6 O and sup 2 sup 8 Si ions in the 5-30 MeV range has been investigated. The ratio between the fast and slow parts of the scintillator signal for BaF sub 2 has been used to separate protons, alpha particles and heavier ions, and the dependence of this ratio on the particle energy has been studied. The time constants and intensities of the two components of the YAP:Ce signal were measured, as were the time constant and intensity of the weak component of the slow part of the BaF sub 2 signal. Furthermore, the dependence of the light yield on the particle energy has been investigated for both BaF sub 2 and YAP:Ce.

  11. Coevaporation of Y, BaF2, and Cu utilizing a quadrupole mass spectrometer as a rate measuring probe

    International Nuclear Information System (INIS)

    Hudner, J.; Oestling, M.; Ohlsen, H.; Stolt, L.

    1991-01-01

    An ultrahigh vacuum coevaporator equipped with three sources for preparation of Y--BaF 2 --Cu--O thin films is described. Evaporation rates of Y, BaF 2 , and Cu were controlled using a quadrupole mass spectrometer operating in a multiplexed mode. To evaluate the method depositions have been performed using different source configurations and evaporation rates. Utilizing Rutherford backscattering spectrometry absolute values of the actual evaporation rates were determined. It was observed that the mass-spectrometer sensitivity is highest for Y, followed by BaF 2 (BaF + is the measured ion) and Cu. A partial pressure of oxygen during evaporation of Y, BaF 2 , and Cu affected mainly the rate of Y. It is shown that the mass spectrometer can be utilized to precisely control the film composition

  12. Quenching of scintillation in BaF2 for light charged particles

    International Nuclear Information System (INIS)

    Matulewicz, T.

    1992-01-01

    Detectors made of a barium fluoride (BaF 2 ) crystal have recently become popular in the spectroscopy of photons and light charged particles at intermediate energies. The quenching of the scintillation light of BaF 2 crystals is described in the framework of Birks law for light charged particles in the energy range of 20-100 A MeV. Based on the recently published data, the analysis yields a value of Birks constant equal to 1.8±0.3 mg MeV -1 cm -2 and a scintillation efficiency equal to 0.79±0.05 MeV ee MeV -1 . (R.P.) 10 refs.; 2 figs

  13. Implementation study for the NRC Application and Development Facility

    International Nuclear Information System (INIS)

    Sherwood, R.J.; Ross, D.J.; Sasser, D.W.

    1979-01-01

    The Nuclear Regulatory Commission (NRC) has expressed the desire to establish an Application and Development Facility (ADF) for NRC Headquarters. The ADF is a computer system which will provide safeguards analysts access to safeguards analysis computer software. This report analyzes the issues, requirements and options available in the establishment of an ADF. The purpose and goals of the ADF are presented, along with some general issues to be considered in the implementation of such a system. A phased approach for ADF implementation, which will allow for the earliest possible access to existing codes and also allow for future expansion, is outlined. Several options for central computers are discussed, along with the characteristics and approximate costs for each. The report concludes with recommended actions proposed to start the development of the ADF

  14. Suppression of HPV E6 and E7 expression by BAF53 depletion in cervical cancer cells

    International Nuclear Information System (INIS)

    Lee, Kiwon; Lee, Ah-Young; Kwon, Yunhee Kim; Kwon, Hyockman

    2011-01-01

    Highlights: → Integration of HPV into host genome critical for activation of E6 and E7 oncogenes. → BAF53 is essential for higher-order chromatin structure. → BAF53 knockdown suppresses E6 and E7 from HPV integrants, but not from episomal HPVs. → BAF53 knockdown decreases H3K9Ac and H4K12Ac on P105 promoter of integrated HPV 18. → BAF53 knockdown restores the p53-dependent signaling pathway in HeLa and SiHa cells. -- Abstract: Deregulation of the expression of human papillomavirus (HPV) oncogenes E6 and E7 plays a pivotal role in cervical carcinogenesis because the E6 and E7 proteins neutralize p53 and Rb tumor suppressor pathways, respectively. In approximately 90% of all cervical carcinomas, HPVs are found to be integrated into the host genome. Following integration, the core-enhancer element and P105 promoter that control expression of E6 and E7 adopt a chromatin structure that is different from that of episomal HPV, and this has been proposed to contribute to activation of E6 and E7 expression. However, the molecular basis underlying this chromatin structural change remains unknown. Previously, BAF53 has been shown to be essential for the integrity of higher-order chromatin structure and interchromosomal interactions. Here, we examined whether BAF53 is required for activated expression of E6 and E7 genes. We found that BAF53 knockdown led to suppression of expression of E6 and E7 genes from HPV integrants in cervical carcinoma cell lines HeLa and SiHa. Conversely, expression of transiently transfected HPV18-LCR-Luciferase was not suppressed by BAF53 knockdown. The level of the active histone marks H3K9Ac and H4K12Ac on the P105 promoter of integrated HPV 18 was decreased in BAF53 knockdown cells. BAF53 knockdown restored the p53-dependent signaling pathway in HeLa and SiHa cells. These results suggest that activated expression of the E6 and E7 genes of integrated HPV is dependent on BAF53-dependent higher-order chromatin structure or nuclear motor

  15. Dose titration of BAF312 attenuates the initial heart rate reducing effect in healthy subjects.

    Science.gov (United States)

    Legangneux, Eric; Gardin, Anne; Johns, Donald

    2013-03-01

    Previous studies have shown transient decreases in heart rate (HR) following administration of sphingosine 1-phosphate (S1P) receptor modulators including BAF312. This study was conducted to determine whether dose titration of BAF312 reduces or eliminates these effects. Fifty-six healthy subjects were randomized 1:1:1:1 to receive BAF312 in one of two dose titration (DT) regimens (DT1 and DT2: 0.25-10 mg over 9-10 days), no titration (10 mg starting dose) or placebo. Pharmacodynamic and pharmacokinetic parameters were assessed. Neither DT1 nor DT2 resulted in clinically significant bradycardia or atrioventricular conduction effects. Both titration regimens showed a favourable difference on each of days 1-12 vs. the non-titration regimen on day 1 for HR effects (P titration was 1.18 (95% confidence interval [CI] 1.13, 1.23) and 1.14 (95% CI 1.09, 1.18) for DT2 (both P titration HRs showed considerable separation from placebo throughout the study. There was no statistically significant reduction in HR vs. placebo on day 1 in either titration regimen. On days 3-7 subjects in DT1 and DT2 experienced minor reductions in HR vs. placebo (approximately 5 beats min⁻¹; P ≤ 0.0001). From days 9-12, HRs in both titration regimens were comparable with placebo. Both titration regimens effectively attenuated the initial bradyarrhythmia observed on day 1 of treatment with BAF312 10 mg. © 2012 Novartis Institutes for BioMedical Research (NIBIR). British Journal of Clinical Pharmacology © 2012 The British Pharmacological Society.

  16. Fluorine dynamics in BaF2 superionic conductors investigated by NMR

    International Nuclear Information System (INIS)

    Gumann, Patryk

    2008-01-01

    In this work the dynamics of fluorine in solid-state electrolytes having BaF 2 -structure was investigated using three different NMR-methods: field cycling relaxometry, lineshape analysis, and static field gradient NMR. For this purpose a pure BaF 2 crystal, as well as crystals doped with trivalent impurities (LaF 3 ), were studied as a function of temperature. Using MAS NMR it was possible to identify two lines in Ba 0.9 La 0.1 F 2.1 having different chemical shift, and to refer them to the modified crystal structure. On this basis a model for the fluorine lineshape has been developed, taking into account three motional processes characterized by their correlation times. It includes jump diffusion of the fluorine ions among equivalent sites within two crystallographically distinct sublattices, and inter-lattice exchange processes. By measuring frequency and temperature-dependent spin lattice relaxation times, it was possible to gain information about fluorine dynamics on microscopic length scales. An attempt was also made to analyze the data for pure BaF 2 and low admixture concentration samples with a non-exponential correlation function. (orig.)

  17. Pyramidal pits created by single highly charged ions in BaF2 single crystals

    International Nuclear Information System (INIS)

    El-Said, A. S.; Heller, R.; Facsko, S.; Aumayr, F.

    2010-01-01

    In various insulators, the impact of individual slow highly charged ions (eV-keV) creates surface nanostructures, whose size depends on the deposited potential energy. Here we report on the damage created on a cleaved BaF 2 (111) surface by irradiation with 4.5xq keV highly charged xenon ions from a room-temperature electron-beam ion trap. Up to charge states q=36, no surface topographic changes on the BaF 2 surface are observed by scanning force microscopy. The hidden stored damage, however, can be made visible using the technique of selective chemical etching. Each individual ion impact develops into a pyramidal etch pits, as can be concluded from a comparison of the areal density of observed etch pits with the applied ion fluence (typically 10 8 ions/cm 2 ). The dimensional analysis of the measured pits reveals the significance of the deposited potential energy in the creation of lattice distortions/defects in BaF 2 .

  18. Ion conductivities of ZrF4-BaF2-CsF glasses

    International Nuclear Information System (INIS)

    Kawamoto, Yoji; Nohara, Ichiro

    1987-01-01

    The glass-forming region in the ZrF 4 -BaF 2 -CsF glass system has been determined and the ac conductivity and the transport number of fluoride ions have been measured. The conductivities of compounds β-Cs 2 ZrF 6 , α-SrZrF 6 , α-BaZrF 6 , β-BaZrF 6 and α-PbZrF 6 have also been measured. These results and a previous study of ZrF 4 -BaF 2 -MF n (M: the groups I-IV metals) glasses revealed the following: (1) the ZrF 4 -BaF 2 -CsF glasses are exclusively fluoride-ion conductors; (2) the ionic conductivities of ZrF 4 -based glasses are predominantly determined by the activation energies for conduction; (3) the activation energy for conduction decreases with an increase in the average polarizability of glass-constituting cations; (4) a decrease in average Zr-F bond length and a lowering of the average F coordination number of Zr are presumed to increase the activation energy for conduction. Principles of developing ZrF 4 -based glasses with higher conductivities have also been proposed. (Auth.)

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  20. BaF2 POST-DEPOSITION REACTION PROCESS FOR THICK YBCO FILMS

    International Nuclear Information System (INIS)

    SUENAGA, M.; SOLOVYOV, V.F.; WU, L.; WIESMANN, H.J.; ZHU, Y.

    2001-01-01

    The basic processes of the so-called BaF 2 process for the formation of YBa 2 Cu 3 O 7 , YBCO, films as well as its advantages over the in situ formation processes are discussed in the previous chapter. The process and the properties of YBCO films by this process were also nicely described in earlier articles by R. Feenstra, (et al.) Here, we will discuss two pertinent subjects related to fabrication of technologically viable YBCO conductors using this process. These are (1) the growth of thick (>> 1 microm) c-axis-oriented YBCO films and (2) their growth rates. Before the detail discussions of these subjects are given, we first briefly discuss what geometrical structure a YBCO-coated conductor should be. Then, we will provide examples of simple arguments for how thick the YBCO films and how fast their growth rates need to be. Then, the discussions in the following two sections are devoted to: (1) the present understanding of the nucleation and the growth process for YBCO, and why it is so difficult to grow thick c-axis-oriented films (> 3 microm), and (2) our present understanding of the YBCO growth-limiting mechanism and methods to increase the growth rates. The values of critical-current densities J c in these films are of primary importance for the applications,. and the above two subjects are intimately related to the control of J c of the films. In general, the lower the temperatures of the YBCO formation are the higher the values of J c of the films. Thus, the present discussion is limited to those films which are reacted at ∼735 C. This is the lowest temperature at which c-axis-oriented YBCO films (1-3 microm thick) are comfortably grown. It is also well known that the non-c-axis oriented YBCO platelets are extremely detrimental to the values of J c such that their effects on J c dwarf essentially all of other microstructural effects which control J c . Hence, the discussion given below is mainly focused on how to avoid the growth of these crystallites

  1. A survey of decontamination processes applicable to DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1997-05-01

    The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs.

  2. A survey of decontamination processes applicable to DOE nuclear facilities

    International Nuclear Information System (INIS)

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1997-05-01

    The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs

  3. Radiation applications research and facilities in AECL Research Company

    International Nuclear Information System (INIS)

    Iverson, S.L.

    1988-01-01

    In the 60's and 70's Atomic Energy of Canada had a very active R and D program to discover and develop applications of ionizing radiation. Widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of the test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal absorbent beds to concentrate the components of gas or liquid waste streams requiring treatment is showing promise as a method of significantly reducing the cost of radiation treatment for some effluents. A number of other projects are described. (author)

  4. 77 FR 33243 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-06-05

    ... expansion process, thermal expansion mismatch between the tube and tubesheet, and from the differential... NUCLEAR REGULATORY COMMISSION [NRC-2012-0125] Applications and Amendments to Facility Operating...

  5. Radiation applications research and facilities in AECL research company

    Science.gov (United States)

    Iverson, S. L.

    In the 60's and 70's Atomic Energy of Canada had a very active R&D program to discover and develop applications of ionizing radiation. Out of this grew the technology underlying the company's current product line of industrial irradiators. With the commercial success of that product line the company turned its R&D attention to other activities. Presently, widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. While many of the applications being considered are straightforward applications of existing knowledge, others depend on more subtle effects including combined effects of two or more agents. Further research is required in these areas. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal adsorbent beds to concentrate

  6. 曝气生物滤池(BAF)的发展与现状%Present Situation and Development of Biological Aerated Filter (BAF)

    Institute of Scientific and Technical Information of China (English)

    张薇; 史开武; 孔惠

    2005-01-01

    自20世纪80年代末法国OTV公司发明BIOCARBONE工艺以来,曝气生物滤池(BAF)工艺有了很大发展,在世界范围内的应用也日益广泛.笔者对常规曝气生物滤池的三种典型工艺BIOCARBONE、BIOSTYR、BIOFOR进行了结构、工艺上的对比分析,并在此基础上对新出现B2A、BIOPUR、BIOSMEDI及一体化反应器进行了介绍,经论证分析表明:曝气生物滤池是符合我国水处理的污水处理方法,有很大的发展潜力.

  7. Laser peening applications for next generation of nuclear power facilities

    International Nuclear Information System (INIS)

    Rankin, J.; Truong, C.; Walter, M.; Chen, H.-L.; Hackel, L.

    2008-01-01

    Generation of electricity by nuclear power can assist in achieving goals of reduced greenhouse gas emissions. Increased safety and reliability are necessary attributes of any new nuclear power plants. High pressure, hot water and radiation contribute to operating environments where Stress Corrosion Cracking (SCC) and hydrogen embrittlement can lead to potential component failures. Desire for improved steam conversion efficiency pushes the fatigue stress limits of turbine blades and other rotating equipment. For nuclear reactor facilities now being designed and built and for the next generations of designs, laser peening could be incorporated to provide significant performance life to critical subsystems and components making them less susceptible to fatigue, SCC and radiation induced embrittlement. These types of components include steam turbine blades, hubs and bearings as well as reactor components including cladding material, housings, welded assemblies, fittings, pipes, flanges, vessel penetrations, nuclear waste storage canisters. Laser peening has proven to be a commercial success in aerospace applications and has recently been put into use for gas and steam turbine generators and light water reactors. An expanded role for this technology for the broader nuclear power industry would be a beneficial extension. (author)

  8. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Lee, Jong Min; Kim, Chang Hoe; Kim, Byung Soo; Sohn, Surg Won; Hwoang, Suk Yeoung; Lee, Yong Bum; Kim, Woong Ki

    1992-12-01

    The objective of this project is to establish the basic technologies for advanced robotic systems operated in unstructured environment. The developed robotic system, which is remotely controlled, is expected to reduce the radiation dosage for workers who do the maintenance, inspection, and repairing work in nuclear facilities. The two major work scopes of this project in this year are to study the control scheme of advanced robotic system and develop a mobile robot. An inverse kinematic algorithm of 7 degrees of freedom anthropomorphic manipulator is investigated for dexterous control. Extended closed-loop schemes for solving the inverse kinematics of the redundant manipulator have been proposed and decentralized adaptive controller was designed by utilizing a new cartesian space controller. Control architecture of neural network has been developed, which has a strong capability on solving the kinematics of manipulator. The planetary wheel assembly has been implemented in the design to be suitable for plant. The design of manipulator has been implemented to operate with the battery power in the mobile system. This project will continue to be a major technical driver, with nuclear plant maintenance and waste management applications in conjunction with 'Long-term nuclear development program' over the next decade. (Author)

  9. The SWI/SNF chromatin-remodeling factors BAF60a, b, and c in nutrient signaling and metabolic control

    Directory of Open Access Journals (Sweden)

    Ruo-Ran Wang

    2017-07-01

    Full Text Available ABSTRACT Metabolic syndrome has become a global epidemic that adversely affects human health. Both genetic and environmental factors contribute to the pathogenesis of metabolic disorders; however, the mechanisms that integrate these cues to regulate metabolic physiology and the development of metabolic disorders remain incompletely defined. Emerging evidence suggests that SWI/SNF chromatin-remodeling complexes are critical for directing metabolic reprogramming and adaptation in response to nutritional and other physiological signals. The ATP-dependent SWI/SNF chromatin-remodeling complexes comprise up to 11 subunits, among which the BAF60 subunit serves as a key link between the core complexes and specific transcriptional factors. The BAF60 subunit has three members, BAF60a, b, and c. The distinct tissue distribution patterns and regulatory mechanisms of BAF60 proteins confer each isoform with specialized functions in different metabolic cell types. In this review, we summarize the emerging roles and mechanisms of BAF60 proteins in the regulation of nutrient sensing and energy metabolism under physiological and disease conditions.

  10. Does the Loss of ARID1A (BAF-250a Expression in Endometrial Clear Cell Carcinomas Have Any Clinicopathologic Significance? A Pilot Assessment

    Directory of Open Access Journals (Sweden)

    Oluwole Fadare, Idris L. Renshaw, Sharon X. Liang

    2012-01-01

    Full Text Available SWI/SNF chromatin-modification complexes use the energy of ATP hydrolysis to remodel nucleosomes and to affect transcription and several cellular processes. Accordingly, their loss of function has been associated with malignant transformation. ARID1A (the expression of whose product, BAF250a, a key complex component, is lost when mutated has recently been identified as a tumor suppressor gene that is mutated in 46-57% of ovarian clear cell carcinoma (CCC. The purposes of this study are to assess the frequency of loss of BAF250a expression in endometrial CCC and whether this loss has any discernable clinicopathologic implications. 34 endometrial carcinomas with a CCC component (including 22 pure CCC, 8 mixed carcinomas with a 10% CCC component, and 4 carcinosarcomas with a CCC epithelial component, were evaluated by immunohistochemistry using a monoclonal antibody directed against the human BAF250a protein. 5 (22.7% of the 22 pure CCC were entirely BAF250a negative, whereas the remainder showed diffuse immunoreactivity. None of 4 carcinosarcomas and only 1 (12.5% of the 8 mixed carcinomas were BAF250a negative. There was no discernable relationship between BAF250a immunoreactivity status and tumor architectural patterns (solid, papillary or tubulocystic areas or cell type (flat, hobnail or polygonal. Of the 22 patients with pure CCC, 14, 2, 3, and 3 were International Federation of Gynecology and Obstetrics stages 1, II, III and IV respectively. Interestingly, all 5 BAF250a negative cases were late stage [stages III or IV] as compared with 1 of 17 BAF250a positive cases (p=0.0002. Thus, 83% (5/6 of all late stage cases were BAF250a [-], as compared with 0 (0% of the 16 early stage (I or II cases (p=.0002. BAF250a negative and positive cases did not show any statistically significant difference regarding patient age and frequency of lymphovascular invasion or myometrial invasion. As may be anticipated from the concentration of late stage cases in

  11. Size distribution of BaF2 nanocrystallites in transparent glass ceramics

    International Nuclear Information System (INIS)

    Bocker, Christian; Bhattacharyya, Somnath; Hoeche, Thomas; Ruessel, Christian

    2009-01-01

    In glasses with the composition 1.9 Na 2 O-15 K 2 O-7.5 Al 2 O 3 -69.6 SiO 2 -6 BaF 2 (in mol.%), BaF 2 nanocrystalline precipitates are formed upon heat treatment. Using dark-field and bright-field transmission electron micrographs, crystallite size distributions are obtained for samples crystallized at various temperatures. According to the 'tomato-salad problem', the size distributions are corrected and then compared to various theories of grain growth taking into account coarsening of the crystallites during heat treatment. The experimental crystallite size distributions show for smaller mean crystallite sizes a more symmetric shape in comparison to the theories of Lifshitz-Slyozov-Wagner (LSW) or Brailsford and Wynblatt (B and W). With increasing mean crystallite sizes to about 18 nm at higher heat-treatment temperatures, the full width at half maximum of the observed distributions decreases and becomes even narrower than the LSW function. These findings indicate that in the investigated nano glass ceramics no coarsening by Ostwald ripening or coalescence occurs. This is explained by the formation of a diffusion barrier around each nanocrystallite which limits the size of the crystallites and hence results in such a narrow and uniform crystallite size distribution.

  12. The SWI/SNF BAF-A complex is essential for neural crest development.

    Science.gov (United States)

    Chandler, Ronald L; Magnuson, Terry

    2016-03-01

    Growing evidence indicates that chromatin remodeler mutations underlie the pathogenesis of human neurocristopathies or disorders that affect neural crest cells (NCCs). However, causal relationships among chromatin remodeler subunit mutations and NCC defects remain poorly understood. Here we show that homozygous loss of ARID1A-containing, SWI/SNF chromatin remodeling complexes (BAF-A) in NCCs results in embryonic lethality in mice, with mutant embryos succumbing to heart defects. Strikingly, monoallelic loss of ARID1A in NCCs led to craniofacial defects in adult mice, including shortened snouts and low set ears, and these defects were more pronounced following homozygous loss of ARID1A, with the ventral cranial bones being greatly reduced in size. Early NCC specification and expression of the BRG1 NCC target gene, PLEXINA2, occurred normally in the absence of ARID1A. Nonetheless, mutant embryos displayed incomplete conotruncal septation of the cardiac outflow tract and defects in the posterior pharyngeal arteries, culminating in persistent truncus arteriosus and agenesis of the ductus arteriosus. Consistent with this, migrating cardiac NCCs underwent apoptosis within the circumpharyngeal ridge. Our data support the notion that multiple, distinct chromatin remodeling complexes govern genetically separable events in NCC development and highlight a potential pathogenic role for NCCs in the human BAF complex disorder, Coffin-Siris Syndrome. Copyright © 2016 Elsevier Inc. All rights reserved.

  13. Survey of computer codes applicable to waste facility performance evaluations

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  14. 224-T Transuranic Waste Storage and Assay Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-01-01

    Westinghouse Hanford Company is a major contractor to the US Department of Energy Richland Field Office and serves as cooperator of the 224-T Transuranic Waste Storage and Assay Facility, the storage unit addressed in this permit application. At the time of submission of this portion of the Hanford Facility. Dangerous Waste Permit Application covering the 224-T Transuranic Waste Storage and Assay Facility, many issues identified in comments to the draft Hanford Facility Dangerous Waste Permit remain unresolved. This permit application reflects the positions taken by the US Department of Energy, Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application (Revision 0) consists of both a Part A and Part B permit application. An explanation of the Part A revisions associated with this unit, including the Part A revision currently in effect, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987). The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application contains information current as of March 1, 1992

  15. The present situation of the irradiation application industry and irradiation facilities in Japan

    International Nuclear Information System (INIS)

    Mizusawa, K.; Baba, T.

    2003-01-01

    The irradiation application industry and irradiation facilities in Japan have been making slow but steady progress for the past 2-3 years. Beside conventional applications, new ones such as carbon fibers and membrane filters have come into the market. There are a lot of new applications about to emerge. PE tubing, already is in the European market, is being evaluated by end users in Japan. Cleaning of dioxin in exhaust gas was successfully tested at a pilot plant. Cross-linked PTFE and polyamide are waiting customers' evaluations as an engineering plastic. Surface cross-linking of artificial polycarbonate teeth has yielded remarkable experimental results. Cross-linking of polycaprolactone will be useful for biodegradable products. Being aware of the future growth of irradiation industry, contract service providers opened new facilities or increased their capability. Beside in-house facilities, there are now three Co-60 facilities and nine EB facilities available for contract irradiation in Japan

  16. 36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

    Science.gov (United States)

    2010-07-01

    ... facilities subject to guidelines and standards. 1150.2 Section 1150.2 Parks, Forests, and Public Property... General Information § 1150.2 Applicability: Buildings and facilities subject to guidelines and standards... provided in paragraph (c) of this section, the standards issued under the Architectural Barriers Act of...

  17. NIREX transport activities since rejection of the rock characterisation facility planning application

    International Nuclear Information System (INIS)

    Barlow, S.; Carr, N.; Sievwright, R.W.T.

    2000-01-01

    The application by Nirex to build an underground Rock Characterisation Facility, was rejected by the Secretary of State on 17 March 1997. This decision has caused Nirex to reconsider its forward programme for the development of an underground disposal facility for intermediate level waste. This paper describes the transport related activities being undertaken by Nirex since that date. (author)

  18. 30 CFR 71.404 - Application for waiver of surface facilities requirements.

    Science.gov (United States)

    2010-07-01

    ... requirements. 71.404 Section 71.404 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE WORK AREAS... Facilities at Surface Coal Mines § 71.404 Application for waiver of surface facilities requirements. (a...

  19. Benefits of explosive cutting for nuclear-facility applications

    International Nuclear Information System (INIS)

    Hazelton, R.F.; Lundgren, R.A.; Allen, R.P.

    1981-06-01

    The study discussed in this report was a cost/benefit analysis to determine: (1) whether explosive cutting is cost effective in comparison with alternative metal sectioning methods and (2) whether explosive cutting would reduce radiation exposure or provide other benefits. Two separate approaches were pursued. The first was to qualitatively assess cutting methods and factors involved in typical sectioning cases and then compare the results for the cutting methods. The second was to prepare estimates of work schedules and potential radiation exposures for candidate sectioning methods for two hypothetical, but typical, sectioning tasks. The analysis shows that explosive cutting would be cost effective and would also reduce radiation exposure when used for typical nuclear facility sectioning tasks. These results indicate that explosive cutting should be one of the principal cutting methods considered whenever steel or similar metal structures or equipment in a nuclear facility are to be sectioned for repair or decommissioning. 13 figures, 7 tables

  20. Application technology for optical fiber in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Kim, Chul Jung; Lee, Yong Bum; Kim, Woong Ki; Yoon, Tae Seob; Sohn, Surg Won; Kim, Chang Hoi; Hwang, Suk Yong; Baik, Sung Hum; Kwon, Seong Ouk

    1987-12-01

    Lately, the optical fiber increasingly used in such adverse environments as nuclear power plant, radiation facilities because of their endurant properties against heat, radiation, corrosion, etc. Moreover, the transmission of signal through optical fiber does not induce interference from the electromagnetic wave. Basic theory about the optical fiber technology was studied and the developed techniques for nuclear facilities were reviewed. Since the radiations change the characteristics of the optical fiber, the effects of γ-ray irradiation on single mode and multimode optical fiber were examined. The image transmission system through optical fiber bundle was designed, constructed, and tested. Its software system was also updated. It can be used for remote internal inspection in adverse environment. (Author)

  1. The CERN-EU high-energy Reference Field (CERF) facility: applications and latest developments

    Science.gov (United States)

    Silari, Marco; Pozzi, Fabio

    2017-09-01

    The CERF facility at CERN provides an almost unique high-energy workplace reference radiation field for the calibration and test of radiation protection instrumentation employed at high-energy accelerator facilities and for aircraft and space dosimetry. This paper describes the main features of the facility and supplies a non-exhaustive list of recent (as of 2005) applications for which CERF is used. Upgrade work started in 2015 to provide the scientific and industrial communities with a state-of-the-art reference facility is also discussed.

  2. Overview of linac applications at future radioactive beam facilities

    International Nuclear Information System (INIS)

    Nolen, J.A.

    1996-01-01

    There is considerable interest worldwide in the research which could be done at a next generation, advanced radioactive beam facility. To generate high quality, intense beams of accelerated radionuclides via the open-quotes isotope separator on-lineclose quotes (ISOL) method requires two major accelerator components: a high power (100 kW) driver device to produce radionuclides in a production target/ion source complex, and a secondary beam accelerator to produce beams of radioactive ions up to energies on the order of 10 MeV per nucleon over a broad mass range. In reviewing the technological challenges of such a facility, several types of modem linear accelerators appear well suited. This paper reviews the properties of the linacs currently under construction and those proposed for future facilities for use either as the driver device or the radioactive beam post-accelerator. Other choices of accelerators, such as cyclotrons, for either the driver or secondary beam devices of a radioactive beam complex will also be compared. Issues to be addressed for the production accelerator include the choice of ion beam types to be used for cost-effective production of radionuclides. For the post-accelerator the choice of ion source technology is critical and dictates the charge-to-mass requirements at the injection stage

  3. Optical absorption of BaF2 crystals with different prehistory when irradiated by high-energy electrons

    International Nuclear Information System (INIS)

    Chinkov, E P; Stepanov, S A; Shtan'ko, V F; Ivanova, T S

    2016-01-01

    The spectra of stable optical absorption of BaF 2 crystals containing uncontrollable impurities after irradiation with 3 MeV electrons are studied at room temperature. The dependence of the efficiency of stable color accumulation in the region of emerging crossluminescence on the absorption coefficients measured near the fundamental absorption edge in unirradiated crystals of various prehistory is traced. (paper)

  4. Novel synthetic lethality screening method identifies TIP60-dependent radiation sensitivity in the absence of BAF180.

    Science.gov (United States)

    Hopkins, Suzanna R; McGregor, Grant A; Murray, Johanne M; Downs, Jessica A; Savic, Velibor

    2016-10-01

    In recent years, research into synthetic lethality and how it can be exploited in cancer treatments has emerged as major focus in cancer research. However, the lack of a simple to use, sensitive and standardised assay to test for synthetic interactions has been slowing the efforts. Here we present a novel approach to synthetic lethality screening based on co-culturing two syngeneic cell lines containing individual fluorescent tags. By associating shRNAs for a target gene or control to individual fluorescence labels, we can easily follow individual cell fates upon siRNA treatment and high content imaging. We have demonstrated that the system can recapitulate the functional defects of the target gene depletion and is capable of discovering novel synthetic interactors and phenotypes. In a trial screen, we show that TIP60 exhibits synthetic lethality interaction with BAF180, and that in the absence of TIP60, there is an increase micronuclei dependent on the level of BAF180 loss, significantly above levels seen with BAF180 present. Moreover, the severity of the interactions correlates with proxy measurements of BAF180 knockdown efficacy, which may expand its usefulness to addressing synthetic interactions through titratable hypomorphic gene expression. Copyright © 2016. Published by Elsevier B.V.

  5. Hanford Central Waste Complex: Waste Receiving and Processing Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Central Waste Complex is an existing and planned series of treatment, and/or disposal (TSD) unites that will centralize the management of solid waste operations at a single location on the Hanford Facility. The Complex includes two units: the WRAP Facility and the Radioactive Mixed Wastes Storage Facility (RMW Storage Facility). This Part B permit application addresses the WRAP Facility. The Facility will be a treatment and storage unit that will provide the capability to examine, sample, characterize, treat, repackage, store, and certify radioactive and/or mixed waste. Waste treated and stored will include both radioactive and/or mixed waste received from onsite and offsite sources. Certification will be designed to ensure and demonstrate compliance with waste acceptance criteria set forth by onsite disposal units and/or offsite facilities that subsequently are to receive waste from the WRAP Facility. This permit application discusses the following: facility description and general provisions; waste characterization; process information; groundwater monitoring; procedures to prevent hazards; contingency plant; personnel training; exposure information report; waste minimization plan; closure and postclosure requirements; reporting and recordkeeping; other relevant laws; certification

  6. Alpha/beta(gamma ray) discrimination and spillover quantification with a BaF2 scintillator

    International Nuclear Information System (INIS)

    DeVol, T.A.; Fjeld, R.A.

    1994-01-01

    A simple pulse shape discrimination technique was used to separate alpha and beta(gamma ray) interactions in a BaF 2 scintillator. The separation was not ideal, resulting in a 5.1% spillover of alpha interactions into the beta(gamma ray) channel and 11.9% spillover of beta(gamma ray) interactions into the alpha channel for a set pulse shape discriminator. The misclassification of events was reduced by post-processing the data using either a simple analytical technique or a more complex linear least squares technique. Both techniques typically reduced the difference between the expected and calculated interaction rates to <10% when the ratio of beta(gamma ray) to alpha count rate was less than 100 : 1. ((orig.))

  7. Economic Feasibility Analysis of the Application of Geothermal Energy Facilities to Public Building Structures

    Directory of Open Access Journals (Sweden)

    Sangyong Kim

    2014-03-01

    Full Text Available This study aims to present an efficient plan for the application of a geothermal energy facility at the building structure planning phase. Energy consumption, energy cost and the primary energy consumption of buildings were calculated to enable a comparison of buildings prior to the application of a geothermal energy facility. The capacity for energy savings and the costs related to the installation of such a facility were estimated. To obtain more reliable criteria for economic feasibility, the lifecycle cost (LCC analysis incorporated maintenance costs (reflecting repair and replacement cycles based on construction work specifications of a new renewable energy facility and initial construction costs (calculated based on design drawings for its practical installation. It is expected that the findings of this study will help in the selection of an economically viable geothermal energy facility at the building construction planning phase.

  8. [Leaching characteristics of heavy metals and utilization of filter media in BAF].

    Science.gov (United States)

    Zou, Jin-long; Dai, Ying

    2007-10-01

    A series of leaching tests were conducted to study the solidification of heavy metals in biological filter media made with dried sludge as an additive. The maximum leaching contents of Cd, Cr, Cu and Pb are obtained when pH is 1; leaching contents of heavy metals have an obvious decrease as pH is greater than or equal to 3; and it can be concluded from the results that pH has a significant influence on the leaching characteristic of heavy metals at leaching time of either 24 h or 30 d. X-ray diffraction analysis performed on filter media reveal the main compounds of the 4 heavy metals are Pb2O(CrO4), CdSiO3 and CuO, and the heavy metals are solidified in the mesh structure of Si--O. Heavy metals (such as Cd, Cr, Cu and Pb) can be solidified in filter media through a series of crystalline phase changes and chemical reaction after high temperature sintering. The new filter media (obtained in test) were used in biological aerated filter (BAF) to treat wastewater (C/N about 11.5 and 25.5) in a simultaneous nitrification and denitrification (SND) system. Based on the mechanism of SND, the average removal efficienciesof NH4(+)-N and TN filled with the new filter media (obtained in test) are about 85.5%, 90.3%, 46.6% and 49.6%, respectively, and it is higher than those of other 3 medias (Jiangxi ceramsite, Guangzhou ceramsite and Shanxi activated carbon). The results provide a better understanding of factors that may affect the immobilization and leaching characteristics of heavy metals in ceramsite, which promotes the extensive use of filter media in BAF.

  9. Mutations in the BAF-Complex Subunit DPF2 Are Associated with Coffin-Siris Syndrome.

    Science.gov (United States)

    Vasileiou, Georgia; Vergarajauregui, Silvia; Endele, Sabine; Popp, Bernt; Büttner, Christian; Ekici, Arif B; Gerard, Marion; Bramswig, Nuria C; Albrecht, Beate; Clayton-Smith, Jill; Morton, Jenny; Tomkins, Susan; Low, Karen; Weber, Astrid; Wenzel, Maren; Altmüller, Janine; Li, Yun; Wollnik, Bernd; Hoganson, George; Plona, Maria-Renée; Cho, Megan T; Thiel, Christian T; Lüdecke, Hermann-Josef; Strom, Tim M; Calpena, Eduardo; Wilkie, Andrew O M; Wieczorek, Dagmar; Engel, Felix B; Reis, André

    2018-03-01

    Variants affecting the function of different subunits of the BAF chromatin-remodelling complex lead to various neurodevelopmental syndromes, including Coffin-Siris syndrome. Furthermore, variants in proteins containing PHD fingers, motifs recognizing specific histone tail modifications, have been associated with several neurological and developmental-delay disorders. Here, we report eight heterozygous de novo variants (one frameshift, two splice site, and five missense) in the gene encoding the BAF complex subunit double plant homeodomain finger 2 (DPF2). Affected individuals share common clinical features described in individuals with Coffin-Siris syndrome, including coarse facial features, global developmental delay, intellectual disability, speech impairment, and hypoplasia of fingernails and toenails. All variants occur within the highly conserved PHD1 and PHD2 motifs. Moreover, missense variants are situated close to zinc binding sites and are predicted to disrupt these sites. Pull-down assays of recombinant proteins and histone peptides revealed that a subset of the identified missense variants abolish or impaire DPF2 binding to unmodified and modified H3 histone tails. These results suggest an impairment of PHD finger structural integrity and cohesion and most likely an aberrant recognition of histone modifications. Furthermore, the overexpression of these variants in HEK293 and COS7 cell lines was associated with the formation of nuclear aggregates and the recruitment of both wild-type DPF2 and BRG1 to these aggregates. Expression analysis of truncating variants found in the affected individuals indicated that the aberrant transcripts escape nonsense-mediated decay. Altogether, we provide compelling evidence that de novo variants in DPF2 cause Coffin-Siris syndrome and propose a dominant-negative mechanism of pathogenicity. Copyright © 2018 American Society of Human Genetics. Published by Elsevier Inc. All rights reserved.

  10. Numerous BAF complex genes are mutated in Coffin-Siris syndrome.

    Science.gov (United States)

    Miyake, Noriko; Tsurusaki, Yoshinori; Matsumoto, Naomichi

    2014-09-01

    Coffin-Siris syndrome (CSS; OMIM#135900) is a rare congenital anomaly syndrome characterized by intellectual disability, coarse face, hypertrichosis, and absence/hypoplasia of the fifth digits' nails. As the majority of patients are sporadic, an autosomal dominant inheritance model has been postulated. Recently, whole exome sequencing (WES) emerged as a comprehensive analytical method for rare variants. We applied WES on five CSS patients and found two de novo mutations in SMARCB1. SMARCB1 was completely sequenced in 23 CSS patients and the mutations were found in two more patients. As SMARCB1 encodes a subunit of the BAF complex functioning as a chromatin remodeling factor, mutations in 15 other subunit genes may cause CSS and thus were analyzed in 23 CSS patients. We identified heterozygous mutations in either of six genes (SMARCA4, SMARCB1, SMARCA2, SMARCE1, ARID1A, and ARID1B) in 20 out of 23 CSS patients. The patient with a SMARCA2 mutation was re-evaluated and identified as having Nicolaides-Baraitser syndrome (OMIM#601358), which is similar to but different from CSS. Additionally, 49 more CSS patients were analyzed as a second cohort. Together with the first cohort, 37 out of 71 (22 plus 49) patients were found to have a mutation in either one of five BAF complex genes. Furthermore, two CSS patients were reported to have a PHF6 abnormality, which can also cause Borjeson-Forssman-Lehmann syndrome (OMIM#301900), an X-linked intellectual disability syndrome with epilepsy and endocrine abnormalities. The current list of mutated genes in CSS is far from being complete and analysis of more patients is required. © 2014 Wiley Periodicals, Inc.

  11. Proposed medical applications of the National Accelerator Centre facilities

    International Nuclear Information System (INIS)

    Jones, D.T.L.

    1982-01-01

    The National Accelerator Centre is at present under construction at Faure, near Cape Town. The complex will house a 200 MeV separated-sector cyclotron which will provide high quality beams for nuclear physics and related diciplines as well as high intensity beams for medical use. The medical aspects catered for will include particle radiotherapy, isotope production and possibly proton radiography. A 30-bed hospital is to be constructed on the site. Building operations are well advanced and the medical facilities should be available for use by the end of 1984

  12. CAD system applications to the nuclear fuel reprocessing facilities

    International Nuclear Information System (INIS)

    Morita, Eiji; Matsumoto, Tadakuni; Shikakura, Sakae; Furuya, Kousei; Sakurai, Shin-ichi.

    1994-01-01

    Effective supporting techniques of design, operation, and maintenance of the reprocessing facility have been developed using the Intergraph CAD system. Two and three dimensional views of the process cells were utilized to rationalize the equipment layout and material handling flows, and to check the piping interference. Interferences of the remote maintenance equipment with the process equipments were also evaluated by the pictures on the CAD display. The newest virtual reality technology will help our future development of the more natural simulation for the remote maintenance operator training. (author)

  13. Application of GIS in siting of linear facilities

    International Nuclear Information System (INIS)

    Gallagher, G.A. III; Heatwole, D.W.; Schmidt, J.A.

    1993-01-01

    Geographic information systems (GIS) are powerful tools in the analysis and selection of environmentally acceptable corridors for linear facilities, such as roads and utility lines. GIS can serve several functions in corridor siting, including managing and manipulating extensive environmental databases, weighting and compositing data layers to enable spatial analysis for a ''path of least resistance,'' summarizing statistics for a comparison of alternative corridors, preparing color graphics for presentations and reports, and providing a record of alternative analysis for permitting reviews and legal challenges. In this paper, the authors examine the benefits and limitations of using GIS to site linear facilities, based mainly on their experience in siting a 600-mile natural gas pipeline in Florida. They implemented a phased analytical approach to define acceptable corridors several miles in width and then selected viable routes within the corridors using a magnified scale. This approach resulted in a dynamic siting process which required numerous iterations of analysis. Consequently, their experience has instilled the benefits derived by expending preliminary effort to create macros of the GIS analytical process so that subsequent effort is minimized during numerous iterations of corridor and route refinement

  14. 48 CFR 23.704 - Application to Government-owned or -leased facilities.

    Science.gov (United States)

    2010-10-01

    ... ACQUISITION REGULATION SOCIOECONOMIC PROGRAMS ENVIRONMENT, ENERGY AND WATER EFFICIENCY, RENEWABLE ENERGY... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Application to Government... and Services 23.704 Application to Government-owned or -leased facilities. Executive Order 13101...

  15. 76 FR 65544 - Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities

    Science.gov (United States)

    2011-10-21

    ... NUCLEAR REGULATORY COMMISSION [NRC-2009-0323] Standard Format and Content of License Applications... revision to regulatory guide (RG) 3.39, ``Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities.'' This guide endorses the standard format and content for license...

  16. An improved safeguards system and its application to large backend facilities

    International Nuclear Information System (INIS)

    1978-12-01

    The evaluation criteria, which are commonly applicable to both Material Accountancy (MA) and Containment and Surveillance (C/S) and applicable to a large backend facilities, are discussed. It is analyzed that substantial increase of the proliferation resistance can be expected by improving the presently existing safeguards systems. The improved safeguards system described in this paper is expected to be applicable to large-scaled backend facilities without giving unnecessary economical and technical burdens. The main purpose of this approach is to move away from the present trend of too much reliance on MA and to develop the synthetical safeguards effects by harmonizing C/S and continuing MA effectively

  17. BAF53b, a Neuron-Specific Nucleosome Remodeling Factor, Is Induced after Learning and Facilitates Long-Term Memory Consolidation.

    Science.gov (United States)

    Yoo, Miran; Choi, Kwang-Yeon; Kim, Jieun; Kim, Mujun; Shim, Jaehoon; Choi, Jun-Hyeok; Cho, Hye-Yeon; Oh, Jung-Pyo; Kim, Hyung-Su; Kaang, Bong-Kiun; Han, Jin-Hee

    2017-03-29

    Although epigenetic mechanisms of gene expression regulation have recently been implicated in memory consolidation and persistence, the role of nucleosome-remodeling is largely unexplored. Recent studies show that the functional loss of BAF53b, a postmitotic neuron-specific subunit of the BAF nucleosome-remodeling complex, results in the deficit of consolidation of hippocampus-dependent memory and cocaine-associated memory in the rodent brain. However, it is unclear whether BAF53b expression is regulated during memory formation and how BAF53b regulates fear memory in the amygdala, a key brain site for fear memory encoding and storage. To address these questions, we used viral vector approaches to either decrease or increase BAF53b function specifically in the lateral amygdala of adult mice in auditory fear conditioning paradigm. Knockdown of Baf53b before training disrupted long-term memory formation with no effect on short-term memory, basal synaptic transmission, and spine structures. We observed in our qPCR analysis that BAF53b was induced in the lateral amygdala neurons at the late consolidation phase after fear conditioning. Moreover, transient BAF53b overexpression led to persistently enhanced memory formation, which was accompanied by increase in thin-type spine density. Together, our results provide the evidence that BAF53b is induced after learning, and show that such increase of BAF53b level facilitates memory consolidation likely by regulating learning-related spine structural plasticity. SIGNIFICANCE STATEMENT Recent works in the rodent brain begin to link nucleosome remodeling-dependent epigenetic mechanism to memory consolidation. Here we show that BAF53b, an epigenetic factor involved in nucleosome remodeling, is induced in the lateral amygdala neurons at the late phase of consolidation after fear conditioning. Using specific gene knockdown or overexpression approaches, we identify the critical role of BAF53b in the lateral amygdala neurons for

  18. Solar energy applications in transportation facilities : a literature review.

    Science.gov (United States)

    1978-01-01

    This report presents the results of a survey of the literature and other sources to determine the types of application that have been made of solar energy in the transportation field. The use of solar energy for powering automatic traffic counters, v...

  19. Experience in the Application of INES scale to events in the Spanish Radioactive facilities

    International Nuclear Information System (INIS)

    Ramirez, M. L.; Alvarez, C.

    2002-01-01

    In February 2001, the International Atomic Energy Agency (IAEA) and the Nuclear energy Agency of the OECD (NEA) published a new edition of the INES User's Manual for the classification of nuclear events. One of the new developments introduced with respect to the scope of the former Manual was the inclusion within the INES of any event associated with radioactive material and/or radiation. This would include events occurred in radioactive facilities so the INES would apply not only to events in nuclear facilities. During the publication process some doubts rose about the applicability of INES to other non nuclear types of events. The IAEA was open to the future development of more practical guidance for the application of the scale. Since the beginning of 2001 the Consejo de Seguridad Nuclear (CSN) has been using INES to test the applicability of the system to classify events in radioactive facilities. A total of 31 events occurred at Spanish radioactive facilities has been classified applying INES scale and a report was sent to IAEA to publish our experience. The objective of this presentation is to introduce the experience obtained by the application of the International Nuclear Events Scale (INES) to classify events in radioactive facilities in Spain and to present several issues raised during its application that may need further development in a practical guidance. (Author)

  20. Diffraction studies applicable to 60-foot microwave research facilities

    Science.gov (United States)

    Schmidt, R. F.

    1973-01-01

    The principal features of this document are the analysis of a large dual-reflector antenna system by vector Kirchhoff theory, the evaluation of subreflector aperture-blocking, determination of the diffraction and blockage effects of a subreflector mounting structure, and an estimate of strut-blockage effects. Most of the computations are for a frequency of 15.3 GHz, and were carried out using the IBM 360/91 and 360/95 systems at Goddard Space Flight Center. The FORTRAN 4 computer program used to perform the computations is of a general and modular type so that various system parameters such as frequency, eccentricity, diameter, focal-length, etc. can be varied at will. The parameters of the 60-foot NRL Ku-band installation at Waldorf, Maryland, were entered into the program for purposes of this report. Similar calculations could be performed for the NELC installation at La Posta, California, the NASA Wallops Station facility in Virginia, and other antenna systems, by a simple change in IBM control cards. A comparison is made between secondary radiation patterns of the NRL antenna measured by DOD Satellite and those obtained by analytical/numerical methods at a frequency of 7.3 GHz.

  1. Management concepts and safety applications for nuclear fuel facilities

    International Nuclear Information System (INIS)

    Eisner, H.; Scotti, R.S.

    1995-05-01

    This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities

  2. Management concepts and safety applications for nuclear fuel facilities

    Energy Technology Data Exchange (ETDEWEB)

    Eisner, H.; Scotti, R.S. [George Washington Univ., Washington, DC (United States). School of Engineering and Applied Science; Delicate, W.S. [KEVRIC Co., Inc., Silver Spring, MD (United States)

    1995-05-01

    This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities.

  3. Advanced Process Control Application and Optimization in Industrial Facilities

    Directory of Open Access Journals (Sweden)

    Howes S.

    2015-01-01

    Full Text Available This paper describes application of the new method and tool for system identification and PID tuning/advanced process control (APC optimization using the new 3G (geometric, gradient, gravity optimization method. It helps to design and implement control schemes directly inside the distributed control system (DCS or programmable logic controller (PLC. Also, the algorithm helps to identify process dynamics in closed-loop mode, optimizes controller parameters, and helps to develop adaptive control and model-based control (MBC. Application of the new 3G algorithm for designing and implementing APC schemes is presented. Optimization of primary and advanced control schemes stabilizes the process and allows the plant to run closer to process, equipment and economic constraints. This increases production rates, minimizes operating costs and improves product quality.

  4. The application of security provisions in accommodation facility – hotel

    OpenAIRE

    Rotbauer, Josef

    2010-01-01

    This thesis treats of security provisions, which hotels are using to protect health and property of accommodated persons. In the opening part is caught the progress of attendance and capacities of hotels in the Czech republic during a specific time period. The next chapter focuses on possible threats, which are imminent to hotels during the operation. The third part of the thesis solves particular methods of application of security provisions, these are verified in two concrete hotels in the ...

  5. Facility layout planning for educational systems: An application of fuzzy GIS and AHP

    Directory of Open Access Journals (Sweden)

    Hossein Ebrhaimzadeh Asmin

    2014-06-01

    Full Text Available One of the most important issues in urban planning programs is to allocate necessary spaces for educational applications. Selecting appropriate locations for training centers increases students' mental capabilities. Suitable location for the establishment of educational facilities is the first fundamental step for development of educational systems. The selection of optimal sites for educational facilities involves numerous parameters and it is essential to use multiple criteria decision making approaches to make wise decisions. This paper presents an empirical investigation on facility layout planning for educational systems in city of Birjand, Iran. Using fuzzy GIS as well as analytical hierarchy process (AHP, the study determines the most appropriate candidates for training centers.

  6. Hanford facility dangerous waste permit application, low-level burial grounds

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    The Hanford Facility Dangerous Plaste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, 'operating' treatment, storage, and/or disposal units, such as the Low-Level Burial Grounds (this document, DOE/RL-88-20)

  7. Hanford facility dangerous waste permit application, low-level burial grounds

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann, R.H.

    1997-08-12

    The Hanford Facility Dangerous Plaste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, `operating` treatment, storage, and/or disposal units, such as the Low-Level Burial Grounds (this document, DOE/RL-88-20).

  8. Application for approval to construct the Waste Receiving And Processing facility

    International Nuclear Information System (INIS)

    1993-02-01

    The following Application For Approval Of Construction is being submitted by the US Department of Energy, Richland Field Office pursuant to 40 CFR 61.07, ''Application for Approval of Construction or Modification,'' for the Waste Receiving and Processing (WRAP) Module 1 facility (also referred to as WRAP 1). The WRAP 1 facility will be a new source of radioactive emissions to the atmosphere. The WRAP 1 facility will be housed in the new 2336-W Building, which will be located in the 200 West Area south of 23rd Street and west of Dayton Avenue. The 200 West Area is located within the boundary of the Hanford Site. The mission of the WRAP 1 facility is to examine, assay, characterize, treat, and repackage solid radioactive and mixed waste to enable permanent disposal of the waste in accordance with all applicable regulations. The solid wastes to be handled in the WRAP 1 facility include low-level waste (LLW), Transuranic (TRU) waste, TRU mixed waste, and low-level mixed waste (LLMW). The WRAP 1 facility will only accept contact handled (CH) waste containers. CH waste is a waste category whose external surface dose rate does not exceed 200 mrem/h. These containers have a surface dose rate of less than 200 mrem/h

  9. Licence applications for low and intermediate level waste predisposal facilities: A manual for operators

    International Nuclear Information System (INIS)

    2009-07-01

    This publication covers all predisposal waste management facilities and practices for receipt, pretreatment (sorting, segregation, characterization), treatment, conditioning, internal relocation and storage of low and intermediate level radioactive waste, including disused sealed radioactive sources. The publication contains an Annex presenting the example of a safety assessment for a small radioactive waste storage facility. Facilities dealing with both short lived and long lived low and intermediate level waste generated from nuclear applications and from operation of small nuclear research reactors are included in the scope. Processing and storage facilities for high activity disused sealed sources and sealed sources containing long lived radionuclides are also covered. The publication does not cover facilities processing or storing radioactive waste from nuclear power plants or any other industrial scale nuclear fuel cycle facilities. Disposal facilities are excluded from the scope of this publication. Authorization process can be implemented in several stages, which may start at the site planning and the feasibility study stage and will continue through preliminary design, final design, commissioning, operation and decommissioning stages. This publication covers primarily the authorization needed to take the facility into operation

  10. Wire sawing for the application for dismantling of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Toenshoff, H.K.; Hillmann-Apmann, H. [Hannover Univ. (Germany). Inst. for Production Engineering and Machine Tools

    2001-07-01

    In recent years diamond wire sawing process has been established as a technique for machining of hard and brittle materials in the quarrying and dimensioning of natural stone, i.e. marble and granite /Bor94/, or in machining of concrete and reinforced concrete /NN89, NN90, Rus93, Zil89/. It is more and more applied in different industrial sectors, namely the building and road-building industry, for purposes of reconstruction and decommissioning/. For the application of cutting austenitic steel most of the current wire sawing tools can not be used. First the diamond get in chemical reaction with the steel (graphitisation) and also the plastic flow of the workpiece material (''smearing'') while processing this material, the chip spaces between the diamonds are filled with the steel chips and thus the effective processing is reduced. Only the very tips of the diamonds are in contact with the workpiece, which leads in most cases to rapid wear of the grains. The tool loses its ability to grind in short terms of time. All these problems exclude the wire sawing technique from wide areas of application of cutting ductile steel materials. (orig.)

  11. Wire sawing for the application for dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Toenshoff, H.K.; Hillmann-Apmann, H.

    2001-01-01

    In recent years diamond wire sawing process has been established as a technique for machining of hard and brittle materials in the quarrying and dimensioning of natural stone, i.e. marble and granite /Bor94/, or in machining of concrete and reinforced concrete /NN89, NN90, Rus93, Zil89/. It is more and more applied in different industrial sectors, namely the building and road-building industry, for purposes of reconstruction and decommissioning/. For the application of cutting austenitic steel most of the current wire sawing tools can not be used. First the diamond get in chemical reaction with the steel (graphitisation) and also the plastic flow of the workpiece material (''smearing'') while processing this material, the chip spaces between the diamonds are filled with the steel chips and thus the effective processing is reduced. Only the very tips of the diamonds are in contact with the workpiece, which leads in most cases to rapid wear of the grains. The tool loses its ability to grind in short terms of time. All these problems exclude the wire sawing technique from wide areas of application of cutting ductile steel materials. (orig.)

  12. Biodegradation behavior of natural organic matter (NOM) in a biological aerated filter (BAF) as a pretreatment for ultrafiltration (UF) of river water

    KAUST Repository

    Huang, Guocheng; Meng, Fangang; Zheng, Xing; Wang, Yuan; Wang, Zhigang; Liu, Huijun; Jekel, Martin R.

    2011-01-01

    In this study, biodegradation of natural organic matter (NOM) in a biological aerated filter (BAF) as pretreatment of UF treating river water was investigated. Photometric measurement, three-dimensional excitation-emission matrix (EEM) fluorescence

  13. Computer applications for the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Worth, G.A.; Patterson, J.R.

    1976-01-01

    Computer applications for the FFTF reactor include plant surveillance functions and fuel handling and examination control functions. Plant surveillance systems provide the reactor operator with a selection of over forty continuously updated, formatted displays of correlated data. All data are checked for limits and validity and the operator is advised of any anomaly. Data are also recorded on magnetic tape for historical purposes. The system also provides calculated variables, such as reactor thermal power and anomalous reactivity. Supplementing the basic plant surveillance computer system is a minicomputer system that monitors the reactor cover gas to detect and characterize absorber or fuel pin failures. In addition to plant surveillance functions, computers are used in the FFTF for controlling selected refueling equipment and for post-irradiation fuel pin examination. Four fuel handling or examination systems operate under computer control with manual monitoring and over-ride capability

  14. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Kim, Seung Ho; Kim, Chang Hoi; Kim, Byung Soo; Hwang, Suk Young; Sohn, Surg Won; Lee, Yong Bum; Kim, Woong Ki

    1991-01-01

    The project of this study is intended to develop the application technology for autonomous robotic systems operated in hostile environments where human access is prohibited. The mobile robot, named as KAEROT, has been designed by adopting the controller of multiprocessor of distributed system architecture in order to get flexibility. 2 driving wheel assembles and 1 steering mechanism has been adopted and each of them is made of planetary wheel which is composed of a couple of star-like arms with 3 wheels. The 6 D.O.F of manipulator is controlled by CCD camera mounted on the elbow and base, to provide wide view of the working area for tele-operation. The off-line programming system is being developed for checking robot constraint violations within workspace prior to execution of robot programming. (Author)

  15. Exploring the Application of Capital Facility Investment Justification Model

    Directory of Open Access Journals (Sweden)

    Marijan Karić

    2013-07-01

    Full Text Available For decades now, the models for identifying and quantifying the level of risk of investment projects and investment justification evaluation have been the subject of investigation by members of professional and research communities. It is important to quantify the level of risk because by evaluating investment justification in terms of the risks involved, the decision-maker (investor is able to choose from available alternatives the one that will achieve the most favourable ratio of expected profit to the assumed risk. In this way, the economic entity can raise its productivity, profitability and the quality of business operation in general. The aim of this paper was to investigate the extent to which medium and large companies have been using modern methods of investment justification evaluation in their decision-making process and determine the level of quality of the application of the selected methods in practice. The study was conducted on a sample of medium and large enterprises in the eastern Croatia during 2011 and 2012, and it was established that despite the fact that a large number of modern investment project profitability and risk assessment models have been developed, the level of their application in practice is not high enough. The analyzed investment proposals included only basic methods of capital budgeting without risk assessment. Hence, it was concluded that individual investors were presented with low-quality and incomplete investment justification evaluation results on the basis of which the decisions of key importance for the development of the economic entity as a whole were made. This paper aims to underline the need for financial managers to get informed and educate themselves about contemporary investment project profitability and risk assessment models as well as the need to create educational programmes and computer solutions that will encourage key people in companies to acquire new knowledge and apply modern

  16. Hardware Development Process for Human Research Facility Applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. The source of hardware requirements is the science community and HRF program. The HRF Science Working Group, consisting of SCientists from various medical disciplines, defined a basic set of equipment with functional requirements. This established the performance requirements of the hardware. HRF program requirements focus on making the hardware safe and operational in a space environment. This includes structural, thermal, human factors, and material requirements. Science and HRF program requirements are defined in a hardware requirements document which includes verification methods. Once the hardware is fabricated, requirements are verified by inspection, test, analysis, or demonstration. All data is compiled and reviewed to certify the hardware for flight. Obviously, the basis for all hardware development activities is requirement definition. Full and complete requirement definition is ideal prior to initiating the hardware development. However, this is generally not the case, but the hardware team typically has functional inputs as a guide. The first step is for engineers to conduct market research based on the functional inputs provided by scientists. CommerCially available products are evaluated against the science requirements as

  17. Application technology for optical fiber in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Kim, Woong Ki; Kim, Seung Ho; Kim, Chang Hoi; Hwang, Suk Yeong; Kim, Byung Soo; Sohn, Surg Won

    1990-01-01

    The objective of this project is to study the radiation effects on optical fiber, to develop remote inspection and image processing system, and to apply image processing technique to X-ray radiography analysis and to laser beam diagnostic system. Thermal neutrons cause nuclear radiation with fiber compositions, so secondary ionizing radiations of high energy are generated. These ionizing radiations from color centers, which increase transmission loss of optical fiber by absorbing propagating light in fiber core. As a result of experiment, owing to Ge, P, and B doping effects the induced loss in multimode fibers has been 5 times larger than that in single mode fibers, the loss at 0.85 μm wavelength region more susceptible for radiations has been twice higher than that at 1.3 μm. Remote inspection mechanism captures images remotely, and the images are inhanced by image processing surfaces of bent or long-straight pipe in hostile environment. Laser beam diagnostic system using image processing techniques can be used to observe and analyze laser beam quality. This system will be effectively applied for laser development and application field. X-ray radiographic image analysis by image processing technique make it easier to inspect and measure irradiated fuel rod, and the accuracy of the obtained data is also improved. (author)

  18. SMARCB1/INI1/BAF47- deficient pleural malignant mesothelioma with rhabdoid features.

    Science.gov (United States)

    Kimura, Noriko; Hasegawa, Masaru; Hiroshima, Kenzo

    2018-02-01

    Malignant mesothelioma (MM) with rhabdoid features is an MM variant. Fifteen cases have been reported previously, all of which were combined with other types of MM. Herein, we report an autopsy case of pleural MM with monomorphic rhabdoid features. The patient was a 62-year-old male without a history of asbestos exposure. An autopsy revealed a soft, granular tumor that replaced the entire left pleura and had invaded to the diaphragm and lower lobe of the lung. The tumor cells, which had eosinophilic plump cytoplasm and eccentric nuclei, were loosely cohesive. Immunohistochemistry showed that the cells were diffusely positive for calretinin, D2-40, vimentin, CAM5.2, and AE1/AE3; and negative for WT-1, TTF-1, CK7, CEA, desmin, CD34, BCL-2, S100 protein, and p40. Neither homozygous deletion of p16 nor BAP-1 protein loss was observed. Loss of INI1/BAF47 protein, an indicator of malignant rhabdoid tumor, was observed. Therefore, MM with rhabdoid features was confirmed. © 2018 Japanese Society of Pathology and John Wiley & Sons Australia, Ltd.

  19. Recycled Water Reuse Permit Renewal Application for the Central Facilities Area Sewage Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Mike [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    This renewal application for a Recycled Water Reuse Permit is being submitted in accordance with the Idaho Administrative Procedures Act 58.01.17 “Recycled Water Rules” and the Municipal Wastewater Reuse Permit LA-000141-03 for continuing the operation of the Central Facilities Area Sewage Treatment Plant located at the Idaho National Laboratory. The permit expires March 16, 2015. The permit requires a renewal application to be submitted six months prior to the expiration date of the existing permit. For the Central Facilities Area Sewage Treatment Plant, the renewal application must be submitted by September 16, 2014. The information in this application is consistent with the Idaho Department of Environmental Quality’s Guidance for Reclamation and Reuse of Municipal and Industrial Wastewater and discussions with Idaho Department of Environmental Quality personnel.

  20. Case study application of the IAEA safeguards assessment methodology to a mixed oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Swartz, J.; McDaniel, T.

    1981-01-01

    Science Applications, Inc. has prepared a case study illustrating the application of an assessment methodology to an international system for safeguarding mixed oxide (MOX) fuel fabrication facilities. This study is the second in a series of case studies which support an effort by the International Atomic Energy Agency (IAEA) and an international Consultant Group to develop a methodology for assessing the effectiveness of IAEA safeguards. 3 refs

  1. 40 CFR 60.540 - Applicability and designation of affected facilities.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) AIR PROGRAMS (CONTINUED) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for the Rubber Tire Manufacturing Industry § 60.540 Applicability and designation of affected... each of the following affected facilities in rubber tire manufacturing plants that commence...

  2. Residential Outcomes for Nursing Facility Applicants Who Have Been Diverted: Where Are They 5 Years Later?

    Science.gov (United States)

    Chapin, Rosemary; Baca, Beth; Macmillan, Kelley; Rachlin, Roxanne; Zimmerman, Mary

    2009-01-01

    Purpose: The purpose of this longitudinal study was to determine the length of community tenure for adults aged 60 and older after application for nursing facility (NF) admission and to examine the proportion of older adults who lost community tenure due to either (a) death while a community resident or (b) permanent NF admission. Design and…

  3. Test and application of thermal neutron radiography facility at Xi'an pulsed reactor

    CERN Document Server

    Yang Jun; Zhao Xiang Feng; Wang Dao Hua

    2002-01-01

    A thermal neutron radiography facility at Xi'an Pulsed Reactor is described as well as its characteristics and application. The experiment results show the inherent unsharpness of BAS ND is 0.15 mm. The efficient thermal neutron n/gamma ratio is lower in not only steady state configuration but also pulsing state configuration and it is improved using Pb filter

  4. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-298; NRC-2013-0139] Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards..., issued to Nebraska Public Power District (the licensee), for operation of the Cooper Nuclear Station (CNS...

  5. 18 CFR 157.18 - Applications to abandon facilities or service; exhibits.

    Science.gov (United States)

    2010-04-01

    ... and terminus of all remaining facilities. (d) Exhibit W—Impact on customers whose service will be.... Applicant may use pro forma accounting entries based on estimated amounts, provided that upon consummation... the amount of federal and state income taxes to be allocated to the gain. If no allocation is to be...

  6. The Text of the Agreement for the Application of Agency Safeguards to United States Reactor Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-08-14

    The text of the Agreement between the Agency and the Government of the United States of America for the application of Agency safeguards to United States reactor facilities, which was signed on 15 June 1964 and entered into force on 1 August 1964, is reproduced in this document for the information of all Members.

  7. The Usage of Mobile Applications in Food and Beverage Facilities: An Example of Foursquare

    Directory of Open Access Journals (Sweden)

    Aydan BEKAR

    2015-12-01

    Full Text Available Foursquare application developed in 2010 in the USA, is one of the most popular locationbased check-in tools used today. Commonly used by food and beverage facilities and their customers, Foursquare app helps enterprises reach potential customers by providing real time communication with current customers for them.The purpose of this study is to determine reasons for customer preferences of using Foursquare app in food and beverage facilities and to determine customers’ suggestions and opinions on this application. The data was gathered from 670 Foursquare users with a questionnaire. During the data analysis, absolute and percent value, arithmetic mean (, standard deviation (sd, student’s t-test, one way Anova and Tukey test were used.As a result of this study, it was determined that users preferred to use Foursquare app mostly for checking-in the facilities they had been, for following other friends using this app and for discovering new food and beverage facilities. It was also found out that men used the app much more than women and most of the customers suggested that the information given by food and beverage facilities on Foursquare app had to be controlled by a complaint system and user information had to become safer on the app

  8. Probabilistic safety analysis for nuclear fuel cycle facilities, an exemplary application for a fuel fabrication plant

    International Nuclear Information System (INIS)

    Gmal, B.; Gaenssmantel, G.; Mayer, G.; Moser, E.F.

    2013-01-01

    In order to assess the risk of complex technical systems, the application of the Probabilistic Safety Assessment (PSA) in addition to the Deterministic Safety Analysis becomes of increasing interest. Besides nuclear installations this applies to e. g. chemical plants. A PSA is capable of expanding the basis for the risk assessment and of complementing the conventional deterministic analysis, by which means the existing safety standards of that facility can be improved if necessary. In the available paper, the differences between a PSA for a nuclear power plant and a nuclear fuel cycle facility (NFCF) are discussed in shortness and a basic concept for a PSA for a nuclear fuel cycle facility is described. Furthermore, an exemplary PSA for a partial process in a fuel assembly fabrication facility is described. The underlying data are partially taken from an older German facility, other parts are generic. Moreover, a selected set of reported events corresponding to this partial process is taken as auxiliary data. The investigation of this partial process from the fuel fabrication as an example application shows that PSA methods are in principle applicable to nuclear fuel cycle facilities. Here, the focus is on preventing an initiating event, so that the system analysis is directed to the modeling of fault trees for initiating events. The quantitative results of this exemplary study are given as point values for the average occurrence frequencies. They include large uncertainties because of the limited documentation and data basis available, and thus have only methodological character. While quantitative results are given, further detailed information on process components and process flow is strongly required for robust conclusions with respect to the real process. (authors)

  9. An Automated DAKOTA and VULCAN-CFD Framework with Application to Supersonic Facility Nozzle Flowpath Optimization

    Science.gov (United States)

    Axdahl, Erik L.

    2015-01-01

    Removing human interaction from design processes by using automation may lead to gains in both productivity and design precision. This memorandum describes efforts to incorporate high fidelity numerical analysis tools into an automated framework and applying that framework to applications of practical interest. The purpose of this effort was to integrate VULCAN-CFD into an automated, DAKOTA-enabled framework with a proof-of-concept application being the optimization of supersonic test facility nozzles. It was shown that the optimization framework could be deployed on a high performance computing cluster with the flow of information handled effectively to guide the optimization process. Furthermore, the application of the framework to supersonic test facility nozzle flowpath design and optimization was demonstrated using multiple optimization algorithms.

  10. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    Energy Technology Data Exchange (ETDEWEB)

    Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

    2012-11-09

    FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  11. Coffin-Siris syndrome and the BAF complex: genotype-phenotype study in 63 patients.

    Science.gov (United States)

    Santen, Gijs W E; Aten, Emmelien; Vulto-van Silfhout, Anneke T; Pottinger, Caroline; van Bon, Bregje W M; van Minderhout, Ivonne J H M; Snowdowne, Ronelle; van der Lans, Christian A C; Boogaard, Merel; Linssen, Margot M L; Vijfhuizen, Linda; van der Wielen, Michiel J R; Vollebregt, M J Ellen; Breuning, Martijn H; Kriek, Marjolein; van Haeringen, Arie; den Dunnen, Johan T; Hoischen, Alexander; Clayton-Smith, Jill; de Vries, Bert B A; Hennekam, Raoul C M; van Belzen, Martine J

    2013-11-01

    De novo germline variants in several components of the SWI/SNF-like BAF complex can cause Coffin-Siris syndrome (CSS), Nicolaides-Baraitser syndrome (NCBRS), and nonsyndromic intellectual disability. We screened 63 patients with a clinical diagnosis of CSS for these genes (ARID1A, ARID1B, SMARCA2, SMARCA4, SMARCB1, and SMARCE1) and identified pathogenic variants in 45 (71%) patients. We found a high proportion of variants in ARID1B (68%). All four pathogenic variants in ARID1A appeared to be mosaic. By using all variants from the Exome Variant Server as test data, we were able to classify variants in ARID1A, ARID1B, and SMARCB1 reliably as being pathogenic or nonpathogenic. For SMARCA2, SMARCA4, and SMARCE1 several variants in the EVS remained unclassified, underlining the importance of parental testing. We have entered all variant and clinical information in LOVD-powered databases to facilitate further genotype-phenotype correlations, as these will become increasingly important because of the uptake of targeted and untargeted next generation sequencing in diagnostics. The emerging phenotype-genotype correlation is that SMARCB1 patients have the most marked physical phenotype and severe cognitive and growth delay. The variability in phenotype seems most marked in ARID1A and ARID1B patients. Distal limbs anomalies are most marked in ARID1A patients and least in SMARCB1 patients. Numbers are small however, and larger series are needed to confirm this correlation. © 2013 WILEY PERIODICALS, INC.

  12. Incident factors in facility location: An application in the Colombian biofuel sector

    Directory of Open Access Journals (Sweden)

    Alexandra Eugenia Duarte

    2013-09-01

    Full Text Available Facility location concerns high impact strategic decision-making in supply chain design. One of the most important issues regarding such decision is a suitable selection of incident factors due to their effects on costs and customer service level. This paper was thus aimed at presenting a methodology for defining and hierarchising a group of factors which affect decision-making concerning facility location. The methodology was based on expert methods, incorporating a goal programming application extended to support weighting. Colombian biofuels sector results are presented.

  13. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    International Nuclear Information System (INIS)

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization

  14. Industrial applications at the new cold neutron radiography and tomography facility of the HMI

    International Nuclear Information System (INIS)

    Kardjilov, N.; Hilger, A.; Manke, I.; Strobl, M.; Treimer, W.; Banhart, J.

    2005-01-01

    The new cold neutron radiography and tomography facility at the Hahn-Meitner-Institut Berlin is suited for the investigation of components and materials from different industrial fields. The high-flux measuring position of the facility allows real-time imaging of fast dynamical processes. Cold neutrons interact stronger with the matter compared to thermal neutrons, which leads to a much better radiography contrast. Some examples of different industry applications like investigations on discharging of a Lithium battery or on oil sediments in a vent pipe are presented

  15. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

  16. Coffin-Siris syndrome and related disorders involving components of the BAF (mSWI/SNF) complex: historical review and recent advances using next generation sequencing.

    Science.gov (United States)

    Kosho, Tomoki; Miyake, Noriko; Carey, John C

    2014-09-01

    This issue of Seminars in Medical Genetics, American Journal of Medical Genetics Part C investigates the human diseases caused by mutations in the BAF complex (also known as the mammalian SWI/SNF complex) genes, particularly focusing on Coffin-Siris syndrome (CSS). CSS is a rare congenital malformation syndrome characterized by developmental delay or intellectual disability (ID), coarse facial appearance, feeding difficulties, frequent infections, and hypoplasia/aplasia of the fifth fingernails and fifth distal phalanges. In 2012, 42 years after the first description of CSS in 1970, five causative genes (SMARCB1, SMARCE1, SMARCA4, ARID1A, ARID1B), all encoding components of the BAF complex, were identified as being responsible for CSS through whole exome sequencing and pathway-based genetic screening. The identification of two additional causative genes (PHF6, SOX11) followed. Mutations in another BAF complex gene (SMARCA2) and (TBC1D24) were found to cause clinically similar conditions with ID, Nicolaides-Baraitser syndrome and DOORS syndrome, respectively. Also, ADNP was found to be mutated in an autism/ID syndrome. Furthermore, there is growing evidences for germline or somatic mutations in the BAF complex genes to be causal for cancer/cancer predisposition syndromes. These discoveries have highlighted the role of the BAF complex in the human development and cancer formation. The biology of BAF is very complicated and much remains unknown. Ongoing research is required to reveal the whole picture of the BAF complex in human development, and will lead to the development of new targeted therapies for related disorders in the future. © 2014 Wiley Periodicals, Inc.

  17. Hanford Central Waste Complex: Radioactive mixed waste storage facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Site is owned by the US Government and operated by the US Department of Energy Field Office, Richland. The Hanford Site manages and produces dangerous waste and mixed waste (containing both radioactive and dangerous components). The dangerous waste is regulated in accordance with the Resource Conversation and Recovery Act of 1976 and the State of Washington Hazardous Waste Management Act of 1976. The radioactive component of mixed waste is interpreted by the US Department of Energy to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous component of mixed waste is interpreted to be regulated under the Resource Conservation and Recovery Act of 1976 and Washington Administrative Code 173--303. Westinghouse Hanford Company is a major contractor to the US Department of Energy Field Office, Richland and serves as co-operator of the Hanford Central Waste Complex. The Hanford Central Waste Complex is an existing and planned series of treatment, storage, and/or disposal units that will centralize the management of solid waste operations at a single location on the Hanford facility. The Hanford Central Waste Complex units include the Radioactive Mixed Waste Storage Facility, the unit addressed by this permit application, and the Waste Receiving and Processing Facility. The Waste Receiving and Processing Facility is covered in a separate permit application submittal

  18. The application of XML in the effluents data modeling of nuclear facilities

    International Nuclear Information System (INIS)

    Yue Feng; Lin Quanyi; Yue Huiguo; Zhang Yan; Zhang Peng; Cao Jun; Chen Bo

    2013-01-01

    The radioactive effluent data, which can provide information to distinguish whether facilities, waste disposal, and control system run normally, is an important basis of safety regulation and emergency management. It can also provide the information to start emergency alarm system as soon as possible. XML technology is an effective tool to realize the standard of effluent data exchange, in favor of data collection, statistics and analysis, strengthening the effectiveness of effluent regulation. This paper first introduces the concept of XML, the choices of effluent data modeling method, and then emphasizes the process of effluent model, finally the model and application are shown, While there is deficiency about the application of XML in the effluents data modeling of nuclear facilities, it is a beneficial attempt to the informatization management of effluents. (authors)

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

    International Nuclear Information System (INIS)

    Sonnichsen, J.C.

    1997-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Sonnichsen, J.C.

    1997-08-21

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

  1. Dynamics of System of Systems and Applications to Net Zero Energy Facilities

    Science.gov (United States)

    2017-10-05

    collections and applied it in a variety of ways to energy - related problems. 1. REPORT DATE (DD-MM-YYYY) 4. TITLE AND SUBTITLE 13. SUPPLEMENTARY...UU UU 05-10-2017 1-Oct-2011 30-Sep-2016 Dynamics of System of Systems and Applications to Net Zero Energy Facilities The views, opinions and/or...Research Triangle Park, NC 27709-2211 Koopman operator analysis, Energy systems REPORT DOCUMENTATION PAGE 11. SPONSOR/MONITOR’S REPORT NUMBER(S) 10

  2. SPES: A new cyclotron-based facility for research and applications with high-intensity beams

    Science.gov (United States)

    Maggiore, M.; Campo, D.; Antonini, P.; Lombardi, A.; Manzolaro, M.; Andrighetto, A.; Monetti, A.; Scarpa, D.; Esposito, J.; Silvestrin, L.

    2017-06-01

    In 2016, Laboratori Nazionali di Legnaro (Italy) started the commissioning of a new accelerator facility based on a high-power cyclotron able to deliver proton beams up to 70 MeV of energy and 700 μA current. Such a machine is the core of the Selective Production of Exotic Species (SPES) project whose main goal is to provide exotics beam for nuclear and astrophysics research and to deliver high-intensity proton beams for medical applications and neutrons generator.

  3. ASAM - The international programme on application of safety assessment methodologies for near surface radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Batandjieva, B.

    2002-01-01

    The IAEA has launched a new Co-ordinated Research Project (CRP) on Application of Safety Assessment Methodologies for Near Surface Waste Disposal Facilities (ASAM). The CRP will focus on the practical application of the safety assessment methodology, developed under the ISAM programme, for different purposes, such as developing design concepts, licensing, upgrading existing repositories, reassessment of operating disposal facilities. The overall aim of the programme is to assist safety assessors, regulators and other specialists involved in the development and review of safety assessment for near surface disposal facilities in order to achieve transparent, traceable and defendable evaluation of safety of these facilities. (author)

  4. Facile Synthesis of Colloidal CuO Nanocrystals for Light-Harvesting Applications

    KAUST Repository

    Lim, Yee-Fun; Choi, Joshua J.; Hanrath, Tobias

    2012-01-01

    CuO is an earth-abundant, nontoxic, and low band-gap material; hence it is an attractive candidate for application in solar cells. In this paper, a synthesis of CuO nanocrystals by a facile alcohothermal route is reported. The nanocrystals are dispersible in a solvent mixture of methanol and chloroform, thus enabling the processing of CuO by solution. A bilayer solar cell comprising of CuO nanocrystals and phenyl-C61-butyric acid methyl ester (PCBM) achieved a power conversion efficiency of 0.04%, indicating the potential of this material for light-harvesting applications.

  5. Defect-induced wetting on BaF 2(111) and CaF 2(111) at ambient conditions

    Science.gov (United States)

    Cardellach, M.; Verdaguer, A.; Fraxedas, J.

    2011-12-01

    The interaction of water with freshly cleaved (111) surfaces of isostructural BaF2 and CaF2 single crystals at ambient conditions (room temperature and under controlled humidity) has been studied using scanning force microscopy in different operation modes and optical microscopy. Such surfaces exhibit contrasting behaviors for both materials: while on BaF2(111) two-dimensional water layers are formed after accumulation at step edges, CaF2(111) does not promote the formation of such layers. We attribute such opposed behavior to lattice match (mismatch) between hexagonal water ice and the hexagonal (111) surfaces of BaF2(CaF2). Optical microscope images reveal that this behavior also determines the way the surfaces become wetted at a macroscopic level.

  6. Production of lightweight ceramisite from iron ore tailings and its performance investigation in a biological aerated filter (BAF) reactor

    International Nuclear Information System (INIS)

    Liu Yangsheng; Du Fang; Yuan Li; Zeng Hui; Kong Sifang

    2010-01-01

    The few reuse and large stockpile of iron ore tailings (IOT) led to a series of social and environmental problems. This study investigated the possibility of using the IOT as one of starting materials to prepare lightweight ceramisite (LWC) by a high temperature sintering process. Coal fly ash (CFA) and municipal sewage sludge (SS) were introduced as additives. The LWC was used to serve as a biomedium in a biological aerated filter (BAF) reactor for municipal wastewater treatment, and its purification performance was examined. The effects of sintering parameters on physical properties of the LWC, and leaching concentrations of heavy metals from the LWC were also determined. The microstructure and the phase composition of the LWC were analyzed by scanning electron microscopy (SEM) and X-ray diffraction (XRD). Results revealed that: (1) IOT could be used to produce the LWC under the optimal sintering parameters; (2) the leaching concentrations of heavy metals from the LWC were well below their respective regulatory levels in the China Environmental Quality Standards for Surface Water (CEQS); and (3) the BAF reactor with the LWC serving as the biomedium achieved high removal efficiencies for COD Cr (>92%), NH 4 + -N (>62%) and total phosphate (T-P) (>63%). Therefore, the LWC produced from the IOT was suitable to serve as the biomedium in the municipal wastewater treatment.

  7. HIC1 interacts with a specific subunit of SWI/SNF complexes, ARID1A/BAF250A

    International Nuclear Information System (INIS)

    Van Rechem, Capucine; Boulay, Gaylor; Leprince, Dominique

    2009-01-01

    HIC1, a tumor suppressor gene epigenetically silenced in many human cancers encodes a transcriptional repressor involved in regulatory loops modulating p53-dependent and E2F1-dependent cell survival and stress responses. HIC1 is also implicated in growth control since it recruits BRG1, one of the two alternative ATPases (BRM or BRG1) of SWI/SNF chromatin-remodeling complexes to repress transcription of E2F1 in quiescent fibroblasts. Here, through yeast two-hybrid screening, we identify ARID1A/BAF250A, as a new HIC1 partner. ARID1A/BAF250A is one of the two mutually exclusive ARID1-containing subunits of SWI/SNF complexes which define subsets of complexes endowed with anti-proliferative properties. Co-immunoprecipitation assays in WI38 fibroblasts and in BRG1-/- SW13 cells showed that endogenous HIC1 and ARID1A proteins interact in a BRG1-dependent manner. Furthermore, we demonstrate that HIC1 does not interact with BRM. Finally, sequential chromatin immunoprecipitation (ChIP-reChIP) experiments demonstrated that HIC1 represses E2F1 through the recruitment of anti-proliferative SWI/SNF complexes containing ARID1A.

  8. Application of advanced remote systems technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at Oak Ridge National Laboratory (ORNL) has been advancing the technology of remote handling and remote maintenance for in-cell systems planned for future nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor is directly applicable to the proposed in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The application of teleoperated, force-reflecting servomanipulators with television viewing could be a major step forward in waste handling facility design. Primary emphasis in the current program is the operation of a prototype remote handling and maintenance system, the advanced servomanipulator (ASM), which specifically addresses the requirements of fuel reprocessing and waste handling with emphasis on force reflection, remote maintainability, reliability, radiation tolerance, and corrosion resistance. Concurrent with the evolution of dexterous manipulators, concepts have also been developed that provide guidance for standardization of the design of the remotely operated and maintained equipment, the interface between the maintenance tools and the equipment, and the interface between the in-cell components and the facility

  9. Insights from the Probabilistic Safety Assessment Application to Subsurface Operations at the Preclosure Facilities

    International Nuclear Information System (INIS)

    Hwang, Mee Jeong; Jung, Jong Tae

    2009-01-01

    In this paper, we present the insights obtained through the PSA (Probabilistic Safety Assessment) application to subsurface operation at the preclosure facilities of the repository. At present, medium-low level waste repository has been constructed in Korea, and studies for disposal of high level wastes are under way. Also, safety analysis for repository operation has been performed. Thus, we performed a probabilistic safety analysis for surface operation at the preclosure facilities with PSA methodology for a nuclear power plant. Since we don't have a code to analyze the waste repository safety analysis, we used the codes, AIMS (Advanced Information Management System for PSA) and FTREX (Fault Tree Reliability Evaluation eXpert) which are developed for a nuclear power plant's PSA to develop ET (Event Tree) and FT (Fault Tree), and to quantify for an example analysis

  10. Environmental risk analysis of oil handling facilities in port areas. Application to Tarragona harbor (NE Spain).

    Science.gov (United States)

    Valdor, Paloma F; Gómez, Aina G; Puente, Araceli

    2015-01-15

    Diffuse pollution from oil spills is a widespread problem in port areas (as a result of fuel supply, navigation and loading/unloading activities). This article presents a method to assess the environmental risk of oil handling facilities in port areas. The method is based on (i) identification of environmental hazards, (ii) characterization of meteorological and oceanographic conditions, (iii) characterization of environmental risk scenarios, and (iv) assessment of environmental risk. The procedure has been tested by application to the Tarragona harbor. The results show that the method is capable of representing (i) specific local pollution cases (i.e., discriminating between products and quantities released by a discharge source), (ii) oceanographic and meteorological conditions (selecting a representative subset data), and (iii) potentially affected areas in probabilistic terms. Accordingly, it can inform the design of monitoring plans to study and control the environmental impact of these facilities, as well as the design of contingency plans. Copyright © 2014 Elsevier Ltd. All rights reserved.

  11. Application of optimization modeling to groundwater remediation at US Department of Energy facilities

    International Nuclear Information System (INIS)

    Bakr, A.A.; Dal Santo, D.J.; Smalley, R.C.; Phillips, E.C.

    1988-01-01

    This paper outlines and explores the fundamentals of the current strategies for groundwater hydraulic and quality management modeling and presents a scheme for the application of such strategies to DOE facilities. The discussion focuses on the DOE-Savannah River Operations (DOE-SR) facility. Remediation of contaminated groundwater at active and abandoned waste disposal sites has become a major element of environmental programs. Traditional groundwater remediation programs (e.g., pumping and treatment) may not represent optimal water quality management strategies at sites to be remediated. Complex, interrelated environmental (geologic/geohydrologic), institutional, engineering, and economic conditions at a site may require a more comprehensive management strategy. Groundwater management models based on the principles of operations research have been developed and used to determine optimal management strategies for water resources needs and for hypothetical remediation programs. Strategies for groundwater remediation programs have ranged from the simple removal of groundwater to complex, hydraulic gradient control programs involving groundwater removal, treatment, and recharge

  12. 40 CFR Table 1 to Subpart Cccccc... - Applicability Criteria and Management Practices for Gasoline Dispensing Facilities With Monthly...

    Science.gov (United States)

    2010-07-01

    ... Criteria and Management Practices for Gasoline Dispensing Facilities With Monthly Throughput of 100,000... 40 Protection of Environment 14 2010-07-01 2010-07-01 false Applicability Criteria and Management Practices for Gasoline Dispensing Facilities With Monthly Throughput of 100,000 Gallons of Gasoline or More...

  13. Overview of the applications of cement-based immobilization technologies developed at US DOE facilities

    International Nuclear Information System (INIS)

    Dole, L.R.

    1985-01-01

    This paper briefly reviews seven cement-based waste form development programs at six of the US Department of Energy (DOE) sites. These sites have developed a variety of processes that range from producing 25-mm-(1-in.-) diam pellets in a glove box to producing 240-m-(800-ft-) diam grout sheets within the bedding planes of a deep shale formation. These successful applications of cement-based waste forms to the many radioactive waste streams from nuclear facilities bear witness to the flexibility and reliability of this class of immobilization materials. The US DOE sites and their programs are: (1) Oak Ridge National Laboratory (ORNL), Hydrofracture Grout; (2) Hanford, Transportable Grout Facility (TGF); (3) Savannah River Plant (SRP), Nitrate Saltcrete; (4) EG and G Idaho, Process Experimental Pilot Plant (PREPP); (5) Mound Laboratory (ML), Waste Pelletization Process; (6) ORNL, FUETAP Concretes, and (7) Rocky Flats Plant (RFP), Inert Carrier Concrete Process (ICCP). The major issues regarding the application of cement-based waste forms to radioactive waste management problems are also presented. These issues are (1) leachability, (2) radiation stability, (3) thermal stability, (4) phase complexity of the matrix, and (5) effects of the waste stream composition. A cursory review of current research in each of these areas is included along with a discussion of future trends in cement-based waste form developments and applications. 35 refs., 12 figs

  14. State waste discharge permit application: 200 Area Treated Effluent Disposal Facility (Project W-049H)

    International Nuclear Information System (INIS)

    1994-08-01

    As part of the original Hanford Federal Facility Agreement and Concent Order negotiations, US DOE, US EPA and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground to the Hanford Site are subject to permitting in the State Waste Discharge Permit Program (SWDP). This document constitutes the SWDP Application for the 200 Area TEDF stream which includes the following streams discharged into the area: Plutonium Finishing Plant waste water; 222-S laboratory Complex waste water; T Plant waste water; 284-W Power Plant waste water; PUREX chemical Sewer; B Plant chemical sewer, process condensate, steam condensate; 242-A-81 Water Services waste water

  15. Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

    Energy Technology Data Exchange (ETDEWEB)

    Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

    1994-08-01

    This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

  16. Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

    International Nuclear Information System (INIS)

    Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

    1994-08-01

    This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected

  17. State waste discharge permit application: 200 Area Treated Effluent Disposal Facility (Project W-049H)

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    As part of the original Hanford Federal Facility Agreement and Concent Order negotiations, US DOE, US EPA and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground to the Hanford Site are subject to permitting in the State Waste Discharge Permit Program (SWDP). This document constitutes the SWDP Application for the 200 Area TEDF stream which includes the following streams discharged into the area: Plutonium Finishing Plant waste water; 222-S laboratory Complex waste water; T Plant waste water; 284-W Power Plant waste water; PUREX chemical Sewer; B Plant chemical sewer, process condensate, steam condensate; 242-A-81 Water Services waste water.

  18. SEE cross section calibration and application to quasi-monoenergetic and spallation facilities

    Directory of Open Access Journals (Sweden)

    Alía Rubén García

    2017-01-01

    Full Text Available We describe an approach to calibrate SEE-based detectors in monoenergetic fields and apply the resulting semi-empiric responses to more general mixed-field cases in which a broad variety of particle species and energy spectra are involved. The calibration of the response functions is based both on experimental proton and neutron data and considerations derived from Monte Carlo simulations using the FLUKA code. The application environments include the quasi-monoenergetic neutrons at RCNP, the atmospheric-like VESUVIO spallation spectrum and the CHARM high-energy accelerator test facility.

  19. Review of past experiments at the FELIX facility and future plans for ITER applications

    International Nuclear Information System (INIS)

    Hua, T.Q.; Turner, L.R.

    1993-01-01

    FELIX is an experimental test facility at Argonne National Laboratory (ANL) for the study of electromagnetic effects in first wall, blanket, shield systems of fusion reactors. From 1983 to 1986 five major test series, including static and dynamic tests, were conducted and are reviewed in this paper. The dynamic tests demonstrated an important coupling effect between eddy currents and motion in a conducting structure. Recently the U.S. has proposed to the ITER Joint Central Team to use FELIX for testing mock-up components to study electromagnetic effects encountered during plasma disruptions and other off-normal events. The near and long term plans for ITER applications are discussed. (author)

  20. Facile synthesis and application of a carbon foam with large mesopores

    KAUST Repository

    Fu, Liling

    2013-01-01

    By combining elements of hard- and soft-templating, a facile synthesis method for carbon foams with large mesopores has been demonstrated. A commercial Pluronic surfactant was used as the structure-directing agent as well as the carbon precursor. No micelle swelling agent or post treatment is necessary to enlarge mesopores. As such this method requires fewer synthesis steps and is highly scalable. The as-synthesized meso-carbons showed potential applications in the fields of carbon oxide capture and lithium-sulfur batteries. © 2013 the Owner Societies.

  1. Problems and solutions in application of IEEE standards at Savannah River Site, Department of Energy (DOE) nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Y.S.; Bowers, T.L.; Chopra, B.J.; Thompson, T.T.; Zimmerman, E.W.

    1993-01-01

    The Department of Energy (DOE) Nuclear Material Production Facilities at the Savannah River Site (SRS) were designed, constructed, and placed into operation in the early 1950's, based on existing industry codes/standards, design criteria, analytical procedures. Since that time, DOE has developed Orders and Polices for the planning, design and construction of DOE Nuclear Reactor Facilities which invoke or reference commercial nuclear reactor codes and standards. The application of IEEE reactor design requirements such as Equipment Qualification, Seismic Qualification, Single Failure Criteria, and Separation Requirement, to non-reactor facilities has been a problem since the IEEE reactor criteria do not directly confirm to the needs of non-reactor facilities. SRS Systems Engineering is developing a methodology for the application of IEEE Standards to non-reactor facilities at SRS

  2. Corrective action management unit application for the Environmental Restoration Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ``Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.`` The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ``package`` for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package.

  3. Corrective action management unit application for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ''Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.'' The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ''package'' for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package

  4. Potential applications of fusion neutral beam facilities for advanced material processing

    International Nuclear Information System (INIS)

    Williams, J.M.; Tsai, C.C.; Stirling, W.L.; Whealton, J.H.

    1994-01-01

    Surface processing techniques involving high energy ion implantation have achieved commercial success for semiconductors and biomaterials. However, wider use has been limited in good part by economic factors, some of which are related to the line-of-sight nature of the beam implantation process. Plasma source ion implantation is intended to remove some of the limitations imposed by directionality of beam systems and also to help provide economies of scale. The present paper will outline relevant technologies and areas of expertise that exist at Oak Ridge National Laboratory in relation to possible future needs in materials processing. Experience in generation of plasmas, control of ionization states, pulsed extraction, and sheath physics exists. Contributions to future technology can be made either for the immersion mode or for the extracted beam mode. Existing facilities include the High Power Test Facility, which could conservatively operate at 1 A of continuous current at 100 kV delivered to areas of about 1 m 2 . Higher instantaneous voltages and currents are available with a reduced duty cycle. Another facility, the High Heat Flux Facility can supply a maximum of 60 kV and currents of up to 60 A for 2 s on a 10% duty cycle. Plasmas may be generated by use of microwaves, radio-frequency induction or other methods and plasma properties may be tailored to suit specific needs. In addition to ion implantation of large steel components, foreseeable applications include ion implantation of polymers, ion implantation of Ti alloys, Al alloys, or other reactive surfaces

  5. Security central processing unit applications in the protection of nuclear facilities

    International Nuclear Information System (INIS)

    Goetzke, R.E.

    1987-01-01

    New or upgraded electronic security systems protecting nuclear facilities or complexes will be heavily computer dependent. Proper planning for new systems and the employment of new state-of-the-art 32 bit processors in the processing of subsystem reports are key elements in effective security systems. The processing of subsystem reports represents only a small segment of system overhead. In selecting a security system to meet the current and future needs for nuclear security applications the central processing unit (CPU) applied in the system architecture is the critical element in system performance. New 32 bit technology eliminates the need for program overlays while providing system programmers with well documented program tools to develop effective systems to operate in all phases of nuclear security applications

  6. CONCERT A high power proton accelerator driven multi-application facility concept

    CERN Document Server

    Laclare, J L

    2000-01-01

    A new generation of High Power Proton Accelerator (HPPA) is being made available. It opens new avenues to a long series of scientific applications in fundamental and applied research, which can make use of the boosted flux of secondary particles. Presently, in Europe, several disciplines are preparing their project of dedicated facility, based on the upgraded performances of HPPAs. Given the potential synergies between these different projects, for reasons of cost effectiveness, it was considered appropriate to look into the possibility to group a certain number of these applications around a single HPPA: CONCERT project left bracket 1 right bracket . The ensuing 2-year feasibility study organized in collaboration between the European Spallation Source and the CEA just started. EURISOL left bracket 2 right bracket project and CERN participate in the steering committee.

  7. Benchmarking study and its application for shielding analysis of large accelerator facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee-Seock; Kim, Dong-hyun; Oranj, Leila Mokhtari; Oh, Joo-Hee; Lee, Arim; Jung, Nam-Suk [POSTECH, Pohang (Korea, Republic of)

    2015-10-15

    Shielding Analysis is one of subjects which are indispensable to construct large accelerator facility. Several methods, such as the Monte Carlo, discrete ordinate, and simplified calculation, have been used for this purpose. The calculation precision is overcome by increasing the trial (history) numbers. However its accuracy is still a big issue in the shielding analysis. To secure the accuracy in the Monte Carlo calculation, the benchmarking study using experimental data and the code comparison are adopted fundamentally. In this paper, the benchmarking result for electrons, protons, and heavy ions are presented as well as the proper application of the results is discussed. The benchmarking calculations, which are indispensable in the shielding analysis were performed for different particles: proton, heavy ion and electron. Four different multi-particle Monte Carlo codes, MCNPX, FLUKA, PHITS, and MARS, were examined for higher energy range equivalent to large accelerator facility. The degree of agreement between the experimental data including the SINBAD database and the calculated results were estimated in the terms of secondary neutron production and attenuation through the concrete and iron shields. The degree of discrepancy and the features of Monte Carlo codes were investigated and the application way of the benchmarking results are discussed in the view of safety margin and selecting the code for the shielding analysis. In most cases, the tested Monte Carlo codes give proper credible results except of a few limitation of each codes.

  8. Benchmarking study and its application for shielding analysis of large accelerator facilities

    International Nuclear Information System (INIS)

    Lee, Hee-Seock; Kim, Dong-hyun; Oranj, Leila Mokhtari; Oh, Joo-Hee; Lee, Arim; Jung, Nam-Suk

    2015-01-01

    Shielding Analysis is one of subjects which are indispensable to construct large accelerator facility. Several methods, such as the Monte Carlo, discrete ordinate, and simplified calculation, have been used for this purpose. The calculation precision is overcome by increasing the trial (history) numbers. However its accuracy is still a big issue in the shielding analysis. To secure the accuracy in the Monte Carlo calculation, the benchmarking study using experimental data and the code comparison are adopted fundamentally. In this paper, the benchmarking result for electrons, protons, and heavy ions are presented as well as the proper application of the results is discussed. The benchmarking calculations, which are indispensable in the shielding analysis were performed for different particles: proton, heavy ion and electron. Four different multi-particle Monte Carlo codes, MCNPX, FLUKA, PHITS, and MARS, were examined for higher energy range equivalent to large accelerator facility. The degree of agreement between the experimental data including the SINBAD database and the calculated results were estimated in the terms of secondary neutron production and attenuation through the concrete and iron shields. The degree of discrepancy and the features of Monte Carlo codes were investigated and the application way of the benchmarking results are discussed in the view of safety margin and selecting the code for the shielding analysis. In most cases, the tested Monte Carlo codes give proper credible results except of a few limitation of each codes

  9. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  10. The development of application technology for image processing in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Bum; Kim, Woog Ki; Sohn, Surg Won; Kim, Seung Ho; Hwang, Suk Yeoung; Kim, Byung Soo

    1991-01-01

    The object of this project is to develop application technology of image processing in nuclear facilities where image signal are used for reliability and safety enhancement of operation, radiation exposure reduce of operator, and automation of operation processing. We has studied such application technology for image processing in nuclear facilities as non-tactile measurement, remote and automatic inspection, remote control, and enhanced analysis of visual information. On these bases, automation system and real-time image processing system are developed. Nuclear power consists in over 50% share of electic power supply of our country nowdays. So, it is required of technological support for top-notch technology in nuclear industry and its related fields. Especially, it is indispensable for image processing technology to enhance the reliabilty and safety of operation, to automate the process in a place like a nuclear power plant and radioactive envionment. It is important that image processing technology is linked to a nuclear engineering, and enhance the reliability abd safety of nuclear operation, as well as decrease the dose rate. (Author)

  11. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future U.S. nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  12. Scoping-level Probabilistic Safety Assessment of a complex experimental facility: Challenges and first results from the application to a neutron source facility (MEGAPIE)

    International Nuclear Information System (INIS)

    Podofillini, L.; Dang, V.N.; Thomsen, K.

    2008-01-01

    This paper presents a scoping-level application of Probabilistic Safety Assessment (PSA) to selected systems of a complex experimental facility. In performing a PSA for this type of facility, a number of challenges arise, mainly due to the extensive use of electronic and programmable components and of one-of-a-kind components. The experimental facility is the Megawatt Pilot Target Experiment (MEGAPIE), which was hosted at the Paul Scherrer Institut (PSI). MEGAPIE demonstrated the feasibility of a liquid lead-bismuth target for spallation facilities at a proton beam power level of 1 MW. Given the challenges to estimate initiating event frequencies and failure event probabilities, emphasis is placed on the qualitative results obtainable from the PSA. Even though this does not allow a complete and appropriate characterization of the risk profile, some level of importance/significance evaluation was feasible, and practical and detailed recommendations on potential system improvements were derived. The second part of the work reports on a preliminary quantification of the facility risk. This provides more information on risk significance, which allows prioritizing the insights and recommendations obtained from the PSA. At the present stage, the limited knowledge on initiating and failure events is reflected in the uncertainties in their probabilities as well as in inputs quantified with bounding values. Detailed analyses to improve the quantification of these inputs, many of which turn out to be important contributors, were out of the scope of this study. Consequently, the reported results should be primarily considered as a demonstration of how quantification of the facility risk by a PSA can support risk-informed decisions, rather than precise figures of the facility risk

  13. A Unique TAS Setup for high multiplicity events at VECC, Kolkata using BaF2 detectors

    Directory of Open Access Journals (Sweden)

    Mukherjee G.

    2014-03-01

    Full Text Available A granular total absorption spectrometer (TAS has been developed at the Variable Energy Cyclotron Centre, Kolkata, India using 50 elements of BaF2 detectors and covering 4π. The advantage with such a granular setup is that one can get sum spectrum with the condition of different multiplicity hits in an event. It has been shown that one can get clean sum-peaks devoid of individual peaks with the choice of two or higher fold of multiplicity. The large granularity makes it a unique TAS setup particularly for the high multiplicity events. The set up has been tested using different radioactive sources with one, two or multiple γ rays in cascade. The set up is ready to be used online.

  14. Recognition of Relevant ORP, pH, and DO Bending Points in Ammonia Removal from Drinking Water through Online BAF System

    Directory of Open Access Journals (Sweden)

    Hassimi Abu Hasan

    2010-01-01

    Full Text Available This study was undertaken to identify the relevant bending points in ORP, pH, and DO profiles in ammonia removal through online monitoring. A novelty BAF system as newl application for drinking water treatment that equipped with ORP, pH, DO NH4 + and NO3 − sensors was used. Two types of polluted drinking water strength (low and high strength with various NH4 + concentrations and aeration flow were treated at a fixed-time reaction of 24 h. Experiments were conducted at four track studies (TS of TS1 (NH4 += 50 mg/L, aeration = 0.3 L/min, TS2 (NH4 + = 100 mg/L, aeration = 2.0 L/min, TS3 (NH4 += 100 mg/L, no aeration and TS4 (NH4 += 10 mg/L, aeration = 0.1 L/min. The results showed that the removal of NH4 + was more than 95% for TS1, TS2, and TS4. From the online monitoring performances, DO elbow and ammonia valley appeared in ORP and pH profiles, respectively. Similarly, new positive plateaus were observed in DO, indicating that the nitrifiers stopped to consume the DO after NH4 + was completely removed. Hence, based on the bending points, the aeration system is possible to be automatically stopped just after DO elbow and ammonia valley appears in order to save the energy consumption and to shorten the time demands for the drinking water treatment process.

  15. 40 CFR 122.24 - Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123...

    Science.gov (United States)

    2010-07-01

    ... NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM Permit Application and Special NPDES Program Requirements... 40 Protection of Environment 21 2010-07-01 2010-07-01 false Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123.25). 122.24 Section 122.24 Protection of...

  16. Safety Report within the licence application for the siting of a radioactive waste repository/disposal facility

    International Nuclear Information System (INIS)

    Horyna, J.; Sinaglova, R.

    2004-01-01

    The initial safety specification report, which is submitted to the licensing authority as one of the application documents, is the basic document assessing the planned repository/disposal facility with respect to the suitability of the chosen site for this purpose. The following topics are covered: General information; Description and evidence of suitability of the site chosen; Description and tentative assessment of the repository/disposal facility design; Tentative assessment of impacts of running the facility on the employees, general public and environment (radionuclide inventory, transport routes, radionuclide release in normal, abnormal and emergency situations); Proposed concept of repository/disposal facility shutdown; and Assessment of quality assurance in the site selection, in preparatory work for the construction of the facility and in the subsequent stages. (P.A.)

  17. Safety Assessment Methodologies and Their Application in Development of Near Surface Waste Disposal Facilities--ASAM Project

    International Nuclear Information System (INIS)

    Batandjieva, B.; Metcalf, P.

    2003-01-01

    Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years

  18. Tricobalt tetroxide nanoplate arrays on flexible conductive fabric substrate: Facile synthesis and application for electrochemical supercapacitors

    Science.gov (United States)

    Nagaraju, Goli; Ko, Yeong Hwan; Yu, Jae Su

    2015-06-01

    Tricobalt tetroxide (Co3O4) nanoplate arrays (NPAs) were synthesized on flexible conductive fabric substrate (FCFs) by a facile two-electrode system based electrochemical deposition method, followed by a simple heat treatment process. Initially, cobalt hydroxide (Co(OH)2) NPAs were electrochemically deposited on FCFs by applying an external voltage of -1.5 V for 30 min. Then, the Co3O4 NPAs on FCFs was obtained by thermal treatment of as-deposited Co(OH)2 NPAs on FCFs at 200 °C for 2 h. From the analysis of morphological and crystal properties, the Co3O4 NPAs were well integrated and uniformly covered over the entire surface of substrate with good crystallinity in the cubic phase. Additionally, the fabricated sample was directly used as a binder-free electrode to examine the feasibility for electrochemical supercapacitors using cyclic voltammetry and galvanic charge-discharge measurements in 1 M KOH electrolyte solution. The Co3O4 NPAs coated FCFs electrode exhibited a maximum specific capacitance of 145.6 F/g at a current density of 1 A/g and an excellent rate capability after 1000 cycles at a current density of 3 A/g. This facile fabrication method for integrating the Co3O4 nanostructures on FCFs could be a promising approach for advanced flexible electronic and energy-storage device applications.

  19. A facile homogeneous precipitation synthesis of NiO nanosheets and their applications in water treatment

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, Junfeng, E-mail: daidai02304@163.com [School of Chemistry and Materials Engineering, Changshu Institute of Technology, Changshu (China); Jiangsu Laboratory of Advanced Functional Materials, Changshu Institute of Technology, Changshu (China); Tan, Yang; Su, Kang; Zhao, Junjie; Yang, Chen; Sang, Lingling [School of Chemistry and Materials Engineering, Changshu Institute of Technology, Changshu (China); Lu, Hongbin [National Laboratory of Solid State Microstructures and College of Engineering and Applied Sciences, Nanjing University, Nanjing (China); Chen, JianHua [School of Chemistry and Materials Engineering, Changshu Institute of Technology, Changshu (China); Jiangsu Laboratory of Advanced Functional Materials, Changshu Institute of Technology, Changshu (China)

    2015-05-15

    Highlights: • NiO nanosheets were synthesized via a facile homogeneous precipitation method. • The NiO nanosheets have a large surface area. • This preparation method was low-cost, simple equipments, easy preparation, short reaction time and better repeatability. • The product also showed a favourable ability to remove Cr(VI) and Congo red (CR) in water treatment. - Abstract: NiO nanosheets were successfully synthesized by a facile homogeneous precipitation method with the assistance of ethanol amine. The sample was characterized by X-ray diffraction (XRD), scanning electronic microscopy (SEM), transmission electron microscopy (TEM), and nitrogen adsorption–desorption techniques. The results demonstrated that the as-prepared product was cubic NiO nanosheets with a large surface area of 170.1 m{sup 2} g{sup −1}. Further, the as-prepared product was used to investigate its potential application for wastewater treatment. The maximum adsorption capacity for Cr(VI) and Congo red (CR) on NiO nanosheets has been determined using the Langmuir equation and found to reach up to 48.98 and 167.73 mg g{sup −1}, respectively. It could be concluded that NiO nanosheets with special surface features had the potential as adsorbents for wastewater treatment.

  20. The development of mobile robot for security application and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, B. S.; Lee, Y. B.; Choi, Y. S.; Seo, Y. C.; Park, Y. M

    1999-12-01

    The use of a mobile robot system in nuclear radioactive environments has the advantage of watching and inspecting the NPP safety-related equipment systematically and repairing damaged parts efficiently, thereby enhancing the safe operations of NPPs as well as reducing significantly personnel's dose rate to radioactive environment. Key technology achieved through the development of such robotic system can be used for security application and can offer new approaches to many of the tasks faced to the industry as well. The mobile robot system was composed of a mobile subsystem, a manipulator subsystem, a control subsystem, and a sensor subsystem to use in security application and nuclear radioactive environments. The mobile subsystem was adopted to synchro-drive method to improve the mobility of it. And the manipulator subsystem was developed to minimize the weight and easy to control at remote site. Finally, we developed the USB-based robot control system considering the expandability and modularity. The developed mobile robot for inspection and security was experimented for the collision avoidance and autonomous algorithm, and then it was confirmed that the mobile robot was very effective to the security application and inspection of nuclear facilities. (author)

  1. The KAERI laser facility with temporal laser beam shaping for application's user

    International Nuclear Information System (INIS)

    Hong, Sung Ki; Kim, Min Suk; Kim, Young Won; Ko, Kwanghoon; Lim, Changhwan; Seo, Young Seok

    2008-01-01

    The Korea Atomic Energy Research Institute(KAERI)has been developed a high energy Nd:Glass laser facility(KLF)for fast ignition research and high energy physics applications at early 2008. Now, we are researching the temporal laser beam shaping for application's user. The temporal laser beam shaping has been applied to a number of industrial applications. The KLF beam shaping system with fiber based consists of two electro optic modulator with DC bias using a Mach Zehnder interferometer, an arbitrary electronic waveform generator, a continuous wavelength fiber laser source, a fiber based pulse amplification system and DC bias source to generate temporally shaped pulses with a high extinction ratio and high resolution. RF signal waveform user defined by an arbitrary electronic waveform generator is only connected to one electro optic modulator. DC bias source with auto feed back or manual controller is connected both two electro optic modulators. Emitting laser light from a continuous wavelength fiber laser source is modulated to meet a user defined laser pulse with a high extinction ratio by two electro optic modulators. Experimental results are shown in Fig.1. Figure 1(a)shows two programmed waveforms with the signal width 10ns in an arbitrary electronic waveform generator. Figure 1(b)shows output laser pulses with sub mJ energy from amplification results of the KLF beam shaping system which can control the pulse width ranges from 400ps to sub us

  2. The development of mobile robot for security application and nuclear facilities

    International Nuclear Information System (INIS)

    Kim, B. S.; Lee, Y. B.; Choi, Y. S.; Seo, Y. C.; Park, Y. M.

    1999-12-01

    The use of a mobile robot system in nuclear radioactive environments has the advantage of watching and inspecting the NPP safety-related equipment systematically and repairing damaged parts efficiently, thereby enhancing the safe operations of NPPs as well as reducing significantly personnel's dose rate to radioactive environment. Key technology achieved through the development of such robotic system can be used for security application and can offer new approaches to many of the tasks faced to the industry as well. The mobile robot system was composed of a mobile subsystem, a manipulator subsystem, a control subsystem, and a sensor subsystem to use in security application and nuclear radioactive environments. The mobile subsystem was adopted to synchro-drive method to improve the mobility of it. And the manipulator subsystem was developed to minimize the weight and easy to control at remote site. Finally, we developed the USB-based robot control system considering the expandability and modularity. The developed mobile robot for inspection and security was experimented for the collision avoidance and autonomous algorithm, and then it was confirmed that the mobile robot was very effective to the security application and inspection of nuclear facilities. (author)

  3. The evolution of the application of mobile robotics to nuclear facility operations and maintenance

    International Nuclear Information System (INIS)

    Carlton, R.E.; Bartholet, S.J.

    1987-01-01

    Application of the concept of mobile robotics to the operation and maintenance of nuclear facilities has evolved over the last four years due, in part, to the efforts of Odetics in the creation of the teleoperated legged transporter. The first step in this evolutionary process was the demonstration of the legged transporter technology, which was accomplished with the design, fabrication and testing of the Odex I functionoid. A second generation ODEX, delivered to the Robotics Technology Group at Savannah River Laboratories, represents the experimental phase of the process. This machine consists of a basic ODEX I transporter body with a unique manipulator arm mounted on a service turret. Currently, the prototype phase of the mobile robotic development effort is underway with the design of the ODEX III which includes enhanced mobility and dexterity, increased intelligence and greater strength in the manipulator arm and transporter

  4. A new and inexpensive temperature-measuring system. Application to photovoltaic solar facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bohorquez, Miguel Angel Martinez; Enrique Gomez, Juan Manuel; Andujar Marquez, Jose Manuel [Departamento de Ingenieria Electronica, de Sistemas Informaticos y Automatica, Universidad de Huelva, Carretera Huelva - Palos de la, Frontera S/N, 21819 Huelva (Spain)

    2009-06-15

    This article presents the design, construction and testing of a new and inexpensive digital sensor-based temperature-measuring system, whose principal characteristics are: precision, ease of connection, immunity to noise, remote operation and easy scaling, and all this at a very low cost. This new digital sensor-based measuring system overcomes the traditional problems of digital measuring sensors, offering characteristics similar to Pt100-based measuring systems, and therefore can be used in any installation where reliable temperature measurement is necessary. It is especially suitable for installations where cost is a deciding factor in the choice of measuring system. It presents a practical application of the developed instrumentation system for use in photovoltaic solar facilities. This new temperature-measuring system has been registered in the Spanish Patent and Trademark Office with the number P200803364. (author)

  5. German offsite accident consequence model for nuclear facilities: further development and application

    International Nuclear Information System (INIS)

    Bayer, A.

    1985-01-01

    The German Offsite Accident Consequence Model - first applied in the German Risk Study for nuclear power plants with light water reactors - has been further developed with the improvement of several important submodels in the areas of atmospheric dispersion, shielding effects of houses, and the foodchains. To aid interpretation, the presentation of results has been extended with special emphasis on the presentation of the loss of life expectancy. The accident consequence model has been further developed for application to risk assessments for other nuclear facilities, e.g., the liquid metal fast breeder reactor (SNR-300) and the high temperature gas cooled reactor. Moreover the model have been further developed in the area of optimal countermeasure strategies (sheltering, evacuation, etc.) in the case of the Central European conditions. Preliminary considerations has been performed in connection with safety goals on the basis of doses

  6. Virtual instrumentation: a new approach for control and instrumentation - application in containment studies facility

    International Nuclear Information System (INIS)

    Gole, N.V.; Shanware, V.M.; Sebastian, A.; Subramaniam, K.

    2001-01-01

    PC based data-acquisition has emerged as a rapidly developing area particularly with respect to process instrumentation. Computer based data acquisition in process instrumentation combined with Supervisory Control and Data Acquisition (SCADA) software has introduced extensive possibilities with respect to formats for presentation of information. The concept of presenting data using any instrument format with the help of software tools to simulate the instrument on screen, needs to be understood, in order to be able to make use of its vast potential. The purpose of this paper is to present the significant features of the Virtual Instrumentation concept and discuss its application in the instrumentation and control system of containment studies facility (CSF). Factors involved in the development of the virtual instrumentation based I and C system for CSF are detailed and a functional overview of the system configuration is given. (author)

  7. Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor

    International Nuclear Information System (INIS)

    Ryskamp, J.M.; Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

    1992-07-01

    This report describes the EG ampersand G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options

  8. Immobilized graphene-based composite from asphalt: Facile synthesis and application in water purification

    Energy Technology Data Exchange (ETDEWEB)

    Sreeprasad, Theruvakkattil Sreenivasan; Gupta, Soujit Sen [DST Unit on Nanoscience, Department of Chemistry, Indian Institute of Technology Madras, Chennai 600036 (India); Maliyekkal, Shihabudheen Mundampra [School of Mechanical and Building Sciences, VIT University, Chennai Campus, Chennai 600048 (India); Pradeep, Thalappil, E-mail: pradeep@iitm.ac.in [DST Unit on Nanoscience, Department of Chemistry, Indian Institute of Technology Madras, Chennai 600036 (India)

    2013-02-15

    Highlights: ► Facile strategy to make graphenic materials from cheaper precursor such as asphalt. ► Material can be made in solution; also as anchored on solid substrates. ► The synthesized material, GSC, was found to be excellent for water purification. ► The applicability was demonstrated through batch and laboratory columns experiments. ► The capacity was compared to other similar adsorbents and was found to be superior. -- Abstract: An in situ strategy for the preparation of graphene immobilized on sand using asphalt, a cheap carbon precursor is presented. The as-synthesized material was characterized in detail using various spectroscopic and microscopic techniques. The presence of G and D bands at 1578 cm{sup −1} and 1345 cm{sup −1} in Raman spectroscopy and the 2D sheet-like structure with wrinkles in transmission electron microscopy confirmed the formation of graphenic materials. In view of the potential applicability of supported graphenic materials in environmental application, the as-synthesized material was tested for purifying water. Removal of a dye (rhodamine-6G) and a pesticide (chlorpyrifos), two of the important types of pollutants of concern in water, were investigated in this study. Adsorption studies were conducted in batch mode as a function of time, particle size, and adsorbent dose. The continuous mode experiments were conducted in multiple cycles and they confirmed that the material can be used for water purification applications. The adsorption efficacy of the present adsorbent system was compared to other reported similar adsorbent systems and the results illustrated that the present materials are superior. The adsorbents were analyzed for post treatment and their reusability was evaluated.

  9. Measurement of the 241Am and the 243Am Neutron Capture Cross Sections at the n_TOF Facility at CERN

    CERN Document Server

    Mendoza, E; Guerrero, C; Altstadt, S; Andrzejewski, J; Audouin, L; Barbagallo, M; Bécares, V; Bečvář, F; Belloni, F; Berthoumieux, E; Billowes, J; Boccone, V; Bosnar, D; Brugger, M; Calviani, M; Calviño, F; Carrapiço, C; Cerutti, F; Chiaveri, E; Chin, M; Colonna, N; Cortés, G; Cortés-Giraldo, M A; Diakaki, M; Domingo-Pardo, C; Duran, I; Dressler, R; Dzysiuk, N; Eleftheriadis, C; Ferrari, A; Fraval, K; Ganesan, S; García, A R; Giubrone, G; Gómez-Hornillos, M B; Gonçalves, I F; González-Romero, E; Griesmayer, E; Gunsing, F; Gurusamy, P; Jenkins, D G; Jericha, E; Kadi, Y; Käppeler, F; Karadimos, D; Kivel, N; Koehler, P; Kokkoris, M; Korschinek, G; Krtička, M; Kroll, J; Langer, C; Lederer, C; Leeb, H; Leong, L S; Losito, R; Manousos, A; Marganiec, J; Martínez, T; Mastinu, P F; Mastromarco, M; Massimi, C; Meaze, M; Mengoni, A; Milazzo, P M; Mingrone, F; Mirea, M; Mondelaers, W; Paradela, C; Pavlik, A; Perkowski, J; Pignatari, M; Plompen, A; Praena, J; Quesada, J M; Rauscher, T; Reifarth, R; Riego, A; Roman, F; Rubbia, C; Sarmento, R; Schillebeeckx, P; Schmidt, S; Schumann, D; Tagliente, G; Tain, J L; Tarrío, D; Tassan-Got, L; Tsinganis, A; Valenta, S; Vannini, G; Variale, V; Vaz, P; Ventura, A; Versaci, R; Vermeulen, M J; Vlachoudis, V; Vlastou, R; Wallner, A; Ware, T; Weigand, M; Weiß, C; Wright, T J; Žugec, P

    2014-01-01

    The capture cross sections of Am-241 and Am-243 were measured at the n\\_TOF facility at CERN in the epithermal energy range with a BaF2 Total Absorption Calorimeter. A preliminary analysis of the Am-241 and a complete analysis of the Am-243 measurement, including the data reduction and the resonance analysis, have been performed.

  10. Facility and application of nuclear and supplementary analytical techniques at Dalat Nuclear Research Institute

    International Nuclear Information System (INIS)

    Nguyen Mong Sinh; Ho Manh Dung; Nguyen Thanh Binh

    2006-01-01

    The main applications of the nuclear and supplementary analytical techniques (N and SATs) in the Dalat Nuclear Research Institute (DNRI) and the facilities for the techniques are presented. The NATs in DNRI include the neutron activation analysis (NAA) with instrumental, radiochemical and prompt gamma methods (INAA, RNAA, PGNAA), the X-ray fluorescence analysis (XRFA) and the low-level counting and spectrometry. The sample irradiation sites for NAA, the automatic and manual pneumatic transfer systems, were installed at channels 7-1 and 13-2 and rotary rack on the Dalat research reactor. An ORTEC automatic sample changer (model ASC2) for γ-ray counting was equipped. A computer software for NAA based on the k 0 -standardization method for calculation of elemental concentration was developed. The low-level counting and spectrometry techniques have been setup. The devices required for sampling, sample preparation and data processing have also been equipped. The applications of N and SATs for determination of elemental composition, particularly important in providing data so-called trace elements, radionuclides and multi-element have been enlarged for objects of geology, archaeology, bio-agriculture, health-nutrition and environment. The implementation a quality system for N and SATs has been planned and initiated. (author)

  11. Jackson State University's Center for Spatial Data Research and Applications: New facilities and new paradigms

    Science.gov (United States)

    Davis, Bruce E.; Elliot, Gregory

    1989-01-01

    Jackson State University recently established the Center for Spatial Data Research and Applications, a Geographical Information System (GIS) and remote sensing laboratory. Taking advantage of new technologies and new directions in the spatial (geographic) sciences, JSU is building a Center of Excellence in Spatial Data Management. New opportunities for research, applications, and employment are emerging. GIS requires fundamental shifts and new demands in traditional computer science and geographic training. The Center is not merely another computer lab but is one setting the pace in a new applied frontier. GIS and its associated technologies are discussed. The Center's facilities are described. An ARC/INFO GIS runs on a Vax mainframe, with numerous workstations. Image processing packages include ELAS, LIPS, VICAR, and ERDAS. A host of hardware and software peripheral are used in support. Numerous projects are underway, such as the construction of a Gulf of Mexico environmental data base, development of AI in image processing, a land use dynamics study of metropolitan Jackson, and others. A new academic interdisciplinary program in Spatial Data Management is under development, combining courses in Geography and Computer Science. The broad range of JSU's GIS and remote sensing activities is addressed. The impacts on changing paradigms in the university and in the professional world conclude the discussion.

  12. Design considerations and analysis of potential applications of a high power ultraviolet FEL at the TESLA test facility at DESY

    International Nuclear Information System (INIS)

    Pagani, C.; Saldin, E.L.; Schneidmiller, E.A.; Yurkov, M.V.

    1999-01-01

    A possibility of constructing a high power ultraviolet free electron laser at the TESLA test facility at DESY is discussed. The proposed facility consists of a tunable master oscillator (P av ∼10 mW, P peak ∼10 kW, λ≅200-350 nm) and an FEL amplifier with a tapered undulator. The average and peak radiation power at the exit of the FEL amplifier is about 7 kW and 220 GW, respectively. Installation of such a facility can significantly extend scientific potential of the TESLA test facility. The UV free electron laser can be used to construct a polarized, monochromatic gamma-source with the ultimate yield up to 10 12 gamma-quanta per second and the maximal energy of about 100 MeV. An intensive gamma-source can also form the base for constructing the test facility for the TESLA positron generation system. Another accelerator application of the proposed facility is verification of the main technical solutions for the laser and the optical system to be used in the gamma-gamma option of the TESLA collider. A high average power UV laser is also promising for industrial applications

  13. 40 CFR 403.19 - Provisions of specific applicability to the Owatonna Waste Water Treatment Facility.

    Science.gov (United States)

    2010-07-01

    ... the Owatonna Waste Water Treatment Facility. 403.19 Section 403.19 Protection of Environment... Owatonna Waste Water Treatment Facility. (a) For the purposes of this section, the term “Participating... Industrial User discharging to the Owatonna Waste Water Treatment Facility in Owatonna, Minnesota, when a...

  14. A neutron beam facility for radioactive ion beams and other applications

    Science.gov (United States)

    Tecchio, L. B.

    1999-06-01

    In the framework of the Italian participation in the project of a high intensity proton facility for the energy amplifier and nuclear waste transmutations, LNL is involved in the design and construction of same prototypes of the injection system of the 1 GeV linac that consists of a RFQ (5 MeV, 30 mA) followed by a 100 MeV linac. This program has already been supported financially and the work is in progress. In this context LNL has proposed a project for the construction of a second generation facility for the production of radioactive ion beams (RIBs) by means of the ISOL method. The final goal is the production of neutron rich RIBs with masses ranging from 30 to 150 by using primary beams of protons, deuterons and light ions with energy of 100 MeV and 100 kW power. This project is expected to be developed in about 10 years from new and intermediate milestones and experiments are foreseen and under consideration for the next INFN five year plan (1999-2003). During that period the construction of a proton/deuteron accelerator of 10 MeV energy and 10 mA current, consisting of a RFQ (5 MeV, 30 mA) and a linac (10 MeV, 10 mA), and of a neutron area dedicated to the RIBs production and to the neutron physics, is proposed. Some remarks on the production methods will be presented. The possibility of producing radioisotopes by means of the fission induced by neutrons will be investigated and the methods of production of neutrons will be discussed. Besides the RIBs production, neutron beams for the BNCT applications and neutron physics are also planned.

  15. Environmental restoration disposal facility applicable or relevant and appropriate requirements study report. Revision 00

    International Nuclear Information System (INIS)

    Roeck, F.V.; Vedder, B.L.; Rugg, J.E.

    1995-10-01

    The Environmental Restoration Disposal Facility (ERDF) will be a landfill authorized under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and will comply with the Resource Conservation and Recovery Act of 1976 (RCRA) substantive requirements. The facility will also comply with applicable or relevant and appropriate requirements (ARAR), including portions of the U.S. Environmental Protection Agency (EPA) regulations, Washington Administrative Code (WAC), and to-be-considered (TBC) elements such as U.S. Department of Energy (DOE) Orders. In considering the requirements of CERCLA, a detailed analysis of various alternatives for ERDF was completed using the nine CERCLA criteria, National Environmental Policy Act of 1969 (NEPA), and public comments. The ERDF record of decision (ROD) selected an alternative that includes a RCRA-compliant double-lined trench for the disposal of radioactive, hazardous, and mixed wastes resulting from the remediation of operable units (OU) within the National Priorities List (NPL) sites in the 100, 200, and 300 Areas. Only wastes resulting from the remediation of Hanford NPL sites will be allowed in the ERDF. Of the various siting and design alternatives proposed for ERDF, the selected alternative provides the best combination of features by balancing the nine CERCLA criteria, ARAR compliance, environmentally protective site, and various stakeholder and public recommendations. The ERDF trench design, compliant with RCRA Subtitle C minimum technical requirements (MTR), will be double lined and equipped with a leachate collection system. This design provides a more reliable system to protect groundwater than other proposed alternatives. The ERDF is located on the Hanford Site Central Plateau, southeast of the 200 West Area

  16. Application of accident progression event tree technology to the Savannah River Site Defense Waste Processing Facility SAR analysis

    International Nuclear Information System (INIS)

    Brandyberry, M.D.; Baker, W.H.; Wittman, R.S.; Amos, C.N.

    1993-01-01

    The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their facilities. This paper describes the application of an extension of the Accident Progression Event Tree (APET) approach to accidents at the SRS DWPF. The APET technique allows an integrated model of the facility risk to be developed, where previous probabilistic accident analyses have been limited to the quantification of the frequency and consequences of individual accident scenarios treated independently. Use of an APET allows a more structured approach, incorporating both the treatment of initiators that are common to more than one accident, and of accident progression at the facility

  17. Use of highly pressurized liquid nitrogen technology for concrete scabbling application at SICN nuclear facility - 59282

    International Nuclear Information System (INIS)

    Moggia, Fabrice; Vaudey, Claire-Emilie; Damerval, Frederique; Varet, Thierry; Toulemonde, Valerie; Richard, Frederic; Anderson, Gary

    2012-01-01

    The decommissioning process is a quite long and complicated stage who may take few years or decades to be achieved. Generally, this process involves the implementation of a large number of technologies dedicated to cutting and decontamination operations. Based on this finding, the Clean- Up Business Unit of AREVA with Air Liquide decided to start the development of a new technology based on the use of liquid nitrogen (-140 deg. C / 3500 bar). The NitroJet R process is a quite interesting and promising technology. It can be used, as we described in this document, for concrete scabbling operations but also for decontamination and cutting applications. The Clean-Up Business Unit, with its partner Air Liquide, realized a complete study of this technology including several tests and optimizations to be able to handle it in a nuclear environment. Thus, we did: - increase of the reliability of the machine, - nuclearization of the system (including the development of efficient shroud system and efficient HP pipes insulation); - development of a dedicated bearer for automatic configuration; - optimization of parameters for D and D applications. As we already mentioned, NitroJet R technology showed promising perspectives as: - economic: increase of rate processing, decrease in site monitoring costs, - environmental: use of an inert gas, no secondary waste generation, non use of chemical, dry process, - social: less strenuous work, decrease of operator dosimetry compatible with ALARA principle The future for the NitroJet R technology will be its implementation in a real high level activity environment. This process will be used in spring 2012 in AREVA nuclear reprocessing facility of La Hague (France) to accomplish concrete scabbling applications. This test will be the last of a long development period before industrial exploitation. (authors)

  18. Complex refractive index measurements for BaF 2 and CaF 2 via single-angle infrared reflectance spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Kelly-Gorham, Molly Rose K.; DeVetter, Brent M.; Brauer, Carolyn S.; Cannon, Bret D.; Burton, Sarah D.; Bliss, Mary; Johnson, Timothy J.; Myers, Tanya L.

    2017-10-01

    We have re-investigated the optical constants n and k for the homologous series of inorganic salts barium fluoride (BaF2) and calcium fluoride (CaF2) using a single-angle near-normal incidence reflectance device in combination with a calibrated Fourier transform infrared (FTIR) spectrometer. Our results are in good qualitative agreement with most previous works. However, certain features of the previously published data near the reststrahlen band exhibit distinct differences in spectral characteristics. Notably, our measurements of BaF2 do not include a spectral feature in the ~250 cm-1 reststrahlen band that was previously published. Additionally, CaF2 exhibits a distinct wavelength shift relative to the model derived from previously published data. We confirmed our results with recently published works that use significantly more modern instrumentation and data reduction techniques

  19. Biodegradation behavior of natural organic matter (NOM) in a biological aerated filter (BAF) as a pretreatment for ultrafiltration (UF) of river water

    KAUST Repository

    Huang, Guocheng

    2011-04-15

    In this study, biodegradation of natural organic matter (NOM) in a biological aerated filter (BAF) as pretreatment of UF treating river water was investigated. Photometric measurement, three-dimensional excitation-emission matrix (EEM) fluorescence spectroscopy and liquid chromatography with online organic carbon detector (LC-OCD) were used to investigate the fate of NOM fractions in the BAF+UF process. Results showed that the BAF process could effectively remove particles and parts of dissolved organic matter, which led to a lower NOM loading in the UF system, but different NOM fractions showed different biodegradation potentials. Further biodegradation batch experiments confirmed this observation and identified that polysaccharides and proteins (quantified using photometric methods) contained a large proportion of readily biodegradable matter while humic substances were mainly composed of inert organic substances. According to EEM measurements, it is evident that protein-like substances were more readily eliminated by microorganisms than humic-like substances. LC-OCD data also supported the phenomena that the polysaccharides and large-size proteins were more degradable than humic substances. © 2011 Springer-Verlag.

  20. Research on sludge-fly ash ceramic particles (SFCP) for synthetic and municipal wastewater treatment in biological aerated filter (BAF).

    Science.gov (United States)

    Zhao, Yaqin; Yue, Qinyan; Li, Renbo; Yue, Min; Han, Shuxin; Gao, Baoyu; Li, Qian; Yu, Hui

    2009-11-01

    Sludge-fly ash ceramic particles (SFCP) and clay ceramic particles (CCP) were employed in two lab-scale up-flow biological aerated filters (BAF) for wastewater treatment to investigate the availability of SFCP used as biofilm support compared with CCP. For synthetic wastewater, under the selected hydraulic retention times (HRT) of 1.5, 0.75 and 0.37 h, respectively, the removal efficiencies of chemical oxygen demand (COD(Cr)) and ammonium nitrogen (NH(4)(+)-N) in SFCP reactor were all higher than those of CCP reactor all through the media height. Moreover, better capabilities responding to loading shock and faster recovery after short intermittence were observed in the SFCP reactor compared with the CCP reactor. For municipal wastewater treatment, which was carried out under HRT of 0.75 h, air-liquid ratio of 7.5 and backwashing period of 48 h, the SFCP reactor also performed better than the CCP reactor, especially for the removal of NH(4)(+)-N.

  1. The Text of the Agreement for the Application of Agency Safeguards to Four United States Reactor Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-05-24

    The text of the Agreement between the Agency and the United States of America for the application of Agency safeguards to four United States reactor facilities, which was signed on 30 March 1962 and will enter into force on 1 June 1962, is reproduced in this document for the information of all Members of the Agency.

  2. Overview of Nintendo WiiTM use and potential applications for the Microsoft KinectTM in residential facilities

    NARCIS (Netherlands)

    C.A: Greenlay; H.R. Marston; J. van Hoof

    2013-01-01

    Marston, H.R., Greenlay, C.A., van Hoof, J. (2013) Overview of Nintendo WiiTM use and potential applications for the Microsoft KinectTM in residential facilities. Technology and Disability 25(2):77-85 doi: 10.3233/TAD-130369

  3. Study on the Application of PSA Method on Non-Nuclear Industry Facilities

    International Nuclear Information System (INIS)

    Andi Sofrany E; Anhar R Antariksawan; Sony T, D.T.; Puradwi IW; Sugiyanto; Giarno

    2003-01-01

    A preliminary study related to utilization of probabilistic method in non-nuclear industry facilities has been conducted The study has been performed by examining literature studies and results of research paper related to the topic. The objective of this study is to know how far the method, which is a standard in the nuclear industry, is applied in the non-nuclear fields. The PSA application in the non-nuclear process industry is mainly performed as risk management. The concept of risk management enables a systematic and realistic framework to be established for accident prevention as a whole process of hazard identification, risk estimation, risk evaluation, control measures establishment, its implementation. The most important part of this study is indeed the hazard identification and risk estimation in order to assess the consequences and to estimate event probability. The risk assessment methodology, which is also used in the probabilistic assessment of nuclear and non-nuclear industry, is performed both quantitatively and qualitatively approached by several technique analysis. Based on literature and research paper study, there are 3 main technique analysis, which can be applied in the risk management of non-nuclear industry, which are fault tree analysis (FTA), event tree analysis (ETA), and Hazard and Operability Studies (HAZOPS). The potential hazard arise in the non-nuclear process industry are flammability hazard; toxicity hazard; reactivity hazard; and elevated pressure hazard The fault tree analysis has been practically applied in the petroleum industry, chemical industry, and also other industry for improvement of safety installation by modification in the installation design or operation procedures. The event tree analysis has been applied only limited in the chemical process industry or other process industry. On the other application, HAZOPS technique can be combined with the event tree analysis with approach of accident scenario identification

  4. Materials science and biophysics applications at the ISOLDE radioactive ion beam facility

    Energy Technology Data Exchange (ETDEWEB)

    Wahl, U., E-mail: uwahl@itn.pt [Instituto Tecnologico e Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal); Centro de Fisica Nuclear da Universidade de Lisboa, Av. Prof. Gama Pinto 2, 1649-003 Lisboa (Portugal)

    2011-12-15

    The ISOLDE isotope separator facility at CERN provides a variety of radioactive ion beams, currently more than 800 different isotopes from {approx}70 chemical elements. The radioisotopes are produced on-line by nuclear reactions from a 1.4 GeV proton beam with various types of targets, outdiffusion of the reaction products and, if possible, chemically selective ionisation, followed by 60 kV acceleration and mass separation. While ISOLDE is mainly used for nuclear and atomic physics studies, applications in materials science and biophysics account for a significant part (currently {approx}15%) of the delivered beam time, requested by 18 different experiments. The ISOLDE materials science and biophysics community currently consists of {approx}80 scientists from more than 40 participating institutes and 21 countries. In the field of materials science, investigations focus on the study of semiconductors and oxides, with the recent additions of nanoparticles and metals, while the biophysics studies address the toxicity of metal ions in biological systems. The characterisation methods used are typical radioactive probe techniques such as Moessbauer spectroscopy, perturbed angular correlation, emission channeling, and tracer diffusion studies. In addition to these 'classic' methods of nuclear solid state physics, also standard semiconductor analysis techniques such as photoluminescence or deep level transient spectroscopy profit from the application of radioactive isotopes, which helps them to overcome their chemical 'blindness' since the nuclear half life of radioisotopes provides a signal that changes in time with characteristic exponential decay or saturation curves. In this presentation an overview will be given on the recent research activities in materials science and biophysics at ISOLDE, presenting some of the highlights during the last five years, together with a short outlook on the new developments under way.

  5. Polyurethane-acrylate-based hydrophobic film: Facile fabrication, characterization, and application

    Science.gov (United States)

    Park, Jongsung; Nguyen, Bui Quoc Huy; Kim, Ji-Kwan; Shanmugasundaram, Arunkumar; Lee, Dong-Weon

    2018-06-01

    Polyurethane-acrylate (PUA) is a versatile UV-curable polymer with a short curing time at room temperature, whose surface structure can be flexibly modified by applying various micropatterns. In this paper, we propose a facile and cost-effective fabrication method for the continuous production of an optically transparent PUA-based superhydrophobic thin film. Poly(dimethylsiloxane) (PDMS) was employed as a soft mold for the fabrication of PUA films through the roll-to-roll technique. In addition, nanosilica was spray-coated onto the PUA surface to further improve the hydrophobicity. The fabricated PUA thin film showed the highest static water contact angle (WCA) of ∼140°. The high durability of the PUA film was also demonstrated through mechanical impacting tests. Furthermore, only ∼2% of voltage loss was observed in the solar panel covered with the PUA-based superhydrophobic film. These obtained results indicate the feasibility of applying the film as a protective layer in applications requiring a high transparency and a self-cleaning effect.

  6. A fuzzy logic based method to monitor organizational resilience: application in a brazilian radioactive facility

    International Nuclear Information System (INIS)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Carvalho, Paulo V.R.; Vidal, Mario C.R.; Cosenza, Carlos A.N.

    2013-01-01

    Resilience is the intrinsic ability of a system to adjust its functioning prior to, during, or following changes and disturbances, so that it can sustain required operations under expected and unexpected conditions. This definition focuses on the ability to function, rather than on being impervious to failure, and thereby overcomes the traditional conflict between productivity and safety. Resilience engineering (RE) has fast become recognized as a valuable complement to the established approaches to safety of complex socio-technical systems and methods to monitor organizational resilience are needed. However, few, if any, comprehensive and systematic research studies focus on developing an objective, reliable and practical assessment model for monitoring organizational resilience. Most methods cannot fully solve the subjectivity of resilience evaluation. In order to remedy this deficiency, the aim of this research is to adopt a Fuzzy Set Theory (FST) approach to establish a method for resilience assessment in organizations based on leading safety performance indicators, defined according to the resilience engineering principles. The method uses FST concepts and properties to model the indicators and to assess the results of their application. To exemplify the method we performed an exploratory case study at the process of radiopharmaceuticals dispatch package of a Brazilian radioactive facility. (author)

  7. Facile and Scalable Preparation of Fluorescent Carbon Dots for Multifunctional Applications

    Directory of Open Access Journals (Sweden)

    Dan Wang

    2017-06-01

    Full Text Available The synthesis of fluorescent nanomaterials has received considerable attention due to the great potential of these materials for a wide range of applications, from chemical sensing through bioimaging to optoelectronics. Herein, we report a facile and scalable approach to prepare fluorescent carbon dots (FCDs via a one-pot reaction of citric acid with ethylenediamine at 150 °C under ambient air pressure. The resultant FCDs possess an optical bandgap of 3.4 eV and exhibit strong excitation-wavelength-independent blue emission (λEm = 450 nm under either one- or two-photon excitation. Owing to their low cytotoxicity and long fluorescence lifetime, these FCDs were successfully used as internalized fluorescent probes in human cancer cell lines (HeLa cells for two-photon excited imaging of cells by fluorescence lifetime imaging microscopy with a high-contrast resolution. They were also homogenously mixed with commercial inks and used to draw fluorescent patterns on normal papers and on many other substrates (e.g., certain flexible plastic films, textiles, and clothes. Thus, these nanomaterials are promising for use in solid-state fluorescent sensing, security labeling, and wearable optoelectronics.

  8. An operator training simulator based on interactive virtual teleoperation: nuclear facilities maintenance applications

    International Nuclear Information System (INIS)

    Kim, Ki Ho; Kim, Seung Ho

    1997-01-01

    Remote manipulation in nuclear hazardous environment is very often complex and difficult to operate and requires excessively careful preparation. Remote slave manipulators for unstructured work are manually controlled by a human operator. Small errors made by the operator via the master manipulator during operation can cause the slave to be surffered from excessive forces and result in considerable damages to the slave iteself and its environment. In this paper, we present a prototype of an operator training simulator for use in nuclear facilities maintenance applications, as part of the ongoing Nuclear Robotics Development Program at Korea Atomic Energy Research Institute (KAERI). The operator training simulator provides a means by which, in virtual task simulation, the operator can try out and train for expected remote tasks that the real slave manipulator will perform in advance. The operator interacts with both the virtual slave and task environment through the real master. Virtual interaction force feedback is provided to the operator. We also describe a man-in-the loop control scheme to realize bilateral force reflection in virtual teleoperation

  9. Application of the finite element groundwater model FEWA to the engineered test facility

    International Nuclear Information System (INIS)

    Craig, P.M.; Davis, E.C.

    1985-09-01

    A finite element model for water transport through porous media (FEWA) has been applied to the unconfined aquifer at the Oak Ridge National Laboratory Solid Waste Storage Area 6 Engineered Test Facility (ETF). The model was developed in 1983 as part of the Shallow Land Burial Technology - Humid Task (ONL-WL14) and was previously verified using several general hydrologic problems for which an analytic solution exists. Model application and calibration, as described in this report, consisted of modeling the ETF water table for three specialized cases: a one-dimensional steady-state simulation, a one-dimensional transient simulation, and a two-dimensional transient simulation. In the one-dimensional steady-state simulation, the FEWA output accurately predicted the water table during a long period in which there were no man-induced or natural perturbations to the system. The input parameters of most importance for this case were hydraulic conductivity and aquifer bottom elevation. In the two transient cases, the FEWA output has matched observed water table responses to a single rainfall event occurring in February 1983, yielding a calibrated finite element model that is useful for further study of additional precipitation events as well as contaminant transport at the experimental site

  10. New applications of 14C measurements at the Lund AMS Facility

    International Nuclear Information System (INIS)

    Stenstroem, K.

    1995-11-01

    Some new applications of accelerator mass spectroscopy (AMS) with 14 C are presented. In the first part the sample preparation used for production of elemental carbon at the Lund AMS facility is described. The second part concerns the release of 14 C from nuclear power plants. In a one-year study, the total airborne discharge of 14 C from two Swedish reactors was measured. In another study, the fraction of 14 CO 2 of the total airborne 14 C release was determined. The third part of the thesis involves the use of 14 C in nuclear medicine. The long-term retention of 14 C-labelled triolein after a fat-malabsorption test has been investigated by means of AMS by analysis of expired CO 2 . The possibilities of using ultra-low amounts of activity for fat-malabsorption tests, employing AMS technique, is demonstrated. In the last part AMS and 14 C-labelled tracers are used in food chemistry studies of interactions between foods and packaging materials. 22 refs, 8 figs, 2 tabs

  11. Facile combustion synthesis of ZnO nanoparticles using Cajanus cajan (L.) and its multidisciplinary applications

    Energy Technology Data Exchange (ETDEWEB)

    Manjunath, K.; Ravishankar, T.N. [Centre for Nano and Material Sciences, Jain University, Jakkasandra, Kanakapura Talluk (India); Kumar, Dhanith [Department of Chemistry, B.M.S. Instsitute of Technology, Yelahanka, Bangalore (India); Priyanka, K.P; Varghese, Thomas [Nanoscience Research Centre, Department of Physics, Nirmala College, Muvattupuzha, Kerala (India); Naika, H.Raja [Department of Studies and Research in Environmental Science, Tumkur University, Tumkur (India); Nagabhushana, H. [CNR Rao Center for Advanced Materials, Tumkur University, Tumkur (India); Sharma, S.C. [Chattisgarh Swami Vivekananda Technical University, Bhilai (India); Dupont, J. [Institute of Chemistry, Laboratory of Molecular Catalysis, UFRGS, Porto Alegre (Brazil); Ramakrishnappa, T. [Centre for Nano and Material Sciences, Jain University, Jakkasandra, Kanakapura Talluk (India); Nagaraju, G., E-mail: nagarajugn@rediffmail.com [Department of Chemistry, B.M.S. Instsitute of Technology, Yelahanka, Bangalore (India)

    2014-09-15

    Graphical abstract: Facile combustion synthesis of ZnO nanoparticles using Cajanuscajan (L.) and its multidisciplinary applications.Zinc oxide nanoparticles were successfully synthesized by solution combustion method (SCM) using pigeon pea as a combustible fuel for the first time. The as-prepared product shows good photocatalytic, dielectric, antibacterial, electrochemical properties. - Highlights: • ZnO Nps were synthesized via combustion method using pigeon pea as a fuel. • The structure of the product was confirmed by XRD technique. • The morphology was confirmed by SEM and TEM images. • The as-prepared product shown good photocatalytic activity, dielectric property. • It has also shown good antibacterial and electrochemical properties. - Abstract: Zinc oxide nanoparticles (ZnO Nps) were successfully synthesized by solution combustion method (SCM) using pigeon pea as a fuel for the first time. X-Ray diffraction pattern reveals that the product belongs to hexagonal system. FTIR spectrum of ZnO Nps shows the band at 420 cm{sup −1} associated with the characteristic vibration of Zn–O. TEM images show that the nanoparticles are found to be ∼40–80 nm. Furthermore, the as-prepared ZnO Nps exhibits good photocatalytic activity for the photodegradation of methylene blue (MB), indicating that they are indeed a promising photocatalytic semiconductor. The antibacterial properties of ZnO nanopowders were investigated by their bactericidal activity against four bacterial strains.

  12. Development of containment system for application to decommissioning of nuclear facilities. 2

    International Nuclear Information System (INIS)

    Mizuno, Oichi; Iwasaki, Yukio; Miyao, Hidehiko; Uchikoshi, Tadaaki; Furuya, Hirotaka; Kamata, Hirofumi

    1998-01-01

    New greenhouse/containment was developed to apply for confining the radioactive materials and preventing the dispersion of radioactive contamination during the maintenance and dismantling of the nuclear facility. The pressed-air tubes for columns and beams of the structure frame were applied and the vinyl chloride sheet reinforced with the polyester fiber was used as a canvas of wall and ceiling. This canvas is possible to use repeatedly and has high efficiency of safe enclosing. The containment can be easily assembled and disassembled by charge and discharge of the pressed air in the tubes of columns and beams. Two standard units (2.5mL x 2.5mW x 2.5mH, 5mL x 5mW x 2.5mH) are prepared, and lateral connection of these standard units makes it applicable to the wide working area. Expansion model up to 5m in height is also available. (author)

  13. 237 Np analytical method using 239 Np tracers and application to a contaminated nuclear disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Snow, Mathew S.; Morrison, Samuel S.; Clark, Sue B.; Olson, John E.; Watrous, Matthew G.

    2017-06-01

    Environmental 237Np analyses are challenged by low 237Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237Np analytical approach employing the short lived 239Np (t1/2 = 2.3 days) as a chemical yield tracer followed by 237Np quantification using inductively coupled plasma-mass spectrometry. 239Np tracer is obtained via separation from a 243Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 watt “Walmart” microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 106 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237Np contamination within 600 meters of this site, with maximum 237Np concentrations on the order of 103 times greater than nuclear weapons testing fallout levels.

  14. Facile combustion synthesis of ZnO nanoparticles using Cajanus cajan (L.) and its multidisciplinary applications

    International Nuclear Information System (INIS)

    Manjunath, K.; Ravishankar, T.N.; Kumar, Dhanith; Priyanka, K.P; Varghese, Thomas; Naika, H.Raja; Nagabhushana, H.; Sharma, S.C.; Dupont, J.; Ramakrishnappa, T.; Nagaraju, G.

    2014-01-01

    Graphical abstract: Facile combustion synthesis of ZnO nanoparticles using Cajanuscajan (L.) and its multidisciplinary applications.Zinc oxide nanoparticles were successfully synthesized by solution combustion method (SCM) using pigeon pea as a combustible fuel for the first time. The as-prepared product shows good photocatalytic, dielectric, antibacterial, electrochemical properties. - Highlights: • ZnO Nps were synthesized via combustion method using pigeon pea as a fuel. • The structure of the product was confirmed by XRD technique. • The morphology was confirmed by SEM and TEM images. • The as-prepared product shown good photocatalytic activity, dielectric property. • It has also shown good antibacterial and electrochemical properties. - Abstract: Zinc oxide nanoparticles (ZnO Nps) were successfully synthesized by solution combustion method (SCM) using pigeon pea as a fuel for the first time. X-Ray diffraction pattern reveals that the product belongs to hexagonal system. FTIR spectrum of ZnO Nps shows the band at 420 cm −1 associated with the characteristic vibration of Zn–O. TEM images show that the nanoparticles are found to be ∼40–80 nm. Furthermore, the as-prepared ZnO Nps exhibits good photocatalytic activity for the photodegradation of methylene blue (MB), indicating that they are indeed a promising photocatalytic semiconductor. The antibacterial properties of ZnO nanopowders were investigated by their bactericidal activity against four bacterial strains

  15. An application of data processing in the radiation measuring means near the nuclear facilities

    International Nuclear Information System (INIS)

    Joffre, H.

    1979-01-01

    The utilization of digital techniques in health physics is becoming general. A recent application, described here, is the realization of the radiation monitoring panel TCR in a building at the 'Centre d'Etudes Nucleaires Saclay'. This building, run by the 'Departement des Rayonnements Ionisants', produces radioelements used in research, medicine and industry. The TCR as designed and built includes 120 measuring channels, its centralizer unit comprises two computers, three visualization screens, two fast printers, a curve plotting table and a recording disc. After some months in operation, this facility proves to be very efficient in its monitoring function by providing new indications, the most important of which is the virtually immediate indication of the level of air contamination by radioactive aerosols in the working areas and in the gas effluents. The data processing by two computers and the super-dimensioned peripherals also appear to ensure an excellent reliability of the whole unit. Finally, in comparison with conventional TCRs, this new installation has very good operational and reliability characteristics in spite of a markedly lower cost [fr

  16. A fuzzy logic based method to monitor organizational resilience: application in a brazilian radioactive facility

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Carvalho, Paulo V.R., E-mail: grecco@ien.gov.br, E-mail: luquetti@ien.gov.br, E-mail: paulov@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana; Vidal, Mario C.R.; Cosenza, Carlos A.N., E-mail: mvidal@ergonomia.ufrj.br, E-mail: cosenza@pep.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (PEP/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia de Producao

    2013-07-01

    Resilience is the intrinsic ability of a system to adjust its functioning prior to, during, or following changes and disturbances, so that it can sustain required operations under expected and unexpected conditions. This definition focuses on the ability to function, rather than on being impervious to failure, and thereby overcomes the traditional conflict between productivity and safety. Resilience engineering (RE) has fast become recognized as a valuable complement to the established approaches to safety of complex socio-technical systems and methods to monitor organizational resilience are needed. However, few, if any, comprehensive and systematic research studies focus on developing an objective, reliable and practical assessment model for monitoring organizational resilience. Most methods cannot fully solve the subjectivity of resilience evaluation. In order to remedy this deficiency, the aim of this research is to adopt a Fuzzy Set Theory (FST) approach to establish a method for resilience assessment in organizations based on leading safety performance indicators, defined according to the resilience engineering principles. The method uses FST concepts and properties to model the indicators and to assess the results of their application. To exemplify the method we performed an exploratory case study at the process of radiopharmaceuticals dispatch package of a Brazilian radioactive facility. (author)

  17. 237Np analytical method using 239Np tracers and application to a contaminated nuclear disposal facility.

    Science.gov (United States)

    Snow, Mathew S; Morrison, Samuel S; Clark, Sue B; Olson, John E; Watrous, Matthew G

    2017-06-01

    Environmental 237 Np analyses are challenged by low 237 Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237 Np analytical approach employing the short lived 239 Np (t 1/2  = 2.3 days) as a chemical yield tracer followed by 237 Np quantification using inductively coupled plasma-mass spectrometry. 239 Np tracer is obtained via separation from a 243 Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 W "Walmart" microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 10 6 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237 Np contamination within 600 m of this site, with maximum 237 Np concentrations on the order of 10 3 times greater than nuclear weapons testing fallout levels. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. Applicability of base-isolation R and D in non-reactor facilities to a nuclear reactor plant

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1989-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. This paper reviews the research and development (R and D) programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R and D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R and D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant

  19. Application of FEPs analysis to identify research priorities relevant to the safety case for an Australian radioactive waste facility

    International Nuclear Information System (INIS)

    Payne, T.E.; McGlinn, P.J.

    2007-01-01

    The Australian Nuclear Science and Technology Organisation (ANSTO) has established a project to undertake research relevant to the safety case for the proposed Australian radioactive waste facility. This facility will comprise a store for intermediate level radioactive waste, and either a store or a near-surface repository for low-level waste. In order to identify the research priorities for this project, a structured analysis of the features, events and processes (FEPs) relevant to the performance of the facility was undertaken. This analysis was based on the list of 137 FEPs developed by the IAEA project on 'Safety Assessment Methodologies for Near Surface Disposal Facilities' (ISAM). A number of key research issues were identified, and some factors which differ in significance for the store, compared to the repository concept, were highlighted. For example, FEPs related to long-term groundwater transport of radionuclides are considered to be of less significance for a store than a repository. On the other hand, structural damage from severe weather, accident or human interference is more likely for a store. The FEPs analysis has enabled the scientific research skills required for the inter-disciplinary project team to be specified. The outcomes of the research will eventually be utilised in developing the design, and assessing the performance, of the future facility. It is anticipated that a more detailed application of the FEPs methodology will be undertaken to develop the safety case for the proposed radioactive waste management facility. (authors)

  20. Near-surface facilities for disposal radioactive waste from non-nuclear application

    International Nuclear Information System (INIS)

    Barinov, A.

    2000-01-01

    The design features of the near-surface facilities of 'Radon', an estimation of the possible emergency situations, and the scenarios of their progress are given. The possible safety enhancing during operation of near-surface facilities, so called 'Historical facilities', and newly developed ones are described. The Moscow SIA 'Radon' experience in use of mobile module plants for liquid radioactive waste purification and principal technological scheme of the plant are presented. Upgrading of the technological scheme for treatment and conditioning of radioactive waste for new-developed facilities is shown. The main activities related to management of spent ionizing sources are mentioned

  1. Development, application, and validation of a survey for infectious disease control practices at equine boarding facilities.

    Science.gov (United States)

    Kirby, Alanna T; Traub-Dargatz, Josie L; Hill, Ashley E; Kogan, Lori R; Morley, Paul S; Heird, James C

    2010-11-15

    To develop a questionnaire for self-assessment of biosecurity practices at equine boarding facilities and to evaluate infectious disease control practices in these facilities in Colorado. Cross-sectional study. 64 equine boarding facilities in Colorado. Survey questions were rated according to importance for prevention and containment of equine infectious diseases. Point values (range, 0 to 20) were assigned for possible responses, with greater values given for optimal infection control methods. Questionnaires were mailed to equine boarding facilities in Colorado advertised on the World Wide Web. Survey responses were compared with assessments made by a member of the research team during visits to 30 randomly selected facilities. Agreement among results was analyzed via a kappa test and rated as poor, fair, moderate, substantial, or nearly perfect. Survey responses were received for 64 of 163 (39%) equine boarding facilities. Scores ranged from 106 to 402 points (maximum possible score, 418). Most facilities received better scores for movement and housing of equids than for other sections of the survey. Respondents at 24 of 48 (50%) facilities that routinely received new equids reported isolation of new arrivals. Agreement between self-assessment by survey respondents and evaluation by a member of the research team was determined to be fair to substantial. Most equine boarding facilities have opportunities to improve measures for prevention or containment of contagious diseases (eg, isolation of newly arrived equids and use of written health management protocols). Most self-assessments of infection control practices were accurate.

  2. Applicability of base-isolation R ampersand D in non-reactor facilities to a nuclear reactor plant

    International Nuclear Information System (INIS)

    Seidensticker, R.W.; Chang, Y.W.

    1990-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R ampersand D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R ampersand D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R ampersand D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R ampersand D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs

  3. Enabling Extreme Scale Earth Science Applications at the Oak Ridge Leadership Computing Facility

    Science.gov (United States)

    Anantharaj, V. G.; Mozdzynski, G.; Hamrud, M.; Deconinck, W.; Smith, L.; Hack, J.

    2014-12-01

    The Oak Ridge Leadership Facility (OLCF), established at the Oak Ridge National Laboratory (ORNL) under the auspices of the U.S. Department of Energy (DOE), welcomes investigators from universities, government agencies, national laboratories and industry who are prepared to perform breakthrough research across a broad domain of scientific disciplines, including earth and space sciences. Titan, the OLCF flagship system, is currently listed as #2 in the Top500 list of supercomputers in the world, and the largest available for open science. The computational resources are allocated primarily via the Innovative and Novel Computational Impact on Theory and Experiment (INCITE) program, sponsored by the U.S. DOE Office of Science. In 2014, over 2.25 billion core hours on Titan were awarded via INCITE projects., including 14% of the allocation toward earth sciences. The INCITE competition is also open to research scientists based outside the USA. In fact, international research projects account for 12% of the INCITE awards in 2014. The INCITE scientific review panel also includes 20% participation from international experts. Recent accomplishments in earth sciences at OLCF include the world's first continuous simulation of 21,000 years of earth's climate history (2009); and an unprecedented simulation of a magnitude 8 earthquake over 125 sq. miles. One of the ongoing international projects involves scaling the ECMWF Integrated Forecasting System (IFS) model to over 200K cores of Titan. ECMWF is a partner in the EU funded Collaborative Research into Exascale Systemware, Tools and Applications (CRESTA) project. The significance of the research carried out within this project is the demonstration of techniques required to scale current generation Petascale capable simulation codes towards the performance levels required for running on future Exascale systems. One of the techniques pursued by ECMWF is to use Fortran2008 coarrays to overlap computations and communications and

  4. Nuclear facilities maintenance in the core of management-advanced trend in IBM Maximo asset management applications

    International Nuclear Information System (INIS)

    Seino, Satoshi; Ujihara, Satoshi; Kikuyama, Kaoru

    2009-01-01

    European and US plant owners have attached importance to plant maintenance, such as prompt grasp of plant states, implementation of maintenance and planning of maintenance programs, as one of asset management. The US advanced trend was introduced in this feature article through the applications of IBM Maximo Asset Management for nuclear facilities maintenance. World trends of nuclear power and related problems, need of nuclear facilities management, key items for introduction of maintenance management systems, required systems for nuclear maintenance management and introduction of functions of the IBM strategic asset management solution-Maximo were described respectively. (T. Tanaka)

  5. The text of the agreement between the Agency and Argentina for the application of safeguards to Embalse Power Reactor Facility

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 6 December 1974 between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Embalse Power Reactor Facility has been suspended

  6. Characterization of BIPV(T) applications in research facility ‘SOLARBEAT’

    NARCIS (Netherlands)

    Valckenborg, R.M.E.; Hensen, J.L.M.; Folkerts, W.; Vries, de A.

    2015-01-01

    The SolarBEAT facility is an outdoor Research & Development infrastructure for innovation on BIPV(T). The facility is a cooperation between SEAC and the Technical University Eindhoven and is located in the Netherlands. It has been founded early 2014 and has grown rapidly to its full capacity at the

  7. Proposal on application of Russian technical facilities for International Mars Research Program for 2009 2015

    Science.gov (United States)

    Polishchuk, Georgy; Pichkhadze, Konstantin; Vorontsov, Victor; Pavel, Kazmerchuk

    2006-07-01

    Recently International Mars Research Program is widely discussed. Well-known initiative of President of the USA, recent progress of American and European scientists and engineers in implementation of “Mars Odyssey” and “Mars-Express” projects and Russian proposals on cooperation and participation in “Phobos Sample Return” mission declare every intention to join efforts in the ambitious Martian Program realization. The final goal of the program for nearly 15 20 years is landing of a man on the Martian surface. Before this event happens another critical stage will be Martian soil sample return. Within the next 10 years, apparently, a major task will be scale research by means of various types of technical facilities. A crucial issue for this research will be creation of research station network which would allow collecting information about planetary conditions at far-remote points. By this time within the frame of “Phobos Sample Return Program” to be launched in 2009 it is planned to deliver some meteorological mini-landers developed by the Russian and Finnish specialists on the Martian surface. From this point view it is also interesting to use balloons capable to cover considerable distance. Such proposals have been made by Russian side for “Scout” mission. European “Aurora” program also anticipates application of wide range of technical means to explore the Martian atmosphere and surface including inflatable devices. Thus, for the International Mars Exploration Program, it seems to be very prospective to use apart from launch vehicles, upper stages etc. such technical means as mini-stations, Mars rovers, penetrators, balloons, etc.

  8. Incorporating uncertainties into risk assessment with an application to the exploratory studies facilities at Yucca Mountain

    International Nuclear Information System (INIS)

    Fathauer, P.M.

    1995-08-01

    A methodology that incorporates variability and reducible sources of uncertainty into the probabilistic and consequence components of risk was developed. The method was applied to the north tunnel of the Exploratory Studies Facility at Yucca Mountain in Nevada. In this assessment, variability and reducible sources of uncertainty were characterized and propagated through the risk assessment models using a Monte Carlo based software package. The results were then manipulated into risk curves at the 5% and 95% confidence levels for both the variability and overall uncertainty analyses, thus distinguishing between variability and reducible sources of uncertainty. In the Yucca Mountain application, the designation of the north tunnel as an item important to public safety, as defined by 10 CFR 60, was determined. Specifically, the annual frequency of a rock fall breaching a waste package causing an off-site dose of 500 mrem (5x10 -3 Sv) was calculated. The annual frequency, taking variability into account, ranged from 1.9x10 -9 per year at the 5% confidence level to 2.5x10 -9 per year at the 95% confidence level. The frequency range after including all uncertainty was 9.5x10 -10 to 1.8x10 -8 per year. The maximum observable frequency, at the 100% confidence level, was 4.9x10 -8 per year. This is below the 10 -6 per year frequency criteria of 10 CFR 60. Therefore, based on this work, the north tunnel does not fall under the items important to public safety designation for the event studied

  9. A study for the fabulously of introducing an acceleration mass spectrometer facility (ABMs) for carbon-14 applications

    International Nuclear Information System (INIS)

    Aly, A.I.M.; Comsan, N.; Sadek, M.

    2004-01-01

    In this work a study was conducted to show the importance and feasibility of introducing an accelerating mass spectrometer facility for carbon-14 analysis in the environmental levels. The different applications of Carbon-14 (e.g. dating and identification of food additives of synthetic origin) are discussed. There are two methods for C- 14 measurements, beta decay counting and accelerator mass spectrometry (AMS). The beta decay method requires gram quantities of the sample carbon, compared to few milligram quantities in case of AMS method. The Central Lab. for Environmental Isotope Hydrology of the National Center for Nuclear Safety and Radiation Control has a Carbon-14 analysis facility based on beta decay counting using a liquid scintillation counter after sample preparation in the form of benzene through rather complicated chemical conversion steps. This strongly limits the capacity of the laboratory to about 100-150 samples per year. Also, the amount of sample required limits our expansion for some very important applications like dating of archaeological small samples and especially old bone samples which normally have a low concentration of organic compounds. These applications are only possible by using the AMS method. For some applications only AMS could be used e.g measuring C-14 in atmospheric gases such as methane and carbon dioxide is virtually impossible using decay counting but quite feasible with AMS. The importance of purchasing an AMS facility or upgrading the existing accelerator is discussed in view of the shortage of such a facility in Africa and the Middle East. Acquiring an AMS in Egypt will make it possible to accurately date the Egyptian antiquities and to act as a regional laboratory and to enter into new applications where the amount of sample is limiting

  10. Electron beam irradiation facility for low to high dose irradiation applications

    International Nuclear Information System (INIS)

    Petwal, V.C.; Wanmode, Yashwant; Verma, Vijay Pal; Bhisikar, Abhay; Dwivedi, Jishnu; Shrivastava, P.; Gupta, P.D.

    2013-01-01

    Electron beam based irradiation facilities are becoming more and more popular over the conventional irradiator facilities due to many inherent advantages such as tunability of beam energy, availability of radiation both in electron mode and X-ray mode, wide range of the dose rate, control of radiation from a ON-OFF switch and other safety related merits. A prototype experimental facility based on electron accelerator has been set-up at RRCAT to meet the low-dose, medium dose and high-dose requirements for radiation processing of food, agricultural and medical products. The facility can be operated in the energy range from 7-10 MeV at variable power level from 0.05-3 kW to meet the dose rate requirement of 100 Gy to kGy. The facility is also equipped with a Bremsstrahlung converter optimized for X-ray irradiation at 7.5 MV. Availability of dose delivery in wide range with precision control and measurement has made the facility an excellent tool for researchers interested in electron/X-ray beam irradiation. A precision dosimetry lab based on alanine EPR and radiochromic film dosimetry system have been established to characterize the radiation field and precise dose measurements. Electron beam scattering technique has been developed to achieve low dose requirement for EB irradiation of various seeds such as groundnut, wheat, soybeans, moong beans, black gram etc. for mutation related studies. This paper describes various features of the facility together with the dosimetric measurements carried out for qualification of the facility and recent irradiation experiments carried out using this facility. (author)

  11. The proceedings of 1993-workshop on 'development and application of facilities for low temperature irradiation as well as controlled irradiation'

    International Nuclear Information System (INIS)

    Kuramoto, Eiichi; Okada, Moritami

    1993-03-01

    This is the proceedings of 1992-workshop of the working group on 'Development and Application of Facilities for Low Temperature Irradiation as well as Controlled Irradiation' held at the Research Reactor Institute of Kyoto University on February 23 and 24, 1993. In this workshop until now, studies on irradiation effects in many materials irradiated at lower and higher temperatures have been reported. It has been clearly defined that a careful choice of irradiation conditions is most important. At the present time, a setting plan of exactly controlled irradiation facility, which is able to irradiate with higher temperatures, is in progress. On the other hand, a plan of vertical low temperature irradiation facility has not yet been performed for lack of funds. In last year, a middle scale plan of low temperature irradiation facility, which is possible to irradiate a fast-neutron dose above 10 17 n/cm 2 at about 5K, was proposed in this workshop. In this proceedings, the advanced facility is required to construct to the KUR as soon as possible by many of the workshop members. (author)

  12. Irradiation Facilities at CERN

    CERN Document Server

    Gkotse, Blerina; Carbonez, Pierre; Danzeca, Salvatore; Fabich, Adrian; Garcia, Alia, Ruben; Glaser, Maurice; Gorine, Georgi; Jaekel, Martin, Richard; Mateu,Suau, Isidre; Pezzullo, Giuseppe; Pozzi, Fabio; Ravotti, Federico; Silari, Marco; Tali, Maris

    2017-01-01

    CERN provides unique irradiation facilities for applications in many scientific fields. This paper summarizes the facilities currently operating for proton, gamma, mixed-field and electron irradiations, including their main usage, characteristics and information about their operation. The new CERN irradiation facilities database is also presented. This includes not only CERN facilities but also irradiation facilities available worldwide.

  13. Assessment of Application Example for a Sodium Fire Extinguishing Facility using Safety Control of Dangerous Substances Act

    International Nuclear Information System (INIS)

    Jung, Minhwan; Jeong, Ji-Young; Kim, Jongman

    2014-01-01

    Sodium is under regulation of four kinds of laws including the Safety Control of Dangerous Substances Act and it is under categorized as Class 3(pyrophoric material, water-prohibiting substance). To obtain a license for a sodium experiment facility, the codes and regulations must be satisfied in the Safety Control of Dangerous Substance Act. However, there are some parts that need to be discussed in related regulations in the Safety Control of Dangerous Substance Act because there are differences with the actual features of sodium. To apply for an actual sodium facility, it is necessary to give a supplementary explanation regarding the regulations. The objective of this study is to assess the application example of a sodium experiment facility using the above mentioned laws and to propose the necessity of an amendment for conventional laws in regard to fire extinguishing systems and agents. In this work, an application example of a sodium experiment facility using the Safety Control of Dangerous Substances Act, and the necessity of amending the existing laws in regard to fire extinguishing systems including the agent used, was assessed. The safest standard was applied for cases in which the consideration of a sodium fire is not mentioned in conventional regulations. For the construction of the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor), the described regulations in this work should be reviewed and improved carefully by the fire safety regulatory body

  14. Radioactive waste package assay facility. Volume 1. Application of assay technology

    International Nuclear Information System (INIS)

    Findlay, D.J.S.; Green, T.H.; Molesworth, T.V.; Staniforth, D.; Strachan, N.R.; Rogers, J.D.; Wise, M.O.; Forrest, K.R.

    1992-01-01

    This report, in three volumes, covers the work carried out by Taylor Woodrow Construction Ltd., and two major sub-contractors: Harwell Laboratory (AEA Technology) and Siemens Plessey Controls Ltd., on the development of a radioactive waste package assay facility, for cemented 500 litre intermediate level waste drums. In volume 1, the reasons for assay are considered together with the various techniques that can be used, and the information that can be obtained. The practical problems associated with the use of the various techniques in an integrated assay facility are identified, and the key parameters defined. Engineering and operational features are examined and provisional designs proposed for facilities at three throughput levels: 15,000, 750 and 30 drums per year respectively. The capital and operating costs for such facilities have been estimated. A number of recommendations are made for further work. 16 refs., 14 figs., 13 tabs

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

    International Nuclear Information System (INIS)

    Meyer, P.D.

    1993-12-01

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

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  17. Thermocouple calibration facility for 2900 deg C high temperature and its applications

    International Nuclear Information System (INIS)

    Chen Daolong

    1991-01-01

    The construction and the performance characteristic of a 2900 deg C high temperature thermocouple calibration facility are described. The calibration error analysis is made. The test results of the calibration characteristics of high temperature thermocouples Mo/Nb, W-3Re/W-25Re, and W-1Mo/W-25Mo are given. The test result of temperature dependent resistivity of BeO made by this facility is given

  18. Biological restoration of major transportation facilities domestic demonstration and application project (DDAP): technology development at Sandia National Laboratories.

    Energy Technology Data Exchange (ETDEWEB)

    Ramsey, James L., Jr. (.,; .); Melton, Brad; Finley, Patrick; Brockman, John; Peyton, Chad E.; Tucker, Mark David; Einfeld, Wayne; Griffith, Richard O.; Brown, Gary Stephen; Lucero, Daniel A.; Betty, Rita G.; McKenna, Sean Andrew; Knowlton, Robert G.; Ho, Pauline

    2006-06-01

    The Bio-Restoration of Major Transportation Facilities Domestic Demonstration and Application Program (DDAP) is a designed to accelerate the restoration of transportation nodes following an attack with a biological warfare agent. This report documents the technology development work done at SNL for this DDAP, which include development of the BROOM tool, an investigation of surface sample collection efficiency, and a flow cytometry study of chlorine dioxide effects on Bacillus anthracis spore viability.

  19. Analysis on the application and actual condition of facilities preservation system in each industry

    International Nuclear Information System (INIS)

    Oh, Yon Woo; Kim, Seon Duk; Nam, Ji Hee

    2000-11-01

    In order to secure the maximum of a company's benefit through increasing the efficiency and the productivity of it. the facility preservation system has been developed and used so that can find it's maximum efficiency with a series of activities which make a plan for, install, maintain, and improve for it. Factories are managed to be classified by operation and maintenance with great interest in the facility preservation in South Korea. and the facilities has taken up much part in the management. But it has not been researched how the facilities affects the management of a company. According to that reasons, the facility preservation is underestimated compared with what it is and is regarded just as a cost. This report has an object to construct a fundamental electronic-database on the facility preservation in order to obtain excellent results in KAERI with researches into the introduction of the TPM technology in South Korea, and analysis the effect of the TPM on a company

  20. Analysis on the application and actual condition of facilities preservation system in each industry

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Yon Woo; Kim, Seon Duk; Nam, Ji Hee

    2000-11-01

    In order to secure the maximum of a company's benefit through increasing the efficiency and the productivity of it. the facility preservation system has been developed and used so that can find it's maximum efficiency with a series of activities which make a plan for, install, maintain, and improve for it. Factories are managed to be classified by operation and maintenance with great interest in the facility preservation in South Korea. and the facilities has taken up much part in the management. But it has not been researched how the facilities affects the management of a company. According to that reasons, the facility preservation is underestimated compared with what it is and is regarded just as a cost. This report has an object to construct a fundamental electronic-database on the facility preservation in order to obtain excellent results in KAERI with researches into the introduction of the TPM technology in South Korea, and analysis the effect of the TPM on a company.

  1. Avenues for research and technology development for industrial applications using electron beam facilities and their exploitation through BRNS schemes

    International Nuclear Information System (INIS)

    Markandeya, S.G.

    2013-01-01

    BARC has been responsible to establish indigenously designed state-of-the-art electron accelerator facilities at its Electron Beam Centre at Kharghar, Navi Mumbai. The centre offers two versatile machines namely, (i) 3 MeV, 30 kW Parallel Coupled Self Capacitance type Multiplier (Dynamitron) DC accelerator and (ii) 10 MeV, 10 kW RF Electron Linac. While these machines are being used by scientists and engineers from within DAE, there is tremendous scope for exploiting their use by researchers in the country for basic research as well as by technologists and entrepreneurs for exploiting its potential for industrial applications. However, due to lack of adequate information about the facilities and due to paucity of research funds for the academia in the country, there is always a gap which researchers seldom look forward to be filled up appropriately. The present talk will give a glimpse of some opportunities to exploit the facilities at EBC, Kharghar for variety of applications followed by a brief presentation on provisions under BRNS to carry out sponsored research activities for basic research as well as for technology development for the industrial applications. (author)

  2. Quality Assurance Project Plan for Closure of the Central Facilities Area Sewage Treatment Plant Lagoon 3 and Land Application Area

    International Nuclear Information System (INIS)

    Lewis, Michael G.

    2016-01-01

    This quality assurance project plan describes the technical requirements and quality assurance activities of the environmental data collection/analyses operations to close Central Facilities Area Sewage treatment Plant Lagoon 3 and the land application area. It describes the organization and persons involved, the data quality objectives, the analytical procedures, and the specific quality control measures to be employed. All quality assurance project plan activities are implemented to determine whether the results of the sampling and monitoring performed are of the right type, quantity, and quality to satisfy the requirements for closing Lagoon 3 and the land application area.

  3. Quality Assurance Project Plan for Closure of the Central Facilities Area Sewage Treatment Plant Lagoon 3 and Land Application Area

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Michael G. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-10-01

    This quality assurance project plan describes the technical requirements and quality assurance activities of the environmental data collection/analyses operations to close Central Facilities Area Sewage treatment Plant Lagoon 3 and the land application area. It describes the organization and persons involved, the data quality objectives, the analytical procedures, and the specific quality control measures to be employed. All quality assurance project plan activities are implemented to determine whether the results of the sampling and monitoring performed are of the right type, quantity, and quality to satisfy the requirements for closing Lagoon 3 and the land application area.

  4. Materials for advanced reactor facilities: development and application. Materials of School-Conference for young scientists and specialists

    International Nuclear Information System (INIS)

    2012-01-01

    In the collection of works there are the texts, summaries and presentations of lectures delivered by the leading specialists of the branch as well as the abstracts of the students of school-conference for young scientists and specialists Materials for advanced reactor facilities: development and application, which took place on October, 29 - November, 2, 2012 in Zvenigorod. In the materials presented different aspects of development and application of materials of reactor cores and vessels of advanced reactors, computerized simulation of properties of radiation-resistant materials and simulation investigations of material radiation hardness are considered [ru

  5. A functional proteogenomic analysis of endometrioid and clear cell carcinomas using reverse phase protein array and mutation analysis: protein expression is histotype-specific and loss of ARID1A/BAF250a is associated with AKT phosphorylation

    International Nuclear Information System (INIS)

    Wiegand, Kimberly C; Lu, Yiling; Zhang, Fan; Anglesio, Michael S; Gilks, Blake; Mills, Gordon B; Huntsman, David G; Carey, Mark S; Hennessy, Bryan T; Leung, Samuel; Wang, Yemin; Ju, Zhenlin; McGahren, Mollianne; Kalloger, Steve E; Finlayson, Sarah; Stemke-Hale, Katherine

    2014-01-01

    Ovarian cancer is now recognized as a number of distinct diseases primarily defined by histological subtype. Both clear cell ovarian carcinomas (CCC) and ovarian endometrioid carcinomas (EC) may arise from endometriosis and frequently harbor mutations in the ARID1A tumor suppressor gene. We studied the influence of histological subtype on protein expression with reverse phase protein array (RPPA) and assessed proteomic changes associated with ARID1A mutation/BAF250a expression in EC and CCC. Immunohistochemistry (IHC) for BAF250a expression was performed on 127 chemotherapy-naive ovarian carcinomas (33 CCC, 29 EC, and 65 high-grade serous ovarian carcinomas (HGSC)). Whole tumor lysates were prepared from frozen banked tumor samples and profiled by RPPA using 116 antibodies. ARID1A mutations were identified by exome sequencing, and PIK3CA mutations were characterized by MALDI-TOF mass spectrometry. SAM (Significance Analysis of Microarrays) was performed to determine differential protein expression by histological subtype and ARID1A mutation status. Multivariate logistic regression was used to assess the impact of ARID1A mutation status/BAF250a expression on AKT phosphorylation (pAKT). PIK3CA mutation type and PTEN expression were included in the model. BAF250a knockdown was performed in 3 clear cell lines using siRNA to ARID1A. Marked differences in protein expression were observed that are driven by histotype. Compared to HGSC, SAM identified over 50 proteins that are differentially expressed in CCC and EC. These included PI3K/AKT pathway proteins, those regulating the cell cycle, apoptosis, transcription, and other signaling pathways including steroid hormone signaling. Multivariate models showed that tumors with loss of BAF250a expression showed significantly higher levels of AKT-Thr 308 and AKT-Ser 473 phosphorylation (p < 0.05). In 31 CCC cases, pAKT was similarly significantly increased in tumors with BAF250a loss on IHC. Knockdown of BAF250a by siRNA in

  6. PNRI Pioneering the Establishment and Operation of the Tc-99m Generator Production Facility for Nuclear Medicine Applications

    International Nuclear Information System (INIS)

    Bulos, Adelina DM.; Borras, Ma. Teresa L.; Ciocson, Gregory R.; Mascariñas, Rommel D.C.; Nuñez, Ivy Angelica A.; Dela Rosa, Alumanda M.

    2015-01-01

    In response to the increasing demand in the nuclear medicine sector in the Philippines, the Philippine Nuclear Research Institute (PNRI) initiated the establishment of a radioisotope production facility. To date, the most commonly used radioisotope in nuclear medicine, Technetium-99m or Tc-99m has been successfully produced in the new laboratory, the PNRI facility has already obtained a license to operate from the Philippine FDA. The new facility is envisioned to meet the country’s requirements for all the major medical radioisotope starting with the local production of Tc-99m and the most commonly used Tc-99m radiopharmaceuticals. At present, all radioisotope supplies in the country are sourced overseas at price that varies accordingly. With the establishment of the PNRI’s laboratories, we now have a GMP-grade Tc-99m generator facility capable of producing 50 Tc-99m generators per batch. Instead of Tc-99m being imported, it will be the parent Mo-99m that will be transferred to PNRI facility from Mo-99 processing facilities overseas, contained in specialized transport containers and via airfreight arrangements so it can be processed locally to make Tc-99m generators. But, to make radiopharmaceuticals, the other non-radioactive components are needed to be sourced from abroad. Thus, it has become imperative to also locally produce these non-radioactive components. All of these components, radioactive and non-radioactive, from the radiopharmaceutical finished products which are utilized in nuclear medicine caters for the diagnosis and detection of critical and non-critical human illnesses. The completion of this program is foreseen as another concrete validation on the capacity of the Philippine as a country that is at par with advanced nations on competency and expertise in the research and development of nuclear medicine application for better healthcare delivery and management. (author)

  7. Magnetic hyperfine interactions of U2 center in CaF2, SrF2 and BaF2

    International Nuclear Information System (INIS)

    Graf, C.J.F.

    1976-02-01

    The magnetic hyperfine parameters of the U 2 center in CaF 2 , SeF 2 and BaF 2 , using a molecular orbitals scheme have been calculated. The need for the inclusion of mechanisms such as Pauli Repulsion and Covalence in order to describe the electronic structure of the defect has been shown. In the molecular orbitals model a weak covalence parameter has been phenomenologically introduced, mixing the is atomic wavefunction of hydrogen with a properly symmetrized linear combination of 2p F - functions centered on the ions of the first fluorine shell. The results obtained are compared with experimental measurements of EPR and ENDOR. (Author) [pt

  8. Alpha-gamma pulse shape discrimination in CsI:Tl, CsI:Na and BaF sub 2 scintillators

    CERN Document Server

    Dinca, L E; Haas, J; Bom, V R; Eijk, C W E

    2002-01-01

    Some scintillating materials offer the possibility of measuring well separated alpha and gamma scintillation response using a single crystal. Eventually aiming at thermal neutron detection using sup 6 Li or sup 1 sup 0 B admixture, pulse shape discrimination measurements were made on three scintillators: CsI:Tl, CsI:Na and pure BaF sub 2 crystals. A very good alpha/gamma discrimination was obtained using sup 2 sup 2 Na, sup 2 sup 4 sup 1 Am (gamma) and sup 2 sup 4 sup 4 Cm (alpha) radioactive sources.

  9. Comparing cost and process performance of activated sludge (AS) and biological aerated filters (BAF) over ten years of full sale operation.

    Science.gov (United States)

    Hansen, R; Thogersen, T; Rogalla, F

    2007-01-01

    In the early 1990s, the Wastewater Treatment Plant (WWTP) of Frederikshavn, Denmark, was extended to meet new requirements for nutrient removal (8 mg/L TN, 1.5 mg TP/L) as well as to increase its average daily flow to 16,500 m(3)/d (4.5 MGD). As the most economical upgrade of the existing activated sludge (AS) plant, a parallel biological aerated filter (BAF) was selected, and started up in 1995. Running two full scale processes in parallel for over ten years on the same wastewater and treatment objectives enabled a direct comparison in relation to operating performance, costs and experience. Common pretreatment consists of screening, an aerated grit and grease removal and three primary settlers with chemical addition. The effluent is then pumped to the two parallel biological treatment stages, AS with recirculation and an upflow BAF with floating media. The wastewater is a mixture of industrial and domestic wastewater, with a dominant discharge of fish processing effluent which can amount to 50% of the flow. The maximum hydraulic load on the pretreatment section as a whole is 1,530 m(3)/h. Approximately 60% of the sewer system is combined with a total of 32 overflow structures. To avoid the direct discharge of combined sewer overflows into the receiving waters, the total hydraulic wet weather capacity of the plant is increased to 4,330 m(3)/h, or 6 times average flow. During rain, some of the raw sewage can be directed through a stormwater bypass to the BAF, which can be modified in its operation to accommodate various treatment needs: either using simultaneous nitrification/denitrification in all filters with recirculation introducing bottom aeration with full nitrification in some filters for storm treatment and/or post-denitrification in one filter. After treatment, the wastewater is discharged to the Baltic Sea through a 500 m outfall. The BAF backwash sludge, approximately 1,900 m(3) per 24 h in dry weather, is redirected to the AS plant. Primary settler

  10. Ionic conductivity of ZrF4-BaF2-MFsub(n) fluoride glasses (M : The group I--V metal elements)

    International Nuclear Information System (INIS)

    Kawamoto, Yoji; Nohara, Ichiro

    1985-01-01

    To glass transition temperature in argon atmosphere using the complex capacitance and complex impedance methods. The ionic conductivity of glasses, represented by log σ = log σ 0 - ΔE/2.303 kT, was nearly dependent only upon the activation energy. The polarizability of cation was found to be a dominant factor which governs activation energy. Thus, glasses with high meanpolarizability of glass-constituting cations exhibited high ionic conductivity, and the ZrF 4 -BaF 2 -CsF system was suggested to be a promising system that may provide a glass with higher fluoride-ion conduction. (author)

  11. Medical Applications of Non-Medical Research: Applications Derived from BES-Supported Research and Research at BES Facilities

    Science.gov (United States)

    1998-07-01

    This publication contains stories that illustrate how the Office of Basic Energy Sciences (BES) research and major user facilities have impacted the medical sciences in the selected topical areas of disease diagnosis, treatment (including drug development, radiation therapy, and surgery), understanding, and prevention.

  12. Safety assessment methodologies and their application in development of near surface waste disposal facilities - the ASAM project

    International Nuclear Information System (INIS)

    Metcalf, P.

    2003-01-01

    The scope of ASAM project covers near surface disposal facilities for all types of low and intermediate level wastes with emphasis of the post-closure safety assessment.The objectives are to explore practical application to a range of disposal facilities for a number of purposes e.g. development of design concepts, safety re-assessment, upgrading safety and to develop practical approaches to assist regulators, operators and other experts in review of safety assessment. The task of the Co-ordination Group are: reassessment of existing facilities - use of safety assessment in decision making on selection of options (volunteer site Hungary); disused sealed sources - evaluation of disposability of disused sealed sources in near surface facilities (volunteer site Saratov, Russia); mining and minerals processing waste - evaluation of long-term safety (volunteer site pmc S. Africa). An agreement on the scope and objectives of the project are reached and the further consideration, such as human intrusion/institutional control/security; waste from oil/gas industry; very low level waste; categorization of sealed sources coordinated with other IAEA activities are outlined

  13. Development of ISA procedure for uranium fuel fabrication and enrichment facilities: overview of ISA procedure and its application

    International Nuclear Information System (INIS)

    Yamate, Kazuki; Yamada, Takashi; Takanashi, Mitsuhiro; Sasaki, Noriaki

    2013-01-01

    Integrated Safety Analysis (ISA) procedure for uranium fuel fabrication and enrichment facilities has been developed for aiming at applying risk-informed regulation to these uranium facilities. The development has carried out referring to the ISA (NUREG-1520) by the Nuclear Regulatory Commission (NRC). The paper presents purpose, principles and activities for the development of the ISA procedure, including Risk Level (RL) matrix and grading evaluation method of IROFS (Items Relied on for Safety), as well as general description and features of the procedure. Also described in the paper is current status in application of risk information from the ISA. Japanese four licensees of the uranium facilities have been conducting ISA for their representative processes using the developed procedure as their voluntary safety activities. They have been accumulating experiences and knowledge on the ISA procedure and risk information through the field activities. NISA (Nuclear and Industrial Safety Agency) and JNES (Japan Nuclear Energy Safety Organization) are studying how to use such risk information for the safety regulation of the uranium facilities, taking into account the licensees' experiences and knowledge. (authors)

  14. Geospatial Data Analysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Geospatial application development, location-based services, spatial modeling, and spatial analysis are examples of the many research applications that this facility...

  15. Prerequisites concerning SSI:s review of applications for an encapsulation facility and a repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Oehlen, Elisabeth

    2006-09-01

    The report outlines some fundamental prerequisites concerning SSI:s review of SKB coming applications for an encapsulation facility (according to the act on nuclear activities) and for the complete final disposal system (according to the act on nuclear activities and the environmental code). The report summarize how the SSI look at the decision making process considering radiation protection requirements according to SSI:s regulations and general advices and earlier standpoints regarding SKB:s RandD-programme. The report also describe the present reviewing capacity of SSI and constitute therefore the basis for the planning of SSI:s review organisation in the prospect of coming applications on nuclear waste facilities (encapsulation facility and a deep disposal repository). It should be noted that the report reflects the present situation. Due to a number of factors as for example changes in SKB:s coming RandD-programme, future governmental decisions, adjustments of SSI:s financial resources or new facts in the case, will of course have an effect on how SSI finally will organise the review work. SSI:s home page will continuously be updated with the latest information in this respect

  16. An application of the value tree analysis methodology within the integrated risk informed decision making for the nuclear facilities

    International Nuclear Information System (INIS)

    Borysiewicz, Mieczysław; Kowal, Karol; Potempski, Sławomir

    2015-01-01

    A new framework of integrated risk informed decision making (IRIDM) has been recently developed in order to improve the risk management of the nuclear facilities. IRIDM is a process in which qualitatively different inputs, corresponding to different types of risk, are jointly taken into account. However, the relative importance of the IRIDM inputs and their influence on the decision to be made is difficult to be determined quantitatively. An improvement of this situation can be achieved by application of the Value Tree Analysis (VTA) methods. The aim of this article is to present the VTA methodology in the context of its potential usage in the decision making on nuclear facilities. The benefits of the VTA application within the IRIDM process were identified while making the decision on fuel conversion of the research reactor MARIA. - Highlights: • New approach to risk informed decision making on nuclear facilities was postulated. • Value tree diagram was developed for decision processes on nuclear installations. • An experiment was performed to compare the new approach with the standard one. • Benefits of the new approach were reached in fuel conversion of a research reactor. • The new approach makes the decision making process more transparent and auditable

  17. Use of a Graded Approach in the Application of the Management System Requirements for Facilities and Activities

    International Nuclear Information System (INIS)

    2014-06-01

    IAEA Safety Standards Series No. GS-R-3, The Management System for Facilities and Activities, defines the requirements for establishing, implementing, assessing and continually improving a management system that integrates safety, health, environmental, security, quality and economical elements. It details the need to grade the application of the management system requirements to ensure that resources are deployed and appropriate controls are applied on the basis of the consideration of: the significance and complexity of each product or activity; the hazards and the magnitude of the potential impact (risks) associated with the safety, health, environmental, security, quality and economical elements of each product or activity; and the possible consequences if a product fails or an activity is carried out incorrectly. The grading of the application of the requirements detailed in IAEA Safety Standards Series No. GS-R-3 is especially essential when they are implemented in smaller facilities and activities. The grading is done to ensure that the management system for smaller facilities and activities are suitably tailored to the hazards and the magnitude of the potential impact of the facilities and activities. Detailed guidance on how the grading requirements of IAEA Safety Standards Series No. GS-R-3 can be met and how to ensure that grading is performed in a consistent manner can be found in IAEA Safety Standards Series No. GS-G-3.1, Application of the Management System for Facilities and Activities. In addition, it contains guidance on systematic grading methods which will reduce the likelihood and consequences of improper grading. This publication provides an overview of grading fundamentals, the grading process, the role of classification in the process and the typical controls that can be graded. It also provides practical guidance and examples of grading as required by IAEA Safety Standards Series No. GS-R-3 to develop and apply a method of grading

  18. Opportunities for artificial intelligence application in computer- aided management of mixed waste incinerator facilities

    International Nuclear Information System (INIS)

    Rivera, A.L.; Ferrada, J.J.; Singh, S.P.N.

    1992-01-01

    The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site. It is designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). This facility, known as the TSCA Incinerator, services seven DOE/OR installations. This incinerator was recently authorized for production operation in the United States for the processing of mixed (radioactively contaminated-chemically hazardous) wastes as regulated under TSCA and RCRA. Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. These requirements impact the characteristics and disposition of incinerator residues, limits the quality of liquid and gaseous effluents, limit the characteristics and rates of waste feeds and operating conditions, and restrict the handling of the waste feed inventories. This incinerator facility presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. Demonstrated computer-aided management systems could be transferred to future mixed waste incinerator facilities

  19. 78 FR 47785 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-08-06

    ... privacy information, such as social security numbers, home addresses, or home phone numbers in their..., ``Reactor Core SLs,'' to reduce the minimum reactor dome pressure associated with the critical power... the facility which will allow for a lower-bound pressure. The change will provide a greater pressure...

  20. Wireless Occupancy Sensors for Lighting Controls: An Applications Guide for Federal Facility Managers

    Energy Technology Data Exchange (ETDEWEB)

    None

    2016-03-15

    This guide provides federal facility managers with an overview of the energy savings potential of wireless lighting occupancy sensors for various room types, cost considerations, key steps to successful installation of wireless sensors, pros and cons of various technology options, light source considerations, and codes and standards.

  1. 40 CFR 60.560 - Applicability and designation of affected facilities.

    Science.gov (United States)

    2010-07-01

    ... recovery section, each product finishing section, and each product storage section. These process sections...) manufacturing processes. (i) Affected facilities with a design capacity to produce less than 1,000 Mg/yr (1,102... Threshold Emission Rates a Production process Process section Uncontrolled emission rate, kg TOC/Mg product...

  2. Wind Atlas Analysis and Application Program: WAsP 11 Help Facility

    DEFF Research Database (Denmark)

    2014-01-01

    of specific wind turbines and wind farms. The WAsP Help Facility includes a Quick Start Tutorial, a User's Guide and a Technical Reference. It further includes descriptions of the Observed Wind Climate Wizard, the WAsP Climate Analyst, the WAsP Map Editor tool, the WAsP Turbine Editor tool, the Air Density...

  3. 76 FR 73727 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-11-29

    ..., Donald C. Cook Nuclear Plant, Unit 2 (DCCNP-2), Berrien County, Michigan; Date of amendment request... Counsel, Indiana Michigan Power Company, One Cook Place, Bridgman, MI 49106. NRC Acting Branch Chief: Thomas J. Wengert. Notice of Issuance of Amendments to Facility Operating Licenses During the period...

  4. Application of the management system for facilities and activities. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    This Safety Guide supports the Safety Requirements publication on The Management System for Facilities and Activities. It provides generic guidance to aid in establishing, implementing, assessing and continually improving a management system that complies with the requirements established. In addition to this Safety Guide, there are a number of Safety Guides for specific technical areas. Together these provide all the guidance necessary for implementing these requirements. This publication supersedes Safety Series No. 50-SG-Q1-Q7 (1996). The guidance provided here may be used by organizations in the following ways: - To assist in the development of the management systems of organizations directly responsible for operating facilities and activities and providing services for: Nuclear facilities; Activities using sources of ionizing radiation; Radioactive waste management; The transport of radioactive material; Radiation protection activities; Any other practices or circumstances in which people may be exposed to radiation from naturally occurring or artificial sources; The regulation of such facilities and activities; - To assist in the development of the management systems of the relevant regulatory bodies; - By the operator, to specify to a supplier, via contractual documentation, any guidance of this Safety Guide that should be included in the supplier's management system for the supply and delivery of products

  5. TRU waste-assay instrumentation and application in nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    Umbarger, C.J.

    1982-01-01

    The Los Alamos TRU waste assay program is developing measurement techniques for TRU and other radioactive waste materials generated by the nuclear industry, including decommissioning programs. Systems are now being fielded for test and evaluation purposes at DOE TRU waste generators. The transfer of this technology to other facilities and the commercial instrumentation sector is well in progress. 6 figures

  6. 78 FR 35058 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-06-11

    ... submitted in a timely fashion based on the availability of the subsequent information. For further details...-cycle 23 refueling outage, currently scheduled for the fall of 2014, and shall be implemented for McGuire 2 within 30 days of the completion of the facility's end-of-cycle 22 refueling outage, currently...

  7. Application of smart differential pressure transmitters (DPTS) for containment studies facility (CSF)

    International Nuclear Information System (INIS)

    Shanware, V.M.; Gole, N.V.; Sebastian, A.; Subramaniam, K.

    2001-01-01

    Containment Studies Facility (CSF) is being set up in BARC for studying various containment related thermal hydraulic and other processes during simulated conditions of pipe rupture. The set up consists of a model reactor containment vessel with a model primary heat transport system. Besides, provisions exist to introduce aerosols and hydrogen also in the containment model. The instrumentation includes measurement of the process temperatures, pressures, levels, flows, humidity, etc. Differential Pressure Transmitters (DPT) will be used for measurement of levels and flows in the CSF. The procured DPTs for this facility are smart. Conventional transmitters have a rangeability specification of 5 or 6. But the smart transmitters have rangeability varying between 40-100. Smart transmitters have facility to change its operating range online. This enables the provision of zooming in on the selected range and narrowing the range around the point of measurement. This facility can be exploited to realise the maximum possible accuracy at the smallest possible range around the point of measurement. This paper describes how the smart DPTs function, how the Highway Addressable Remote Transmitter (HART) protocol works and how we propose to use the on-line rangeability of these DPTs get the highest resolution in our measurements. (author)

  8. 75 FR 51258 - Boott Hydropower, Inc.; Eldred L Field Hydroelectric Facility Trust; Notice of Application for...

    Science.gov (United States)

    2010-08-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2790-055] Boott Hydropower... Hydropower, Inc. and Eldred L Field Hydroelectric Facility Trust. e. Name of Project: Lowell Hydroelectric... Affairs Coordinator, Boott Hydropower, Inc., One Tech Drive, Suite 220, Andover, MA 01810. Tel: (978) 681...

  9. 45 CFR 1309.10 - Applications for the purchase, construction and major renovation of facilities.

    Science.gov (United States)

    2010-10-01

    ... legal description of the site of the facility, and an explanation of the appropriateness of the location... grantee's ability to collaborate with other child care, early education programs, social services and... permanent grant-supported improvements. (m) An assessment of the impact of the proposed project on the human...

  10. Summary of Off-Normal Events in US Fuel Cycle Facilities for AFCI Applications

    Energy Technology Data Exchange (ETDEWEB)

    L. C. Cadwallader; S. J. Piet; S. O. Sheetz; D. H. McGuire; W. B. Boore

    2005-09-01

    This report is a collection and review of system operation and failure experiences for facilities comprising the fission reactor fuel cycle, with the exception of reactor operations. This report includes mines, mills, conversion plants, enrichment plants, fuel fabrication plants, transportation of fuel materials between these centers, and waste storage facilities. Some of the facilities discussed are no longer operating; others continue to produce fuel for the commercial fission power plant industry. Some of the facilities discussed have been part of the military’s nuclear effort; these are included when the processes used are similar to those used for commercial nuclear power. When reading compilations of incidents and accidents, after repeated entries it is natural to form an opinion that there exists nothing but accidents. For this reason, production or throughput values are described when available. These adverse operating experiences are compiled to support the design and decisions needed for the Advanced Fuel Cycle Initiative (AFCI). The AFCI is to weigh options for a new fission reactor fuel cycle that is efficient, safe, and productive for US energy security.

  11. Facile Synthesis of Gold Nanorice Enclosed by High- Index Facets and Its Application for CO Oxidation

    International Nuclear Information System (INIS)

    Zheng, Y.; Tao, J.; Liu, H.; Zeng, J.; Yu, T.; Ma, Y.; Moran, C.; Wu, L.; Zhu, Y.; Liu, J.; Xia, Y.

    2011-01-01

    A facile method for generating Au nanorice enclosed by high-index facets in high purity. The nanorice shows much higher catalytic activity for CO oxidation than multiply twinned particles of Au enclosed by {111} facets at temperatures below 300 C.

  12. Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility.

    Energy Technology Data Exchange (ETDEWEB)

    Talamo, A.; Gohar, Y.; Nuclear Engineering Division

    2007-05-15

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,{gamma}), (n,2n), (n,p), and ({gamma},n). In the second part

  13. Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility

    International Nuclear Information System (INIS)

    Talamo, A.; Gohar, Y.

    2007-01-01

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,γ), (n,2n), (n,p), and (γ,n). In the second part, the parent

  14. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    Energy Technology Data Exchange (ETDEWEB)

    Calderoni, P., E-mail: Pattrick.Calderoni@inl.gov [Fusion Safety Program, Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-7113 (United States); Sharpe, J.; Shimada, M.; Denny, B.; Pawelko, B.; Schuetz, S.; Longhurst, G. [Fusion Safety Program, Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-7113 (United States); Hatano, Y.; Hara, M. [Hydrogen Isotope Research Center, University of Toyama, Gofuku 3190, Toyama 930-8555 (Japan); Oya, Y. [Radioscience Research Laboratory, Faculty of Science, Shizuoka University, 836 Ohya, Suruga-ku, Shizuoka 422-8529 (Japan); Otsuka, T.; Katayama, K. [Interdisciplinary Graduate School of Engineering Sciences, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan); Konishi, S.; Noborio, K.; Yamamoto, Y. [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)

    2011-10-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  15. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    International Nuclear Information System (INIS)

    Calderoni, P.; Sharpe, J.; Shimada, M.; Denny, B.; Pawelko, B.; Schuetz, S.; Longhurst, G.; Hatano, Y.; Hara, M.; Oya, Y.; Otsuka, T.; Katayama, K.; Konishi, S.; Noborio, K.; Yamamoto, Y.

    2011-01-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  16. Issues in the review of a license application for an above grade low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Ringenberg, J.D. [Nebraska Dept. of Environmental Quality, NE (United States)

    1993-03-01

    In December 1987, Nebraska was selected by the Central Interstate Compact (CIC) Commission as the host state for the construction of a low-level radioactive waste disposal facility. After spending a year in the site screening process, the Compact`s developer, US Ecology, selected three sites for detailed site characterization. These sites were located in Nemaha, Nuckolls and Boyd Counties. One year later the Boyd County site was selected as the preferred site and additional site characterization studies were undertaken. On July 29, 1990, US Ecology submitted a license application to the Nebraska Department of Environmental Control (now Department of Environmental Quality-NDEQ). This paper will present issues that the NDEQ has dealt with since Nebraska`s selection as the host state for the CIC facility.

  17. State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site

    International Nuclear Information System (INIS)

    1993-08-01

    Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS

  18. The Case for the Application of Worldwide Marine Radioactivity Studies In the Search for Undeclared Facilities and Activities

    Energy Technology Data Exchange (ETDEWEB)

    Mark Schanfein

    2013-06-01

    Undeclared nuclear facilities unequivocally remain the most difficult safeguards challenge facing the International Atomic Energy Agency (IAEA). Recent cases of undeclared facilities revealed in Iran and Syria, which are NPT signatory States, show both the difficulty and the seriousness of this threat to nonproliferation. In the case of undeclared nuclear facilities, the most effective deterrent against proliferation is the application of Wide-Area Environmental Sampling (WAES); however, WAES is currently cost-prohibitive. As with any threat, the most effective countering strategy is a multifaceted approach. Some of the approaches applied by the IAEA include: open source analysis, satellite imagery, on-site environmental sampling, complementary access under the Additional Protocol (where in force), traditional safeguards inspections, and information provided by member States. These approaches, naturally, are focused on specific States. Are there other opportunities not currently within the IAEA purview to assess States that may provide another opportunity to detect clandestine facilities? In this paper, the author will make the case that the IAEA Department of Safeguards should explore the area of worldwide marine radioactivity studies as one possible opportunity. One such study was released by the IAEA Marine Environment Laboratory in January 2005. This technical document focused on 90Sr, 137Cs, and 239/240Pu. It is clearly a challenging area because of the many sources of anthropogenic radionuclides in the world’s oceans and seas including: nuclear weapons testing, reprocessing, accidents, waste dumping, and industrial and medical radioisotopes, whose distributions change based on oceanographic, geochemical, and biological processes, and their sources. It is additionally challenging where multiple States share oceans, seas, and rivers. But with the application of modern science, historical sampling to establish baselines, and a focus on the most relevant

  19. Applicability of the 5S management method for quality improvement in health-care facilities: a review.

    Science.gov (United States)

    Kanamori, Shogo; Shibanuma, Akira; Jimba, Masamine

    2016-01-01

    The 5S management method (where 5S stands for sort, set in order, shine, standardize, and sustain) was originally implemented by manufacturing enterprises in Japan. It was then introduced to the manufacturing sector in the West and eventually applied to the health sector for organizing and standardizing the workplace. 5S has recently received attention as a potential solution for improving government health-care services in low- and middle-income countries. We conducted a narrative literature review to explore its applicability to health-care facilities globally, with a focus on three aspects: (a) the context of its application, (b) its impacts, and (c) its adoption as part of government initiatives. To identify relevant research articles, we researched public health databases in English, including CINAHL, PubMed, ScienceDirect, and Web of Science. We found 15 of the 114 articles obtained from the search results to be relevant for full-text analysis of the context and impacts of the 5S application. To identify additional information particularly on its adoption as part of government initiatives, we also examined other types of resources including reference books, reports, didactic materials, government documents, and websites. The 15 empirical studies highlighted its application in primary health-care facilities and a wide range of hospital areas in Brazil, India, Jordan, Senegal, Sri Lanka, Tanzania, the UK, and the USA. The review also found that 5S was considered to be the starting point for health-care quality improvement. Ten studies presented its impacts on quality improvements; the changes resulting from the 5S application were classified into the three dimensions of safety, efficiency, and patient-centeredness. Furthermore, 5S was adopted as part of government quality improvement strategies in India, Senegal, Sri Lanka, and Tanzania. 5S could be applied to health-care facilities regardless of locations. It could be not only a tool for health workers and

  20. Readout concepts for the suppression of the slow component of BaF2 for the upgrade of the TAPS spectrometer at ELSA

    Science.gov (United States)

    Diehl, Stefan; Novotny, Rainer W.; Wohlfahrt, Benjamin; Beck, Reinhard

    2015-02-01

    For the measurement at extremely high interaction rates with fast scintillators, pile-up of consecutive events is a limiting factor. With a decay time of 600 ps of the fast crossluminescence component, Barium Fluoride (BaF2) is one of the fastest inorganic scintillators known today. However, the dominating slow component with a 3 orders of magnitude longer decay time of 630 ns limits the rate capability. To circumvent this limit, different approaches have been made in the past. The slow component can be suppressed for example by doping the crystals with rare earth ions like La3+. The paper will give an overview over the various concepts investigated in the past and present the suppression via optical band pass filters. This method has been chosen for the upgrade of the BaF2 crystals in the most forward region of the TAPS-spectrometer at ELSA in Bonn. It allows to reuse the existing crystals and to achieve a high degree of suppression of the slow component. The focus of the paper will be on the selection of the filters, the achievable rate capability and the energy resolution of the fast component.

  1. Spectroscopic properties and energy transfer analysis of Tm3+-doped BaF2-Ga2O3-GeO2-La2O3 glass.

    Science.gov (United States)

    Yu, Shenglei; Yang, Zhongmin; Xu, Shanhui

    2010-05-01

    This paper reports on the spectroscopic properties and energy transfer analysis of Tm(3+)-doped BaF(2)-Ga(2)O(3)-GeO(2)-La(2)O(3) glasses with different Tm(2)O(3) doping concentrations (0.2, 0.5, 2.0, 2.5, 3.0, 3.5, 3.5, 4.0 wt%). Mid-IR fluorescence intensities in the range of 1,300 nm-2,200 nm have been measured when excited under an 808 nm LD for all the samples with the same pump power. Energy level structure and Judd-Ofelt parameters have been calculated based on the absorption spectra of Tm(3+), cross-relaxation rates and multi-phonon relaxation rates have been estimated with different Tm(2)O(3) doping concentrations. The maximum fluorescence intensity at around 1.8 mum has been obtained in Tm(2)O(3)-3 wt% sample and the maximum value of calculated stimulated emission cross-section of Tm(3+) in this sample is about 0.48 x 10(-20) cm(2) at 1,793 nm, and there is not any crystallization peak in the DSC curve of this sample, which indicate the potential utility of Tm(3+)-doped BaF(2)-Ga(2)O(3)-GeO(2)- La(2)O(3) glass for 2.0-microm optical fiber laser.

  2. Characterization of siderophore produced by Pseudomonas syringae BAF.1 and its inhibitory effects on spore germination and mycelium morphology of Fusarium oxysporum.

    Science.gov (United States)

    Yu, Sumei; Teng, Chunying; Liang, Jinsong; Song, Tao; Dong, Liying; Bai, Xin; Jin, Yu; Qu, Juanjuan

    2017-11-01

    In this study, an antagonistic bacterium against Fusarium oxysporum was identified and designated as Pseudomonas syringae strain BAF.1 on the basis of 16S rDNA sequence analysis and physiological-biochemical characteristics. It produced catechol-species siderophore at a molecular weight of 488.59 Da and a maximum amount of 55.27 μg/ml with glucose as a carbon source and asparagine as a nitrogen source at a C/N ratio of 10:1, 30°C and pH 7. The siderophore exhibited prominent antagonistic activity against Fusarium oxysporum with a maximum inhibition rate of 95.24% and had also suppressive effects on other kinds of 11 phytopathogenic fungi in the absence of FeCl 3 ·6H 2 O. Spore germination was completely inhibited by 50 μl of the siderophorecontaining solution, and the ultrastructures of mycelia and spores were also considerably suppressed by siderophore treatment as established by electron microscopy observation. These results indicate that the siderophore produced by Pseudomonas syringae BAF.1 could be potentially used for biocontrol of pathogenic Fusarium oxysporum.

  3. The Text of the Agreement Between the Agency and Argentina for the Application of Safeguards to the Embalse Power Reactor Facility

    International Nuclear Information System (INIS)

    1975-01-01

    The text of the Agreement between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Embalse Power Reactor Facility is reproduced in this document for the information of all Members

  4. Global Daily Sea Ice Concentration Reprocessing Data Set for 1978-2007 from the EUMETSAT Ocean and Sea Ice Satellite Application Facility (NODC Accession 0068294)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — These data constitute the reprocessed sea ice concentration data set from the EUMETSAT Ocean and Sea Ice Satellite Application Facility (OSI SAF), covering the...

  5. The Text of the Agreement between the Agency and Argentina for the Application of Safeguards to the Atucha Power Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-01-25

    The text of the Agreement between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Atucha Power Reactor Facility is reproduced in this document for the information of all Members.

  6. Application of probabilistic methods to accident analysis at waste management facilities

    International Nuclear Information System (INIS)

    Banz, I.

    1986-01-01

    Probabilistic risk assessment is a technique used to systematically analyze complex technical systems, such as nuclear waste management facilities, in order to identify and measure their public health, environmental, and economic risks. Probabilistic techniques have been utilized at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, to evaluate the probability of a catastrophic waste hoist accident. A probability model was developed to represent the hoisting system, and fault trees were constructed to identify potential sequences of events that could result in a hoist accident. Quantification of the fault trees using statistics compiled by the Mine Safety and Health Administration (MSHA) indicated that the annual probability of a catastrophic hoist accident at WIPP is less than one in 60 million. This result allowed classification of a catastrophic hoist accident as ''not credible'' at WIPP per DOE definition. Potential uses of probabilistic techniques at other waste management facilities are discussed

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  8. Clearance of surface-contaminated objects from the controlled area of a nuclear facility. Application of the SUDOQU methodology

    Energy Technology Data Exchange (ETDEWEB)

    Russo, F.; Mommaert, C. [Bel V, Brussels (Belgium); Dillen, T. van [National Institute for Public Health and the Environment (RIVM), Bilthoven (Netherlands)

    2018-01-15

    The lack of clearly defined surface-clearance levels in the Belgian regulation led Bel V to start a collaboration with the Dutch National Institute for Public Health and the Environment (RIVM) to evaluate the applicability of the SUDOQU methodology for the derivation of nuclide-specific surface-clearance criteria for objects released from nuclear facilities. SUDOQU is a methodology for the dose assessment of exposure to a surface-contaminated object, with the innovative assumption of a time-dependent surface activity whose evolution is influenced by removal and deposition mechanisms. In this work, calculations were performed to evaluate the annual effective dose resulting from the use of a typical office item, e.g. a bookcase. Preliminary results allow understanding the interdependencies between the model's underlying mechanisms, and show a strong sensitivity to the main input parameters. The results were benchmarked against those from a model described in Radiation Protection 101, to investigate the impact of the model's main assumptions. Results of the two models were in good agreement. The SUDOQU methodology appears to be a flexible and powerful tool, suitable for the proposed application. Therefore, the project will be extended to more generic study cases, to eventually develop surface-clearance levels applicable to objects leaving nuclear facilities.

  9. Application of the Management System for Facilities and Activities. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities.

  10. Radioactive Air Emmission Notice of Construction (NOC) Application for the Waste Receiving and Processing Facility (WRAP)

    International Nuclear Information System (INIS)

    MENARD, N.M.

    2000-01-01

    This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61.07 for the Waste Receiving and Processing (WRAP) Facility. The rewrite of this NOC incorporates all the approved revisions (Sections 5.0, 6.0, 8.0, and 9.0), a revised potential to emit (PTE) based on the revised maximally exposed individual (MEI) (Sections 8.0, 10.0, 11.0, 12.0, 13.0, 14.0, and 15.0), the results of a study on fugitive emissions (Sections 6.0, 10.0, and 15.0), and reflects the current operating conditions at the WRAP Facility (Section 5.0). This NOC replaces DOE/RL-93-15 and DOE/RL-93-16 in their entirety. The primary function of the WRAP Facility is to examine, assay, characterize, treat, verify, and repackage radioactive material and mixed waste. There are two sources of emissions from the WRAP Facility: stack emissions and fugitive emissions. The stack emissions have an unabated total effective dose equivalent (TEDE) estimate to the hypothetical offsite MEI of 1.13 E+02 millirem per year. The abated TEDE for the stack emissions is estimated at 5.63 E-02 millirem per year to the MEI. The fugitive emissions have an unabated TEDE estimate to the hypothetical offsite MEI of 5.87 E-04. There is no abatement for the fugitive emissions

  11. Study on application of radiation and radioisotopes -Development of the radioisotope production facilities for the HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ji Bok; Woo, Jong Sub; Kang, Byung Woi; Baek, Sam Tae; Jeong, Un Soo; Park, Yong Chul; Jeon, Young Keon; Chang, Chun Ik; Lee, Bong Jae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-08-01

    Development and construction of the lead hot cell for radioisotope production and related facility. 1. Fabrication and installation of the lead H/C system. 2. Development and installation of the hydraulic transfer system. 3. Development of the radiation monitoring system. 4. Fabrication and installation of the fire extinguishing system in the H/C. 5. Fabrication and installation of the fume hood. 4 tabs.,10 figs. (Author).

  12. Facile fabrication of boron nitride nanosheets-amorphous carbon hybrid film for optoelectronic applications

    KAUST Repository

    Wan, Shanhong

    2015-01-01

    A novel boron nitride nanosheets (BNNSs)-amorphous carbon (a-C) hybrid film has been deposited successfully on silicon substrates by simultaneous electrochemical deposition, and showed a good integrity of this B-C-N composite film by the interfacial bonding. This synthesis can potentially provide the facile control of the B-C-N composite film for the potential optoelectronic devices. This journal is

  13. MCNP Variance Reduction technique application for the Development Of the Citrusdal Irradiation Facility

    International Nuclear Information System (INIS)

    Makgae, R.

    2008-01-01

    A private company, Citrus Research International (CIR) is intending to construct an insect irradiation facility for the irradiation of insect for pest management in south western region of South Africa. The facility will employ a Co-60 cylindrical source in the chamber. An adequate thickness for the concrete shielding walls and the ability of the labyrinth leading to the irradiation chamber, to attenuate radiation to dose rates that are acceptably low, were determined. Two methods of MCNP variance reduction techniques were applied to accommodate the two pathways of deep penetration to evaluate the radiological impact outside the 150 cm concrete walls and steaming of gamma photons through the labyrinth. The point-kernel based MicroShield software was used in the deep penetration calculations for the walls around the source room to test its accuracy and the results obtained are in good agreement with about 15-20% difference. The dose rate mapping due to radiation Streaming along the labyrinth to the facility entrance is also to be validated with the Attila code, which is a deterministic code that solves the Discrete Ordinates approximation. This file provides a template for writing papers for the conference. (authors)

  14. MCNP Variance Reduction technique application for the Development Of the Citrusdal Irradiation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Makgae, R. [Pebble Bed Modular Reactor (PBMR), P.O. Box 9396, Centurion (South Africa)

    2008-07-01

    A private company, Citrus Research International (CIR) is intending to construct an insect irradiation facility for the irradiation of insect for pest management in south western region of South Africa. The facility will employ a Co-60 cylindrical source in the chamber. An adequate thickness for the concrete shielding walls and the ability of the labyrinth leading to the irradiation chamber, to attenuate radiation to dose rates that are acceptably low, were determined. Two methods of MCNP variance reduction techniques were applied to accommodate the two pathways of deep penetration to evaluate the radiological impact outside the 150 cm concrete walls and steaming of gamma photons through the labyrinth. The point-kernel based MicroShield software was used in the deep penetration calculations for the walls around the source room to test its accuracy and the results obtained are in good agreement with about 15-20% difference. The dose rate mapping due to radiation Streaming along the labyrinth to the facility entrance is also to be validated with the Attila code, which is a deterministic code that solves the Discrete Ordinates approximation. This file provides a template for writing papers for the conference. (authors)

  15. Application of demography to energy facility development projects. Working Paper No. 39

    International Nuclear Information System (INIS)

    Krannich, R.S.; Stanfield, G.G.

    1977-01-01

    The emergence of concern regarding socioeconomic consequences of large-scale development projects has resulted in a growing literature directed as estimating the types and levels of various impact dimensions which can be expected to result in human communities experiencing such development. Among these dimensions, a focus on population change has been prevalent. Accurate demographic predictions may be viewed as critical for the adequate comprehension of and preparation for impacts deriving from projects such as energy facility developments. Unfortunately, the state of the art in projecting demographic consequences of energy projects has been generally inadequate. Several of the more influential prior methods for estimating local demographic effects of developing energy facilities are critiqued, although their specific prediction figures are not summarized. The studies reviewed were found to be of dubious practical utility, probably due in part to the failure of basic demography to provide a base of support for applied demographic research. This report sets forth recommendations for the development of a theoretical perspective which would more adequately serve the needs of practitioners attempting to predict local demographic effects of energy facility development

  16. Application of earthquake early warning system for disaster prevention in nuclear facilities

    International Nuclear Information System (INIS)

    Ionescu, C.; Dumitru, G.; Oprescu, T.; Ana, E.; Sofilca, N.; Grigore, D.

    2007-01-01

    Full text: The Romanian seismicity is dominated by the Vrancea deep (60-200 km) earthquakes which take place in a small volume located at the bend of Carpathian mountains, the place where three tectonic units are interacting: East-European, Intra-Alpine plates and Moesic sub-plate. Two or three events per century are devastating; having high energy they are felt over large and highly populated areas. The achievement of a seismic vulnerability reduction system for industrial and technological processes in the nuclear field intends to reduce possible after-earthquake damages which can take place in nuclear facilities situated in an extended area as compared to the usual one affected by Vrancea earthquakes. In this situation there are nuclear specific facilities like: - Van de Graaff Accelerator of IFIN-HH at Magurele; - TRIGA reactor operated at Pitesti, Mioveni, Jud. Arges; - Experimental Pilot Plant for tritium and deuterium separation of ICSI at Ramnicu Valcea; - Heavy water plant Drobeta Turnu Severin, Mehedinti. We intend to implement EEWS in the above sites in order to have a warning decision for earthquakes produced in Vrancea, Campulung Muscel and Herculane areas and its error-free transmission for activating the safety regulations for these facilities. (authors)

  17. Lessons learned from application of the Swedish regulations for decommissioning of nuclear facilities - The regulator's perspective

    International Nuclear Information System (INIS)

    Efraimsson, Henrik; Amft, Martin; Leisvik, Mathias

    2016-01-01

    The paper presents an overview of the Swedish regulations for decommissioning of nuclear facilities. It describes some of the experiences that the Swedish Radiation Safety Authority has gained from the application of these regulations. The focus of the present paper lies on administrative aspects of the care and maintenance operation and on the safety related documentation that has to be prepared before dismantling commences. Lessons learned during recent years will be considered when revising the regulations for decommissioning. Also these lessons learned will help to streamline the administration of the large NPP decommissioning projects that are anticipated to commence in Sweden in the near future. (authors)

  18. 1993 RCRA Part B permit renewal application, Savannah River Site: Volume 10, Consolidated Incineration Facility, Section C, Revision 1

    International Nuclear Information System (INIS)

    Molen, G.

    1993-08-01

    This section describes the chemical and physical nature of the RCRA regulated hazardous wastes to be handled, stored, and incinerated at the Consolidated Incineration Facility (CIF) at the Savannah River Site. It is in accordance with requirements of South Carolina Hazardous Waste Management Regulations R.61-79.264.13(a) and(b), and 270.14(b)(2). This application is for permit to store and teat these hazardous wastes as required for the operation of CIF. The permit is to cover the storage of hazardous waste in containers and of waste in six hazardous waste storage tanks. Treatment processes include incineration, solidification of ash, and neutralization of scrubber blowdown

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

    International Nuclear Information System (INIS)

    Cardenas, Jose Patricio Nahuel

    2010-01-01

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

  20. Examination of methods of proliferation control for application to nuclear fuel reprocessing facilities

    International Nuclear Information System (INIS)

    O'Hara, F.A.

    1980-01-01

    Potential methods are examined that could be applied to the nuclear fuel reprocessing facility as a means of more effectively controlling the proliferation threat and, at the same time, permitting the further development of nuclear power as an energy source. The proposed remedies for this problem are basically technical or economic and political in nature and include: ''technical fixes'', institutional arrangements, and international political solutions. Each of these approaches to the problem is examined, along with a consideration of their interaction and an estimation of their effectiveness, either individually or in combination. 22 refs

  1. Facile Synthesis of Novel Nanostructured MnO2Thin Films and Their Application in Supercapacitors

    Directory of Open Access Journals (Sweden)

    Xia H

    2009-01-01

    Full Text Available Abstract Nanostructured α-MnO2thin films with different morphologies are grown on the platinum substrates by a facile solution method without any assistance of template or surfactant. Microstructural characterization reveals that morphology evolution from dandelion-like spheres to nanoflakes of the as-grown MnO2is controlled by synthesis temperature. The capacitive behavior of the MnO2thin films with different morphologies are studied by cyclic voltammetry. The α-MnO2thin films composed of dandelion-like spheres exhibit high specific capacitance, good rate capability, and excellent long-term cycling stability.

  2. Application of Glycine-TTC dosimeter in gamma radiation processing facility

    International Nuclear Information System (INIS)

    Shinde, S.H.; Mondal, S.; Kulkarni, M.S.

    2018-01-01

    Glycine-TTC dosimeter was found to have a useful dose range of 5 to 30 kGy using spectro-photometric read-out method. Potential use of this dosimeter was demonstrated by measuring dose-rate in gamma chamber GC 900. The aim of the present study was to verify the performance of this dosimeter in actual industrial processing conditions encountered in radiation processing facility such as Gamma Radiation Processing Plant for Spices (GRPPS), BRIT, Vashi. Accordingly, glycine-TTC dosimeters were irradiated along with routine dosimeter viz. ceric-cerous of GRPPS and reference standard dosimeter viz. alanine EPR

  3. Application of the LR-56 at DOE Facilities in the United States

    International Nuclear Information System (INIS)

    Smith, A.C.

    1998-05-01

    The ability to ship Type B liquid packages will be necessary for the nuclear industry to meet the energy production requirements of the next century. There are no packages licensed in the United States for transportation of large quantities of such liquids at present. Packages designed for transporting liquids must address technical challenges and incorporate features which are not common to packages designed for solid contents. These issues and the methods of addressing them are illustrated by the safety analysis performed for utilization of the LR-56 Liquid Package at US DOE facilities

  4. Application of Bayesian network methodology to the probabilistic risk assessment of nuclear waste disposal facility

    International Nuclear Information System (INIS)

    Lee, Chang Ju

    2006-02-01

    The scenario in a risk analysis can be defined as the propagating feature of specific initiating event which can go to a wide range of undesirable consequences. If one takes various scenarios into consideration, the risk analysis becomes more complex than do without them. A lot of risk analyses have been performed to actually estimate a risk profile under both uncertain future states of hazard sources and undesirable scenarios. Unfortunately, in case of considering some stochastic passive systems such as a radioactive waste disposal facility, since the behaviour of future scenarios is hardly predicted without special reasoning process, we cannot estimate their risk only with a traditional risk analysis methodology. Moreover, it is believed that the sources of uncertainty at future states can be reduced pertinently by setting up dependency relationships interrelating geological, hydrological, and ecological aspects of the site with all the scenarios. It is then required current methodology of uncertainty analysis of the waste disposal facility be revisited under this belief. In order to consider the effects predicting from an evolution of environmental conditions of waste disposal facilities, this study proposes a quantitative assessment framework integrating the inference process of Bayesian network to the traditional probabilistic risk analysis. In this study an approximate probabilistic inference program for the specific Bayesian network developed and verified using a bounded-variance likelihood weighting algorithm. Ultimately, specific models, including a Monte-Carlo model for uncertainty propagation of relevant parameters, were developed with a comparison of variable-specific effects due to the occurrence of diverse altered evolution scenarios (AESs). After providing supporting information to get a variety of quantitative expectations about the dependency relationship between domain variables and AESs, this study could connect the results of probabilistic

  5. Manitoba Hydro's environmental management system and its application to hydraulic facilities and operations

    International Nuclear Information System (INIS)

    Windsor, D. C.

    1996-01-01

    Development at Manitoba Hydro of a series of environmental practices manuals, as part of the public utilities' approach to environmental management, were described. Experiences gained during the process of developing these manuals were described. It has been found that to be accepted environmental practices must: (1) support existing facilities, operations and procedures, (2) be presented in an easily accessible form, (3) have an evident purpose, (4) be stated clearly; (5) be practical and feasible, and (6) have implementation clearly defined. The audience level of detail, style of presentation, implementation, frequency of revision and update were also summarized. A detailed outline of the current policy of Manitoba Hydro was included in the appendices

  6. Applicability of Long Duration Exposure Facility environmental effects data to the design of Space Station Freedom electrical power system

    Science.gov (United States)

    Christie, Robert J.; Lu, Cheng-Yi; Aronoff, Irene

    1992-01-01

    Data defining space environmental effects on the Long Duration Exposure Facility (LDEF) are examined in terms of the design of the electrical power system (EPS) of the Space Station Freedom (SSF). The significant effects of long-term exposure to space are identified with respect to the performance of the LDEF's materials, components, and systems. A total of 57 experiments were conducted on the LDEF yielding information regarding coatings, thermal systems, electronics, optics, and power systems. The resulting database is analyzed in terms of the specifications of the SSF EPS materials and subsystems and is found to be valuable in the design of control and protection features. Specific applications are listed for findings regarding the thermal environment, atomic oxygen, UV and ionizing radiation, debris, and contamination. The LDEF data are shown to have a considerable number of applications to the design and planning of the SSF and its EPS.

  7. Application of the MOSAR method to the safety analysis of facilities at the French atomic energy commission

    International Nuclear Information System (INIS)

    Donie, Ph.; Kimmel, D.; Launay, R.

    2002-09-01

    This document presents the MOSAR method (systemic organized method of risk analysis) developed by the French atomic energy commission (CEA) for the carrying out of 'a priori' (before any accident occurrence) risk analyses. The objective of the method is to look for technical and operational malfunctions in a facility or in a process and in a defined environment. The MOSAR method is based both on a systemic approach and on the analysis of all potential sources of danger intrinsic to the system. The aim of this document is: to recall the principles of the method, to present its tools in a standardized way, to give some application rules for a pragmatic and progressive approach based on validated data, and to show in conclusion the different types of application using a consistent approach. (J.S.)

  8. Application of Plenoptic PIV for 3D Velocity Measurements Over Roughness Elements in a Refractive Index Matched Facility

    Science.gov (United States)

    Thurow, Brian; Johnson, Kyle; Kim, Taehoon; Blois, Gianluca; Best, Jim; Christensen, Ken

    2014-11-01

    The application of Plenoptic PIV in a Refractive Index Matched (RIM) facility housed at Illinois is presented. Plenoptic PIV is an emerging 3D diagnostic that exploits the light-field imaging capabilities of a plenoptic camera. Plenoptic cameras utilize a microlens array to measure the position and angle of light rays captured by the camera. 3D/3C velocity fields are determined through application of the MART algorithm for volume reconstruction and a conventional 3D cross-correlation PIV algorithm. The RIM facility is a recirculating tunnel with a 62.5% aqueous solution of sodium iodide used as the working fluid. Its resulting index of 1.49 is equal to that of acrylic. Plenoptic PIV was used to measure the 3D velocity field of a turbulent boundary layer flow over a smooth wall, a single wall-mounted hemisphere and a full array of hemispheres (i.e. a rough wall) with a k/ δ ~ 4.6. Preliminary time averaged and instantaneous 3D velocity fields will be presented. This material is based upon work supported by the National Science Foundation under Grant No. 1235726.

  9. The application of advanced remote systems technology to future waste handling facilities: Waste Systems Data and Development Program

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two FWMS major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment. 5 refs., 7 figs

  10. Agreement Between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities. Addition to the List of Facilities Subject to Safeguards Under the Agreement

    International Nuclear Information System (INIS)

    2014-01-01

    In accordance with Paragraph 14(a) of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities (hereinafter “the Agreement”), India shall notify the Agency in writing of its decision to offer any facility identified by India for Agency safeguards under the Agreement. Any facility so notified by India becomes subject to the Agreement as of the date of receipt by the Agency of such written notification from India, and is to be included in the Annex to the Agreement. On 11 March 2014, the Agency received from India written notification, pursuant to Paragraph 14(a) of the Agreement, of its decision to bring one additional facility under safeguards in accordance with the provisions of the Agreement. Pursuant to Paragraph 14 4(a) of the Agreement, the Annex to the Agreement has been updated and is reproduced in this document for the information of all Members of the Agency

  11. Development and application of computerized maintenance management system at a nuclear fuel cycle facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Yon Woo; Kim, S D; Jang, K D; Kim, Y G

    2001-12-01

    In order to accomplish the purpose of research, it is the most important for the equipment to work well. The computerized maintenance management system proven by the case-studies can have an effect on the research and it can be one of the most major elements to assist the research at the research laboratory. To prevent the breakdown of the equipment at the research facility which can hinder the improvement of the research work, it is essential to maintain the equipment of facility without the sudden breakdown and to short the recovery time. If these elements such as the causes of the breakdown were well-managed and suvervised with care, this recovery time could be minimized. The aims of this research, therefore, are to introduce the development of the computerized maintenance management system and to apply it at the field in order to minimize the breakdown of the equipment and the recovery time and in order to perform the equipment maintenance service with the minimized expense and maximize the service efficiency through the planned management of the budget, the manpower and the service00.

  12. Slow positron applications at slow positron facility of institute of materials structure science, KEK

    Science.gov (United States)

    Hyodo, Toshio; Mochizuki, Izumi; Wada, Ken; Toge, Nobukazu; Shidara, Tetsuo

    2018-05-01

    Slow Positron Facility at High Energy Accelerator Research Organization (KEK) is a user dedicated facility with an energy-tunable (0.1 - 35 keV) slow positron beam created by a dedicated ˜ 50 MeV linac. It operates in a short pulse (width 1-12 ns, variable, 5×106 e+/s) and a long pulse (width 1.2 µs, 5×107 e+/s) modes of 50 Hz. High energy positrons from pair creation are moderated by reemission after thermalization in W foils. The reemitted positrons are then electrostatically accelerated to a desired energy up to 35 keV and magnetically transported. A pulse-stretching section (pulse stretcher) is installed in the middle of the beamline. It stretches the slow positron pulse for the experiments where too many positrons annihilating in the sample at the same time has to be avoided. Four experiment stations for TRHEPD (total-reflection high-energy positron diffraction), LEPD (low-energy positron diffraction), Ps- (positronium negative ion), and Ps-TOF (positronium time-of-flight) experiments are connected to the beamline branches, SPF-A3, SPF-A4, SPF-B1 and SPF-B2, respectively. Recent results of these stations are briefly described.

  13. Development and application of computerized maintenance management system at a nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Oh, Yon Woo; Kim, S. D.; Jang, K. D.; Kim, Y. G.

    2001-12-01

    In order to accomplish the purpose of research, it is the most important for the equipment to work well. The computerized maintenance management system proven by the case-studies can have an effect on the research and it can be one of the most major elements to assist the research at the research laboratory. To prevent the breakdown of the equipment at the research facility which can hinder the improvement of the research work, it is essential to maintain the equipment of facility without the sudden breakdown and to short the recovery time. If these elements such as the causes of the breakdown were well-managed and suvervised with care, this recovery time could be minimized. The aims of this research, therefore, are to introduce the development of the computerized maintenance management system and to apply it at the field in order to minimize the breakdown of the equipment and the recovery time and in order to perform the equipment maintenance service with the minimized expense and maximize the service efficiency through the planned management of the budget, the manpower and the service

  14. Application of personal computer to development of entrance management system for radiating facilities

    International Nuclear Information System (INIS)

    Suzuki, Shogo; Hirai, Shouji

    1989-01-01

    The report describes a system for managing the entrance and exit of personnel to radiating facilities. A personal computer is applied to its development. Major features of the system is outlined first. The computer is connected to the gate and two magnetic card readers provided at the gate. The gate, which is installed at the entrance to a room under control, opens only for those who have a valid card. The entrance-exit management program developed is described next. The following three files are used: ID master file (random file of the magnetic card number, name, qualification, etc., of each card carrier), entrance-exit management file (random file of time of entrance/exit, etc., updated everyday), and entrance-exit record file (sequential file of card number, name, date, etc.), which are stored on floppy disks. A display is provided to show various lists including a list of workers currently in the room and a list of workers who left the room at earlier times of the day. This system is useful for entrance management of a relatively small facility. Though small in required cost, it requires only a few operators to perform effective personnel management. (N.K.)

  15. Applicability of water-jet cutting technology to nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Abe, Tadashi; Nisizaki, Tadashi; Matumura, Hiroyuki; Ikemoto, Yosikazu; Simizu, Hideki

    1991-01-01

    In nuclear facilities there exist, besides relatively simple components, such as vessels and piping, numerous complex components including the multilayered plate with water layer in between, a bunch of thin tubes and composite lamination of dissimilar materials like metal/non-metal. In conventional development of reactor dismantling technology, the technology development has been made mainly for remote cutting of thick-walled structures like the reactor pressure vessel and the reactor internals. These techniques, however, are not always suitable in cutting the above-mentioned structures. As means of cutting such structures efficiently, these is available the abrasion water-jet cutting technology. This technology is now drawing attention for cutting or shaping new materials like composite material and ceramics in high precision and high efficiency. In the present report by way of its feasibility in nuclear facilities decommissioning the following are described. Principle and features of the water-jet cutting technology, system con-figuration, cutting or shaping performance, and some examples of the cutting and shaping. (author)

  16. The DRAGON aerosol research facility to study aerosol behaviour for reactor safety applications

    International Nuclear Information System (INIS)

    Suckow, Detlef; Guentay, Salih

    2008-01-01

    During a severe accident in a nuclear power plant fission products are expected to be released in form of aerosol particles and droplets. To study the behaviour of safety relevant reactor components under aerosol loads and prototypical severe accident conditions the multi-purpose aerosol generation facility DRAGON is used since 1994 for several projects. DRAGON can generate aerosol particles by the evaporation-condensation technique using a plasma torch system, fluidized bed and atomization of particles suspended in a liquid. Soluble, hygroscopic aerosol (i.e. CsOH) and insoluble aerosol particles (i.e. SnO 2 , TiO 2 ) or mixtures of them can be used. DRAGON uses state-of-the-art thermal-hydraulic, data acquisition and aerosol measurement techniques and is mainly composed of a mixing chamber, the plasma torch system, a steam generator, nitrogen gas and compressed air delivery systems, several aerosol delivery piping, gas heaters and several auxiliary systems to provide vacuum, coolant and off-gas treatment. The facility can be operated at system pressure of 5 bars, temperatures of 300 deg. C, flow rates of non-condensable gas of 900 kg/h and steam of 270 kg/h, respectively. A test section under investigation is attached to DRAGON. The paper summarizes and demonstrates with the help of two project examples the capabilities of DRAGON for reactor safety studies. (authors)

  17. Tetraphenylpyrimidine-Based AIEgens: Facile Preparation, Theoretical Investigation and Practical Application

    Directory of Open Access Journals (Sweden)

    Junkai Liu

    2017-10-01

    Full Text Available Aggregation-induced emission (AIE has become a hot research area and tremendous amounts of AIE-active luminogens (AIEgens have been generated. To further promote the development of AIE, new AIEgens are highly desirable. Herein, new AIEgens based on tetraphenylpyrimidine (TPPM are rationally designed according to the AIE mechanism of restriction of intramolecular motion, and facilely prepared under mild reaction conditions. The photophysical property of the generated TPPM, TPPM-4M and TPPM-4P are systematically investigated and the results show that they feature the aggregation-enhanced emission (AEE characteristics. Theoretical study shows the high-frequency bending vibrations in the central pyrimidine ring of TPPM derivatives dominate the nonradiative decay channels. Thanks to the AEE feature, their aggregates can be used to detect explosives with super-amplification quenching effects, and the sensing ability is higher than typical AIE-active tetraphenylethene. It is anticipated that TPPM derivatives could serve as a new type of widely used AIEgen based on their facile preparation and good thermo-, photo- and chemostabilities.

  18. Study of the application of near-real-time materials accountancy to safeguards for reprocessing facilities

    International Nuclear Information System (INIS)

    Ikawa, Koji; Ihara, Hitoshi; Nishimura, Hideo; Hirata, Mitsuho; Sakuragi, Hirotaka; Ido, Masaru.

    1983-09-01

    This report describes the results of TASTEX task F, the basic purpose of which was to investigate the feasibility of applying the basic concepts of near-real-time materials accountancy to small or medium-sized spent fuel reprocessing facilities, using the PNC-Tokai facility as a model. The background of Task-F and the proposed IAEA requirements on reprocessing plant safeguards are briefly shown. A model of near-real-time materials accountancy based on weekly material balances covering the entire process MBA is outlined, and the effectiveness of this model is evaluated based on simulation and analysis procedures developed for the study. The results show that the proposed materials accountancy model should provide sufficient information to satisfy IAEA guidelines for detection goals. Field testing of the model began in 1980, and the preliminary evaluation of this field test data shows that weekly in-process physical inventories are possible without affecting process operations. This report also describes studies related to IAEA verification procedures, and identifies necessary further work. (author)

  19. Co9S8 nanotubes: facile synthesis and application in the catalytic ...

    Indian Academy of Sciences (India)

    spectrometry and scanning electron microscopy. The result displays that the ... research interest due to their potential applications in cata- lysis, optical, electronic ... for catalysts, supercapacitors and Li-ion batteries [5–8]. In recent years, cobalt ...

  20. Installation of a flow cytometry facility and some applications in radiobiology

    International Nuclear Information System (INIS)

    Walsh, M.; Kellington, J.P.

    1988-01-01

    Flow cytometry has enormous potential in many areas of experimental pathology. Details of the installation and commissioning of a flow cytometer at the Harwell Laboratory are described. Following an explanation of the principles of flow cytometry, several applications to specific problems in radiobiology are discussed. Also included are results of some preliminary studies with the Harwell flow cytometer on samples such as blood, bone marrow, macrophages and cell cultures, and a discussion of future applications. (author)

  1. Preparing to review the license application of the French geological disposal facility - Issues, challenges and perspectives

    International Nuclear Information System (INIS)

    Dandrieux, Geraldine

    2014-01-01

    This paper briefly describes the French context for GDR authorization, the French dedicated legislative framework (28 June 2006 Act on sustainable management of radioactive materials and waste), the challenges (regulatory issues, long-term project supervision, technical issues, procedural issues), and the preparing for the review of the DGR license application. A planning schedule is propose with Andra to submit license application for DGR in 2015

  2. Application Platform for Intelligent Mobility – research facility for intelligent mobility services

    OpenAIRE

    Schnieder, Lars

    2012-01-01

    Traffic can be seen as a multi-dimensional field of research. Traffic can be best described as a socio-technical system which brings about new challenges for the design of future transportation systems. With its Application Platform for Intelligent Mobility (AIM), the German Aerospace Center (DLR), together with the state of Lower Saxony, the city of Braunschweig and other partners, is creating a unique way of linking up research, development and applications for intelligent transportation an...

  3. Application of the Management System for Facilities and Activities. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix I: Transition to an integrated management system; Appendix II: Activities in the document control process; Appendix III: Activities in the procurement process; Appendix IV: Performance of independent assessments; Annex I: Electronic document management system; Annex II: Media for record storage; Annex III: Record retention and storage; Glossary.

  4. Bejing synchrotron radiation TXRF facility and its applications on trace element study of cells

    International Nuclear Information System (INIS)

    Yuying, H.; Yingrong, W.; Limin, Z.; Guangcheng, L.; Wie, H.

    2000-01-01

    In this paper, Beijing synchrotron radiation TXRF facility and experimental method were described. The minimum detection limits of some elements were tested by using several kinds of standard reference materials. The feasibility of using TXRF in biomedical field is discussed. With this technique small intestine cells of both normal and radiated white mice were analyzed, and the elemental average contents of each single cell are also given. The results indicated that the contents of some trace elements for normal and radiated white mice are greatly different, which may be used to provide valuable reference for clinic medicine. On the other hand, the trace elements of cells of lung and cervix cancer before and after apoptosis were determined by SRTXRF and the changes of trace elements in these cells were discussed. (author)

  5. Application of SAFRAN Tool for Knowledge Management at the Decommissioning Stage of Nuclear Facilities

    International Nuclear Information System (INIS)

    Smetnik, A.; Potapov, V.; Kapralov, E.; Murlis, D.

    2016-01-01

    Full text: As a result of the work performed by specialists of FSUE VO “Safety” under the scope of the CRAFT Project, the IAEA methodology and SAFRAN tool were used for safety assessment of radioactive waste removal from historical near-surface storage of the radon type. SAFRAN tool can be considered as an effective tool for record keeping, safety assessment and knowledge management at the stage of decommissioning of nuclear facilities. Main advantages of SAFRAN: • it uses methodologies agreed upon at the international level, namely, by IAEA standards; • several experts can work more effectively when performing the same safety assessment. SAFRAN makes it easier to exchange experience through sharing projects and data bases; • it is helpful for systematic and structured safety assessment as per safety standards; • it manages information and data in the same software environment. (author

  6. Compilation of nuclear safety criteria potential application to DOE nonreactor facilities

    International Nuclear Information System (INIS)

    1992-03-01

    This bibliographic document compiles nuclear safety criteria applied to the various areas of nuclear safety addressed in a Safety Analysis Report for a nonreactor nuclear facility (NNF). The criteria listed are derived from federal regulations, Nuclear Regulatory Commission (NRC) guides and publications, DOE and DOE contractor publications, and industry codes and standards. The titles of the chapters and sections of Regulatory Guide 3.26, ''Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants'' were used to format the chapters and sections of this compilation. In each section the criteria are compiled in four groups, namely: (1) Code of Federal Regulations, (2) USNRC Regulatory Guides, (3) Codes and Standards, and (4) Supplementary Information

  7. nPEG-TiO₂ nanoparticles: a facile route to elaborate nanostructured surfaces for biological applications.

    Science.gov (United States)

    Spadavecchia, J; Boujday, S; Landoulsi, J; Pradier, C-M

    2011-07-01

    We report the synthesis of diacid-terminated PEG-functionalized cubic TiO(2) nanocrystals by a simple one-step solvothermal method, and their further use to form nanostructured surfaces for protein immobilization. The relevance and major interest of the so-obtained nanocrystals are the presence of terminal carboxylic acid groups at their surface, as confirmed by infrared analyses, in addition to the surrounding PEG chains, essential to avoid non specific interactions. These functional chemical groups were used to (i) immobilize the synthesized nanocubes on a cysteamine-modified Au surface, and to (ii) attach proteins via a presumable covalent link. AFM images show that the shapes and the narrow size distribution of the nanocubes, observed by TEM, were preserved after their immobilization on the modified Au surface. Moreover, the efficiency and specificity of antigen recognition were demonstrated using spectroscopic analyses. Our successful approach provides a versatile and facile way to elaborate specific and sensitive nanostructured surfaces for biosensors.

  8. Seismic fragility of reinforced concrete structures and components for application to nuclear facilities

    International Nuclear Information System (INIS)

    Gergely, P.

    1984-09-01

    The failure and fragility analyses of reinforced concrete structures and elements in nuclear reactor facilities within the Seismic Safety Margins Research Program (SSMRP) at the Lawrence Livermore National Laboratory are evaluated. Uncertainties in material modeling, behavior of low shear walls, and seismic risk assessment for nonlinear response receive special attention. Problems with ductility-based spectral deamplification and prediction of the stiffness of reinforced concrete walls at low stress levels are examined. It is recommended to use relatively low damping values in connection with ductility-based response reductions. The study of static nonlinear force-deflection curves is advocated for better nonlinear dynamic response predictions. Several details of the seismic risk analysis of the Zion plant are also evaluated. 73 references

  9. Facile Synthesis of Porous Silicon Nanofibers by Magnesium Reduction for Application in Lithium Ion Batteries.

    Science.gov (United States)

    Cho, Daehwan; Kim, Moonkyoung; Hwang, Jeonghyun; Park, Jay Hoon; Joo, Yong Lak; Jeong, Youngjin

    2015-12-01

    We report a facile fabrication of porous silicon nanofibers by a simple three-stage procedure. Polymer/silicon precursor composite nanofibers are first fabricated by electrospinning, a water-based spinning dope, which undergoes subsequent heat treatment and then reduction using magnesium to be converted into porous silicon nanofibers. The porous silicon nanofibers are coated with a graphene by using a plasma-enhanced chemical vapor deposition for use as an anode material of lithium ion batteries. The porous silicon nanofibers can be mass-produced by a simple and solvent-free method, which uses an environmental-friendly polymer solution. The graphene-coated silicon nanofibers show an improved cycling performance of a capacity retention than the pure silicon nanofibers due to the suppression of the volume change and the increase of electric conductivity by the graphene.

  10. The application of integrated safety management principles to the Tritium Extraction Facility project

    International Nuclear Information System (INIS)

    Hickman, M.O.; Viviano, R.R.

    2000-01-01

    The DOE has developed a program that is accomplishing a heightened safety posture across the complex. The Integrated Safety Management (ISM) System (ISMS) program utilizes five core functions and seven guiding principles as the basis for implementation. The core functions define the work scope, analyze the hazards, develop and implement hazard controls, perform the work, and provide feedback for improvement. The guiding principles include line management responsibility, clear roles and responsibilities, competence per responsibilities, identification of safety standards/requirements, tailored hazard control, balanced priorities, and operations authorization. There exists an unspecified eighth principle, that is, worker involvement. A program requiring the direct involvement of the employees who are actually performing the work has been shown to be quite an effective method of communicating safety requirements, controlling work in a safe manner, and reducing safety violations and injuries. The Tritium Extraction Facility (TEF) projects, a component of the DOE's Commercial Light Water Reactor Tritium Production program, has taken the ISM principles and core functions and applied them to the project's design. The task of the design team is to design a facility and systems that will meet the production requirements of the DOE tritium mission as well as a design that minimizes the workers' exposure to adverse safety situations and hazards/hazardous materials. During the development of the preliminary design for the TEF, design teams consisted of not only designers but also personnel who had operational experience in the existing tritium and personnel who had operational experience in the existing tritium and personnel who had specialized experience from across the DOE complex. This design team reviewed multiple documents associated with the TEF operation in order to identify and document the hazards associated with the tritium process. These documents include hazards

  11. Application of quality assurance to the design, procurement and construction of the fast flux test facility

    International Nuclear Information System (INIS)

    Garland, D.L.; Glasscock, R.B.

    1978-01-01

    Experience has clearly demonstrated the need for effective quality assurance programmes throughout the design, procurement and construction phases of the Fast Flux Test Facility (FFTF). Formal quality assurance programmes for FFTF have contributed significantly to the achievement of project objectives thus far in a safe, reliable and predictable manner. Quality assurance programmes empolyed by major FFTF Project participants are based on the requirements of RDT Standard F 2-2, one of the first and most comprehensive standards of its kind. RDT F 2-2 is similar in its basic requirements to ANSI N45.2 and other quality assurance programme standards but differs in its degree of specificity, particularly in its coverage of development activities. RDT F 2-2 is widely applied to a variety of large and small nuclear energy development projects and technology programmes. Full implementation of RDT F 2-2 across the FFTF Project has had its problems and rewards. Problems have been encountered involving misinterpretation or overapplication of requirements. In some instances the problems pointed to the need for more specific requirements, and so the standard was amended to rectify the shortcomings. One valuable lesson learned is that feedback of use experience is essential to the development of a living, viable standard which can be beneficially applied to other projects. Benefits and cost savings have accrued from the preventive aspects of RDT F 2-2. Some examples of experiences and resulting amendments to RDT F 2-2, and their favourable impact on facility costs and schedule, are discussed in this paper. (author)

  12. A web-based three-tier control and monitoring application for integrated facility management of photovoltaic systems

    Directory of Open Access Journals (Sweden)

    Apostolos Meliones

    2014-01-01

    Full Text Available The architecture of a control system can be designed vertically with the distinction between functional levels. We adopt this layered approach for the design and implementation of a network-based control and monitoring application. In this paper we present the design and implementation of a network-based management application for controlling and monitoring the input and output data of remote equipment aiming at performance macro-observation, alarm detection, handling operation failures, installation security, access control, collection and recording of statistical data and provisioning of reports. The main services provided to the user and operating over the public internet and/or mobile network include control, monitoring, notification, reporting and data export. Our proposed system consists of a front-end for field (site-level control and monitoring as well as a service back-end which undertakes to collect, store and manage data from all remote installations. Hierarchical data acquisition methodology and performance macro-observation are according to the IEC 61724 standard. We have successfully used our control and monitoring application for integrated facility management of photovoltaic plant installations; nevertheless it can be easily migrated to other renewable energy generation installations and remote automation applications in general.

  13. Using limnological and optical knowledge to detect discharges from nuclear facilities - Potential application of satellite imagery for international safeguards

    International Nuclear Information System (INIS)

    Borstad, G.; Truong, Q.S. Bob; Keeffe, R.; Baines, P.; Staenz, K.; Neville, R.

    2001-01-01

    Previous work carried out under the Canadian Safeguards Support Program, has shown that thermal imagery from the American Landsat satellites could be used to detect the cooling water discharges, and could therefore be used to verify the operational status of nuclear facilities. In some images, thermal plumes could be easily detected in single band imagery with no mathematical manipulation and little image enhancement because there was a very strong thermal contrast between the effluent and the receiving water. However, for certain situations such as discharges into well mixed conditions (cold water and violent tides) the thermal plume may be more subtle. We show here that the visible bands of Landsat and IKONOS images often contain additional information, and that the thermal signature of a discharge from a nuclear facility is not the only signal available to describe its operation. This paper introduces some important hydrological phenomena that govern the biological and physical organization of water bodies, and discusses some basic concepts of marine and aquatic optics that are relevant to the safeguards problem. Using image analysis techniques that have been used widely in ocean optics work and in applications in the mapping and monitoring of water quality, we have re-analyzed data that were obtained under a joint project between various Canadian government departments. We present a preliminary examination of imagery from both satellite multispectral and aircraft hyperspectral sensors, and discuss methods to extract information that could be useful in the detection and verification of declared or undeclared nuclear activities. In one example of an IKONOS image of the Canadian Bruce Nuclear Generating Facility, simple enhancement techniques failed to find any plume other than a small jet visible in the surface wave field. With knowledge of limnology, oceanography and aquatic optics, we have been able to separate and remove the surface reflection, and detect a

  14. Nm23-M2/NDP kinase B induces endogenous c-myc and nm23-M1/NDP kinase A overexpression in BAF3 cells. Both NDP kinases protect the cells from oxidative stress-induced death

    International Nuclear Information System (INIS)

    Arnaud-Dabernat, Sandrine; Masse, Karine; Smani, Moneim; Peuchant, Evelyne; Landry, Marc; Bourbon, Pierre-Marie; Le Floch, Renaud; Daniel, Jean-Yves; Larou, Monique

    2004-01-01

    The nm23 gene family encodes nucleoside diphosphate kinases (NDPKs) which supply the cell with (d)NTPs. The human NDPKB, also known as the PuF protein, binds the c-myc promoter and transactivates the c-myc protooncogene. We have now studied the effects of mouse NDPKA and NDPKB overexpression on endogenous c-myc transactivation in the mouse BAF3 and the rat PC12 cell lines. c-myc transcripts were found to be up-regulated by NDPKB only in the BAF3 line. This suggests that c-myc transcriptional control via NDPKB depends on the presence of cell-specific co-factors. Unexpectedly, NDPKB also induced NDPKA expression. This new effect was found in both cell lines, suggesting that NDPKB-dependent nm23-M1 gene transactivation requires cis and/or trans elements different from those involved in c-myc transactivation. Moreover, the BAF3 cell proliferation capacities were found to be independent of NDPKA or B cell contents. Interestingly, cell death induced by c-myc overexpression or H 2 O 2 exposure was decreased in nm23-transfected compared to control BAF3 cells. These data collectively suggest that NDPKs might improve cell survival by a mechanism coupling DNA repair and transcriptional regulation of genes involved in DNA damage response

  15. Solar hot water systems application to the solar building test facility and the Tech House

    Science.gov (United States)

    Goble, R. L.; Jensen, R. N.; Basford, R. C.

    1976-01-01

    Projects which relate to the current national thrust toward demonstrating applied solar energy are discussed. The first project has as its primary objective the application of a system comprised of a flat plate collector field, an absorption air conditioning system, and a hot water heating system to satisfy most of the annual cooling and heating requirements of a large commercial office building. The other project addresses the application of solar collector technology to the heating and hot water requirements of a domestic residence. In this case, however, the solar system represents only one of several important technology items, the primary objective for the project being the application of space technology to the American home.

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

    International Nuclear Information System (INIS)

    Abelovszky, L.

    1979-01-01

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

  17. Two-dimensional wetting: the role of atomic steps on the nucleation of thin water films on BaF2(111) at ambient conditions.

    Science.gov (United States)

    Cardellach, M; Verdaguer, A; Santiso, J; Fraxedas, J

    2010-06-21

    The interaction of water with freshly cleaved BaF(2)(111) surfaces at ambient conditions (room temperature and under controlled humidity) has been studied using scanning force microscopy in different operation modes. The images strongly suggest a high surface diffusion of water molecules on the surface indicated by the accumulation of water at step edges forming two-dimensional bilayered structures. Steps running along the 110 crystallographic directions show a high degree of hydrophilicity, as evidenced by small step-film contact angles, while steps running along other directions exhibiting a higher degree of kinks surprisingly behave in a quite opposite way. Our results prove that morphological defects such as steps can be crucial in improving two-dimensional monolayer wetting and stabilization of multilayer grown on surfaces that show good lattice mismatch with hexagonal ice.

  18. Calculation of the hyperfine constants of Vk center in CaF2, SrF2 and BaF2

    International Nuclear Information System (INIS)

    Bufaical, R.F.

    1975-03-01

    The magnetic hyperfine constants of the V sub(K) center in CaF 2 , SrF 2 and BaF 2 have been calculated, assuming a phenomenological model, based on the F 2 central molecule, to describe the wave function of the defect. The introduction of covalence, with the ions neighboring the central molecule, have shown that this is a better description for the defect than a simple central molecule model. It was also shown that the results for the hyperfine constants are strongly dependent on the relaxations of these neighboring ions, which have been determined by fitting the experimental data. The present results are compared with other previous calculations where similar and different methods have been used. A better description for the wave function of the defect is suggested

  19. Calculation of the hyperfine constants of the V sub (K) center in CaF2, SrF2 e BaF2

    International Nuclear Information System (INIS)

    Bufaical, R.F.

    1975-03-01

    The magnetic hyperfine constants of the V sub(K) center in CaF 2 , SrF 2 and BaF 2 have been calculated, assuming a phenomenological model, based on the F - 2 'central molecule', to describe the wave function of the defect. The introduction of covalence with the ions neighboring the 'central molecule', has shown that this is a better description for the defect than a simple 'central molecule' model. It was also shown that the results for the hyperfine constants are strongly dependent on the relaxations of these neighboring ions, which have been determined by fitting the experimental data. The present results are compared with other previous calculations where similar and different methods have been used. A better description for the wave function of the defect is suggested. (author) [pt

  20. 1887 nm lasing in Tm3+-doped TeO2-BaF2-Y2O3 glass microstructured fibers

    Science.gov (United States)

    Wang, Shunbin; Yao, Chuanfei; Jia, Zhixu; Qin, Guanshi; Qin, Weiping

    2017-04-01

    In this paper, we demonstrate ∼2 μm lasing in Tm3+-doped fluorotellurite microstructured fibers. The Tm3+-doped fibers are based on TeO2-BaF2-Y2O3 glasses and fabricated by using a rod-in-tube method. Under the pump of a 1570 nm Er3+-doped fiber laser, lasing at 1887 nm is obtained in a ∼42.5 cm long Tm3+-doped fiber with a threshold pump power of 94 mW. As the pump power increases to 780 mW, the obtained maximum unsaturated power reaches up to ∼408 mW with a slop efficiency of ∼58.1%. This result indicates that the Tm3+-doped fluorotellurite fibers are promising gain media for ∼2 μm fiber lasers.

  1. 77 FR 9998 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2012-02-21

    ... more conservative values that incorporate measurement uncertainty. Additionally, one of the operating..., in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to... purpose of the adjudicatory filings and would constitute a Fair Use application, participants are...

  2. 40 CFR 60.630 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ... storage tank, field gas gathering system, or liquefied natural gas unit is covered by this subpart if it... Performance for Equipment Leaks of VOC From Onshore Natural Gas Processing Plants. § 60.630 Applicability and... onshore natural gas processing plants. (2) A compressor in VOC service or in wet gas service is an...

  3. Wireless sensor network in a nuclear facility: A technology application proposal

    International Nuclear Information System (INIS)

    Maciel, F.; Fernandez, R. O; Vilugron, R. M

    2009-01-01

    This work presents an overview of a pretended testbed implementation in order to test a bunch of developments and work in WSN technology and to acquire confidence in deployment of WSN applications and to test the integration of WSN with legacy instrumentation or information systems to improve the information coverage. [es

  4. 78 FR 54280 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-09-03

    ... the Commission's ``Agency Rules of Practice and Procedure'' in 10 CFR part 2. Interested person(s...-Filing system also distributes an email notice that provides access to the document to the NRC's Office... clarify language in the LSCS, Units 1 and 2, Technical Specifications (TS) applicable to the design...

  5. 76 FR 18801 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-04-05

    ... request: The proposed change would revise the application of Risk-Managed Technical Specifications (RMTS) to Technical Specification (TS) 3.7.7, ``Control Room Makeup and Cleanup Filtration System.'' This... change allows the Configuration Risk Management Program (CRMP) to be applied to Technical Specification...

  6. Applications of deuteration for neutron scattering, at the Australian National Deuteration Facility

    International Nuclear Information System (INIS)

    Holden, Peter

    2009-01-01

    ANSTO and Australia National Collaborative Research Infrastructure Strategy have funded a 4 year program to establish the National Deuteration Facility (NDF) which offers both in vivo deuteration of biomolecules and chemical deuteration of synthesised organic molecules to the structural biology and soft matter communities in Australia and internationally. The NDF has bio deuterated a range of native and novel polyhydroxy alkanoate (PHA) bio polyesters and is using deuterated polymers to probe interfacial phenomena in PHA/ ethyl cellulose blends and the chain behaviour of PHAs in solution using SANS. The NDF has also undertaken partial deuteration of proteins to investigate the disposition of protein subunits in complexes and protein interactions using SANS as well as per deuteration of proteins for neutron crystallographic studies.αB-crystalline is a molecular chaperone of the small heat shock protein family which prevents the formation of amyloid fibrils in various proteins including α-synuclein which is implicated in Parkinson disease. Deuteration is being used to facilitate investigation of the multimeric distribution of the A and B subunits in the 32 mer chaperone, and the mode of interaction with α-synuclein in prevention of fibril formation. Similarly, deuteration of selected subunits of magnesium chelatase (the enzyme responsible for insertion of Mg 2+ into protoporphyrin) and SANS will be used to support or exclude competing models of their organisation. Two laboratories for chemical synthesis and characterisation of completely, partially, or selectively deuterated compounds were established during 2008. Methodological trials have commenced and success demonstrated for deuterated fatty acids, alcohols, surfactants, glycols and amino acids. Such deuterated molecules will be useful in investigation of co-polymer structure, polymer behaviour in solution, micelle behaviour and bio membrane phenomena using SANS and neutron reflectometry. For example, NDF

  7. Facile synthesis of porous graphene as binder-free electrode for supercapacitor application

    Energy Technology Data Exchange (ETDEWEB)

    Luo, Guangsheng [Nanjing National Laboratory of Microstructures and Department of Physics, Jiangsu Key Laboratory for Nanotechnology, Nanjing University, Nanjing 210093 (China); Academy of Space Technolgy, Nanchang University, Nanchang, Jiangxi 330031 (China); Huang, Haifu, E-mail: haifuh@gmail.com [Nanjing National Laboratory of Microstructures and Department of Physics, Jiangsu Key Laboratory for Nanotechnology, Nanjing University, Nanjing 210093 (China); College of Physics Science and Engineering, Guangxi University, Nanning 530004 (China); Lei, Chenglong; Cheng, Zhenzhi; Wu, Xiaoshan [Nanjing National Laboratory of Microstructures and Department of Physics, Jiangsu Key Laboratory for Nanotechnology, Nanjing University, Nanjing 210093 (China); Tang, Shaolong, E-mail: tangsl@nju.edu.cn [Nanjing National Laboratory of Microstructures and Department of Physics, Jiangsu Key Laboratory for Nanotechnology, Nanjing University, Nanjing 210093 (China); Du, Youwei [Nanjing National Laboratory of Microstructures and Department of Physics, Jiangsu Key Laboratory for Nanotechnology, Nanjing University, Nanjing 210093 (China)

    2016-03-15

    Graphical abstract: - Highlights: • Our results provide a facile method to fabricate a binder-free porous rGO electrode for supercapacitors. • Polystyrene (PS) colloidal particles were used as spacers to prepare high-performance porous grapheme deposited directly on Ni foam substrate. • The specific capacitance of the rGO/NF electrode decreased by 7% after 2000 cycles and high rate capability of 53% capacitance retention at 100 A g{sup −1}. - Abstract: Here, porous grapheme oxide (GO) gel deposited on nickel foam was prepared by using polystyrene (PS) colloidal particles as spacers for use as electrodes in high rate supercapacitors, then reduced by Vitamin C aqueous solution in ambient condition. The PS particles were surrounded by reduced graphene oxide (rGO) sheets, forming crinkles and rough textures. When PS particles were selectively removed, rGO gel coated on the skeleton of Ni foam can formed an open porous structure, which prevents elf-aggregation and restacking of graphene sheets. The porous rGO-based supercapacitors exhibit excellent electrochemical performances such as a specific capacitance of 152 F g{sup −1} at 1 A g{sup −1}, high rate capability of 53% capacitance retention upon a current increase to 100 A g{sup −1} and good cycle stability, due to effective rapid and short pathways for ionic and electronic transport provided by the sub-micrometer structure of rGO gel and 3D interconnected network of Ni foam.

  8. Radiation resistant, decontaminable and sealing jointing compounds for application in nuclear facilities

    International Nuclear Information System (INIS)

    Kunze, S.

    1991-09-01

    The sealing jointing compounds applied in practice and already examined for decontaminability will be presented here. Solvent-free sealing compounds, emulsifiable in water, with low molecular epoxy resins as binders, quite a number of curing versions, and little hygroscopic filler mixtures adapted in grain size have been tested with a view to ceramic tile jointing in nuclear facilities. The sealing compounds were examined before and after exposure to gamma irradiation (300 KGy energy dose) for decontaminability, color, gloss and resistance to decontaminants. Out of fourteeen compounds exhaustively investigated ten are very well decontaminable and four well decontaminable. After exposure to radiation no or only minor changes in color and gloss, respectively, were observed. Visible changes such as cracking, bubbles, etc. were not found and the resistance to decontaminants was neither affected. It has even been possible to replace in the well decontaminable sealing compounds developed until now part of the epoxy resin binder with elasticizing components such as Thiokol which is very important as a base material for sealing compounds in the construction industry, but difficult to decontaminate. (orig.) [de

  9. Application of GIS in site selection for nuclear waste disposal facility

    International Nuclear Information System (INIS)

    Sheng, G.; Luginaah, I.N.; Sorrell, J.

    1996-01-01

    Whether designing a new facility or investigating, potential contaminant migration at an existing site, proper characterization of the subsurface conditions and their interaction with surface features is critical to the process. The Atomic Energy Control Board, states in its regulatory document R-104 that, open-quotes For the long-term management of radioactive wastes, the preferred approach is disposal, a permanent method of management in which there is no intention of retrieval and which, ideally uses techniques and designs that do not rely for their success on long-term institutional control beyond a reasonable period of timeclose quotes. Thus although storage is safe, eventually disposal is necessary to avoid long-term reliance on continuing care and attention, such as monitoring and maintenance. In Canada, the concept being proposed by Atomic Energy of Canada Limited (AECL) involves disposal in deep underground repositories in intrusive igneous rock. The aim of this concept as a disposal method is to build multiple barriers that would protect humans and the natural environment from contaminants in the radioactive waste. The multiple barriers include the geosphere, which consists of the rock, any sediments overlying the rock, and the groundwater. Nevertheless, immediate, as well as long-term, consequences, including, risk involved with technological systems and the inherent uncertainty of any forecast, make the prediction and analysis tasks of increasing importance. This uncertainty in the area of nuclear waste disposal is leading to growing concerns about nuclear waste site selection

  10. Facile preparation and characterization of ZnCdS nanocrystals for interfacial applications in photovoltaic devices.

    Science.gov (United States)

    Duan, Chenghao; Luo, Weining; Jiu, Tonggang; Li, Jiangsheng; Wang, Yao; Lu, Fushen

    2018-02-15

    Recently, ZnCdS nanocrystals (NCs) have attracted intense attention because of their specific optical properties and electrical characteristics. In this paper, a green and facile solution method is reported for the preparation of ZnCdS nanocrystals using dimethylsulfoxide as small molecular ligands. The ZnCdS nanocrystals are used as an interface modification material in the photovoltaic devices. It is found that the modification of ZnCdS on TiO 2 surface not only suppresses the recombination loss of carriers but also reduces the series resistance of TiO 2 /active layer. Consequently, both of the short circuit current (J sc ) and the fill factor (FF) of the solar cells were significantly improved. Power conversion efficiency (PCE) of 7.75% based on TiO 2 /ZnCdS was achieved in contrast to 6.65% of the reference devices based on pure TiO 2 film in organic solar cells. Furthermore, the PCE of perovskite solar cells based on TiO 2 /ZnCdS was observed with 8.3% enhancement compared to that of pure TiO 2 -based ones. Copyright © 2017 Elsevier Inc. All rights reserved.

  11. Study of applicable methods on safety verification of disposal facilities and waste packages

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Three subjects about safety verification on the disposal of low level radioactive waste were investigated in FY. 2012. For radioactive waste disposal facilities, specs and construction techniques of covering with soil to prevent possible destruction caused by natural events (e.g. earthquake) were studied to consider verification methods for those specs. For waste packages subject to near surface pit disposal, settings of scaling factor and average radioactivity concentration (hereafter referred to as ''SF'') on container-filled and solidified waste packages generated from Kashiwazaki Kariwa Nuclear Power Station Unit 1-5, setting of cesium residual ratio of molten solidified waste generated from Tokai and Tokai No.2 Power Stations, etc. were studied. Those results were finalized in consideration of the opinion from advisory panel, and publicly opened as JNES-EV reports. In FY 2012, five JNES reports were published and these have been used as standards of safety verification on waste packages. The verification method of radioactive wastes subject to near-surface trench disposal and intermediate depth disposal were also studied. For radioactive wastes which will be returned from overseas, determination methods of radioactive concentration, heat rate and hydrogen generation rate of CSD-C were established. Determination methods of radioactive concentration and heat rate of CSD-B were also established. These results will be referred to verification manuals. (author)

  12. Facile synthesis of silver nanoparticles and their application in dye degradation

    International Nuclear Information System (INIS)

    Joseph, Siby; Mathew, Beena

    2015-01-01

    Graphical abstract: - Highlights: • This synthetic method uses the novel reducing agent hexamine. • The method is simple, fast and environment friendly. • This is a cost-effective method as all materials used are inexpensive and readily available. • The method provides highly stable spherical silver nanoparticles. • The nanoparticles show outstanding catalytic activity in the degradation of organic dyes. - Abstract: The present article reports a simple, facile and eco-friendly method based on microwave irradiation for the synthesis of silver nanoparticles in aqueous medium using starch as stabilizing agent and a new reducing agent namely hexamine. The silver nanoparticles were characterized by UV–vis, FTIR, XRD and HR-TEM analysis. UV–vis spectroscopic studies provided sufficient evidences for the formation of nanoparticles. The role of starch in the synthesis and stabilization of the nanoparticles was obtained from FTIR studies. The XRD and HR-TEM investigations clearly demonstrated the crystalline nature of the nanoparticles. From the TEM images, the silver nanoparticles were found to be spherical and of nearly uniform size with an average diameter of 18.2 ± 0.97 nm. The nanoparticles showed excellent catalytic activity in the degradation of methyl orange and rhodamine B by NaBH 4

  13. Application of international safeguards to fast critical assembly facilities. FY 1980 summary report

    International Nuclear Information System (INIS)

    1980-12-01

    Nuclear materials inventory-verification techniques for large split-table fast critical assemblies are being studied in this program. Emphasis has been given to techniques that minimize fuel handling in order to reduce facility downtime and radiation exposure to the inventory team. The techniques studied include drawer seals, autoradiography, and spectral index measurements. Two-drawer sealing techniques have been studied, and the relative strengths and weaknesses are pointed out. The rod-type locking mechanism would not disrupt the reactor cooling air flow or interfere with autoradiography but is more expensive to implement. Passive autoradiography was used in a ZPPR inventory to verify to a 93% confidence level that less than 8-kg Pu was missing. The inventory was completed in four days by a five-member team with radiation exposures well within acceptable limits. Two autoradiographic film packages were developed to distinguish HEU from a DU matrix. The 30-mil pack requires an exposure between 4 and 16 hours and fits into most of the drawers. The 40-mil pack requires only a two-hour exposure but fits into less than half the drawers

  14. Health workers' knowledge of and attitudes towards computer applications in rural African health facilities.

    Science.gov (United States)

    Sukums, Felix; Mensah, Nathan; Mpembeni, Rose; Kaltschmidt, Jens; Haefeli, Walter E; Blank, Antje

    2014-01-01

    The QUALMAT (Quality of Maternal and Prenatal Care: Bridging the Know-do Gap) project has introduced an electronic clinical decision support system (CDSS) for pre-natal and maternal care services in rural primary health facilities in Burkina Faso, Ghana, and Tanzania. To report an assessment of health providers' computer knowledge, experience, and attitudes prior to the implementation of the QUALMAT electronic CDSS. A cross-sectional study was conducted with providers in 24 QUALMAT project sites. Information was collected using structured questionnaires. Chi-squared tests and one-way ANOVA describe the association between computer knowledge, attitudes, and other factors. Semi-structured interviews and focus groups were conducted to gain further insights. A total of 108 providers responded, 63% were from Tanzania and 37% from Ghana. The mean age was 37.6 years, and 79% were female. Only 40% had ever used computers, and 29% had prior computer training. About 80% were computer illiterate or beginners. Educational level, age, and years of work experience were significantly associated with computer knowledge (pworkplace. Given the low levels of computer knowledge among rural health workers in Africa, it is important to provide adequate training and support to ensure the successful uptake of electronic CDSSs in these settings. The positive attitudes to computers found in this study underscore that also rural care providers are ready to use such technology.

  15. Characteristics of SUS-MI cables and it's application to wiring in nuclear power facilities

    International Nuclear Information System (INIS)

    Okuno, Michio; Sato, Toshio; Handa, Katsue; Ohya, Shingo; Ioroi, Masaya

    1984-01-01

    SUS-MI cables are the inorganic insulation cables using austenitic stainless steel SUS 321 as the sheath, oxygen-free copper as the conductor and high purity magnesium oxide as the insulatingmaterial. Because of the excellent characteristics of the composing materials, the properties withstanding radiation, fire and heat, and sodium of the cables are superior. In the nuclear power facilities being developed such as fast breeder reactors and nuclear fusion reactors, there is the environment the cables with organic materials as the components cannot meet. As the cables to be applied to such places, the SUS-MI cables are most suitable. In this report, the electric properties and the mechanical strength of the cables and the examples of practical use are described. The highest temperature of using the SUS-MI cables is 800 deg C. The form and the composing materials of the SUS-MI cables, the characteristics and the cable laying are reported. Ceramic connectors and heat-resistant wall penetration parts were developed. The characteristics of the cables for the preheaters of fast breeder reactors are compared. (Kako, I.)

  16. Application of EMCAS timeliness model to the safeguards/facility interface

    International Nuclear Information System (INIS)

    Eggers, R.F.; Giese, E.W.

    1987-01-01

    The Hanford operating contractor has developed a timeliness model for periodic mass balance tests (MBTs) for loss of special nuclear material (SNM). The purpose of the model is to compute the probability that an adversary will be detected by a periodic MBT before he could escape from a facility with stolen SNM using stealth and deceit to avoid detection. The model considers (a) the loss detection sensitivity of the MBT, (b) the time between MBTs, and (c) the statistical distribution of the total time required to complete stealth and deceit strategies. The model shows whether or not it is cost-effective to conduct frequent MBTs for loss and where improvements should be made. The Evaluation Methods for Material Control and Accountability Safeguards Systems (EMCAS) timeliness model computes the loss detection capability of periodic materials control and accounting (MC ampersand A) tests in terms of (a) the ability of the test to detect the specified target quantity and (b) the probability that the MC ampersand A test will occur before the adversary can complete the sequence of stealth and deceit strategies required to avoid detection

  17. Facile synthesis of silver nanoparticles and their application in dye degradation

    Energy Technology Data Exchange (ETDEWEB)

    Joseph, Siby, E-mail: sibyjoseph4@gmail.com [Department of Chemistry, St. George' s College, Aruvithura, Kottayam 686122, Kerala (India); Mathew, Beena, E-mail: beenamscs@gmail.com [School of Chemical Sciences, Mahatma Gandhi University, Kottayam 686560, Kerala (India)

    2015-05-15

    Graphical abstract: - Highlights: • This synthetic method uses the novel reducing agent hexamine. • The method is simple, fast and environment friendly. • This is a cost-effective method as all materials used are inexpensive and readily available. • The method provides highly stable spherical silver nanoparticles. • The nanoparticles show outstanding catalytic activity in the degradation of organic dyes. - Abstract: The present article reports a simple, facile and eco-friendly method based on microwave irradiation for the synthesis of silver nanoparticles in aqueous medium using starch as stabilizing agent and a new reducing agent namely hexamine. The silver nanoparticles were characterized by UV–vis, FTIR, XRD and HR-TEM analysis. UV–vis spectroscopic studies provided sufficient evidences for the formation of nanoparticles. The role of starch in the synthesis and stabilization of the nanoparticles was obtained from FTIR studies. The XRD and HR-TEM investigations clearly demonstrated the crystalline nature of the nanoparticles. From the TEM images, the silver nanoparticles were found to be spherical and of nearly uniform size with an average diameter of 18.2 ± 0.97 nm. The nanoparticles showed excellent catalytic activity in the degradation of methyl orange and rhodamine B by NaBH{sub 4}.

  18. Application of lifecycle management to design of the UK geological disposal facility

    International Nuclear Information System (INIS)

    Rendell, Philip G.P.; O'Grady, Henry J.P.; Currie, Malcolm F.

    2011-01-01

    The Radioactive Waste Management Directorate (RWMD) of the United Kingdom's (UK) Nuclear Decommissioning Authority (NDA) has been given the responsibility for delivery of a Geological Disposal Facility (GDF) for the UK's higher activity wastes in accordance with government policy. As part of this process, the RWMD has developed a project lifecycle, which addresses the overall lifecycle of the GDF in terms of five phases, from Preparatory Studies through to Operation and finally Closure, and is developing a staged approach to engineering design. The Engineering Design Process is broken down into seven stages, encompassing option development, requirements definition and preliminary and detailed design through to 'design development during closure'. Each stage finishes with a formally defined milestone (a 'gate') comprising a technical review and a specific set of engineering deliverables. This paper describes the background to the UK GDF development programme, the organisational issues associated with the RWMD's evolving role, the relationship between the top-level UK Government's Managing Radioactive Waste Safely programme and the RWMD engineering lifecycle, the formal reviews, the milestones and the overall contribution this makes to RWMD organisational development and UK regulatory approval. It also describes some of the lessons learnt. (author)

  19. Further development of a facility for channeling studies: application to lattice location

    International Nuclear Information System (INIS)

    Lopes, D.R.

    1984-08-01

    Equipment modifications at the Lawrence Berkeley Laboratory (LBL) Rutherford backscattering facility, including the addition of a high precision goniometer, have been made to enhance the performance of channeling experiments. The angular divergence of the alpha particle beam was also reduced to 0 by improving the collimation. To demonstrate improved channeling capability angular scans were performed about the [100], [110], and [111] axial channels of a 3400 A (100) silicon membrane. Both the minimum yield, chi/sub min/, and the critical angle, psi/sub 1/2/, were consistent with accepted values. A preliminary investigation of the lattice location of cobalt on the (100) silicon surface was undertaken. Approximately 4.5 x 10 15 Co atoms/cm 2 were electron beam deposited on a 3900 A, HF etched silicon membrane in a system using oilless pumps. Preliminary channeling data taken approximately one month later indicated a preferred site for approximately 16% of the cobalt atoms. Channeling data obtained six months later with the new goniometer showed no evidence for a preferred site. Room temperature oxidation between experiments was observed and is thought to have affected the location of the cobalt atoms. 33 references, 15 figures

  20. Application of PLUTO Test Facility for U. S. NRC Licensing of a Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Dongseok; Shin, Changhwan; Lee, Kanghee; Kang, Heungseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The fuel assembly of the PLUS-7 loaded in the APR-1400 follows the same schedule. Meanwhile, In July 1998, the U.S. NRC adopted a research plan to address the effects of high burnup from a Loss of Coolant Accident (LOCA). From these programs, several important technical findings for rule revision were obtained. Based on the technical findings, the U. S. NRC has amended the 10 CFR 50.46 which will be proclaimed sooner or later. Through the amendment, a LOCA analysis on the fuel assembly has to show the safety at both a fresh and End of Life (EOL) state. The U. S. NRC has already required EOL effects on seismic/LOCA performance for a fuel assembly since 1998. To obtain U.S NRC licensing of a fuel assembly, based on the amendment of 10CFR50.46, a LOCA analysis of the fuel assembly has to show safety both fresh and EOL states. The proper damping factor of the fuel assembly measured at the hydraulic test loop for a dynamic model in a LOCA and a seismic analysis code are at least required. In this paper, we have examined the damping technologies and compared the test facility of PLUTO with others in terms of performance. PLUTO has a better performance on the operating conditions than any others.

  1. Ultra-compact photoionization analyzers. Ecological monitoring application at hazardous production facilities

    Science.gov (United States)

    Mustafaev, Alexander; Rastvorova, Iuliia; Arslanova, Fatima

    2017-10-01

    It is generally recognized that careful implementation of ecological monitoring should be provided at hazardous production facilities continuously to protect the surrounding environment as well as health and safety of employees. However, the existing devices may not be able to control the environmental situation uninterruptedly due to their technical characteristics or measurement methods. Developed by The Mining University Plasma Research Group ultra-compact photoionization analyzer is proposed as innovative equipment which creates the basis for a new measuring approach. The general operating principle is based on the patented method of stabilization of electric parameters - CES (Collisional Electron Spectroscopy). During the operation at the atmospheric pressure, the vacuum ultraviolet (VUV) photoionization sensor measures the energy of electrons produced by means of ionization with the resonance photons whose wavelength is situated in the VUV. A special software tool was developed to obtain the second-order derivative of the I-U characteristics, taken by the VUV sensor, to construct the characteristic electrons energy spectra. The portable analyzer with a unique set of parameters such as small size (10*10*1 mm), low cost, a wide range of recognizable molecules, great measurement accuracy at the atmospheric pressure can be effectively used both for rapid testing of air pollution load and the study of noxious factors that influence oil and gas industry employees. Dr. Sci., Ph.D, Principal Scientist, Professor.

  2. Understanding the application of knowledge management to the safety critical facilities

    International Nuclear Information System (INIS)

    Ilina, Elena

    2010-01-01

    Challenges to the operating nuclear power plants and transport infrastructures are outlined. It is concluded that most aggravating factors are related to knowledge. Thus, of necessity, effective knowledge management is required. Knowledge management theories are reviewed in their historical perspective as a natural extension and unification of information theories and theories about learning. The first line is identified with names as Wiener, Ashby, Shannon, Jaynes, Dretske, Harkevich. The second line - with Vygotsky, Engestroem, Carayannis. The recent developments of knowledge management theorists as Davenport, Prusak, Drew, Wiig, Zack are considered stressing learning, retaining of knowledge, approaching the state awareness of awareness, and alignment of knowledge management with the strategy of the concerned organizations. Further, some of the details and results are presented of what is achieved so far. More specifically, knowledge management tools are applied to the practical work activities as event reporting, data collection, condition assessment, verification of safety functions and incident investigation. Obstacles are identified and improvements are proposed. Finally, it is advised to continue to implement and further develop knowledge management tools in the organizations involved in various aspects of safety critical facilities

  3. Analysis of the application of selected physico-chemical methods in eliminating odor nuisance of municipal facilities

    Directory of Open Access Journals (Sweden)

    Miller Urszula

    2018-01-01

    Full Text Available Operation of municipal management facilities is inseparable from the problem of malodorous compounds emissions to the atmospheric air. In that case odor nuisance is related to the chemical composition of waste, sewage and sludge as well as to the activity of microorganisms whose products of life processes can be those odorous compounds. Significant reduction of odorant emission from many sources can be achieved by optimizing parameters and conditions of processes. However, it is not always possible to limit the formation of odorants. In such cases it is best to use appropriate deodorizing methods. The choice of the appropriate method is based on in terms of physical parameters, emission intensity of polluted gases and their composition, if it is possible to determine. Among the solutions used in municipal economy, there can be distinguished physico-chemical methods such as sorption and oxidation. In cases where the source of the emission is not encapsulated, odor masking techniques are used, which consists of spraying preparations that neutralize unpleasant odors. The paper presents the characteristics of selected methods of eliminating odor nuisance and evaluation of their applicability in municipal management facilities.

  4. The role of human error in risk analysis: Application to pre- and post-maintenance procedures of process facilities

    International Nuclear Information System (INIS)

    Noroozi, Alireza; Khakzad, Nima; Khan, Faisal; MacKinnon, Scott; Abbassi, Rouzbeh

    2013-01-01

    Human factors play an important role in the safe operation of a facility. Human factors include the systematic application of information about human characteristics and behavior to increase the safety of a process system. A significant proportion of human errors occur during the maintenance phase. However, the quantification of human error probabilities in the maintenance phase has not been given the amount of attention it deserves. This paper focuses on a human factors analysis in pre-and post- pump maintenance operations. The procedures for removing process equipment from service (pre-maintenance) and returning the equipment to service (post-maintenance) are considered for possible failure scenarios. For each scenario, human error probability is calculated for each activity using the Success Likelihood Index Method (SLIM). Consequences are also assessed in this methodology. The risk assessment is conducted for each component and the overall risk is estimated by adding individual risks. The present study is aimed at highlighting the importance of considering human error in quantitative risk analyses. The developed methodology has been applied to a case study of an offshore process facility

  5. Analysis of the application of selected physico-chemical methods in eliminating odor nuisance of municipal facilities

    Science.gov (United States)

    Miller, Urszula; Grzelka, Agnieszka; Romanik, Elżbieta; Kuriata, Magdalena

    2018-01-01

    Operation of municipal management facilities is inseparable from the problem of malodorous compounds emissions to the atmospheric air. In that case odor nuisance is related to the chemical composition of waste, sewage and sludge as well as to the activity of microorganisms whose products of life processes can be those odorous compounds. Significant reduction of odorant emission from many sources can be achieved by optimizing parameters and conditions of processes. However, it is not always possible to limit the formation of odorants. In such cases it is best to use appropriate deodorizing methods. The choice of the appropriate method is based on in terms of physical parameters, emission intensity of polluted gases and their composition, if it is possible to determine. Among the solutions used in municipal economy, there can be distinguished physico-chemical methods such as sorption and oxidation. In cases where the source of the emission is not encapsulated, odor masking techniques are used, which consists of spraying preparations that neutralize unpleasant odors. The paper presents the characteristics of selected methods of eliminating odor nuisance and evaluation of their applicability in municipal management facilities.

  6. Techniques and applications of the human reliability analysis in nuclear facilities

    International Nuclear Information System (INIS)

    Pinto, Fausto C.

    1995-01-01

    The analysis and prediction of the man-machine interaction are the objectives of human reliability analysis. In this work is presented in a manner that could be used by experts in the field of Probabilistic Safety Assessment, considering primarily the aspects of human errors. The Technique of Human Error Rate Prediction (THERP) is used in large scale to obtain data on human error. Applications of this technique are presented, as well as aspects of the state-of-art and of research and development of this particular field of work, where the construction of a reliable data bank is considered essential. In this work is also developed an application of the THERP for the TRIGA Mark 1 IPR R-1 Reactor of the Centro de Desenvolvimento de Tecnologia Nuclear, Brazilian research institute of nuclear technology. The results indicate that some changes must be made in the emergency procedures of the reactor, in order to achieve a higher level of safety

  7. A survey of atmospheric dispersion models applicable to risk studies for nuclear facilities in complex terrain

    International Nuclear Information System (INIS)

    Wittek, P.

    1985-09-01

    Atmospheric dispersion models are reviewed with respect to their application to the consequence assessment within risk studies for nuclear power plants located in complex terrain. This review comprises: seven straight-line Gaussian models, which have been modified in order to take into account in a crude way terrain elevations, enhanced turbulence and some others effects; three trajectory/puff-models, which can handle wind direction changes and the resulting plume or puff trajectories; five three-dimensional wind field models, which calculate the wind field in complex terrain for the application in a grid model; three grid models; one Monte-Carlo-model. The main features of the computer codes are described, along with some informations on the necessary computer time and storage capacity. (orig.) [de

  8. Multimedia Application for Facility Information on Cassette Trand's Music Stores Using Macromedia Flash 8

    OpenAIRE

    Nicholas Ardiansyah; Rahayu Noveandini, SKom, MMSI

    2010-01-01

    Interesting development of the computer with the various trends that have increasedas never stopped. One thing that this trend is about the use of multimedia, where tocreate a multimedia application programs in search of songs - songs that not onlylisten but can see the songs that we choose to use as a means of information hasattracted the attention of society at a record store that is "Shop Cassette Trend's Music".

  9. Reliability design of a critical facility: An application of PRA methods

    International Nuclear Information System (INIS)

    Souza Vieira Neto, A.; Souza Borges, W. de

    1987-01-01

    Although a general agreement concerning the enforcement of reliability (probabilistic) design criteria for nuclear utilities is yet to be achieved. PRA methodology can still be used successfully as a project design and review tool, aimed at improving system's prospective performance or minimizing expected accident consequences. In this paper, the potential of such an application of PRA methods is examined in the special case of a critical design project currently being developed in Brazil. (orig.)

  10. Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2017-06-15

    To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper.

  11. Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

    International Nuclear Information System (INIS)

    Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak

    2017-01-01

    To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  13. Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

    International Nuclear Information System (INIS)

    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

  14. 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.

  15. Using Modeling and Simulation to Analyze Application and Network Performance at the Radioactive Waste and Nuclear Material Disposition Facility

    International Nuclear Information System (INIS)

    LIFE, ROY A.; MAESTAS, JOSEPH H.; BATEMAN, DENNIS B.

    2003-01-01

    Telecommunication services customers at the Radioactive Waste and Nuclear Material Disposition Facility (RWNMDF) have endured regular service outages that seem to be associated with a custom Microsoft Access Database. In addition, the same customers have noticed periods when application response times are noticeably worse than at others. To the customers, the two events appear to be correlated. Although many network design activities can be accomplished using trial-and-error methods, there are as many, if not more occasions where computerized analysis is necessary to verify the benefits of implementing one design alternative versus another. This is particularly true when network design is performed with application flows and response times in mind. More times than not, it is unclear whether upgrading certain aspects of the network will provide sufficient benefit to justify the corresponding costs, and network modeling tools can be used to help staff make these decisions. This report summarizes our analysis of the situation at the RWNMDF, in which computerized analysis was used to accomplish four objectives: (1) identify the source of the problem; (2) identify areas where improvements make the most sense; (3) evaluate various scenarios ranging from upgrading the network infrastructure, installing an additional fiber trunk as a way to improve local network performance, and re-locating the RWNMDF database onto corporate servers; and (4) demonstrate a methodology for network design using actual application response times to predict, select, and implement the design alternatives that provide the best performance and cost benefits

  16. Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    1994-04-01

    The Standard Review Plan (SRP) (NUREG-1200) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform safety reviews of applications to construct and operate low-level radioactive waste disposal facilities. The SRP ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate proposed changes in the scope and requirements of the staff reviews. The SRP makes information about the regulatory licensing process widely available and serves to improve the understanding of the staff's review process by interested members of the public and the industry. Each individual SRP addresses the responsibilities of persons performing the review, the matters that are reviewed, the Commission's regulations and acceptance criteria necessary for the review, how the review is accomplished, the conclusions that are appropriate, and the implementation requirements

  17. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Reilkoff, T. E.; Hetland, M. D.; O' Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  18. A facile TiO{sub 2}/PVDF composite membrane synthesis and their application in water purification

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Wei, E-mail: wei.zhang@unisa.edu.au; Zhang, Yiming; Fan, Rong; Lewis, Rosmala [University of South Australia, Centre for Water Management and Reuse (Australia)

    2016-01-15

    In this work, we have demonstrated a facile wet chemical method to synthesise TiO{sub 2}/PVDF composite membranes as alternative water purification method to traditional polymer-based membrane. For the first time, hydrothermally grown TiO{sub 2} nanofibers under alkali conditions were successfully inserted into PVDF membranes matrix. The structure, permeability and anti-fouling performance of as-prepared PVDF/TiO{sub 2} composite membranes were studied systematically. The TiO{sub 2}/PVDF composite membranes prepared in this work promise great potential uses in water purification applications as microfiltration membranes due to its excellent physical/chemical resistance, anti-fouling and mechanical properties.

  19. The Precipitation Products Generation Chain for the EUMETSAT Hydrological Satellite Application Facility at C.N.M.C.A.

    Science.gov (United States)

    Zauli, Francesco; Biron, Daniele; Melfi, Davide

    2009-11-01

    The EUMETSA T Satellite Application Facility in support to Hydrology (H-SAF) focuses on the development of new geophysical products on precipitation, soil moisture and snow parameters and the utilisation of these parameters in hydrological models, NWP models and water management. The development phase of the H-SAF started in September 2005 under the leadership of Italian Meteorological Service.The Centro Nazionale di Meteorologia e Climatologia Aeronautica (C.N.M.C.A.), the Italian National Weather Centre, that physically hosts the generation chain of precipitation products, developed activities to reach the final target: development of algorithms, validation of results, implementation of operative procedure to supply the service and to monitor the service performances.The paper shows the recent architectural review of H- SAF precipitation group, stressing components of operation for high sustainability, full redundancy, absolute continuity of service.

  20. Facile Deposition of Ultrafine Silver Particles on Silicon Surface Not Submerged in Precursor Solutions for Applications in Antireflective Layer

    Directory of Open Access Journals (Sweden)

    Bing Jiang

    2014-01-01

    Full Text Available Using a facile deposition method, the ultrafine silver particles are successfully deposited on the Si surface that is not submerged in precursor solutions. The ultrafine silver particles have many advantages, such as quasiround shape, uniformity in size, monodisperse distribution, and reduction of agglomeration. The internal physical procedure in the deposition is also investigated. The results show that there are more particles on the rough Si surface due to the wetting effect of solid-liquid interface. The higher concentration of ethanol solvent can induce the increase of quantity and size of particles on Si surface not in solutions. The ultrafine particles can be used to prepare porous Si antireflective layer in solar cell applications.

  1. Applications and results of X-ray spectroscopy in implosion experiments on the National Ignition Facility

    Science.gov (United States)

    Epstein, R.; Regan, S. P.; Hammel, B. A.; Suter, L. J.; Scott, H. A.; Barrios, M. A.; Bradley, D. K.; Callahan, D. A.; Cerjan, C.; Collins, G. W.; Dixit, S. N.; Döppner, T.; Edwards, M. J.; Farley, D. R.; Fournier, K. B.; Glenn, S.; Glenzer, S. H.; Golovkin, I. E.; Hamza, A.; Hicks, D. G.; Izumi, N.; Jones, O. S.; Key, M. H.; Kilkenny, J. D.; Kline, J. L.; Kyrala, G. A.; Landen, O. L.; Ma, T.; MacFarlane, J. J.; Mackinnon, A. J.; Mancini, R. C.; McCrory, R. L.; Meyerhofer, D. D.; Meezan, N. B.; Nikroo, A.; Park, H.-S.; Patel, P. K.; Ralph, J. E.; Remington, B. A.; Sangster, T. C.; Smalyuk, V. A.; Springer, P. T.; Town, R. P. J.; Tucker, J. L.

    2017-03-01

    Current inertial confinement fusion experiments on the National Ignition Facility (NIF) [G. H. Miller, E. I. Moses, and C. R. Wuest, Opt. Eng. 43, 2841 (2004)] are attempting to demonstrate thermonuclear ignition using x-ray drive by imploding spherical targets containing hydrogen-isotope fuel in the form of a thin cryogenic layer surrounding a central volume of fuel vapor [J. Lindl, Phys. Plasmas 2, 3933 (1995)]. The fuel is contained within a plastic ablator layer with small concentrations of one or more mid-Z elements, e.g., Ge or Cu. The capsule implodes, driven by intense x-ray emission from the inner surface of a hohlraum enclosure irradiated by the NIF laser, and fusion reactions occur in the central hot spot near the time of peak compression. Ignition will occur if the hot spot within the compressed fuel layer attains a high-enough areal density to retain enough of the reaction product energy to reach nuclear reaction temperatures within the inertial hydrodynamic disassembly time of the fuel mass [J. Lindl, Phys. Plasmas 2, 3933 (1995)]. The primary purpose of the ablator dopants is to shield the ablator surface adjacent to the DT ice from heating by the hohlraum x-ray drive [S. W. Haan et al., Phys. Plasmas 18, 051001 (2011)]. Simulations predicted that these dopants would produce characteristic K-shell emission if ablator material mixed into the hot spot [B. A. Hammel et al., High Energy Density Phys. 6, 171 (2010)]. In NIF ignition experiments, emission and absorption features from these dopants appear in x-ray spectra measured with the hot-spot x-ray spectrometer in Supersnout II [S. P. Regan et al., "Hot-Spot X-Ray Spectrometer for the National Ignition Facility," to be submitted to Review of Scientific Instruments]. These include K-shell emission lines from the hot spot (driven primarily by inner-shell collisional ionization and dielectronic recombination) and photoionization edges, fluorescence, and absorption lines caused by the absorption of the

  2. Evaluation of Antidiabetic Prescriptions from Medical Reimbursement Applications at Banaras Hindu University Health Care Facility

    Directory of Open Access Journals (Sweden)

    Dev Priya

    2015-10-01

    Full Text Available Background: Diabetes is on rapid increase in third world countries undergoing rapid transition in terms of development particularly in India, which is often being referred as Diabetic capital. It is a disease more prevalent at latter part of life of human beings when finances dwindle and social care gets neglected. The medication continues till the whole life on a regular basis. In present study, the objective has been to provide pharmacoeconomic medication to the diabetic pensioners in the backdrop as mentioned in above background.Methods: The data was collected at the medical reimbursement section of pensioners of the University. The data was examined to answer issues of therapeutic decisions in the light of the pharmacoeconomic considerations. In this paper essentially data on choice of prescriptions with the angle of pharmacoeconomic prudence were included. The dichotomy of specialist versus non specialist prescribers at the tertiary center (i.e. medical college hospital was compared. Effort was made to define merit of the prescription based on comprehensive considerations of patient profile, disease profile and therapeutic choice.Results: Total 72 prescriptions were analyzed for the study in which 475 drugs were prescribed to the patients.  Total antidiabetic drugs prescribed to the patients were 169. Out of 72 cases 39 were males and 33 were females with mean age 66.04 ± 5.80 (Mean ± SEM. The average number of drugs per prescription was 6.59 which was very high as per guidelines. Most commonly prescribed antidiabetic drug was Metformin (63.89% followed by Glimepiride (31.95%.Conclusion: This study reflects that there is need to make available the standard therapeutic optionat University Health Care Facility based upon pharmacoeconomic considerations.

  3. Applications of remote sensing and GIS technologies to wetland assessment and monitoring at a DOE facility

    International Nuclear Information System (INIS)

    Mackey, H.E.

    1993-01-01

    The Savannah River Site (SRS), a 777-km 2 site, located in the Upper Coastal Plain of South Carolina, was established in the early 1950s for the production of nuclear materials to support the defense needs of the United States. The SRS was closed to the public and shortly after its formation, much of the uplands and previous farmlands were planted to managed pine plantations for the US Department of Energy by the US Forest Service. More than 7500 hectares of wetlands, ranging from a large, 3000-hectare swamp, to extensive bottomland hardwood forests, to isolated upland Carolina bays, were present on the SRS at the time of its formation. During the subsequent 40-yr operation of the site, five stream systems and portions of the Savannah River swamp on the SRS were influenced by discharges of once-through cooling water from site operations. In addition, two large cooling lakes were constructed, Par Pond in 1958 and L Lake in 1985, to support reactor operations. Thus, the wetlands of the SRS have had a variety of influences, ranging from the protection afforded by the exclusion of the public from the site, past construction of major facilities, and discharges from site operations. Evaluation, assessment, and monitoring long-term changes to the extensive and varied wetlands of the SRS are formidable tasks. Archived remote sensing data of a variety of types, along with the advances in computer technologies that allow the integration of land-use/land-cover geographic information system (GIS) data layer and related GIS data bases, are providing the necessary tools and information to integrate wetlands protection and management into an effective operational environment

  4. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-06

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

  5. 'Isotopo' a database application for facile analysis and management of mass isotopomer data.

    Science.gov (United States)

    Ahmed, Zeeshan; Zeeshan, Saman; Huber, Claudia; Hensel, Michael; Schomburg, Dietmar; Münch, Richard; Eylert, Eva; Eisenreich, Wolfgang; Dandekar, Thomas

    2014-01-01

    The composition of stable-isotope labelled isotopologues/isotopomers in metabolic products can be measured by mass spectrometry and supports the analysis of pathways and fluxes. As a prerequisite, the original mass spectra have to be processed, managed and stored to rapidly calculate, analyse and compare isotopomer enrichments to study, for instance, bacterial metabolism in infection. For such applications, we provide here the database application 'Isotopo'. This software package includes (i) a database to store and process isotopomer data, (ii) a parser to upload and translate different data formats for such data and (iii) an improved application to process and convert signal intensities from mass spectra of (13)C-labelled metabolites such as tertbutyldimethylsilyl-derivatives of amino acids. Relative mass intensities and isotopomer distributions are calculated applying a partial least square method with iterative refinement for high precision data. The data output includes formats such as graphs for overall enrichments in amino acids. The package is user-friendly for easy and robust data management of multiple experiments. The 'Isotopo' software is available at the following web link (section Download): http://spp1316.uni-wuerzburg.de/bioinformatics/isotopo/. The package contains three additional files: software executable setup (installer), one data set file (discussed in this article) and one excel file (which can be used to convert data from excel to '.iso' format). The 'Isotopo' software is compatible only with the Microsoft Windows operating system. http://spp1316.uni-wuerzburg.de/bioinformatics/isotopo/. © The Author(s) 2014. Published by Oxford University Press.

  6. Cobalt nanoparticles for biomedical applications: Facile synthesis, physiochemical characterization, cytotoxicity behavior and biocompatibility

    Science.gov (United States)

    Ansari, S. M.; Bhor, R. D.; Pai, K. R.; Sen, D.; Mazumder, S.; Ghosh, Kartik; Kolekar, Y. D.; Ramana, C. V.

    2017-08-01

    Cobalt (Co) nanoparticles (NPs) were produced by a simple, one step hydrothermal method with the capping of oleic acid. Intrinsic structural, physiochemical and magnetic properties of Co NPs were investigated and demonstrated their applicability in biomedicine. X-ray diffraction, Raman spectroscopy and infrared (IR) spectroscopic studies confirm the single phase Co NPs with a high structural quality. The IR data revealed the capping of oleic acid via monodentate interaction. Small angle scattering studies suggest the existence of sticky hard sphere type of interaction among the Co NPs because of magnetic interaction which is further evidenced by electron microscopy imaging analyses. The Co NPs exhibit a ferromagnetic character over a wide range of temperature (20-300 K). The temperature dependence of magnetic parameters namely, saturation magnetization, remanent magnetization, coercivity and reduced remanent magnetization were determined and correlated with structure of Co NPs. The Cytotoxicity studies demonstrate that these Co NPs exhibit the mild anti-proliferative character against the cancer cells (cisplatin resistant ovarian cancer (A2780/CP70)) and safe nature towards the normal cells. Haemolytic behavior of human red blood cells (RBC) revealed (<5%) haemolysis signifying the compatibility of Co NPs with human RBC which is an essential feature in vivo biomedical applications without creating any harmful effects in the human blood stream.

  7. Development of electron beam facilities for research and applications in Thailand

    International Nuclear Information System (INIS)

    Vilaithong, Thiraphat

    2004-01-01

    Linear accelerators (linac) were introduced into the Kingdom of Thailand almost twenty years ago. They were installed at major hospitals around the country for radiotherapy. At present there are 20 medical electron linacs in Thailand. Three of the new linacs are recently installed at Chiang Mai University Hospital. The first industrial electron accelerator was commissioned in 1997 for sterilization of medical products such as doctor gown, pampas etc. for export. It has accelerating voltage in the range between 1.8 to 2.4 MeV and power of 10 kW. The second electron accelerator was introduced in the year 2000 for gemstone enhancement. This one is a 15 MeV, 8.5 kW electron linac. Since 2000 a program to generate electron beams for research and industrial application has been realized at Chiang Mai University. Both high (10-30 MeV) and low (300 keV) energy electron accelerating systems are being explored. Here we describe the present development status and near future applications. (author)

  8. Facile synthesis of Curcuma longa tuber powder engineered metal nanoparticles for bioimaging applications

    Science.gov (United States)

    Sankar, Renu; Rahman, Pattanathu K. S. M.; Varunkumar, Krishnamoorthy; Anusha, Chidambaram; Kalaiarasi, Arunachalam; Shivashangari, Kanchi Subramanian; Ravikumar, Vilwanathan

    2017-02-01

    Nanomaterials based fluorescent agents are rapidly becoming significant and promising transformative tools for improving medical diagnostics for extensive in vivo imaging modalities. Compared with conventional fluorescent agents, nano-fluorescence has capabilities to improve the in vivo detection and enriched targeting efficiencies. In our laboratory we synthesized fluorescent metal nanoparticles of silver, copper and iron using Curcuma longa tuber powder by simple reduction. The physicochemical properties of the synthesized metal nanoparticles were attained using UV-visible spectrophotometry, scanning electron microscopy with EDAX spectroscopy, dynamic light scattering, Fourier-transform infrared spectroscopy and X-ray diffraction. The Curcuma longa tuber powder has one of the bioactive compound Curcumin might act as a capping agent during the synthesis of nanoparticles. The synthesized metal nanoparticles fluorescence property was confirmed by spectrofluorometry. When compared with copper and iron nanoparticles the silver nanoparticles showed high fluorescence intensity under spectrofluorometry. Moreover, in vitro cell images of the silver nanoparticles in A549 cell lines also correlated with the results of spectrofluorometry. These silver nanoparticles show inspiring cell-imaging applications. They enter into cells without any further modifications, and the fluorescence property can be utilized for fluorescence-based cell imaging applications.

  9. Integrated ground-water monitoring strategy for NRC-licensed facilities and sites: Case study applications

    Science.gov (United States)

    Price, V.; Temples, T.; Hodges, R.; Dai, Z.; Watkins, D.; Imrich, J.

    2007-01-01

    This document discusses results of applying the Integrated Ground-Water Monitoring Strategy (the Strategy) to actual waste sites using existing field characterization and monitoring data. The Strategy is a systematic approach to dealing with complex sites. Application of such a systematic approach will reduce uncertainty associated with site analysis, and therefore uncertainty associated with management decisions about a site. The Strategy can be used to guide the development of a ground-water monitoring program or to review an existing one. The sites selected for study fall within a wide range of geologic and climatic settings, waste compositions, and site design characteristics and represent realistic cases that might be encountered by the NRC. No one case study illustrates a comprehensive application of the Strategy using all available site data. Rather, within each case study we focus on certain aspects of the Strategy, to illustrate concepts that can be applied generically to all sites. The test sites selected include:Charleston, South Carolina, Naval Weapons Station,Brookhaven National Laboratory on Long Island, New York,The USGS Amargosa Desert Research Site in Nevada,Rocky Flats in Colorado,C-Area at the Savannah River Site in South Carolina, andThe Hanford 300 Area.A Data Analysis section provides examples of detailed data analysis of monitoring data.

  10. Cobalt nanoparticles for biomedical applications: Facile synthesis, physiochemical characterization, cytotoxicity behavior and biocompatibility

    Energy Technology Data Exchange (ETDEWEB)

    Ansari, S.M. [Department of Physics, Savitribai Phule Pune University, Pune, 411007, Maharashtra (India); Bhor, R.D.; Pai, K.R. [Department of Zoology, Savitribai Phule Pune University, Pune, 411007, Maharashtra (India); Sen, D.; Mazumder, S. [Solid State Physics Division, Bhabha Atomic Research Centre, Mumbai, 400 085 (India); Ghosh, Kartik [Department of Physics, Astronomy and Materials Science, Missouri State University, Springfield, MO, 65897 (United States); Kolekar, Y.D., E-mail: ydkolekar@gmail.com [Department of Physics, Savitribai Phule Pune University, Pune, 411007, Maharashtra (India); Ramana, C.V., E-mail: rvchintalapalle@utep.edu [Department of Mechanical Engineering, University of Texas at El Paso, El Paso, TX, 79968 (United States)

    2017-08-31

    Cobalt (Co) nanoparticles (NPs) were produced by a simple, one step hydrothermal method with the capping of oleic acid. Intrinsic structural, physiochemical and magnetic properties of Co NPs were investigated and demonstrated their applicability in biomedicine. X-ray diffraction, Raman spectroscopy and infrared (IR) spectroscopic studies confirm the single phase Co NPs with a high structural quality. The IR data revealed the capping of oleic acid via monodentate interaction. Small angle scattering studies suggest the existence of sticky hard sphere type of interaction among the Co NPs because of magnetic interaction which is further evidenced by electron microscopy imaging analyses. The Co NPs exhibit a ferromagnetic character over a wide range of temperature (20–300 K). The temperature dependence of magnetic parameters namely, saturation magnetization, remanent magnetization, coercivity and reduced remanent magnetization were determined and correlated with structure of Co NPs. The Cytotoxicity studies demonstrate that these Co NPs exhibit the mild anti-proliferative character against the cancer cells (cisplatin resistant ovarian cancer (A2780/CP70)) and safe nature towards the normal cells. Haemolytic behavior of human red blood cells (RBC) revealed (<5%) haemolysis signifying the compatibility of Co NPs with human RBC which is an essential feature in vivo biomedical applications without creating any harmful effects in the human blood stream.

  11. Preliminary liver dose estimation in the new facility for biomedical applications at the RA-3 reactor

    International Nuclear Information System (INIS)

    Gadan, M.; Crawley, V.; Thorp, S.; Miller, M.

    2009-01-01

    , even for the most conservative case, minimum tumor dose will be acceptable from the treatment point of view, which shows that the irradiation conditions at this facility have quite good characteristics for the proposed irradiation.

  12. Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the content and review of an application

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, D.J.; Bauser, M.A. [Morgan, Lewis and Bockius, Washington, DC (United States); Baird, R.D. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application.

  13. Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the content and review of an application

    International Nuclear Information System (INIS)

    Silverman, D.J.; Bauser, M.A.; Baird, R.D.

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

  14. Catalytic Fuel Conversion Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility enables unique catalysis research related to power and energy applications using military jet fuels and alternative fuels. It is equipped with research...

  15. A facile route to ketene-functionalized polymers for general materials applications

    Science.gov (United States)

    Leibfarth, Frank A.; Kang, Minhyuk; Ham, Myungsoo; Kim, Joohee; Campos, Luis M.; Gupta, Nalini; Moon, Bongjin; Hawker, Craig J.

    2010-03-01

    Function matters in materials science, and methodologies that provide paths to multiple functionality in a single step are to be prized. Therefore, we introduce a robust and efficient strategy for exploiting the versatile reactivity of ketenes in polymer chemistry. New monomers for both radical and ring-opening metathesis polymerization have been developed, which take advantage of Meldrum's acid as both a synthetic building block and a thermolytic precursor to dialkyl ketenes. The ketene-functionalized polymers are directly detected by their characteristic infrared absorption and are found to be stable under ambient conditions. The inherent ability of ketenes to provide crosslinking via dimerization and to act as reactive chemical handles via addition, provides simple methodology for application in complex materials challenges. Such versatile characteristics are illustrated by covalently attaching and patterning a dye through microcontact printing. The strategy highlights the significant opportunities afforded by the traditionally neglected ketene functional group in polymer chemistry.

  16. New Concepts in FFAG Design for Secondary Beam Facilities and Other Applications

    CERN Document Server

    Craddock, Michael

    2005-01-01

    Fixed Field Alternating Gradient accelerators offer much higher acceptances and repetition rates - and therefore higher beam intensities - than synchrotrons, at the cost of more complicated magnet and rf cavity designs. Perhaps because of the difficulty and expense anticipated, early studies never progressed beyond the stage of successful electron models, but in recent years, with improvements in magnet and rf design technology, FFAGs have become the focus of renewed attention. Two proton machines have now been built, and three more, plus a muon phase rotator, are under construction. In addition, more than 20 designs are under study for the acceleration of protons, heavy ions, electrons and muons, with applications as diverse as treating cancer, irradiating materials, driving subcritical reactors, boosting high-energy proton intensity, and producing neutrinos. Moreover, it has become apparent that FFAG designs need not be restricted to the traditional 'scaling' approach, in which the orbit shape, optics and t...

  17. Radioactive Air Emissions Notice of Construction (NOC) Application for the Waste Sampling and Characterization Facility (WSCF)

    International Nuclear Information System (INIS)

    BATES, J.A.

    2000-01-01

    This NOC application is provided to update the description of amounts of material handled, and to update the calculation of potential for emissions and resultant calculation of offsite TEDE. This NOC also includes an updated description of the various emission units at WSCF, including use of portable tanks to receive and remove liquid waste contaminated with low levels of radioactive contamination. The resultant, adjusted estimate for TEDE to the hypothetical MEI due to all combined unabated emissions from WSCF is 1.4 E-02 millirem per year. The total adjusted estimate for all combined abated emissions is 2.8 E-03 millirem per year. No single emission unit at the WSCF Complex exceeds a potential (unabated) offsite dose of 2.7 E-03 millirem per year

  18. Current regulatory and licensing status for byproduct sources, facilities and applications

    International Nuclear Information System (INIS)

    Tingey, G.L.; Jensen, G.A.; Hazelton, R.F.

    1985-02-01

    Public use of nuclear byproducts, especially radioactive isotopes, will require approval by various regulatory agencies. Use of cesium-137 as an irradiation source for sterilizing medical products will require US Nuclear Regulatory Commission (NRC) approval. Two applications have been filed with NRC, and approval is expected soon. Widespread use of irradiation for food products depends on a favorable ruling by the Food and Drug Administration (FDA). A ruling is pending that would permit irradiation of fruits and vegetables up to 100 krad. NRC also controls the use of isotopes in remote power generators, but little regulatory action has been required in recent years. Recent development of radioluminescent (RL) lighting for runway lights has led to interest by commercial manufacturers. At the present time, a license has been issued to at least one manufacturer for sale of tritium-powered runway lights. 28 refs., 1 fig

  19. The Application of RFID in Brazilian Harvest Facilities: Two Case Studies

    Directory of Open Access Journals (Sweden)

    Priscilla Cristina Cabral Ribeiro

    2011-02-01

    Full Text Available Using the two case studies presented in this work, this article aims to evaluate identification technology used in the Brazilian cattle market. Although Brazil possesses large companies in this sector (one of which is the largest exporter of meat in the world some of them have yet to implement information technology (IT for cattle identification purposes. Radio Frequency Identification (RFID is an IT that identifies cattle using electronic ear tags. This particular form of technology is especially accurate and dependable as it can be used to trace a product from the origin of conception to the consumer. This paper utilizes a qualitative approach – two case studies – which were created with the application of a questionnaire (open and closed questions. Using RFID for internal control purposes only, each of the sample companies has limited use of the technology. Instead, these companies use barcode systems to trace and identify cattle and to send important information to their supply chain partners.

  20. Application of mathematical models in assessing environmental impacts of nuclear facilities

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    Mathematical models are divided into atmospheric models which monitoring the migration of radioactive substances in the atmosphere, hydrological models which monitoring the discharge of radioactive substances into the hydrosphere and their concentrations in sediments, water flora and fauna, and hydrogeological models which monitoring the migration of radioactive substances in ground water. The application is described of the hydrogeological model in the evaluation of the radiation burden in the environment of the Dobronin radioactive waste disposal site. This model contains the determination of the maximal amounts of disposed radioactive substances, maximal design-basis accident, the amounts of leached radioactive substances, the calculation of the time of migration of substances in the soil, the determination of the dispersion in the aquifer and the determination of the radiation burden of the population. (H.S.)

  1. Application of protective distances in vicinity of dangerous facilities in urban and spatial plans

    Directory of Open Access Journals (Sweden)

    Stojanović Božidar

    2006-01-01

    Full Text Available Environmental risk management in production, use and transportation of dangerous materials having been actual theme in the world and in Serbia. Although environmental risk is mostly connected with technical issues, since chemical catastrophe in Bophal-lndia (1986 in the world was recognized that this is complex issue that besides of technical-technological, includes also social-economic, organizational and spatial factors. Spatial component of risk management which is regulated by Seveso II Directive in EU is important for planners. This paper considers basic elements of environmental risk assessment, procedures and methods used in Europe, particularly in the process of land use planning, and characteristics of method for application of separation distances used in General plan of Belgrade.

  2. Lessons learned in over 100 zebra mussel control applications at industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    McGough, C.M.; Gilland, P.H.; Muia, R.A. [Calgon Corp., Pittsburgh, PA (United States)

    1998-12-31

    Since their introduction into US waterways, Zebra Mussels (Dreissena polymorphae) have spread rapidly throughout the Great Lakes and Mississippi regions. These mussels have continued to colonize the intake pipes of industrial water supplies and water distribution systems throughout the affected areas. Their colonization has compromised plant safety and production efficiency, and steadily increased costs to water users. The design of each industrial plant water distribution system is unique. A comprehensive zebra mussel control strategy using the best available options must be considered in each specific situation. This paper discusses the successful use of one strategy (a quaternary ammonia-based molluscicide) in the battle against zebra mussels. The commercial life cycle of an industrial molluscicide began with initial toxicity screening in the laboratory. The evaluation continued at plant sites through field trials and applications. Lessons learned from these experiences helped direct the efforts toward the development of a second generation program.

  3. Brookhaven Regional Energy Facility Siting Model (REFS): model development and application

    Energy Technology Data Exchange (ETDEWEB)

    Meier, P.; Hobbs, B.; Ketcham, G.; McCoy, M.; Stern, R.

    1979-06-01

    A siting methodology developed specifically to bridge the gap between regional-energy-system scenarios and environmental transport models is documented. Development of the model is described in Chapter 1. Chapter 2 described the basic structure of such a model. Additional chapters on model development cover: generation, transmission, demand disaggregation, the interface to other models, computational aspects, the coal sector, water resource considerations, and air quality considerations. These subjects comprise Part I. Part II, Model Applications, covers: analysis of water resource constraints, water resource issues in the New York Power Pool, water resource issues in the New England Power Pool, water resource issues in the Pennsylvania-Jersey-Maryland Power Pool, and a summary of water resource constraint analysis. (MCW)

  4. A facile synthesis method of hydroxyethyl cellulose-silver nanoparticle scaffolds for skin tissue engineering applications.

    Science.gov (United States)

    Zulkifli, Farah Hanani; Hussain, Fathima Shahitha Jahir; Zeyohannes, Senait Sileshi; Rasad, Mohammad Syaiful Bahari Abdull; Yusuff, Mashitah M

    2017-10-01

    Green porous and ecofriendly scaffolds have been considered as one of the potent candidates for tissue engineering substitutes. The objective of this study is to investigate the biocompatibility of hydroxyethyl cellulose (HEC)/silver nanoparticles (AgNPs), prepared by the green synthesis method as a potential host material for skin tissue applications. The substrates which contained varied concentrations of AgNO 3 (0.4%-1.6%) were formed in the presence of HEC, were dissolved in a single step in water. The presence of AgNPs was confirmed visually by the change of color from colorless to dark brown, and was fabricated via freeze-drying technique. The outcomes exhibited significant porosity of >80%, moderate degradation rate, and tremendous value of water absorption up to 1163% in all samples. These scaffolds of HEC/AgNPs were further characterized by SEM, UV-Vis, ATR-FTIR, TGA, and DSC. All scaffolds possessed open interconnected pore size in the range of 50-150μm. The characteristic peaks of Ag in the UV-Vis spectra (417-421nm) revealed the formation of AgNPs in the blend composite. ATR-FTIR curve showed new existing peak, which implies the oxidation of HEC in the cellulose derivatives. The DSC thermogram showed augmentation in T g with increased AgNO 3 concentration. Preliminary studies of cytotoxicity were carried out in vitro by implementation of the hFB cells on the scaffolds. The results substantiated low toxicity of HEC/AgNPs scaffolds, thus exhibiting an ideal characteristic in skin tissue engineering applications. Copyright © 2017 Elsevier B.V. All rights reserved.

  5. Candu Energy's Aging and Obsolescence Program and its Application to Operating Facilities and New Plant Design

    International Nuclear Information System (INIS)

    Dam, R.; Gold, R.; McCrea, L.

    2012-01-01

    While plant aging is inevitable, predictable and 'graceful 'aging' behavior can be achieved through the implementation of a comprehensive and integrated Plant Life Management (PLiM) program. Despite organizations like the IAEA and INPO placing more emphasis on equipment reliability, there is still a lack of completely integrated programs in the industry as evidenced by: - Piece-meal, often crisis-driven, implementation comprising many different, partial solutions; - Duplication of effort often seen when different groups work in 'silos'. A strategy which fits with existing plant processes and programs, and which coordinates a broad range of equipment reliability activities is key to achieving the desired results. An example of such a program is the Aging and Obsolescence Program (AOP). AOP follows application of INPO AP-913 guidance for equipment reliability. The program is augmented to include single point vulnerability identification, unified approach to short and long lived components, risk management, spare parts management, and the identification and resolution of obsolescence issues. The systematic nature of the program provides the needed foundation to old and new stations alike. For existing operating stations some of the key uses include outage interval extension, reduced forced outages, and/or outage time reduction, any of which can translate into improving plant performance, competitiveness, and significant dollars saved. Program elements applied to new plant design are commensurate with the industry direction to 'design for reliability', and has allowed Candu Energy to learn and to improve upon what it can offer to operating stations. This paper intends to describe the basic elements of Candu Energy's Aging and Obsolescence Program and will share some of the experience having applied it to existing operating stations, consider applications to support expanding regulatory requirements, and describe the integration into the design of new plants, promoting

  6. Analysis on online word-of-mouth of customer satisfaction in cultural and creative industries of Taiwan: using cultural heritage application and performance facilities as examples

    Science.gov (United States)

    Tsai, Li-Fen; Shaw, Jing-Chi; Wang, Pei-Wen; Shih, Meng-Long; Su, Yi-Jing

    2011-10-01

    This study aims to probe into customers' online word-of-mouth regarding cultural heritage applications and performance facilities in Cultural and Creative Industries. Findings demonstrate that, regarding online word-of-mouth for art museums, museums, and art villages, items valued by customers are design aesthetics of displays and collections, educational functions, and environments and landscapes. The percentages are 10.102%, 11.208% and 11.44%, respectively. In addition, cultural heritage applications and performance facility industries in Taiwan are highly valued in online word-of-mouth.

  7. Field Sampling Plan for Closure of the Central Facilities Area Sewage Treatment Plant Lagoon 3 and Land Application Area

    International Nuclear Information System (INIS)

    Lewis, Michael George

    2016-01-01

    This field sampling plan describes sampling of the soil/liner of Lagoon 3 at the Central Facilities Area Sewage Treatment Plant. The lagoon is to be closed, and samples obtained from the soil/liner will provide information to determine if Lagoon 3 and the land application area can be closed in a manner that renders it safe to human health and the environment. Samples collected under this field sampling plan will be compared to Idaho National Laboratory background soil concentrations. If the concentrations of constituents of concern exceed the background level, they will be compared to Comprehensive Environmental Response, Compensation, and Liability Act preliminary remediation goals and Resource Conservation and Recovery Act levels. If the concentrations of constituents of concern are lower than the background levels, Resource Conservation and Recovery Act levels, or the preliminary remediation goals, then Lagoon 3 and the land application area will be closed. If the Resource Conservation and Recovery Act levels and/or the Comprehensive Environmental Response, Compensation, and Liability Act preliminary remediation goals are exceeded, additional sampling and action may be required.

  8. A Facile Strategy for the Preparation of MoS3 and its Application as a Negative Electrode for Supercapacitors.

    Science.gov (United States)

    Zhang, Tong; Kong, Ling-Bin; Dai, Yan-Hua; Yan, Kun; Shi, Ming; Liu, Mao-Cheng; Luo, Yong-Chun; Kang, Long

    2016-09-06

    Owing to their graphene-like structure and available oxidation valence states, transition metal sulfides are promising candidates for supercapacitors. Herein, we report the application of MoS3 as a new negative electrode for supercapacitors. MoS3 was fabricated by the facile thermal decomposition of a (NH4 )2 MoS4 precursor. For comparison, samples of MoS3 &MoS2 and MoS2 were also synthesized by using the same method. Moreover, this is the first report of the application of MoS3 as a negative electrode for supercapacitors. MoS3 displayed a high specific capacitance of 455.6 F g(-1) at a current density of 0.5 A g(-1) . The capacitance retention of the MoS3 electrode was 92 % after 1500 cycles, and even 71 % after 5000 cycles. In addition, an asymmetric supercapacitor assembly of MoS3 as the negative electrode demonstrated a high energy density at a high potential of 2.0 V in aqueous electrolyte. These notable results show that MoS3 has significant potential in energy-storage devices. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  9. Facile method to synthesize magnetic iron oxides/TiO2 hybrid nanoparticles and their photodegradation application of methylene blue

    Directory of Open Access Journals (Sweden)

    Wu Wei

    2011-01-01

    Full Text Available Abstract Many methods have been reported to improving the photocatalytic efficiency of organic pollutant and their reliable applications. In this work, we propose a facile pathway to prepare three different types of magnetic iron oxides/TiO2 hybrid nanoparticles (NPs by seed-mediated method. The hybrid NPs are composed of spindle, hollow, and ultrafine iron oxide NPs as seeds and 3-aminopropyltriethyloxysilane as linker between the magnetic cores and TiO2 layers, respectively. The composite structure and the presence of the iron oxide and titania phase have been confirmed by transmission electron microscopy, X-ray diffraction, and X-ray photoelectron spectra. The hybrid NPs show good magnetic response, which can get together under an external applied magnetic field and hence they should become promising magnetic recovery catalysts (MRCs. Photocatalytic ability examination of the magnetic hybrid NPs was carried out in methylene blue (MB solutions illuminated under Hg light in a photochemical reactor. About 50% to 60% of MB was decomposed in 90 min in the presence of magnetic hybrid NPs. The synthesized magnetic hybrid NPs display high photocatalytic efficiency and will find recoverable potential applications in cleaning polluted water with the help of magnetic separation.

  10. Field Sampling Plan for Closure of the Central Facilities Area Sewage Treatment Plant Lagoon 3 and Land Application Area

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Michael George [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-10-01

    This field sampling plan describes sampling of the soil/liner of Lagoon 3 at the Central Facilities Area Sewage Treatment Plant. The lagoon is to be closed, and samples obtained from the soil/liner will provide information to determine if Lagoon 3 and the land application area can be closed in a manner that renders it safe to human health and the environment. Samples collected under this field sampling plan will be compared to Idaho National Laboratory background soil concentrations. If the concentrations of constituents of concern exceed the background level, they will be compared to Comprehensive Environmental Response, Compensation, and Liability Act preliminary remediation goals and Resource Conservation and Recovery Act levels. If the concentrations of constituents of concern are lower than the background levels, Resource Conservation and Recovery Act levels, or the preliminary remediation goals, then Lagoon 3 and the land application area will be closed. If the Resource Conservation and Recovery Act levels and/or the Comprehensive Environmental Response, Compensation, and Liability Act preliminary remediation goals are exceeded, additional sampling and action may be required.

  11. Facile and green synthesis of mesoporous Co3O4 nanocubes and their applications for supercapacitors

    Science.gov (United States)

    Liu, Xiangmei; Long, Qing; Jiang, Chunhui; Zhan, Beibei; Li, Chen; Liu, Shujuan; Zhao, Qiang; Huang, Wei; Dong, Xiaochen

    2013-06-01

    Nanostructured Co3O4 materials attracted significant attention due to their exceptional electrochemical (pseudo-capacitive) properties. However, rigorous preparation conditions are needed to control the size (especially nanosize), morphology and size distribution of the products obtained by conventional methods. Herein, we describe a novel one step shape-controlled synthesis of uniform Co3O4 nanocubes with a size of 50 nm with the existence of mesoporous carbon nanorods (meso-CNRs). In this synthesis process, meso-CNRs not only act as a heat receiver to directly obtain Co3O4 eliminating the high-temperature post-calcination, but also control the morphology of the resulting Co3O4 to form nanocubes with uniform distribution. More strikingly, mesoporous Co3O4 nanocubes are obtained by further thermal treatment. The structure and morphology of the samples were characterized by scanning electron microscopy, transmission electron microscopy and X-ray diffraction. A possible formation mechanism of mesoporous Co3O4 nanocubes is proposed here. Electrochemical tests have revealed that the prepared mesoporous Co3O4 nanocubes demonstrate a remarkable performance in supercapacitor applications due to the porous structure, which endows fast ion and electron transfer.Nanostructured Co3O4 materials attracted significant attention due to their exceptional electrochemical (pseudo-capacitive) properties. However, rigorous preparation conditions are needed to control the size (especially nanosize), morphology and size distribution of the products obtained by conventional methods. Herein, we describe a novel one step shape-controlled synthesis of uniform Co3O4 nanocubes with a size of 50 nm with the existence of mesoporous carbon nanorods (meso-CNRs). In this synthesis process, meso-CNRs not only act as a heat receiver to directly obtain Co3O4 eliminating the high-temperature post-calcination, but also control the morphology of the resulting Co3O4 to form nanocubes with uniform

  12. Application of exemption principles to the recycle and reuse of materials from nuclear facilities

    International Nuclear Information System (INIS)

    1992-01-01

    Radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials in industrial applications, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. The Radioactive Waste Safety Standards (RADWASS) programme is the IAEA's contribution to establishing and promoting, in a coherent and comprehensive manner, the basic safety philosophy for radioactive waste management and the steps necessary to ensure its implementation. The RADWASS publications will: (a) reflect the existing international consensus in the approaches and methodologies for safe waste management, including disposal, and provide mechanisms to establish consensus where it does not yet exist; and (b) provide Member States with a comprehensive series of internationally agreed upon documents to assist in the derivation of new, or to complement existing, national criteria, standards and practices. This Safety Practices publication is concerned with procedures for determining the levels of radionuclides in materials below which they can be exempted from regulatory control and recycled or reused without any further restriction. It describes how the internationally agreed upon principles for exemption can be applied in the case of recycle and reuse. The methodology is applied to derive the typical ranges of exempt concentrations for representative radionuclides. Refs, figs and tabs

  13. Facile 3D Metal Electrode Fabrication for Energy Applications via Inkjet Printing and Shape Memory Polymer

    International Nuclear Information System (INIS)

    Roberts, R C; Wu, J; Li, D C; Hau, N Y; Chang, Y H; Feng, S P

    2014-01-01

    This paper reports on a simple 3D metal electrode fabrication technique via inkjet printing onto a thermally contracting shape memory polymer (SMP) substrate. Inkjet printing allows for the direct patterning of structures from metal nanoparticle bearing liquid inks. After deposition, these inks require thermal curing steps to render a stable conductive film. By printing onto a SMP substrate, the metal nanoparticle ink can be cured and substrate shrunk simultaneously to create 3D metal microstructures, forming a large surface area topology well suited for energy applications. Polystyrene SMP shrinkage was characterized in a laboratory oven from 150-240°C, resulting in a size reduction of 1.97-2.58. Silver nanoparticle ink was patterned into electrodes, shrunk, and the topology characterized using scanning electron microscopy. Zinc-Silver Oxide microbatteries were fabricated to demonstrate the 3D electrodes compared to planar references. Characterization was performed using 10M potassium hydroxide electrolyte solution doped with zinc oxide (57g/L). After a 300s oxidation at 3Vdc, the 3D electrode battery demonstrated a 125% increased capacity over the reference cell. Reference cells degraded with longer oxidations, but the 3D electrodes were fully oxidized for 4 hours, and exhibited a capacity of 5.5mA-hr/cm 2 with stable metal performance

  14. Application of airborne photogrammetry for the visualisation and assessment of contamination migration arising from a Fukushima waste storage facility.

    Science.gov (United States)

    Connor, D T; Martin, P G; Smith, N T; Payne, L; Hutson, C; Payton, O D; Yamashiki, Y; Scott, T B

    2018-03-01

    Airborne systems such as lightweight and highly portable unmanned aerial vehicles (UAVs) are becoming increasingly widespread in both academia and industry - with an ever-increasing range of applications, including (but not limited to), air quality sampling, wildlife monitoring and land-use mapping. In this work, high-resolution airborne photogrammetry obtained using a multi-rotor system operating at low survey altitudes, is combined with ground-based radiation mapping data acquired at an interim storage facility for wastes removed as part of the large-scale Fukushima clean-up program. The investigation aimed to assess the extent to which the remediation program at a specific site has contained the stored contaminants, as well as present a new methodology for rapidly surveying radiological sites globally. From the three-dimensional rendering of the site of interest, it was possible to not only generate a powerful graphic confirming the elevated radiological intensity existing at the location of the waste bags, but also to also illustrate the downslope movement of contamination due to species leakage from the large 1m 3 storage bags. The entire survey took less than 1 h to perform, and was subsequently post-processed using graphical information software to obtain the renderings. The conclusions within this study not only highlight the usefulness of incorporating three-dimensional renderings within radiation mapping protocols, but also conclude that current methods of monitoring these storage facilities in the long term could be improved through the integration of UAVs within the standard protocol. Copyright © 2017 The Authors. Published by Elsevier Ltd.. All rights reserved.

  15. Facile synthesis of palladium nanoparticle doped polyaniline nanowires in soft templates for catalytic applications

    Science.gov (United States)

    Kshirasagar, Krushna J.; Markad, Uddhav S.; Saha, Abhijit; Sharma, Kiran Kumar K.; Sharma, Geeta K.

    2017-02-01

    Palladium nanoparticles doped polyaniline (Pd-PANI) nanocomposite (NCs) is synthesized in surfactant based liquid crystalline mesophase by chemical oxidation followed by radiolysis. The confinement of the liquid crystalline mesophase facilitates polymerization of aniline monomers and their 1D growth into polyaniline (PANI) nanowires by using ammonium persulfate. The PANI nanowires have an average diameter of 30-40 nm. The in situ radiolytic reduction of palladium ions ensures uniform size distribution of the palladium (Pd) nanoparticles on the surface of the PANI nanowires. The synthesized Pd-PANI nanocomposites show wire like structures of PANI (diameter ~30-40 nm) on which Pd nanoparticles of the size 10 nm are decorated. The identical average diameter of the PANI nanowires before and post gamma irradiation suggest high stability of the PANI nanowires in liquid crystalline mesophase. Surface characterization of the NCs were carried out using BET and XPS. The catalytic activity of Pd-PANI NCs are investigated in the reduction of methylene blue (MB) and 4-nitro phenol (4-NP) by sodium borohydride (NaBH4). The kinetics of the Pd-PANI NCs catalysed reactions are analysed using the Langmuir-Hinshelwood model. The apparent rate constant (k app) for the MB and 4-NP reduction reactions is 29  ×  10-3 s-1 and 20  ×  10-3 s-1 respectively with an actual Pd catalyst loading of 2.665  ×  10-4 ppm. Further, the recyclability of the Pd-PANI NCs catalyst in both the reduction reactions shows the stability of the catalyst up to four reaction cycles tested in this investigation and the multifunctional nature of the catalyst. The study provides a new approach for the directional synthesis of conducting polymer-metal nanocomposites and their possible application as a nanocatalyst in environmental remediation.

  16. A facile route to the synthesis of anilinic electroactive colloidal hydrogels for neural tissue engineering applications.

    Science.gov (United States)

    Zarrintaj, Payam; Urbanska, Aleksandra M; Gholizadeh, Saman Seyed; Goodarzi, Vahabodin; Saeb, Mohammad Reza; Mozafari, Masoud

    2018-04-15

    An innovative drug-loaded colloidal hydrogel was synthesized for applications in neural interfaces in tissue engineering by reacting carboxyl capped aniline dimer and gelatin molecules. Dexamethasone was loaded into the gelatin-aniline dimer solution as a model drug to form an in situ drug-loaded colloidal hydrogel. The conductivity of the hydrogel samples fluctuated around 10 -5  S/cm which appeared suitable for cellular activities. Cyclic voltammetry was used for electroactivity determination, in which 2 redox states were observed, suggesting that the short chain length and steric hindrance prevented the gel from achieving a fully oxidized state. Rheological data depicted the modulus decreasing with aniline dimer increment due to limited hydrogen bonds accessibility. Though the swelling ratio of pristine gelatin (600%) decreased by the introduction and increasing the concentration of aniline dimer because of its hydrophobic nature, it took the value of 300% at worst, which still seems promising for drug delivery uses. Degradation rate of hydrogel was similarly decreased by adding aniline dimer. Drug release was evaluated in passive and stimulated patterns demonstrating tendency of aniline dimer to form a vesicle that controls the drug release behavior. The optimal cell viability, proper cell attachment and neurite extension was achieved in the case of hydrogel containing 10 wt% aniline dimer. Based on tissue/organ behavior, it was promisingly possible to adjust the characteristics of the hydrogels for an optimal drug release. The outcome of this simple and effective approach can potentially offer additional tunable characteristics for recording and stimulating purposes in neural interfaces. Copyright © 2018 Elsevier Inc. All rights reserved.

  17. Foodstuff Survey Around a Major Nuclear Facility with Test of Satellite Image Application

    International Nuclear Information System (INIS)

    Fledderman, P.D.

    1999-01-01

    'A foodstuff survey was performed around the Savannah River Site, Aiken SC. It included a census of buildings and fields within 5 km of the boundary and determination of the locations and amounts of crops grown within 80 km of SRS center. Recent information for this region was collected on the amounts of meat, poultry, milk, and eggs produced, of deer hunted, and of sports fish caught. The locations and areas devoted to growing each crop were determined in two ways: by the usual process of assuming uniform crop distribution in each county on the basis of agricultural statistics reported by state agencies, and by analysis of two LANDSAT TM images obtained in May and September. For use with environmental radionuclide transfer and radiation dose calculation codes, locations within 80 km were defined for 64 sections by 16 sectors centered on the Site and by 16-km distance intervals from 16 km to 80 km. Most locally-raised foodstuff was distributed regionally and not retained locally for consumption. For four food crops, the amounts per section based on county agricultural statistics prorated by area were compared with the amounts per section based on satellite image analysis. The median ratios of the former to the latter were 0.6 - 0.7, suggesting that the two approaches are comparable but that satellite image analysis gave consistently higher amounts. Use of satellite image analysis is recommended on the basis of these findings to obtain site-specific, as compared to area-averaged, information on crop locations in conjunction with radionuclide pathway modelling. Some improvements in technique are suggested for satellite image application to characterize additional crops.'

  18. Facile synthesis of flower like copper oxide and their application to hydrogen peroxide and nitrite sensing

    Directory of Open Access Journals (Sweden)

    Zhang Li

    2011-12-01

    Full Text Available Abstract Background The detection of hydrogen peroxide (H2O2 and nitrite ion (NO2- is of great important in various fields including clinic, food, pharmaceutical and environmental analyses. Compared with many methods that have been developed for the determination of them, the electrochemical detection method has attracted much attention. In recent years, with the development of nanotechnology, many kinds of micro/nano-scale materials have been used in the construction of electrochemical biosensors because of their unique and particular properties. Among these catalysts, copper oxide (CuO, as a well known p-type semiconductor, has gained increasing attention not only for its unique properties but also for its applications in many fields such as gas sensors, photocatalyst and electrochemistry sensors. Continuing our previous investigations on transition-metal oxide including cuprous oxide and α-Fe2O3 modified electrode, in the present paper we examine the electrochemical and electrocatalytical behavior of flower like copper oxide modified glass carbon electrodes (CuO/GCE. Results Flower like copper oxide (CuO composed of many nanoflake was synthesized by a simple hydrothermal reaction and characterized using field-emission scanning electron microscopy (FE-SEM and X-ray diffraction (XRD. CuO modified glass carbon electrode (CuO/GCE was fabricated and characterized electrochemically. A highly sensitive method for the rapid amperometric detection of hydrogen peroxide (H2O2 and nitrite (NO2- was reported. Conclusions Due to the large specific surface area and inner characteristic of the flower like CuO, the resulting electrode show excellent electrocatalytic reduction for H2O2 and oxidation of NO2-. Its sensitivity, low detection limit, fast response time and simplicity are satisfactory. Furthermore, this synthetic approach can also be applied for the synthesis of other inorganic oxides with improved performances and they can also be extended to

  19. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    International Nuclear Information System (INIS)

    Ruokola, E.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  20. 137Cs Radiological risk estimation of NSD facility at Karawang site by using RESRAD onsite application: effect of cover thickness

    Science.gov (United States)

    Setiawan, B.; Prihastuti, S.; Moersidik, S. S.

    2018-02-01

    The operational of near surface disposal facility during waste packages loading activity into the facility, or in a monitoring activity around disposal facility at Karawang area is predicted to give a radiological risk to radiation workers. The thickness of disposal facility cover system affected the number of radiological risk of workers. Due to this reason, a radiological risk estimation needs to be considered. RESRAD onsite code is applied for this purpose by analyse the individual accepted dose and radiological risk data of radiation workers. The obtained results and then are compared with radiation protection reference in accordance with national regulation. In this case, the data from the experimental result of Karawang clay as host of disposal facility such as Kd value of 137Cs was used. Results showed that the thickness of the cover layer of disposal facility affected to the radiological risk which accepted by workers in a near surface disposal facility.

  1. Facile formation of dendrimer-stabilized gold nanoparticles modified with diatrizoic acid for enhanced computed tomography imaging applications.

    Science.gov (United States)

    Peng, Chen; Li, Kangan; Cao, Xueyan; Xiao, Tingting; Hou, Wenxiu; Zheng, Linfeng; Guo, Rui; Shen, Mingwu; Zhang, Guixiang; Shi, Xiangyang

    2012-11-07

    We report a facile approach to forming dendrimer-stabilized gold nanoparticles (Au DSNPs) through the use of amine-terminated fifth-generation poly(amidoamine) (PAMAM) dendrimers modified by diatrizoic acid (G5.NH(2)-DTA) as stabilizers for enhanced computed tomography (CT) imaging applications. In this study, by simply mixing G5.NH(2)-DTA dendrimers with gold salt in aqueous solution at room temperature, dendrimer-entrapped gold nanoparticles (Au DENPs) with a mean core size of 2.5 nm were able to be spontaneously formed. Followed by an acetylation reaction to neutralize the dendrimer remaining terminal amines, Au DSNPs with a mean size of 6 nm were formed. The formed DTA-containing [(Au(0))(50)-G5.NHAc-DTA] DSNPs were characterized via different techniques. We show that the Au DSNPs are colloid stable in aqueous solution under different pH and temperature conditions. In vitro hemolytic assay, cytotoxicity assay, flow cytometry analysis, and cell morphology observation reveal that the formed Au DSNPs have good hemocompatibility and are non-cytotoxic at a concentration up to 3.0 μM. X-ray absorption coefficient measurements show that the DTA-containing Au DSNPs have enhanced attenuation intensity, much higher than that of [(Au(0))(50)-G5.NHAc] DENPs without DTA or Omnipaque at the same molar concentration of the active element (Au or iodine). The formed DTA-containing Au DSNPs can be used for CT imaging of cancer cells in vitro as well as for blood pool CT imaging of mice in vivo with significantly improved signal enhancement. With the two radiodense elements of Au and iodine incorporated within one particle, the formed DTA-containing Au DSNPs may be applicable for CT imaging of various biological systems with enhanced X-ray attenuation property and detection sensitivity.

  2. Agreement Between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities. Addition to the List of Facilities Subject to Safeguards Under the Agreement

    International Nuclear Information System (INIS)

    2014-01-01

    In accordance with Paragraph 14(a) of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities (hereinafter “the Agreement”), India shall notify the Agency in writing of its decision to offer any facility identified by India for Agency safeguards under the Agreement. Any facility so notified by India becomes subject to the Agreement as of the date of receipt by the Agency of such written notification from India, and is to be included in the Annex to the Agreement. On 11 March 2014, the Agency received from India written notification, pursuant to Paragraph 14(a) of the Agreement, of its decision to bring one additional facility under safeguards in accordance with the provisions of the Agreement. Pursuant to Paragraph 14 4(a) of the Agreement, the Annex to the Agreement has been updated and is reproduced in this document for the information of all Members of the Agency [es

  3. Facile synthesis of iron oxides/reduced graphene oxide composites: application for electromagnetic wave absorption at high temperature.

    Science.gov (United States)

    Zhang, Lili; Yu, Xinxin; Hu, Hongrui; Li, Yang; Wu, Mingzai; Wang, Zhongzhu; Li, Guang; Sun, Zhaoqi; Chen, Changle

    2015-03-19

    Iron oxides/reduced graphene oxide composites were synthesized by facile thermochemical reactions of graphite oxide and FeSO4 · 7H2O. By adjusting reaction temperature, α-Fe2O3/reduced graphene oxide and Fe3O4/reduced graphene oxide composites can be obtained conveniently. Graphene oxide and reduced graphene oxide sheets were demonstrated to regulate the phase transition from α-Fe2O3 to Fe3O4 via γ-Fe2O3, which was reported for the first time. The hydroxyl groups attached on the graphene oxide sheets and H2 gas generated during the annealing of graphene oxide are believed to play an important role during these phase transformations. These samples showed good electromagnetic wave absorption performance due to their electromagnetic complementary effect. These samples possess much better electromagnetic wave absorption properties than the mixture of separately prepared Fe3O4 with rGO, suggesting the crucial role of synthetic method in determining the product properties. Also, these samples perform much better than commercial absorbers. Most importantly, the great stability of these composites is highly advantageous for applications as electromagnetic wave absorption materials at high temperatures.

  4. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    International Nuclear Information System (INIS)

    Elicson, Tom; Harwood, Bentley; Yorg, Richard; Lucek, Heather; Bouchard, Jim; Jukkola, Ray; Phan, Duan

    2011-01-01

    The application NUREG/CR-6850 EPRI/NRC fire PRA methodology to DOE facility presented several challenges. This paper documents the process and discusses several insights gained during development of the fire PRA. A brief review of the tasks performed is provided with particular focus on the following: Tasks 5 and 14: Fire-induced risk model and fire risk quantification. A key lesson learned was to begin model development and quantification as early as possible in the project using screening values and simplified modeling if necessary. Tasks 3 and 9: Fire PRA cable selection and detailed circuit failure analysis. In retrospect, it would have been beneficial to perform the model development and quantification in 2 phases with detailed circuit analysis applied during phase 2. This would have allowed for development of a robust model and quantification earlier in the project and would have provided insights into where to focus the detailed circuit analysis efforts. Tasks 8 and 11: Scoping fire modeling and detailed fire modeling. More focus should be placed on detailed fire modeling and less focus on scoping fire modeling. This was the approach taken for the fire PRA. Task 14: Fire risk quantification. Typically, multiple safe shutdown (SSD) components fail during a given fire scenario. Therefore dependent failure analysis is critical to obtaining a meaningful fire risk quantification. Dependent failure analysis for the fire PRA presented several challenges which will be discussed in the full paper.

  5. Facile solution-processed aqueous MoOx for feasible application in organic light-emitting diode

    Science.gov (United States)

    Zheng, Qinghong; Qu, Disui; Zhang, Yan; Li, Wanshu; Xiong, Jian; Cai, Ping; Xue, Xiaogang; Liu, Liming; Wang, Honghang; Zhang, Xiaowen

    2018-05-01

    Solution-processed techniques attract increasing attentions in organic electronics for their low-cost and scalable manufacturing. We demonstrate the favorite hole injection material of solution-processed aqueous MoOx (s-MoOx) with facile fabrication process and cast successful application to constructing efficient organic light-emitting diodes (OLEDs). Atomic force microscopy and X-ray photoelectron spectroscopy analysis show that s-MoOx behaves superior film morphology and non-stoichiometry with slight oxygen deficiency. With tris(8-hydroxy-quinolinato)aluminium as emitting layer, s-MoOx based OLED shows maximum luminous efficiency of 7.9 cd/A and power efficiency of 5.9 lm/W, which have been enhanced by 43.6% and 73.5%, respectively, in comparison with the counterpart using conventional vacuum thermal evaporation MoOx. Current-voltage, impedance-voltage, phase-voltage and capacitance-voltage characteristics of hole-only devices indicate that s-MoOx with two processes of "spin-coating/annealing" shows mostly enhanced hole injection capacity and thus promoting device performance. Our experiments provide an alternative approach for constructing efficient OLED with solution process.

  6. Facile Method and Novel Dielectric Material Using a Nanoparticle-Doped Thermoplastic Elastomer Composite Fabric for Triboelectric Nanogenerator Applications.

    Science.gov (United States)

    Zhang, Zhi; Chen, Ying; Debeli, Dereje Kebebew; Guo, Jian Sheng

    2018-04-18

    The trends toward flexible and wearable electronic devices give rise to the attention of triboelectric nanogenerators (TENGs) which can gather tiny energy from human body motions. However, to accommodate the needs, wearable electronics are still facing challenges for choosing a better dielectric material to improve their performance and practicability. As a kind of synthetic rubber, the thermoplastic elastomer (TPE) contains many advantages such as lightweight, good flexibility, high tear strength, and friction resistance, accompanied by good adhesion with fabrics, which is an optimal candidate of dielectric materials. Herein, a novel nanoparticle (NP)-doped TPE composite fabric-based TENG (TF-TENG) has been developed, which operates based on the NP-doped TPE composite fabric using a facile coating method. The performances of the TENG device are systematically investigated under various thicknesses of TPE films, NP kinds, and doping mass. After being composited with a Cu NP-doped TPE film, the TPE composite fabric exhibited superior elastic behavior and good bending property, along with excellent flexibility. Moreover, a maximum output voltage of 470 V, a current of 24 μA, and a power of 12 mW under 3 MΩ can be achieved by applying a force of 60 N on the TF-TENG. More importantly, the TF-TENG can be successfully used to harvest biomechanical energy from human body and provides much more comfort. In general, the TF-TENG has great application prospects in sustainable wearable devices owing to its lightweight, flexibility, and high mechanical properties.

  7. Chemo-mechanical modeling of low-pH concretes: Application to the calculation of storage facilities for radioactive waste

    International Nuclear Information System (INIS)

    El Bitouri, Youssef

    2014-01-01

    The purpose of this work concerns to design a tool able to simulate the chemo-mechanical behavior of low-pH concretes used in radioactive waste storage, from early age to a long-term. This tool consists of a phenomenological hydration model and an original chemical evolution model. The first model is used for short-term. It can predict the development of hydration at early age and its consequences. But taking into account that this model has been developed for applications at a young age, it is based on a fixed stoichiometry of hydrates and does not take into account the specificities of low-pH cements (chemical evolution at the long-term by reaction of residual silica). Thus, a chemical evolution model at the long-term is proposed. This model is based on a variable stoichiometry of hydrates. For this, it uses the calcium mass balance for describing calcium exchange between the various hydrates and anhydrous. This equation includes the kinetics of exchanges which are based on the difference in the thermodynamic equilibrium, of the microstructure and temperature. Finally, a coupling with mechanical properties evolution was performed to simulate the mechanical behavior of the radioactive waste storage facility. (author)

  8. Prevention of significant deterioration permit application for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    This New Source Review'' has been submitted by the US Department of Energy-Richland Operations Office (PO Box 550, Richland, Washington 99352), pursuant to WAC 173-403-050 and in compliance with the Department of Ecology Guide to Processing A Prevention Of Significant Deterioration (PSD) Permit'' for three new sources of radionuclide emissions at the Hanford Site in Washington State. The three new sources, the Fueled Clad Fabrication System (FCFS), the Radioisotope Power Systems Facility (RPSF), and the Fuel Assembly Area (FAA), will be located in one facility, the Fuels and Materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post-irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies for use in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, these systems will be dealt with separately to the extent possible. The FAA is a comparatively independent operation though it will share the FMEF complex.

  9. Electron paramagnetic resonance and optical spectroscopy of Yb sup 3 sup + ions in SrF sub 2 and BaF sub 2; an analysis of distortions of the crystal lattice near Yb sup 3 sup +

    CERN Document Server

    Falin, M L; Latypov, V A; Leushin, A M

    2003-01-01

    SrF sub 2 and BaF sub 2 crystals, doped with the Yb sup 3 sup + ions, have been investigated by electron paramagnetic resonance and optical spectroscopy. As-grown crystals of SrF sub 2 and BaF sub 2 show the two paramagnetic centres for the cubic (T sub c) and trigonal (T sub 4) symmetries of the Yb sup 3 sup + ions. Empirical diagrams of the energy levels were established and the potentials of the crystal field were determined. Information was obtained on the SrF sub 2 and BaF sub 2 phonon spectra from the electron-vibrational structure of the optical spectra. The crystal field parameters were used to analyse the crystal lattice distortions in the vicinity of the impurity ion and the F sup - ion compensating for the excess positive charge in T sub 4. Within the frames of a superposition model, it is shown that three F sup - ions from the nearest surrounding cube, located symmetrically with respect to the C sub 3 axis from the side of the ion-compensator, approach the impurity ion and cling to the axis of the...

  10. The text of the agreement between the Agency and Argentina for the application of safeguards to the Atucha power reactor facility

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 3 October 1972 between Argentina and the IAEA for the application of safeguards to the Atucha Power Reactor Facility has been suspended

  11. Study on Safety Assessment for TINT- Pre disposal Radioactive Waste Management Facilities by the Application of SAFRAN Software

    International Nuclear Information System (INIS)

    Ya-anant, Nanthavan

    2011-06-01

    Full text: The Radioactive Waste Management Center, Thailand Institute of Nuclear Technology (TINT) provides a centralized radioactive waste management (RWM) service in the country. The pre disposal RWM facilities are composed of low and intermediate level waste treatment and storage facilities. The benefits of this study are (1) to improve the safety of pre disposal RWM facilities (2) to experience with the SAFRAN software tool for the safety assessment of pre disposal RWM facilities, which has been developed following to the methodology from International Atomic Energy Agency (IAEA). The work was performed on collecting all waste management data, the diagram of facilities, buildings, location, procedure, waste classification, waste form, radiological/chemical/physical properties including scenarios in normal and accidental conditions. The result of normal condition is that the effective dose per year of worker and public is less than 20 mSv and 1 mSv respectively. So the TINT-RWM operation is safe, as referred to the regulation

  12. Radiation activities and application of ionizing radiation on cultural heritage at ENEA Calliope gamma facility (Casaccia R.C., Rome, Italy

    Directory of Open Access Journals (Sweden)

    Baccaro Stefania

    2017-12-01

    Full Text Available Since the 1980s, research and qualification activities are being carried out at the 60Co gamma Calliope plant, a pool-type irradiation facility located at the Research Centre ENEA-Casaccia (Rome, Italy. The Calliope facility is deeply involved in radiation processing research and on the evaluation and characterization of the effects induced by gamma radiation on materials for different applications (crystals, glasses, optical fibres, polymers and biological systems and on devices to be used in hostile radiation environment such as nuclear plants, aerospace and high energy physics experiments. All the activities are carried out in the framework of international projects and collaboration with industries and research institutions. In the present work, particular attention will be paid to the cultural heritage activities performed at the Calliope facility, focused on two different aspects: (a conservation and preservation by bio-deteriogen eradication in archived materials, and (b consolidation and protection by degraded wooden and stone porous artefacts consolidation.

  13. The disparity of health facilities in an urban area discourages proposed treatment application in inoperable lung cancer patients

    International Nuclear Information System (INIS)

    Hillas, Georgios; Bakakos, Petros; Trichas, Miltiadis; Vlastos, Fotis

    2010-01-01

    Patients with a newly diagnosed non-small cell lung cancer (NSCLC) stage IIIB are offered chemoradiotherapy, as proposed by the current guidelines. This combination treatment is facilitated by the coexistence of corresponding departments in the same establishment. The geographical disparity of these health facilities influences patients’ willingness to be treated and may influence their survival. This is an observational study that compares the survival of two groups of patients with NSCLC stage IIIB: those treated with chemoradiotherapy versus those treated only with chemotherapy. These two comparable groups were formed exclusively by patients’ and/or their families’ decisions. One hundred fifteen consecutive NSCLC stage IIIB patients were included in the study. All were hospitalized in the biggest Chest Disease Hospital in Athens and were offered sequential chemoradiotherapy. Only 54 patients opted for the proposed treatment, while 61 decided to be treated with chemotherapy only, denying continuing their treatment in another health care unit (radiotherapy). Their survival and related factors were analyzed. Mean overall survival was estimated 10 months (95% confidence interval [CI]: 7.96–12.04). Patients treated with chemoradiotherapy had almost double overall survival compared to those under chemotherapy (P = 0.001): 13.6 months (95% CI: 12.3–14.9) versus 7.5 (95% CI: 6.1–8.9). Patients aged ≤ 65 years (P < 0.001), smokers (P < 0.001), and those without a cancer history (P < 0.001) survived longer. The lack of a radiotherapy department in a hospital providing chemotherapy impedes the application of current guidelines advocating combined radiochemotherapy. When recommended radiotherapy after six chemo cycles, half of the patients are unwilling to be displaced and do not follow the recommendations. This has an impact on patient survival

  14. Materials Characterization at Utah State University: Facilities and Knowledge-base of Electronic Properties of Materials Applicable to Spacecraft Charging

    Science.gov (United States)

    Dennison, J. R.; Thomson, C. D.; Kite, J.; Zavyalov, V.; Corbridge, Jodie

    2004-01-01

    In an effort to improve the reliability and versatility of spacecraft charging models designed to assist spacecraft designers in accommodating and mitigating the harmful effects of charging on spacecraft, the NASA Space Environments and Effects (SEE) Program has funded development of facilities at Utah State University for the measurement of the electronic properties of both conducting and insulating spacecraft materials. We present here an overview of our instrumentation and capabilities, which are particularly well suited to study electron emission as related to spacecraft charging. These measurements include electron-induced secondary and backscattered yields, spectra, and angular resolved measurements as a function of incident energy, species and angle, plus investigations of ion-induced electron yields, photoelectron yields, sample charging and dielectric breakdown. Extensive surface science characterization capabilities are also available to fully characterize the samples in situ. Our measurements for a wide array of conducting and insulating spacecraft materials have been incorporated into the SEE Charge Collector Knowledge-base as a Database of Electronic Properties of Materials Applicable to Spacecraft Charging. This Database provides an extensive compilation of electronic properties, together with parameterization of these properties in a format that can be easily used with existing spacecraft charging engineering tools and with next generation plasma, charging, and radiation models. Tabulated properties in the Database include: electron-induced secondary electron yield, backscattered yield and emitted electron spectra; He, Ar and Xe ion-induced electron yields and emitted electron spectra; photoyield and solar emittance spectra; and materials characterization including reflectivity, dielectric constant, resistivity, arcing, optical microscopy images, scanning electron micrographs, scanning tunneling microscopy images, and Auger electron spectra. Further

  15. Facilities & Leadership

    Data.gov (United States)

    Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

  16. Impact of uranium-233/thorium cycle on advanced accountability concepts and fabrication facilities. Addendum 2 to application of advanced accountability concepts in mixed oxide fabrication

    International Nuclear Information System (INIS)

    Bastin, J.J.; Jump, M.J.; Lange, R.A.; Crandall, C.C.

    1977-11-01

    The Phase I study of the application of advanced accountability methods (DYMAC) in a uranium/plutonium mixed oxide facility was extended to cover the possible fabrication of uranium-233/thorium fuels. Revisions to Phase II of the DYMAC plan which would be necessitated by such a process are specified. These revisions include shielding requirements, measurement systems, licensing conditions, and safeguards considerations. The impact of the uranium/thorium cycle on a large-scale fuel fabrication facility was also reviewed; it was concluded that the essentially higher radioactivity of uranium/thorium feeds would lead to increased difficulties which tend to preclude early commercial application of the process. An amended schedule for Phase II is included

  17. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    International Nuclear Information System (INIS)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-01

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample

  18. Solid Waste Management Facilities with Permits by the Iowa DNR

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — All types of facilities that handle solid waste, including: sanitary landfills, appliance demanufacturing facilities, transfer stations, land application sites,...

  19. Biochemistry Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Biochemistry Facility provides expert services and consultation in biochemical enzyme assays and protein purification. The facility currently features 1) Liquid...

  20. The role of objective facial analysis using FDNA in making diagnoses following whole exome analysis. Report of two patients with mutations in the BAF complex genes.

    Science.gov (United States)

    Gripp, Karen W; Baker, Laura; Telegrafi, Aida; Monaghan, Kristin G

    2016-07-01

    The genetic basis of numerous intellectual disability (ID) syndromes has recently been identified by applying exome analysis on a research or clinical basis. There is significant clinical overlap of biologically related syndromes, as exemplified by Nicolaides-Baraitser (NCBRS) and Coffin-Siris (CSS) syndrome. Both result from mutations affecting the BAF (mSWI/SNF) complex and belong to the growing category of BAFopathies. In addition to the notable clinical overlap between these BAFopathies, heterogeneity exists for patients clinically diagnosed with one of these conditions. We report two teenagers with ID whose molecular diagnosis of a SMARC2A or ARID1B mutation, respectively, was established through clinical exome analysis. Interestingly, using only the information provided in a single clinically obtained facial photograph from each patient, the facial dysmorphology analysis detected similarities to facial patterns associated with NCBRS as the first suggestion for both individuals, followed by CSS as the second highest ranked in the individual with the ARID1B mutation. Had this information been available to the laboratory performing the exome analysis, it could have been utilized during the variant analysis and reporting process, in conjunction with the written summary provided with each test requisition. While the available massive parallel sequencing technology, variant calling and variant interpretation are constantly evolving, clinical information remains critical for this diagnostic process. When trio analysis is not feasible, additional diagnostic tools may become particularly valuable. Facial dysmorphology analysis data may supplement the clinical phenotype summary and provide data independent of the clinician's personal experience and bias. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  1. Hanford facility dangerous waste Part A, Form 3, and Part B permit application documentation for the Central Waste Complex (WA7890008967) (TSD: TS-2-4)

    International Nuclear Information System (INIS)

    Saueressig, D.G.

    1998-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating, treatment, storage, and/or disposal units, such as the Central Waste Complex (this document, DOE/RL-91-17). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the Central Waste Complex permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the Central Waste Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this Central Waste Complex permit application documentation is current as of May 1998

  2. Hanford facility dangerous waste Part A, Form 3 and Part B permit application documentation, Central Waste Complex (WA7890008967)(TSD: TS-2-4)

    Energy Technology Data Exchange (ETDEWEB)

    Saueressig, D.G.

    1998-05-20

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating, treatment, storage, and/or disposal units, such as the Central Waste Complex (this document, DOE/RL-91-17). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the Central Waste Complex permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the Central Waste Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this Central Waste Complex permit application documentation is current as of May 1998.

  3. Use of Persistent Identifiers to link Heterogeneous Data Systems in the Integrated Earth Data Applications (IEDA) Facility

    Science.gov (United States)

    Hsu, L.; Lehnert, K. A.; Carbotte, S. M.; Arko, R. A.; Ferrini, V.; O'hara, S. H.; Walker, J. D.

    2012-12-01

    The Integrated Earth Data Applications (IEDA) facility maintains multiple data systems with a wide range of solid earth data types from the marine, terrestrial, and polar environments. Examples of the different data types include syntheses of ultra-high resolution seafloor bathymetry collected on large collaborative cruises and analytical geochemistry measurements collected by single investigators in small, unique projects. These different data types have historically been channeled into separate, discipline-specific databases with search and retrieval tailored for the specific data type. However, a current major goal is to integrate data from different systems to allow interdisciplinary data discovery and scientific analysis. To increase discovery and access across these heterogeneous systems, IEDA employs several unique IDs, including sample IDs (International Geo Sample Number, IGSN), person IDs (GeoPass ID), funding award IDs (NSF Award Number), cruise IDs (from the Marine Geoscience Data System Expedition Metadata Catalog), dataset IDs (DOIs), and publication IDs (DOIs). These IDs allow linking of a sample registry (System for Earth SAmple Registration), data libraries and repositories (e.g. Geochemical Research Library, Marine Geoscience Data System), integrated synthesis databases (e.g. EarthChem Portal, PetDB), and investigator services (IEDA Data Compliance Tool). The linked systems allow efficient discovery of related data across different levels of granularity. In addition, IEDA data systems maintain links with several external data systems, including digital journal publishers. Links have been established between the EarthChem Portal and ScienceDirect through publication DOIs, returning sample-level objects and geochemical analyses for a particular publication. Linking IEDA-hosted data to digital publications with IGSNs at the sample level and with IEDA-allocated dataset DOIs are under development. As an example, an individual investigator could sign up

  4. DUPIC facility engineering

    International Nuclear Information System (INIS)

    Park, J. J.; Lee, H. H.; Kim, K. H.

    2002-03-01

    With starting DUPIC fuel fabrication experiment by using spent fuels, 1) operation and refurbishment for DFDF (DUPIC fuel development facility), and 2) operation and improvement of transportation equipment for radioactive materials between facilities became the objectives of this study. This report describes objectives of the project, necessities, state of related technology, R and D scope, R and D results, proposal for application etc

  5. Dance Facilities.

    Science.gov (United States)

    Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

    This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

  6. Application of HACCP principles as a management tool for monitoring and controlling microbiological hazards in water treatment facilities.

    Science.gov (United States)

    Jagals, C; Jagals, P

    2004-01-01

    HACCP (hazard analysis and critical control points) principles were applied to evaluate the effectiveness of two water treatment facilities to continually produce potable water free of microbiological health hazards. This paper reports a hazard analyses protocol (microbiological hazards based on faecal coliforms (FC) and turbidity (TBY) as indicators) for critical control points (CCPs) within each facility. The CCPs were raw resource water, sedimentation, filtration and chlorine-disinfection. The aim was to determine the effectiveness of each CCP to remove the indicators from the water under treatment. Arbitrary critical performance limit targets (CPLTs) were set up for each CCP to determine to what extent each contributed to effective removal and to predict what the effect would be if any of the CCPs should fail. Health-related water quality guideline limits for expected health effects were applied and compliance measured at the 90th percentile. The raw resource river water used at both treatment facilities complied with raw resource water extraction CPLTs. The treated potable water complied with health-related drinking water guidelines. Sedimentation removed the largest proportion of the indicators from the raw water, but showed failure potential that could overload the consequent system. Filtration effectiveness at both treatment facilities showed potential to break down the overall effectiveness of the entire treatment facility, since the filter systems failed to meet their respective CPLTs. This left the disinfection phase to remove the remaining portion of indicators. Faecal coliforms appeared to be completely removed from post-chlorination samples. This indicated that both chlorine disinfection phases were 100% effective in meeting their disinfection CPLTs, despite having to "clean up" the indicator organisms that spilt over from the upstream CCPs. This, nevertheless, implied a risk of unsafe water release into distribution. CCPs at these treatment

  7. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    Energy Technology Data Exchange (ETDEWEB)

    Ruokola, E. [ed.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  8. An Application Of Facility Location Models With Hotspot Analysis For Optimal Location Of Abattoir Bio-Energy Plant In Anambra State Of Nigeria

    Directory of Open Access Journals (Sweden)

    E. C. Chukwuma

    2015-08-01

    Full Text Available Poor waste management strategy in abattoir in the the study area has needs a major attention considering it negative impacts on man land and water. Sitting of centralized biogas plant in a strategic location in the state would be the major means of combating the environmental challenges of increase in abattoir waste generation as result of population explosion in the state. This study investigates optimal location for sitting central abattoir waste treatment facility in Anambra State of Nigeria using facility location models with hotspot analysis in GIS environment. The result of the study shows that Using centre of gravity model the central location was estimated to be at Xc Yc 6.900953016 6.110157865. Based on inadequacy of the model hotspot analysis operation was done the hotspot analysis delineated clusters of abattoirs significantly higher in bio-wastes production than the overall study area. The hotspot analysis shows that the West regions of the study area has many abattoir that is classified as hotspot abattoirs. Using the hotspot abattoirs as proposed sites for load-distance model three abattoirs were identified as proposed sites- Obosi slaugher house Nkpor Private slaughter house and Oye-olise Ogbunike slaugher house. Their load distance values are 17250.40058 16299.24005 and 18210.14631 respectively. The optimal location for construction of central abattoir bio-waste treatment facility based on the application of these location facility models and hotspot analysis is Nkpor private slaughter house or its environs.

  9. Application of an experimental irradiation facility type K-120 for the radiation treatment of agricultural products in large quantity

    International Nuclear Information System (INIS)

    Stenger, V.; Foeldiak, G.; Horvath, I.; Hargittai, P.; Bartfai, Cs.

    1979-01-01

    During experimental and pilot irradiation carried out by the 60 Co irradiation facility type K-120 of the Institute of Isotopes of the Hungarian Academy of Sciences an irradiation technology for the treatment of agricultural and food products of considerable density has been developed. Applying transport containers of commercial size the intermittent radiation treatment of great quantity products was made possible with homogeneous dose distribution. The radiation technical characteristics, the utilization coefficient and the capacity of the facility for every agricultural product were calculated. (author)

  10. Use and Application of the SADRWMS Methodology and SAFRAN Tool on the Thailand Institute of Nuclear Technology (TINT) Radioactive Waste Management Facility. Test Case Results. 05 October 2011

    International Nuclear Information System (INIS)

    2015-01-01

    The purpose of this document is to describe the working procedure of the test case and to provide feedback on the application of the methodology described in DS284 and the SAFRAN tool. This report documents how the test case was performed, describes how the methodology and software tool were applied, and provides feedback on the use and application of the SAFRAN Tool. The aim of this document is to address the key elements of the safety assessment and to demonstrate their principle contents and roles within the overall context of the safety case. This is done with particular emphasis on investigating the role of the SAFRAN Tool in developing a safety case for facilities similar to the TINT Facility. It is intended that this report will be the first of a series of complimentary safety reports illustrating the use and application of the methodology prescribed in DS284 and the application of the SAFRAN tool to a range of predisposal radioactive waste management activities

  11. Correspondence of Concept Hierarchies in Semantic Web Based upon Global Instances and its Application to Facility Management Database

    Science.gov (United States)

    Takahashi, Hiroki; Nishi, Yuusuke; Gion, Tomohiro; Minami, Shinichi; Fukunaga, Tatsuya; Ogata, Jiro; Yoshie, Osamu

    Semantic Web is the technology which determines the relevance of data over the Web using meta-data and which enables advanced search of global information. It is now desired to develop and apply this technology to many situations of facility management. In facility management, vocabulary should be unified to share the database of facilities for generating optimal maintenance schedule and so on. Under such situations, ontology databases are usually used to describe composition or hierarchy of facility parts. However, these vocabularies used in databases are not unified even between factories of same company, and this situation causes communication hazard between them. Moreover, concept involved in the hierarchy cannot be corresponded each other. There are some methods to correspond concepts of different hierarchy. But these methods have some defects, because they only attend target hierarchy itself and the number of instances. We propose improved method for corresponding concepts between different concepts' hierarchies, which uses other hierarchies all over the world of Web and the distance of instances to identify their relations. Our method can work even if the sets of instances belonging to the concepts are not identical.

  12. The clinically-tested S1P receptor agonists, FTY720 and BAF312, demonstrate subtype-specific bradycardia (S1P₁ and hypertension (S1P₃ in rat.

    Directory of Open Access Journals (Sweden)

    Ryan M Fryer

    Full Text Available Sphingosine-1-phospate (S1P and S1P receptor agonists elicit mechanism-based effects on cardiovascular function in vivo. Indeed, FTY720 (non-selective S1P(X receptor agonist produces modest hypertension in patients (2-3 mmHg in 1-yr trial as well as acute bradycardia independent of changes in blood pressure. However, the precise receptor subtypes responsible is controversial, likely dependent upon the cardiovascular response in question (e.g. bradycardia, hypertension, and perhaps even species-dependent since functional differences in rodent, rabbit, and human have been suggested. Thus, we characterized the S1P receptor subtype specificity for each compound in vitro and, in vivo, the cardiovascular effects of FTY720 and the more selective S1P₁,₅ agonist, BAF312, were tested during acute i.v. infusion in anesthetized rats and after oral administration for 10 days in telemetry-instrumented conscious rats. Acute i.v. infusion of FTY720 (0.1, 0.3, 1.0 mg/kg/20 min or BAF312 (0.5, 1.5, 5.0 mg/kg/20 min elicited acute bradycardia in anesthetized rats demonstrating an S1P₁ mediated mechanism-of-action. However, while FTY720 (0.5, 1.5, 5.0 mg/kg/d elicited dose-dependent hypertension after multiple days of oral administration in rat at clinically relevant plasma concentrations (24-hr mean blood pressure = 8.4, 12.8, 16.2 mmHg above baseline vs. 3 mmHg in vehicle controls, BAF312 (0.3, 3.0, 30.0 mg/kg/d had no significant effect on blood pressure at any dose tested suggesting that hypertension produced by FTY720 is mediated S1P₃ receptors. In summary, in vitro selectivity results in combination with studies performed in anesthetized and conscious rats administered two clinically tested S1P agonists, FTY720 or BAF312, suggest that S1P₁ receptors mediate bradycardia while hypertension is mediated by S1P₃ receptor activation.

  13. The development and medical applications of a simple facility for partial body in vivo neutron activation analysis using californium-252 sources

    International Nuclear Information System (INIS)

    Boddy, K.

    1978-11-01

    A simple and cheap facility for partial body neutron activation analysis has been designed, based on the use of two 100 μg 252 Cf neutron sources. The results reported show that calcium can be measured in parts of the body such as the tibia with a precision as good as +- 1.6 % for a radiation dose of 2 rem. The uniformity of the thermal neutron flux density is better than +- 3 % over 10 cm. Some applications of this irradiation facility for studies of trace elements, in particular cadmium in liver and aluminium in liver or brain, have also been explored. However, the sensitivity attainable is not yet sufficient for the study of normal levels, but could be of interest in toxicological investigations

  14. Impact of receipt of coprocessed uranium/plutonium on advanced accountability concepts and fabrication facilities. Addendum 1 to application of advanced accountability concepts in mixed oxide fabrication

    International Nuclear Information System (INIS)

    Bastin, J.J.; Jump, M.J.; Lange, R.A.; Randall, C.C.

    1977-11-01

    The Phase I study of the application of advanced accountability methods (DYMAC) in a uranium/plutonium mixed oxide facility was extended to assess the effect of coprocessed UO 2 --PuO 2 feed on the observations made in the original Phase I effort and on the proposed Phase II program. The retention of plutonium mixed with uranium throughout the process was also considered. This addendum reports that coprocessed feed would have minimal effect on the DYMAC program, except in the areas of material specifications, starting material delivery schedule, and labor requirements. Each of these areas is addressed, as are the impact of coprocessed feed at a large fuel fabrication facility and the changes needed in the dirty scrap recovery process to maintain the lower plutonium levels which may be required by future nonproliferation philosophy. An amended schedule for Phase II is included

  15. Facility transition instruction

    International Nuclear Information System (INIS)

    Morton, M.R.

    1997-01-01

    The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

  16. Potential applications of artificial intelligence in computer-based management systems for mixed waste incinerator facility operation

    International Nuclear Information System (INIS)

    Rivera, A.L.; Singh, S.P.N.; Ferrada, J.J.

    1991-01-01

    The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site, designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conversion and Recovery Act (RCRA). Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. This presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. This paper describes mixed waste incinerator facility performance-oriented tasks that could be assisted by Artificial Intelligence (AI) and the requirements for AI tools that would implement these algorithms in a computer-based system. 4 figs., 1 tab

  17. Fission reactor based epithermal neutron irradiation facilities for routine clinical application in BNCT-Hatanaka memorial lecture

    International Nuclear Information System (INIS)

    Harling, Otto K.

    2009-01-01

    Based on experience gained in the recent clinical studies at MIT/Harvard, the desirable characteristics of epithermal neutron irradiation facilities for eventual routine clinical BNCT are suggested. A discussion of two approaches to using fission reactors for epithermal neutron BNCT is provided. This is followed by specific suggestions for the performance and features needed for high throughput clinical BNCT. An example of a current state-of-the-art, reactor based facility, suited for routine clinical use is discussed. Some comments are provided on the current status of reactor versus accelerator based epithermal neutron sources for BNCT. This paper concludes with a summary and a few personal observations on BNCT by the author.

  18. Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

    International Nuclear Information System (INIS)

    2004-05-01

    Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

  19. Calculation of damage function of Al{sub 2}O{sub 3} in irradiation facilities for fusion reactor applications

    Energy Technology Data Exchange (ETDEWEB)

    Mota, F., E-mail: fernando.mota@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Ortiz, C.J., E-mail: christophe.ortiz@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Vila, R., E-mail: rafael.vila@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Casal, N., E-mail: natalia.casal@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); García, A., E-mail: angela.garcia@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Ibarra, A., E-mail: Angel.ibarra@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain)

    2013-11-15

    A rigorous material testing program is essential for the development of the nuclear fusion world program. In particular, it is very important to predict the generation of the displacement damage in materials, because the irradiation intensity expected in fusion conditions is such that the performance of materials and components under these extreme conditions is unknown. To study the damage produced by neutrons in materials of interest for fusion, a specific computational methodology was developed. Neutron fluxes expected in different irradiation facilities (International Fusion Materials Irradiation Facility [IFMIF] and DEMO-HCLL) and in different irradiation spots were obtained with particles transport codes (McDeLicious, MCNP). The energy differential cross sections of primary knock-on atoms were calculated using the NJOY code. Resulting data were input into the Monte Carlo code MARLOWE to calculate the corresponding displacements (i.e., interstitials (I) and vacancies (V)). However, the number of Frenkel pairs created during irradiation strongly depends on the recombination radius between interstitials and vacancies. This parameter corresponds to the minimum distance below which instantaneous recombination occurs. Mainly, the influence of such parameter on the damage function in Al{sub 2}O{sub 3} was assessed in this report. The displacements per atom values calculated as a function of the recombination radius considered are compared to experimental data to determine the most appropriate capture radius. In addition, the damage function and damage dose generated at different experimental irradiation facilities are compared with those expected in DEMO. The conclusion is that both IFMIF and TechnoFusión (future triple beam ion accelerator to emulate fusion neutron irradiation effects in materials) facilities are suited to perform relevant irradiation experiments for the design of DEMO.

  20. The Potential and Utilization of Unused Energy Sources for Large-Scale Horticulture Facility Applications under Korean Climatic Conditions

    Directory of Open Access Journals (Sweden)

    In Tak Hyun

    2014-07-01

    Full Text Available As the use of fossil fuel has increased, not only in construction, but also in agriculture due to the drastic industrial development in recent times, the problems of heating costs and global warming are getting worse. Therefore, introduction of more reliable and environmentally-friendly alternative energy sources has become urgent and the same trend is found in large-scale horticulture facilities. In this study, among many alternative energy sources, we investigated the reserves and the potential of various different unused energy sources which have infinite potential, but are nowadays wasted due to limitations in their utilization. In addition, we utilized available unused energy as a heat source for a heat pump in a large-scale horticulture facility and analyzed its feasibility through EnergyPlus simulation modeling. Accordingly, the discharge flow rate from the Fan Coil Unit (FCU in the horticulture facility, the discharge air temperature, and the return temperature were analyzed. The performance and heat consumption of each heat source were compared with those of conventional boilers. The result showed that the power load of the heat pump was decreased and thus the heat efficiency was increased as the temperature of the heat source was increased. Among the analyzed heat sources, power plant waste heat which had the highest heat source temperature consumed the least electric energy and showed the highest efficiency.