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Sample records for bnct facility application

  1. Dosimetry and radiobiology at the new RA-3 reactor boron neutron capture therapy (BNCT) facility: application to the treatment of experimental oral cancer.

    Science.gov (United States)

    Pozzi, E; Nigg, D W; Miller, M; Thorp, S I; Heber, E M; Zarza, L; Estryk, G; Monti Hughes, A; Molinari, A J; Garabalino, M; Itoiz, M E; Aromando, R F; Quintana, J; Trivillin, V A; Schwint, A E

    2009-07-01

    The National Atomic Energy Commission of Argentina (CNEA) constructed a novel thermal neutron source for use in boron neutron capture therapy (BNCT) applications at the RA-3 research reactor facility located in Buenos Aires. The aim of the present study was to perform a dosimetric characterization of the facility and undertake radiobiological studies of BNCT in an experimental model of oral cancer in the hamster cheek pouch. The free-field thermal flux was 7.1 x 10(9) n cm(-2)s(-1) and the fast neutron flux was 2.5 x 10(6) n cm(-2)s(-1), indicating a very well-thermalized neutron field with negligible fast neutron dose. For radiobiological studies it was necessary to shield the body of the hamster from the neutron flux while exposing the everted cheek pouch bearing the tumors. To that end we developed a lithium (enriched to 95% in (6)Li) carbonate enclosure. Groups of tumor-bearing hamsters were submitted to BPA-BNCT, GB-10-BNCT, (GB-10+BPA)-BNCT or beam only treatments. Normal (non-cancerized) hamsters were treated similarly to evaluate normal tissue radiotoxicity. The total physical dose delivered to tumor with the BNCT treatments ranged from 6 to 8.5 Gy. Tumor control at 30 days ranged from 73% to 85%, with no normal tissue radiotoxicity. Significant but reversible mucositis in precancerous tissue surrounding tumors was associated to BPA-BNCT. The therapeutic success of different BNCT protocols in treating experimental oral cancer at this novel facility was unequivocally demonstrated.

  2. Characterisation of the TAPIRO BNCT epithermal facility.

    Science.gov (United States)

    Burn, K W; Colli, V; Curzio, G; d'Errico, F; Gambarini, G; Rosi, G; Scolari, L

    2004-01-01

    A collimated epithermal beam for boron neutron capture therapy (BNCT) research has been designed and built at the TAPIRO fast research reactor. A complete experimental characterisation of the radiation field in the irradiation chamber has been performed, to verify agreement with IAEA requirements. Slow neutron fluxes have been measured by means of an activation technique and with thermoluminescent detectors (TLDs). The fast neutron dose has been determined with gel dosemeters, while the fast neutron spectrum has been acquired by means of a neutron spectrometer based on superheated drop detectors. The gamma-dose has been measured with gel dosemeters and TLDs. For an independent verification of the experimental results, fluxes, doses and neutron spectra have been calculated with Monte Carlo simulations using the codes MCNP4B and MCNPX_2.1.5 with the direct statistical approach (DSA). The results obtained confirm that the epithermal beams achievable at TAPIRO are of suitable quality for BNCT purposes.

  3. Characterisation of the TAPIRO BNCT thermal facility.

    Science.gov (United States)

    Rosi, G; Gambarini, G; Colli, V; Gay, S; Scolari, L; Fiorani, O; Perrone, A; Nava, E; Fasolo, F; Visca, L; Zanini, A

    2004-01-01

    Dosimetry and spectrometry measurements have been carried out in the thermal column of the research fast reactor RSV-TAPIRO (ENEA-Casaccia, Rome) in order to investigate its suitability for irradiation of cells or mice, with a view to research in the interests of boron neutron capture therapy (BNCT). The thermal column consists of a graphite moderator (40 cm thick) containing a lead shield (13 cm thick) in order to shield reactor background. The irradiation volume, inside this structure, has cubic shape (18 x 18 x 18 cm3). Besides measurements of fluence and dose rates in air or in phantom performed with thermoluminescence dosemeters (TLDs) and using the activation technique, dose and fluence profiles have been generated using a method based on gel dosemeters analysed with optical imaging. To check the consistency of the results, spectrometry measurements in the same irradiation volume have been performed by means of bubble detectors.

  4. Characteristics and application of spherical-type activation detectors in neutron spectrum measurements at a boron neutron capture therapy (BNCT) facility

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Heng-Xiao; Chen, Wei-Lin [Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu 300, Taiwan, ROC (China); Liu, Yuan-Hao [Neuboron Medtech Ltd., Nanjing, Jiangsu Province 21112 (China); Sheu, Rong-Jiun, E-mail: rjsheu@mx.nthu.edu.tw [Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu 300, Taiwan, ROC (China); Department of Engineering and System Science, National Tsing Hua University, Hsinchu 300, Taiwan, ROC (China)

    2016-03-01

    A set of spherical-type activation detectors was developed aiming to provide better determination of the neutron spectrum at the Tsing Hua Open-pool Reactor (THOR) BNCT facility. An activation foil embedded in a specially designed spherical holder exhibits three advantages: (1) minimizing the effect of neutron angular dependence, (2) creating response functions with broadened coverage of neutron energies by introducing additional moderators or absorbers to the central activation foil, and (3) reducing irradiation time because of improved detection efficiencies to epithermal neutron beam. This paper presents the design concept and the calculated response functions of new detectors. Theoretical and experimental demonstrations of the performance of the detectors are provided through comparisons of the unfolded neutron spectra determined using this method and conventional multiple-foil activation techniques.

  5. Feasibility of BNCT radiobiological experiments at the HYTHOR facility

    Science.gov (United States)

    Esposito, J.; Ceballos, C.; Soncin, M.; Fabris, C.; Friso, E.; Moro, D.; Colautti, P.; Jori, G.; Rosi, G.; Nava, E.

    2008-06-01

    HYTHOR (HYbrid Thermal spectrum sHifter tapirO Reactor) is a new thermal-neutron irradiation facility, which was installed and became operative in mid 2005 at the TAPIRO (TAratura PIla Rapida potenza 0) fast reactor, in the Casaccia research centre (near Rome) of ENEA (Ente per le Nuove tecnologie Energia ed Ambiente). The facility has been designed for in vivo radiobiological studies. In HYTHOR irradiation cavity, 1-6 mice can be simultaneously irradiated to study skin melanoma treatments with the BNCT (boron neutron capture therapy). The therapeutic effects of HYTHOR radiation field on mouse melanoma has been studied as a preliminary investigation before studying the tumour local control due to boron neutron capture effect after boronated molecule injection. The method to properly irradiate small animals has been precisely defined. Results show that HYTHOR radiation field is by itself effective in reducing the tumour-growth rate. This finding has to be taken into account in studying the effectiveness of new 10B carriers. A method to properly measure the reduction of the tumour-growth rate is reported and discussed.

  6. Investigation of development and management of treatment planning systems for BNCT at foreign facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    A new computational dosimetry system for BNCT: JCDS is developed by JAERI in order to carry out BNCT with epithermal neutron beam at present. The development and management situation of computational dosimetry system, which are developed and are used in BNCT facilities in foreign countries, were investigated in order to accurately grasp functions necessary for preparation of the treatment planning and its future subjects. In present state, 'SERA', which are developed by Idaho National Engineering and Environmental Laboratory (INEEL), is used in many BNCT facilities. Followings are necessary for development and management of the treatment planning system. (1) Reliability confirmation of system performance by verification as comparison examination of calculated value with actual experimental measured value. (2) Confirmation systems such as periodic maintenance for retention of the system quality. (3) The improvement system, which always considered relative merits and demerits with other computational dosimetry system. (4) The development of integrated system with patient setting. (author)

  7. Design of an epithermal column for BNCT based on D D fusion neutron facility

    Science.gov (United States)

    Durisi, E.; Zanini, A.; Manfredotti, C.; Palamara, F.; Sarotto, M.; Visca, L.; Nastasi, U.

    2007-05-01

    Boron Neutron Capture Therapy (BNCT) is currently performed on patients at nuclear reactors. At the same time the international BNCT community is engaged in the development of alternative facilities for in-hospital treatments. This paper investigates the potential of a novel high-output D-D neutron generator, developed at Lawrence Berkeley National Laboratory (CA, USA), for BNCT. The simulation code MCNP-4C is used to realize an accurate study of the epithermal column in view of the treatment of deep tumours. Different materials and Beam Shaping Assemblies (BSA) are investigated and an optimized configuration is proposed. The neutron beam quality is defined by the standard free beam parameters, calculated averaging over the collimator aperture. The results are discussed and compared with the performances of other facilities.

  8. On-line neutron beam monitoring of the Finnish BNCT facility

    Science.gov (United States)

    Tanner, Vesa; Auterinen, Iiro; Helin, Jori; Kosunen, Antti; Savolainen, Sauli

    1999-02-01

    A Boron Neutron Capture Therapy (BNCT) facility has been built at the FiR 1 research reactor of VTT Chemical Technology in Espoo, Finland. The facility is currently undergoing dosimetry characterisation and neutron beam operation research for clinical trials. The healthy tissue tolerance study, which was carried out in the new facility during spring 1998, demonstrated the reliability and user-friendliness of the new on-line beam monitoring system designed and constructed for BNCT by VTT Chemical Technology. The epithermal neutron beam is monitored at a bismuth gamma shield after an aluminiumfluoride-aluminium moderator. The detectors are three pulse mode U 235-fission chambers for epithermal neutron fluence rate and one current mode ionisation chamber for gamma dose rate. By using different detector sensitivities the beam intensity can be measured over a wide range of reactor power levels (0.001-250 kW). The detector signals are monitored on-line with a virtual instrumentation (LabView) based PC-program, which records and displays the actual count rates and total counts of the detectors in the beam. Also reactor in-core power instrumentation and control rod positions can be monitored via another LabView application. The main purpose of the monitoring system is to provide a dosimetric link to the dose in a patient during the treatment, as the fission chamber count rates have been calibrated to the induced thermal neutron fluence rate and to the absorbed dose rate at reference conditions in a tissue substitute phantom.

  9. Towards the final BSA modeling for the accelerator-driven BNCT facility at INFN LNL

    Energy Technology Data Exchange (ETDEWEB)

    Ceballos, C. [Centro de Aplicaciones Tecnlogicas y Desarrollo Nuclear, 5ta y30, Miramar, Playa, Ciudad Habana (Cuba); Esposito, J., E-mail: juan.esposito@lnl.infn.it [INFN, Laboratori Nazionali di Legnaro (LNL), via dell' Universita, 2, I-35020 Legnaro (PD) (Italy); Agosteo, S. [Politecnico di Milano, Dipartimento di Energia, Piazza Leonardo da Vinci 32, 20133 Milano (Italy)] [INFN, Sezione di Milano, via Celoria 16, 20133 Milano (Italy); Colautti, P.; Conte, V.; Moro, D. [INFN, Laboratori Nazionali di Legnaro (LNL), via dell' Universita, 2, I-35020 Legnaro (PD) (Italy); Pola, A. [Politecnico di Milano, Dipartimento di Energia, Piazza Leonardo da Vinci 32, 20133 Milano (Italy)] [INFN, Sezione di Milano, via Celoria 16, 20133 Milano (Italy)

    2011-12-15

    Some remarkable advances have been made in the last years on the SPES-BNCT project of the Istituto Nazionale di Fisica Nucleare (INFN) towards the development of the accelerator-driven thermal neutron beam facility at the Legnaro National Laboratories (LNL), aimed at the BNCT experimental treatment of extended skin melanoma. The compact neutron source will be produced via the {sup 9}Be(p,xn) reactions using the 5 MeV, 30 mA beam driven by the RFQ accelerator, whose modules construction has been recently completed, into a thick beryllium target prototype already available. The Beam Shaping Assembly (BSA) final modeling, using both neutron converter and the new, detailed, Be(p,xn) neutron yield spectra at 5 MeV energy recently measured at the CN Van de Graaff accelerator at LNL, is summarized here.

  10. Evaluation of the effective dose during BNCT at TRR thermal column epithermal facility.

    Science.gov (United States)

    Jarahi, Hossein; Kasesaz, Yaser; Saleh-Koutahi, Seyed Mohsen

    2016-04-01

    An epithermal neutron beam has been designed for Boron neutron Capture Therapy (BNCT) at the thermal column of Tehran Research Reactor (TRR) recently. In this paper the whole body effective dose, as well as the equivalent doses of several organs have been calculated in this facility using MCNP4C Monte Carlo code. The effective dose has been calculated by using the absorbed doses determined for each individual organ, taking into account the radiation and tissue weighting factors. The ICRP 110 whole body male phantom has been used as a patient model. It was found that the effective dose during BNCT of a brain tumor is equal to 0.90Sv. This effective dose may induce a 4% secondary cancer risk.

  11. Postoperative treatment of glioblastoma with BNCT at the petten irradiation facility (EORTC protocol 11,961).

    Science.gov (United States)

    Hideghéty, K; Sauerwein, W; Haselsberger, K; Grochulla, F; Fankhauser, H; Moss, R; Huiskamp, R; Gabel, D; de Vries, M

    1999-06-01

    The boron neutron capture therapy is based on the reaction occurring between the isotope 10B and thermal neutrons. A low energy neutron is captured by the nucleus and it disintegrates into two densely ionising particles, Li nucleus and He nucleus (alpha particle), with high biological effectiveness. On the basis of comprehensive preclinical investigations in the frame of the European Collaboration with Na2B12H11SH (BSH), as boron delivery agent, the first European phase I, clinical trial was designed at the only available epithermal beam in Europe, at the High Flux Reactor, Petten, in the Netherlands. The goal of this study is to establish the safe BNCT dose for cranial tumors under defined conditions. BNCT is applied as postoperative radiotherapy in 4 fractions, after removal of the tumor for a group of patients suffering from glioblastoma, who would have no benefit from conventional treatment, but have sufficient life expectancy to detect late radiation morbidity due to BNCT. The starting dose is set at 80% of the dose where neurological effects occurred in preclinical large animal experiments following a single fraction. The radiation dose will be escalated, by constant boron concentration in blood, in 4 steps for cohorts of ten patients, after an observation period of at least 6 months after the end of BNCT of the last patient of a cohort. The adverse events on healthy tissues due to BSH and due to the radiotherapy will be analysed in order to establish the maximal tolerated dose and dose limiting toxicity. Besides of the primary aim of this study the survival will be recorded. The first patient was treated in October 1997, and further four patients have been irradiated to-date. The protocol design proved to be well applicable, establishing the basis for scientific evaluation, for performance of safe patient treatment in a very complex situation and for opening the possibility to perform further clinical research work on BNCT.

  12. Postoperative treatment of glioblastoma with BNCT at the Petten Irradiation Facility (EORTC Protocol 11961)

    Energy Technology Data Exchange (ETDEWEB)

    Hideghety, K.; Sauerwein, W. [Strahlenklinik, Universitaetsklinikum Essen (Germany); Haselsberger, K. [Klinik fuer Neurochirurgie, Graz Univ. (Austria); Grochulla, F. [Klinik fuer Neurochirurgie, Zentralkrankenhaus Bremen (Germany); Frankhauser, H. [Service de Neurochirurgie, CHUV Lausanne (Switzerland); Moss, R. [European Commission Joint Research Centre Petten (Netherlands); Huiskamp, R. [Netherlands Energy Research Foundation, ECN Petten (Netherlands); Gabel, D. [Chemistry Dept., Univ. Bremen (Germany); Vries, M. de [EORTC, New Drug Development Office Amsterdam (Netherlands)

    1999-06-01

    The boron neutron capture therapy is based on the reaction occurring between the isotope {sup 10}B and thermal neutrons. A low energy neutron is captured by the nucleus and it disintegrates into two densely ionising particles, Li nucleus and He nucleus ({alpha} particle), with high biological effectiveness. On the basis of comprehensive preclinical investigations in the frame of the European Collaboration with Na{sub 2}B{sub 12}H{sub 11}SH (BSH), as boron delivery agent, the first European phase I, clinical trial was designed at the only available epithermal beam in Europe, at the High Flux Reactor, Petten, in the Netherland. The goal of this study is to establish the safe BNCT dose for cranial tumors under defined conditions. BNCT is applied as postoperative radiotherapy in 4 fractions, after removal of the tumor for a group of patients suffering from glioblastoma, who would have no benefit from conventional treatment, but have sufficient life expectancy to detect late radiation morbidity due to BNCT. The starting dose is set at 80% of the dose where neurological effects occured in preclinical large animal experiments following a single fraction. The radiation dose will be escalated, by constant boron concentration in blood, in 4 steps for cohorts of ten patients, after an observation period of at least 6 months after the end of BNCT of the last patient of a cohort. The adverse events on healthy tissues due to BSH and due to the radiotherapy will be analysed in order to establish the maximal tolerated dose and dose limiting toxicity. Besides of the primary aim of this study the survival will be recorded. The first patient was treated in October 1997, and further four patients have been irradiated todate. The protocol design proved to be well applicable, establishing the basis for scientific evaluation, for performance of safe patient treatment in a very complex situation and for opening the possibility to perform further clinical research work on BNCT. (orig.)

  13. The new hybrid thermal neutron facility at TAPIRO reactor for BNCT radiobiological experiments.

    Science.gov (United States)

    Esposito, J; Rosi, G; Agosteo, S

    2007-01-01

    A new thermal neutron irradiation facility, devoted to carry out both dosimetric and radiobiological studies on boron carriers, which are being developed in the framework of INFN BNCT project, has been installed at the ENEA Casaccia TAPIRO research fast reactor. The thermal column, based on an original, hybrid, neutron spectrum shifter configuration, has been recently become operative. In spite of its low power (5 kW), the new facility is able to provide a high thermal neutron flux level, uniformly distributed inside the irradiation cavity, with a quite low gamma background. The main features and preliminary benchmark measurements of the Beam-shaping assembly are here presented and discussed.

  14. In-phantom characterisation studies at the Birmingham Accelerator-Generated epIthermal Neutron Source (BAGINS) BNCT facility.

    Science.gov (United States)

    Culbertson, Christopher N; Green, Stuart; Mason, Anna J; Picton, David; Baugh, Gareth; Hugtenburg, Richard P; Yin, Zaizhe; Scott, Malcolm C; Nelson, John M

    2004-11-01

    A broad experimental campaign to validate the final epithermal neutron beam design for the BNCT facility constructed at the University of Birmingham concluded in November 2003. The final moderator and facility designs are overviewed briefly, followed by a summary of the dosimetric methods and presentation of a small subset of the results from this campaign. The dual ionisation chamber technique was used together with foil activation to quantify the fast neutron, photon, and thermal neutron beam dose components in a large rectangular phantom exposed to the beam with a 12 cm diameter beam delimiter in place. After application of a normalisation factor, dose measurements agree with in-phantom MCNP4C predictions within 10% for the photon dose, within 10% for thermal neutron dose, and within 25% for the proton recoil dose along the main beam axis.

  15. Development of a tandem-electrostatic-quadrupole accelerator facility for BNCT.

    Science.gov (United States)

    Kreiner, A J; Thatar Vento, V; Levinas, P; Bergueiro, J; Di Paolo, H; Burlon, A A; Kesque, J M; Valda, A A; Debray, M E; Somacal, H R; Minsky, D M; Estrada, L; Hazarabedian, A; Johann, F; Suarez Sandin, J C; Castell, W; Davidson, J; Davidson, M; Giboudot, Y; Repetto, M; Obligado, M; Nery, J P; Huck, H; Igarzabal, M; Fernandez Salares, A

    2009-07-01

    In this work we describe the present status of an ongoing project to develop a tandem-electrostatic-quadrupole (TESQ) accelerator facility for accelerator-based (AB) BNCT at the Atomic Energy Commission of Argentina in Buenos Aires. The project final goal is a machine capable of delivering 30 mA of 2.4 MeV protons to be used in conjunction with a neutron production target based on the (7)Li(p,n)(7)Be reaction slightly beyond its resonance at 2.25 MeV. These are the specifications needed to produce sufficiently intense and clean epithermal neutron beams, based on the (7)Li(p,n)(7)Be reaction, to perform BNCT treatment for deep-seated tumors in less than an hour. An electrostatic machine is the technologically simplest and cheapest solution for optimized AB-BNCT. The machine being designed and constructed is a folded TESQ with a high-voltage terminal at 1.2 MV intended to work in air. Such a machine is conceptually shown to be capable of transporting and accelerating a 30 mA proton beam to 2.4 MeV. The general geometric layout, its associated electrostatic fields, and the acceleration tube are simulated using a 3D finite element procedure. The design and construction of the ESQ modules is discussed and their electrostatic fields are investigated. Beam transport calculations through the accelerator are briefly mentioned. Likewise, work related to neutron production targets, strippers, beam shaping assembly and patient treatment room is briefly described.

  16. Be target development for the accelerator-based SPES-BNCT facility at INFN Legnaro.

    Science.gov (United States)

    Esposito, J; Colautti, P; Fabritsiev, S; Gervash, A; Giniyatulin, R; Lomasov, V N; Makhankov, A; Mazul, I; Pisent, A; Pokrovsky, A; Rumyantsev, M; Tanchuk, V; Tecchio, L

    2009-07-01

    An accelerator-driven thermal neutron source for BNCT, planned to be installed at the INFN Laboratori Nazionali di Legnaro (LNL), is in progress in the framework of the SPES (selective production of exotic species) research program. The most critical element of such a facility is the construction of a reliable neutron converter based on the (9)Be(p,xn) nuclear reaction, working at a high power level (150 kW) and 5 MeV beam energy, due to the SPES driver constraints. Two original, beryllium-based, target concepts have been designed for such a purpose. The present status of the neutron converter, as well as the test results performed so far on prototypes constructed, is reported here.

  17. Neutron collimator design of neutron radiography based on the BNCT facility

    Science.gov (United States)

    Yang, Xiao-Peng; Yu, Bo-Xiang; Li, Yi-Guo; Peng, Dan; Lu, Jin; Zhang, Gao-Long; Zhao, Hang; Zhang, Ai-Wu; Li, Chun-Yang; Liu, Wan-Jin; Hu, Tao; Lü, Jun-Guang

    2014-02-01

    For the research of CCD neutron radiography, a neutron collimator was designed based on the exit of thermal neutron of the Boron Neutron Capture Therapy (BNCT) reactor. Based on the Geant4 simulations, the preliminary choice of the size of the collimator was determined. The materials were selected according to the literature data. Then, a collimator was constructed and tested on site. The results of experiment and simulation show that the thermal neutron flux at the end of the neutron collimator is greater than 1.0×106 n/cm2/s, the maximum collimation ratio (L/D) is 58, the Cd-ratio(Mn) is 160 and the diameter of collimator end is 10 cm. This neutron collimator is considered to be applicable for neutron radiography.

  18. Neutron collimator design of neutron radiography based on the BNCT facility

    CERN Document Server

    Yang, XP; Li, YG; Peng, D; Lu, J; Zhang, GL; Zhao, H; Zhang, AW; Li, CY; Liu, WJ; Hu, T; Lv, JG

    2013-01-01

    For the research of CCD neutron radiography, a neutron collimator was designed based on the exit of thermal neutron of the Boron Neutron Capture Therapy (BNCT) reactor. Based on the Geant4 simulations, the preliminary choice of the size of the collimator was determined. The materials were selected according to the literature data. Then, a collimator was constructed and tested on site. The results of experiment and simulation show that the thermal neutron flux at the end of theneutron collimator is greater than 10^6 n/cm^2/s, the maximum collimation ratio (L/D) is 58, the Cd-ratio(Mn) is 160 and the diameter of collimator end is 10 cm. This neutron collimator is considered to be applicable for neutron radiography.

  19. BNCT Technology Development on HANARO Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Ki Jung; Park, Kyung Bae; Whang, Seung Ryul; Kim, Myong Seop

    2007-06-15

    So as to establish the biological effects of BNCT in the HANARO Reactor, biological damages in cells and animals with treatment of boron/neutron were investigated. And 124I-BPA animal PET image, analysis technology of the boron contents in the mouse tissues by ICP-AES was established. A Standard clinical protocol, a toxicity evaluation report and an efficacy investigation report of BNCT has been developed. Based on these data, the primary permission of clinical application was acquired through IRB of our hospital. Three cases of pre-clinical experiment for boron distribution and two cases of medium-sized animal simulation experiment using cat with verifying for 2 months after BNCT was performed and so the clinical demonstration with a patient was prepared. Also neutron flux, fast neutron flux and gamma ray dose of BNCT facility were calculated and these data will be utilized good informations for clinical trials and further BNCT research. For the new synthesis of a boron compound, o-carboranyl ethylamine, o-carboranylenepiperidine, o-carboranyl-THIQ and o-carboranyl-s-triazine derivatives were synthesized. Among them, boron uptake in the cancer cell of the triazine derivative was about 25 times than that of BPA and so these three synthesized methods of new boron compounds were patented.

  20. First tomographic image of neutron capture rate in a BNCT facility

    Energy Technology Data Exchange (ETDEWEB)

    Minsky, D.M., E-mail: minsky@tandar.cnea.gov.ar [Gerencia de Investigacion y Aplicaciones, CAC, CNEA, Av. Gral. Paz 1499 (B1650KNA), San Martin, Prov. Bs. As. (Argentina)] [Escuela de Ciencia y Tecnologia, , UNSAM, M. de Irigoyen 3100 (1650), San Martin, Prov. Bs. As. (Argentina)] [Conicet, Av. Rivadavia 1917 (C1033AAJ), Buenos Aires (Argentina); Valda, A.A. [Gerencia de Investigacion y Aplicaciones, CAC, CNEA, Av. Gral. Paz 1499 (B1650KNA), San Martin, Prov. Bs. As. (Argentina)] [Escuela de Ciencia y Tecnologia, , UNSAM, M. de Irigoyen 3100 (1650), San Martin, Prov. Bs. As. (Argentina); Kreiner, A.J. [Gerencia de Investigacion y Aplicaciones, CAC, CNEA, Av. Gral. Paz 1499 (B1650KNA), San Martin, Prov. Bs. As. (Argentina)] [Escuela de Ciencia y Tecnologia, , UNSAM, M. de Irigoyen 3100 (1650), San Martin, Prov. Bs. As. (Argentina)] [Conicet, Av. Rivadavia 1917 (C1033AAJ), Buenos Aires (Argentina); Green, S.; Wojnecki, C. [School of Physics and Astronomy, University of Birmingham, B15 2 TT (United Kingdom)] [Department of Medical Physics, University Hospital Birmingham, Birmingham B15 2TH (United Kingdom); Ghani, Z. [Department of Medical Physics, University Hospital Birmingham, Birmingham B15 2TH (United Kingdom)

    2011-12-15

    This work discusses the development of online dosimetry of the boron dose via Single Photon Emission Computed Tomography (SPECT) during a BNCT treatment irradiation. Such a system will allow the online computation of boron dose maps without the large current uncertainties in the assessment of the boron concentration in different tissues. The first tomographic boron dose image with a SPECT prototype is shown.

  1. Gel dosimetry in the BNCT facility for extra-corporeal treatment of liver cancer at the HFR Petten.

    Science.gov (United States)

    Gambarini, G; Daquino, G G; Moss, R L; Carrara, M; Nievaart, V A; Vanossi, E

    2007-01-01

    A thorough evaluation of the dose inside a specially designed and built facility for extra-corporeal treatment of liver cancer by boron neutron capture therapy (BNCT) at the High Flux Reactor (HFR) Petten (The Netherlands) is the necessary step before animal studies can start. The absorbed doses are measured by means of gel dosemeters, which help to validate the Monte Carlo simulations of the spheroidal liver holder that will contain the human liver for irradiation with an epithermal neutron beam. These dosemeters allow imaging of the dose due to gammas and to the charged particles produced by the (10)B reaction. The thermal neutron flux is extrapolated from the boron dose images and compared to that obtained by the calculations. As an additional reference, Au, Cu and Mn foil measurements are performed. All results appear consistent with the calculations and confirm that the BNCT liver facility is able to provide an almost homogeneous thermal neutron distribution in the liver, which is a requirement for a successful treatment of liver metastases.

  2. Optimization of the irradiation beam in the bnct research facility at IEA-R1 reactor

    OpenAIRE

    Vinicius Alexandre de Castro

    2015-01-01

    A Terapia por Captura de Nêutrons pelo Boro (BNCT) é uma técnica radioterapêutica, que visa o tratamento de alguns tipos de câncer, em que sua energia útil é proveniente da reação nuclear promovida pela incidência de nêutrons térmicos no isótopo de 10B. No Brasil existe uma instalação, localizada junto ao canal de irradiação número 3 do Reator de Pesquisas IEA-R1 do IPEN, que foi projetada para o desenvolvimento de pesquisas em BNCT. Para uma aplicação adequada da técnica é necessário que o f...

  3. Optimization of the irradiation beam in the BNCT research facility at IEA-R1 reactor; Otimizacao do feixe de irradiacao na instalacao para estudos em BNCT junto ao reator IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Castro, Vinicius Alexandre de

    2014-07-01

    Boron Neutron Capture Therapy (BNCT) is a radiotherapeutic technique for the treatment of some types of cancer whose useful energy comes from a nuclear reaction that occurs when thermal neutron impinges upon a Boron-10 atom. In Brazil there is a research facility built along the beam hole number 3 of the IEA-R1 research reactor at IPEN, which was designed to perform BNCT research experiments. For a good performance of the technique, the irradiation beam should be mostly composed of thermal neutrons with a minimum as possible gamma and above thermal neutron components. This work aims to monitor and evaluate the irradiation beam on the sample irradiation position through the use of activation detectors (activation foils) and also to propose, through simulation using the radiation transport code, MCNP, new sets of moderators and filters which shall deliver better irradiation fields at the irradiation sample position In this work, a simulation methodology, based on a MCNP card, known as wwg (weight window generation) was studied, and the neutron energy spectrum has been experimentally discriminated at 5 energy ranges by using a new set o activation foils. It also has been concluded that the BNCT research facility has the required thermal neutron flux to perform studies in the area and it has a great potential for improvement for tailoring the irradiation field. (author)

  4. INEL BNCT Program

    Energy Technology Data Exchange (ETDEWEB)

    Ackermann, A.L. (ed.)

    1991-08-01

    This Bulletin presents a summary of accomplishments and highlights in the Idaho National Engineering Laboratory's (INEL) Boron Neutron Capture Therapy (BNCT) Program for August 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

  5. Procedural and practical applications of radiation measurements for BNCT at the HFR Petten

    Science.gov (United States)

    Moss, R. L.; Stecher-Rasmussen, F.; Rassow, J.; Morrissey, J.; Voorbraak, W.; Verbakel, W.; Appelman, K.; Daquino, G. G.; Muzi, L.; Wittig, A.; Bourhis-Martin, E.; Sauerwein, W.

    2004-01-01

    Since October 1997, a clinical trial of Boron Neutron Capture Therapy (BNCT) for glioblastoma patients has been in progress at the High Flux Reactor, Petten, the Netherlands. The trial is a European Organisation for Research and Treatment of Cancer (EORTC) protocol (#11 961) and, as such, must be conducted following the highest quality management and procedures, according to good clinical practice and also other internationally accepted codes. The complexity of BNCT involves not only strict international procedures, but also a variety of techniques to measure the different aspects of the irradiation involved when treating the patient. Applications include: free beam measurements using packets of activation foils; in-phantom measurements for beam calibration using ionisation chambers, pn-diodes and activation foils; monitoring of the irradiation beam during patient treatment using fission chambers and GM-counters; boron in blood measurements using prompt gamma ray spectroscopy; radiation protection of the patient and staff using portable radiation dosimeters and personal dosimeters; and in vivo measurements of the boron in the patient using a prompt gamma ray telescope. The procedures and applications of such techniques are presented here, with particular emphasis on the importance of the quality assurance/quality control procedures and its reporting.

  6. Building of scientific information system for sustainable development of BNCT in Bulgaria.

    Science.gov (United States)

    Mitev, M; Ilieva, K; Apostolov, T

    2009-07-01

    Building a boron neutron capture therapy (BNCT) facility is foreseen within the reconstruction of the Research Reactor IRT (IRT) of the Institute for Nuclear Research and Nuclear Energy of the Bulgaria Academy of Sciences (INRNE). The development of BNCT at IRT plays a very significant role in the plan for sustainable application of the reactor. A centralized scientific information system on BNCT is being built at the INRNE with the purpose to collect and sort new information as knowledge accumulated during more than thirty years history of BNCT. This BNCT information system will help the creation and consolidation of a well informed and interconnected interdisciplinary team of physicists, chemists, biologists, and radio-oncologists for establishing BNCT cancer treatment in Bulgaria. It will strengthen more intensive development of the national network as well as its enlargement to the Balkan region countries. Furthermore, to acquaint the public at large with the opportunity for BNCT cancer treatment will be addressed. Human, social, and economics results due to BNCT for many patients from Balkan region are expected.

  7. Initial Experimental Verification of the Neutron Beam Modeling for the LBNL BNCT Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bleuel, D.L.; Chu, W.T.; Donahue, R.J.; Ludewigt, B.A.; McDonald, R.J.; Smith, A.R.; Stone, N.A.; Vuji, J.

    1999-01-19

    In preparation for future clinical BNCT trials, neutron production via the 7Li(p,n) reaction as well as subsequent moderation to produce epithermal neutrons have been studied. Proper design of a moderator and filter assembly is crucial in producing an optimal epithermal neutron spectrum for brain tumor treatments. Based on in-phantom figures-of-merit,desirable assemblies have been identified. Experiments were performed at the Lawrence Berkeley National Laboratory's 88-inch cyclotron to characterize epithermal neutron beams created using several microampere of 2.5 MeV protons on a lithium target. The neutron moderating assembly consisted of Al/AlF3 and Teflon, with a lead reflector to produce an epithermal spectrum strongly peaked at 10-20 keV. The thermal neutron fluence was measured as a function of depth in a cubic lucite head phantom by neutron activation in gold foils. Portions of the neutron spectrum were measured by in-air activation of six cadmium-covered materials (Au, Mn, In, Cu, Co, W) with high epithermal neutron absorption resonances. The results are reasonably reproduced in Monte Carlo computational models, confirming their validity.

  8. Positron emission tomography and [{sup 18}F]BPA: A perspective application to assess tumour extraction of boron in BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Menichetti, L. [Department of PET and Radiopharmaceutical Chemistry, C.N.R. Institute of Clinical Physiology, Pisa (Italy)], E-mail: luca.menichetti@ifc.cnr.it; Cionini, L. [Unit of Radiotherapy, AOUP-University Hospital, Pisa (Italy); Sauerwein, W.A. [Department of Radiation Oncology, University Duisburg-Essen, University Hospital Essen (Germany); Altieri, S. [University of Pavia, Department of Nuclear Physics, Pavia (Italy); Solin, O.; Minn, H. [Turku PET Centre, University of Turku (Finland); Salvadori, P.A. [Department of PET and Radiopharmaceutical Chemistry, C.N.R. Institute of Clinical Physiology, Pisa (Italy)

    2009-07-15

    Positron emission tomography (PET) has become a key imaging tool in clinical practice and biomedical research to quantify and study biochemical processes in vivo. Physiologically active compounds are tagged with positron emitters (e.g. {sup 18}F, {sup 11}C, {sup 124}I) while maintaining their biological properties, and are administered intravenously in tracer amounts (10{sup -9}-10{sup -12} M quantities). The recent physical integration of PET and computed tomography (CT) in hybrid PET/CT scanners allows a combined anatomical and functional imaging: nowadays PET molecular imaging is emerging as powerful pharmacological tool in oncology, neurology and for treatment planning as guidance for radiation therapy. The in vivo pharmacokinetics of boron carrier for BNCT and the quantification of {sup 10}B in living tissue were performed by PET in the late nineties using compartmental models based on PET data. Nowadays PET and PET/CT have been used to address the issue of pharmacokinetic, metabolism and accumulation of BPA in target tissue. The added value of the use of L-[{sup 18}F]FBPA and PET/CT in BNCT is to provide key data on the tumour extraction of {sup 10}B-BPA versus normal tissue and to predict the efficacy of the treatment based on a single-study patient analysis. Due to the complexity of a binary treatment like BNCT, the role of PET/CT is currently to design new criteria for patient enrolment in treatment protocols: the L-[{sup 18}F]BPA/PET methodology could be considered as an important tool in newly designed clinical trials to better estimate the concentration ratio of BPA in the tumour as compared to neighbouring normal tissues. Based on these values for individual patients the decision could be made whether BNCT treatment could be advantageous due to a selective accumulation of BPA in an individual tumour. This approach, applicable in different tumour entities like melanoma, glioblastoma and head and neck malignancies, make this methodology as reliable

  9. Monte Carlo optimisation of a BNCT facility for treating brain gliomas at the TAPIRO reactor.

    Science.gov (United States)

    Nava, E; Burn, K W; Casalini, L; Petrovich, C; Rosi, G; Sarotto, M; Tinti, R

    2005-01-01

    An epithermal boron neutron capture therapy facility for treating brain gliomas is currently under construction at the 5 kW fast-flux reactor TAPIRO located at ENEA, Casaccia, near Rome. In this work, the sensitivity of the results to the boron concentrations in healthy tissue and tumour is investigated and the change in beam quality on modifying the moderator thickness (within design limits) is studied. The Monte Carlo codes MCNP and MCNPX were used together with the DSA in-house variance reduction patch. Both usual free beam parameters and the in-phantom treatment planning figures-of-merit have been calculated in a realistic anthropomorphic phantom ('ADAM').

  10. A feasibility study of the Tehran research reactor as a neutron source for BNCT.

    Science.gov (United States)

    Kasesaz, Yaser; Khalafi, Hossein; Rahmani, Faezeh; Ezati, Arsalan; Keyvani, Mehdi; Hossnirokh, Ashkan; Shamami, Mehrdad Azizi; Monshizadeh, Mahdi

    2014-08-01

    Investigation on the use of the Tehran Research Reactor (TRR) as a neutron source for Boron Neutron Capture Therapy (BNCT) has been performed by calculating and measuring energy spectrum and the spatial distribution of neutrons in all external irradiation facilities, including six beam tubes, thermal column, and the medical room. Activation methods with multiple foils and a copper wire have been used for the mentioned measurements. The results show that (1) the small diameter and long length beam tubes cannot provide sufficient neutron flux for BNCT; (2) in order to use the medical room, the TRR core should be placed in the open pool position, in this situation the distance between the core and patient position is about 400 cm, so neutron flux cannot be sufficient for BNCT; and (3) the best facility which can be adapted for BNCT application is the thermal column, if all graphite blocks can be removed. The epithermal and fast neutron flux at the beginning of this empty column are 4.12×10(9) and 1.21×10(9) n/cm(2)/s, respectively, which can provide an appropriate neutron beam for BNCT by designing and constructing a proper Beam Shaping Assembly (BSA) structure.

  11. A toolkit for epithermal neutron beam characterisation in BNCT.

    Science.gov (United States)

    Auterinen, Iiro; Serén, Tom; Uusi-Simola, Jouni; Kosunen, Antti; Savolainen, Sauli

    2004-01-01

    Methods for dosimetry of epithermal neutron beams used in boron neutron capture therapy (BNCT) have been developed and utilised within the Finnish BNCT project as well as within a European project for a code of practise for the dosimetry of BNCT. One outcome has been a travelling toolkit for BNCT dosimetry. It consists of activation detectors and ionisation chambers. The free-beam neutron spectrum is measured with a set of activation foils of different isotopes irradiated both in a Cd-capsule and without it. Neutron flux (thermal and epithermal) distribution in phantoms is measured using activation of Mn and Au foils, and Cu wire. Ionisation chamber (IC) measurements are performed both in-free-beam and in-phantom for determination of the neutron and gamma dose components. This toolkit has also been used at other BNCT facilities in Europe, the USA, Argentina and Japan.

  12. Advances in boron neutron capture therapy (BNCT) at kyoto university - From reactor-based BNCT to accelerator-based BNCT

    Science.gov (United States)

    Sakurai, Yoshinori; Tanaka, Hiroki; Takata, Takushi; Fujimoto, Nozomi; Suzuki, Minoru; Masunaga, Shinichiro; Kinashi, Yuko; Kondo, Natsuko; Narabayashi, Masaru; Nakagawa, Yosuke; Watanabe, Tsubasa; Ono, Koji; Maruhashi, Akira

    2015-07-01

    At the Kyoto University Research Reactor Institute (KURRI), a clinical study of boron neutron capture therapy (BNCT) using a neutron irradiation facility installed at the research nuclear reactor has been regularly performed since February 1990. As of November 2014, 510 clinical irradiations were carried out using the reactor-based system. The world's first accelerator-based neutron irradiation system for BNCT clinical irradiation was completed at this institute in early 2009, and the clinical trial using this system was started in 2012. A shift of BCNT from special particle therapy to a general one is now in progress. To promote and support this shift, improvements to the irradiation system, as well as its preparation, and improvements in the physical engineering and the medical physics processes, such as dosimetry systems and quality assurance programs, must be considered. The recent advances in BNCT at KURRI are reported here with a focus on physical engineering and medical physics topics.

  13. INEL BNCT Program: Volume 5, No. 9

    Energy Technology Data Exchange (ETDEWEB)

    Ackermann, A.L. (ed.)

    1991-01-01

    This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory's (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

  14. Shielding design of a treatment room for an accelerator-based epithermal neutron irradiation facility for BNCT.

    Science.gov (United States)

    Evans, J F; Blue, T E

    1996-11-01

    Protecting the facility personnel and the general public from radiation exposure is a primary safety concern of an accelerator-based epithermal neutron irradiation facility. This work makes an attempt at answering the questions "How much?" and "What kind?" of shielding will meet the occupational limits of such a facility. Shielding effectiveness is compared for ordinary and barytes concretes in combination with and without borated polyethylene. A calculational model was developed of a treatment room , patient "scatterer," and the epithermal neutron beam. The Monte Carlo code, MCNP, was used to compute the total effective dose equivalent rates at specific points of interest outside of the treatment room. A conservative occupational effective dose rate limit of 0.01 mSv h-1 was the guideline for this study. Conservative Monte Carlo calculations show that constructing the treatment room walls with 1.5 m of ordinary concrete, 1.2 m of barytes concrete, 1.0 m of ordinary concrete preceded by 10 cm of 5% boron-polyethylene, or 0.8 m of barytes concrete preceded by 10 cm of 5% boron-polyethylene will adequately protect facility personnel.

  15. Boron neutron capture therapy (BNCT) in Finland: technological and physical prospects after 20 years of experiences.

    Science.gov (United States)

    Savolainen, Sauli; Kortesniemi, Mika; Timonen, Marjut; Reijonen, Vappu; Kuusela, Linda; Uusi-Simola, Jouni; Salli, Eero; Koivunoro, Hanna; Seppälä, Tiina; Lönnroth, Nadja; Välimäki, Petteri; Hyvönen, Heini; Kotiluoto, Petri; Serén, Tom; Kuronen, Antti; Heikkinen, Sami; Kosunen, Antti; Auterinen, Iiro

    2013-05-01

    Boron Neutron Capture Therapy (BNCT) is a binary radiotherapy method developed to treat patients with certain malignant tumours. To date, over 300 treatments have been carried out at the Finnish BNCT facility in various on-going and past clinical trials. In this technical review, we discuss our research work in the field of medical physics to form the groundwork for the Finnish BNCT patient treatments, as well as the possibilities to further develop and optimize the method in the future. Accordingly, the following aspects are described: neutron sources, beam dosimetry, treatment planning, boron imaging and determination, and finally the possibilities to detect the efficacy and effects of BNCT on patients.

  16. BNCT-RTPE: BNCT radiation treatment planning environment

    Energy Technology Data Exchange (ETDEWEB)

    Wessol, D.E.; Wheeler, F.J. [Idaho National Engineering Lab., Idaho Fall, ID (United States); Babcock, R.S. [and others

    1995-11-01

    Several improvements have been developed for the BNCT radiation treatment planning environment (BNCT-Rtpe) during 1994. These improvements have been incorporated into Version 1.0 of BNCT-Rtpe which is currently installed at the INEL, BNL, Japanese Research Center (JRC), and Finland`s Technical Research Center. Platforms supported by this software include Hewlett-Packard (HP), SUN, International Business Machines (IBM), and Silicon Graphics Incorporated (SGI). A draft version of the BNCT-Rtpe user manual is available. Version 1.1 of BNCT-Rtpe is scheduled for release in March 1995. It is anticipated that Version 2.x of BNCT-Rtpe, which includes the nonproprietary NURBS library and data structures, will be released in September 1995.

  17. Employment of MCNP in the study of TLDS 600 and 700 seeking the implementation of radiation beam characterization of BNCT facility at IEA-R1; Emprego do MCNP no estudo dos TLDS 600 e 700 visando a implementacao da caracterizacao do feixe de irradiacao da instalacao de BNCT do IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Cavalieri, Tassio Antonio

    2013-07-01

    Boron Neutron Capture Therapy, BNCT, is a bimodal radiotherapy procedure for cancer treatment. Its useful energy comes from a nuclear reaction driven by impinging thermal neutron upon Boron 10 atoms. A BNCT research facility has been constructed in IPEN at the IEA-R1 reactor, to develop studies in this area. One of its prime experimental parameter is the beam dosimetry which is nowadays made by using activation foils, for neutron measurements, and TLD 400, for gamma dosimetry. For mixed field dosimetry, the International Commission on Radiation Units and Measurements, ICRU, recommends the use of pair of detectors with distinct responses to the field components. The TLD 600/ TLD 700 pair meets this criteria, as the amount of {sup 6}Li, a nuclide with high thermal neutron cross section, greatly differs in their composition. This work presents a series of experiments and simulations performed in order to implement the mixed field dosimetry based on the use of TLD 600/TLD 700 pair. It also intended to compare this mixed field dosimetric methodology to the one so far used by the BNCT research group of IPEN. The response of all TLDs were studied under irradiations in different irradiation fields and simulations, underwent by MCNP, were run in order to evaluate the dose contribution from each field component. Series of repeated irradiations under pure gamma field and mixed field neutron/gamma field showed differences in the TLD individual responses which led to the adoption of a Normalization Factor. It has allowed to overcome TLD selection. TLD responses due to different field components and spectra were studied. It has shown to be possible to evaluate the relative gamma/neutron fluxes from the relative responses observed in the two Regions of Interest, ROIs, from TLD 600 and TLD 700. It has also been possible to observe the TLD 700 response to neutron, which leads to a gamma dose overestimation when one follows the ICRU recommended mixed field dosimetric procedure. Dose

  18. Experimental Studies of Boronophenylalanine ({sup 10}BPA) Biodistribution for the Individual Application of Boron Neutron Capture Therapy (BNCT) for Malignant Melanoma Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Carpano, Marina; Perona, Marina; Rodriguez, Carla [Department of Radiobiology, National Atomic Energy Commission, San Martín (Argentina); Nievas, Susana; Olivera, Maria; Santa Cruz, Gustavo A. [Department of Boron Neutron Capture Therapy, National Atomic Energy Commission, San Martín (Argentina); Brandizzi, Daniel; Cabrini, Romulo [Department of Radiobiology, National Atomic Energy Commission, San Martín (Argentina); School of Dentistry, University of Buenos Aires, Buenos Aires (Argentina); Pisarev, Mario [Department of Radiobiology, National Atomic Energy Commission, San Martín (Argentina); National Research Council of Argentina, Buenos Aires (Argentina); Department of Human Biochemistry, School of Medicine, University of Buenos Aires, Buenos Aires (Argentina); Juvenal, Guillermo Juan [Department of Radiobiology, National Atomic Energy Commission, San Martín (Argentina); National Research Council of Argentina, Buenos Aires (Argentina); Dagrosa, Maria Alejandra, E-mail: dagrosa@cnea.gov.ar [Department of Radiobiology, National Atomic Energy Commission, San Martín (Argentina); National Research Council of Argentina, Buenos Aires (Argentina)

    2015-10-01

    Purpose: Patients with the same histopathologic diagnosis of cutaneous melanoma treated with identical protocols of boron neutron capture therapy (BNCT) have shown different clinical outcomes. The objective of the present studies was to evaluate the biodistribution of boronophenilalanina ({sup 10}BPA) for the potential application of BNCT for the treatment of melanoma on an individual basis. Methods and Materials: The boronophenilalanine (BPA) uptake was evaluated in 3 human melanoma cell lines: MEL-J, A375, and M8. NIH nude mice were implanted with 4 10{sup 6} MEL-J cells, and biodistribution studies of BPA (350 mg/kg intraperitoneally) were performed. Static infrared imaging using a specially modified infrared camera adapted to measure the body infrared radiance of small animals was used. Proliferation marker, Ki-67, and endothelial marker, CD31, were analyzed in tumor samples. Results: The in vitro studies demonstrated different patterns of BPA uptake for each analyzed cell line (P<.001 for MEL-J and A375 vs M8 cells). The in vivo studies showed a maximum average boron concentration of 25.9 ± 2.6 μg/g in tumor, with individual values ranging between 11.7 and 52.0 μg/g of {sup 10}B 2 hours after the injection of BPA. Tumor temperature always decreased as the tumors increased in size, with values ranging between 37°C and 23°C. A significant correlation between tumor temperature and tumor-to-blood boron concentration ratio was found (R{sup 2} = 0.7, rational function fit). The immunohistochemical studies revealed, in tumors with extensive areas of viability, a high number of positive cells for Ki-67, blood vessels of large diameter evidenced by the marker CD31, and a direct logistic correlation between proliferative status and boron concentration difference between tumor and blood (R{sup 2} = 0.81, logistic function fit). Conclusion: We propose that these methods could be suitable for designing new screening protocols applied before melanoma BNCT

  19. Measurement of the 33S(n,α) cross-section at n_TOF(CERN): Applications to BNCT

    Science.gov (United States)

    Sabaté-Gilarte, Marta; Praena, Javier; Porras, Ignacio; Quesada, José Manuel; Mastinu, Pierfrancesco

    2016-01-01

    Aim The main purpose of this work is to present a new (n,α) cross-section measurement for a stable isotope of sulfur, 33S, in order to solve existing discrepancies. Background 33S has been studied as a cooperating target for Boron Neutron Capture Therapy (BNCT) because of its large (n,α) cross-section in the epithermal neutron energy range, the most suitable one for BNCT. Although the most important evaluated databases, such as ENDF, do not show any resonances in the cross-section, experimental measurements which provided data from 10 keV to 1 MeV showed that the lowest-lying and strongest resonance of 33S(n,α) cross-section occurs at 13.5 keV. Nevertheless, the set of resonance parameters that describe such resonance shows important discrepancies (more than a factor of 2) between them. Materials and methods A new measurement of the 33S(n,α)30Si reaction cross-section was proposed to the ISOLDE and Neutron Time-of-Flight Experiments Committee of CERN. It was performed at n_TOF(CERN) in 2012 using MicroMegas detectors. Results In this work, we will present a brief overview of the experiment as well as preliminary results of the data analysis in the neutron energy range from thermal to 100 keV. These results will be taken into account to calculate the kerma-fluence factors corresponding to 33S in addition to 10B and those of a standard four-component ICRU tissue. Conclusions MCNP simulations of the deposited dose, including our experimental data, shows an important kerma rate enhancement at the surface of the tissue, mainly due to the presence of 33S. PMID:26933393

  20. INEL BNCT Program: Volume 5, No. 9. Bulletin, September 1991

    Energy Technology Data Exchange (ETDEWEB)

    Ackermann, A.L. [ed.

    1991-12-31

    This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory`s (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

  1. Clinical Requirements and Accelerator Concepts for BNCT

    Science.gov (United States)

    Ludewigt, Bernhard A.

    1997-05-01

    Accelerator-driven epithermal neutron sources are an attractive alternative to nuclear reactors for Boron Neutron Capture Therapy (BNCT). In BNCT the goal of delivering a sufficient dose to the tumor without exceeding the dose limits of the surrounding normal tissues is achieved by administering a ^10B-containing compound which is selectively taken up in the tumor cells. Subsequent irradiation with epithermal neutrons leads to the release of short ranged (neutron-capture reaction. By carefully shaping the neutron spectrum the background dose, partially due to recoil protons and external gamma radiation, can be minimized and the depth dose distribution optimized. Excellent epithermal neutron beams for BNCT can be produced by bombarding a Li-target with a high current proton beam at energies ranging from the (p,n) reaction threshold to 2.5 MeV and subsequent moderation and filtering of the primary neutrons. In comparison the use of Be-targets and higher proton or deuteron energies, up to 20 MeV, leads to higher neutron yields but also to higher primary neutron energies requiring more moderation and resulting in less desirable neutron spectra. Accelerator options for possible neutron sources include dc-accelerators, RFQs, LINACs and cyclotrons. An electrostatic quadrupole (ESQ) accelerator has been chosen to provide a 2.5 MeV proton beam for the BNCT facility currently being designed at LBNL. An ESQ-accelerator is ideally suited to provide the high beam currents which are desired for producing high quality neutron beams for BNCT treatments. A novel power supply based on the air-coupled transformer concept is under development. It will enable the accelerator to deliver proton beam currents up to about 50 mA. A Li-target has been designed which can handle beam power in excess of 50 kW establishing the practicability of this approach. Monte Carlo simulation studies have shown that at a proton beam current of 20 mA high quality treatments for brain tumors can be delivered

  2. Boron concentration measurement system for the Czech BNCT project

    Science.gov (United States)

    Honzátko, J.; Tomandl, I.

    2000-07-01

    In the framework of the Czech Boron Neutron Capture Therapy (BNCT) project a Prompt Gamma Ray Analysis (PGRA) facility for the determination of the boron concentration in biological samples was built at light-water reactor at Řež. The facility utilizes the beam of thermal neutrons from a neutron guide. The pure beam of thermal neutrons and background conditions enables the determination of 1 ppm with the reasonable statistical error 5% within 15 minutes.

  3. INEEL BNCT Research Program Annual Report, CY-2000

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, James Robert

    2001-03-01

    This report is a summary of the activities conducted in conjunction with the Idaho National Engineering and Environmental Laboratory (INEEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 2000. Applications of supportive research and development, as well as technology deployment in the fields of chemistry, radiation physics and dosimetry, neutron source design and demonstration, and support the Department of Energy’s (DOE) National BNCT Program goals are the goals of this Program. Contributions from the individual contributors about their projects are included, specifically described are the following, chemistry: analysis of biological samples and an infrared blood-boron analyzer, and physics: progress in the patient treatment planning software, measurement of neutron spectra for the Argentina RA-6 reactor, and recalculation of the Finnish research reactor FiR 1 neutron spectra, BNCT accelerator technology, and modification to the research reactor at Washington State University for an epithermal-neutron beam.

  4. Preliminary modeling of BNCT beam tube on IRT in Sofia.

    Science.gov (United States)

    Belousov, S; Ilieva, K

    2009-07-01

    The technical design of the research reactor IRT in Sofia is in progress. It includes an arrangement for a BNCT facility for tumor treatment. Modeling of geometry and material composition of filter/collimator for the BNCT beam tube on IRT has been carried out following the beam tube configuration of the Massachusetts Institute of Technology Reactor [Harling et al., 2002. The fission converter-based epithermal neutron irradiation facility at the Massachusetts Institute of Technology Reactor. Nucl. Sci. Eng. 140, 223-240.] and taking into account an ability to include the tube into the IRT reactor geometry. The results of neutron and gamma transport calculations performed for the model have shown that the facility will be able to supply an epithermal neutron flux of about 5 x 10(9) n cm(-2)s(-1), with low contamination from fast neutrons and gamma rays that would be among the best facilities currently available. An optimiziation study has been performed for the beam collimator, following similar studies for the TAPIRO research reactor in Italy. [Nava et al., 2005. Monte Carlo optimization of a BNCT facility for treating brain gliomas at the TAPIRO reactor. Radiat. Prot. Dosim. 116 (1-4), 475-481.].

  5. INEL BNCT research program: Annual report, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R. [ed.

    1996-04-01

    This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1995. Contributions from the principal investigators about their individual projects are included, specifically, physics (treatment planning software, real-time neutron beam measurement dosimetry), and radiation biology (large animal models efficacy studies). Design of a reactor based epithermal neutron extraction facility is discussed in detail. Final results of boron magnetic resonance imagining is included for both borocaptate sodium (BSH) and boronophenylalanine (BPA) in rats, and BSH in humans. Design of an epithermal neutron facility using electron linear accelerators is presented, including a treatise on energy removal from the beam target. Information on the multiple fraction injection of BSH in rats is presented.

  6. Irradiation facility for boron neutron capture therapy application based on a rf-driven D-T neutron source and a new beam shaping assembly (abstract)

    Science.gov (United States)

    Cerullo, N.; Esposito, J.; Leung, K. N.

    2002-02-01

    Selecting the best neutron source for boron neutron capture therapy (BNCT) requires optimizing neutron beam parameters. This involves solving many complex problems. Safety issues related to the use of nuclear reactor in hospital environments, as well as lower costs have led to interest in the development of accelerator-driven neutron sources. The BNCT research programs at the Nuclear Departments of Pisa and Genova Universities (DIMNP and DITEC) focus on studies of new concepts for accelerator-based DT neutron sources. Simple and compact accelerator designs using relatively low deuteron beam energy, ˜100 keV, have been developed which, in turn, can generate high neutron yields. New studies have been started for optimization of moderator materials for the 14.1 MeV DT neutrons. Our aim is to obtain an epithermal neutron beam for therapeutic application at the exit end, with minimal beam intensity losses, the specific goal is to achieve an epithermal neutron flux of at least of 1×109 n/cm2 s at the beam port, with low gamma and fast neutron dose contamination. According to the most recent neutron BNCT beam parameters some moderating and spectrum shifter materials and geometrical configurations have thus far been tested, and neutron and gamma beam data at beam port have been computed. A possible beam shaping assembly model has been designed. This research demonstrates that a DT neutron source could be successfully implemented for BNCT application, with performance surpassing the minimum requirements stated above, using DT neutron sources with yields in the range 1013-1014 n/s. The latest Monte Carlo simulation results of an accelerator based facility which relies on a rf-driven DT fusion neutron generator will be presented.

  7. Spectrum shaping of accelerator-based neutron beams for BNCT

    CERN Document Server

    Montagnini, B; Esposito, J; Giusti, V; Mattioda, F; Varone, R

    2002-01-01

    We describe Monte Carlo simulations of three facilities for the production of epithermal neutrons for Boron Neutron Capture Therapy (BNCT) and examine general aspects and problems of designing the spectrum-shaping assemblies to be used with these neutron sources. The first facility is based on an accelerator-driven low-power subcritical reactor, operating as a neutron amplifier. The other two facilities have no amplifier and rely entirely on their primary sources, a D-T fusion reaction device and a conventional 2.5 MeV proton accelerator with a Li target, respectively.

  8. Exploration of Adiabatic Resonance Crossing Through Neutron Activator Design for Thermal and Epithermal Neutron Formation in (99)Mo Production and BNCT Applications.

    Science.gov (United States)

    Khorshidi, Abdollah

    2015-10-01

    A feasibility study was performed to design thermal and epithermal neutron sources for radioisotope production and boron neutron capture therapy (BNCT) by moderating fast neutrons. The neutrons were emitted from the reaction between (9)Be, (181)Ta, and (184)W targets and 30 MeV protons accelerated by a small cyclotron at 300 μA. In this study, the adiabatic resonance crossing (ARC) method was investigated by means of (207)Pb and (208)Pb moderators, graphite reflector, and boron absorber around the moderator region. Thermal/epithermal flux, energy, and cross section of accumulated neutrons in the activator were examined through diverse thicknesses of the specified regions. Simulation results revealed that the (181)Ta target had the highest neutron yield, and also tungsten was found to have the highest values in both surface and volumetric flux ratio. Transmutation in the (98)Mo sample through radiative capture was investigated for the natural lead moderator. When the sample radial distance from the target was increased inside the graphite region, the production yield had the greatest value of activity. The potential of the ARC method is a replacement or complements the current reactor-based supply sources of BNCT purposes.

  9. Bnct

    Science.gov (United States)

    Rossi, F.; Ono, K.; Suzuki, M.; Tanaka, H.; Morigi, M. P.

    The purpose of this work is to analyze dose distribution inside tissues. To do this, we performed some MCNP simulations using the neutron flux obtained from the Kyoto University Reactor. We have tried to analyze the behavior of neutrons in different types of tissues in relation to their depth. We have found that the value of dose from neutron interaction with 10B depends not only on 10B concentration inside the tissues (a higher concentration produces a higher dose), but also on the tissue density. In fact, tissues with a density considerably different from that of water receive a lower dose. Another dose contribution is given by the presence of 14N inside tissues: this dose contribution is lower compared with the previous one; it is influenced both by the tissue density and the percentage of nitrogen inside the tissue. Finally, the delivered dose decreases very quickly after a depth of about 4 cm, which implies that boron neutron capture therapy is not an effective therapy for the deepest tumors. However, there are some factors that can be taken into account to reach the deepest zone.

  10. Treatment planning capability assessment of a beam shaping assembly for accelerator-based BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Herrera, M.S., E-mail: herrera@tandar.cnea.gov.ar [Comision Nacional de Energia Atomica, CNEA, Av. Gral. Paz 1499, San Martin (Argentina)] [Consejo Nacional de Investigaciones Cientificas y Tecnicas, CONICET, Av. Rivadavia 191, Buenos Aires (Argentina)] [Universidad Nacional de San Martin, UNSAM, Av. 25 de Mayo y Francia Buenos Aires (Argentina); Gonzalez, S.J. [Comision Nacional de Energia Atomica, CNEA, Av. Gral. Paz 1499, San Martin (Argentina)] [Consejo Nacional de Investigaciones Cientificas y Tecnicas, CONICET, Av. Rivadavia 191, Buenos Aires (Argentina); Burlon, A.A. [Comision Nacional de Energia Atomica, CNEA, Av. Gral. Paz 1499, San Martin (Argentina)] [Universidad Nacional de San Martin, UNSAM, Av. 25 de Mayo y Francia Buenos Aires (Argentina); Minsky, D.M.; Kreiner, A.J. [Comision Nacional de Energia Atomica, CNEA, Av. Gral. Paz 1499, San Martin (Argentina)] [Consejo Nacional de Investigaciones Cientificas y Tecnicas, CONICET, Av. Rivadavia 191, Buenos Aires (Argentina)] [Universidad Nacional de San Martin, UNSAM, Av. 25 de Mayo y Francia Buenos Aires (Argentina)

    2011-12-15

    Within the frame of an ongoing project to develop a folded Tandem-Electrostatic-Quadrupole accelerator facility for Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT) a theoretical study was performed to assess the treatment planning capability of different configurations of an optimized beam shaping assembly for such a facility. In particular this study aims at evaluating treatment plans for a clinical case of Glioblastoma.

  11. The Boron Neutron Capture Therapy (BNCT) Project at the TRIGA Reactor in Mainz, Germany

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, G.; Grunewald, C.; Schutz, C.; Schmitz, T.; Kratz, J.V. [Nuclear Chemistry, University of Mainz, D-55099 Mainz (Germany); Brochhausen, C.; Kirkpatrick, J. [Department of Pathology, University of Mainz, D-55099 Mainz (Germany); Bortulussi, S.; Altieri, S. [Department of Nuclear and Theoretical Physics University of Pavia, Pavia (Italy); National Institute of Nuclear Physics (INFN) Pavia Section, Pavia (Italy); Kudejova, P. [Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universitaet Muenchen, D-85748 Garching (Germany); Appelman, K.; Moss, R. [Joint Research Centre (JRC) of the European Commission, NL-1755 ZG Petten (Netherlands); Bassler, N. [University of Aarhus, Norde Ringade, DK-8000, Aarhus C (Denmark); Blaickner, M.; Ziegner, M. [Molecular Medicine, Health and Environment Department, AIT Austrian Institute of Technology GmbH (Austria); Sharpe, P.; Palmans, H. [National Physical Laboratory, Teddington TW11 0LW, Middlesex (United Kingdom); Otto, G. [Department of Hepatobiliary, Pancreatic and Transplantation Surgery, University of Mainz, D-55099 Mainz (Germany)

    2011-07-01

    The thermal column of the TRIGA reactor in Mainz is being used very effectively for medical and biological applications. The BNCT (boron neutron capture therapy) project at the University of Mainz is focussed on the treatment of liver tumours, similar to the work performed in Pavia (Italy) a few years ago, where patients with liver metastases were treated by combining BNCT with auto-transplantation of the organ. Here, in Mainz, a preclinical trial has been started on patients suffering from liver metastases of colorectal carcinoma. In vitro experiments and the first animal tests have also been initiated to investigate radiobiological effects of radiation generated during BNCT. For both experiments and the treatment, a reliable dosimetry system is necessary. From work elsewhere, the use of alanine detectors appears to be an appropriate dosimetry technique. (author)

  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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-09-18

    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.

  14. BNCT dosimetry performed with a mini twin tissue-equivalent proportional counters (TEPC).

    Science.gov (United States)

    Moro, D; Colautti, P; Lollo, M; Esposito, J; Conte, V; De Nardo, L; Ferretti, A; Ceballos, C

    2009-07-01

    The BNCT radiation field is complex because different beam components are mixed, each one having different relative biological effectiveness (RBE). Microdosimetry with tissue-equivalent proportional counters (TEPC) has proven to be an ideal dosimetric technique for mixed radiation fields, because it is able both to measure the absorbed dose and to assess the radiation field relative biological effectiveness with good accuracy. An ideal detector for BNCT should contain two TEPCs, one detector loaded with, while the other one without (10)B in order to record all beam components with a unique measurement. Moreover, such a detector should be of tiny size in order to be able to measure in the intense BNCT radiation fields without significant pile-up effects. TEPCs have been shown to be pretty good dosimeters for mixed radiation fields. In this paper the first mini twin TEPC counter for BNCT is presented, as well as first measurement at the new HYTHOR thermal irradiation facility at TAPIRO nuclear reactor and comparison with related Monte Carlo calculations.

  15. The Boron Neutron Capture Therapy (BNCT) Project at the TRIGA Reactor in Mainz, Germany

    DEFF Research Database (Denmark)

    Hampel, G.; Grunewald, C.; Schütz, C.

    2011-01-01

    The thermal column of the TRIGA reactor in Mainz is being used very effectively for medical and biological applications. The BNCT (boron neutron capture therapy) project at the University of Mainz is focussed on the treatment of liver tumours, similar to the work performed at Pavia (Italy) a few...

  16. Progress on the accelerator based SPES-BNCT project at INFN Legnaro

    Science.gov (United States)

    Esposito, J.; Colautti, P.; Pisent, A.; De Nardo, L.; Conte, V.; Moro, D.; Agosteo, S.; Jori, G.; Tinti, R.; Rosi, G.

    2007-02-01

    In the framework of an advanced Exotic Ion Beam facility, named SPES (Study and Production of Exotic Species), that will allow a frontier program both in nuclear and interdisciplinary physics, an intense thermal neutron beam facility, devoted to perform Boron Neutron Capture Therapy (BNCT) experimental treatments on skin melanoma tumor, is currently under construction based on the SPES proton driver. A vast radiobiological investigation in vitro and in vivo has started with the new 10B carriers developed. Special microdosimetric detectors have been constructed to properly measure all the BNCT dose components and their qualities. Both microdosimetric and radiobiological measurements are being performed at the new HYTHOR beam shaping assembly at the Enea-Casaccia TAPIRO reactor.

  17. Design of epithermal neutron beam for clinical BNCT treatment at Slovenian TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Maucec, Marko [Jozef Stefan Institute, Reactor Physics Division, Lubljana (Slovenia). E-mail: marko.mauce@ijs.si

    1999-07-01

    The Monte Carlo feasibility study of development of epithermal neutron beam for BNCT clinical trials on Jozef Stefan Institute (JSI) TRIGA reactor is presented. The investigation of the possible use of fission converter for the purpose of enhancement of neutron beam, as well as the set-up of TRIGA reactor core is performed. The optimization of the irradiation facility components is carried out and the configuration with the most favorable cost/performance ratio is proposed. The simulation results prove that a BNCT irradiation facility with performances, comparable to existing beams throughout the world, could be installed in the thermalizing column of the TRIGA reactor, quite suitable for the clinical treatments of human patients. (author)

  18. Evaluation of BPA uptake in clear cell sarcoma (CCS) in vitro and development of an in vivo model of CCS for BNCT studies

    Energy Technology Data Exchange (ETDEWEB)

    Fujimoto, T., E-mail: fujitaku@hp.pref.hyogo.jp [Department of Orthopaedic Surgery, Hyogo Cancer Center, Akashi 673-0021 (Japan); Andoh, T. [Faculty of Pharmaceutical Sciences and Cooperative Research Center of Life Sciences, Kobe Gakuin University, Kobe 650-8586 (Japan); Sudo, T. [Section of Translational Research, Hyogo Cancer Center, Akashi 673-0021 (Japan); Fujita, I.; Imabori, M. [Department of Orthopaedic Surgery, Hyogo Cancer Center, Akashi 673-0021 (Japan); Moritake, H. [Division of Pediatrics, University of Miyazaki, Miyazaki 889-1692 (Japan); Sugimoto, T. [Department of Pediatrics, Saiseikai Shigaken Hospital, Ritto 520-3046 (Japan); Sakuma, Y. [Department of Pathology, Hyogo Cancer Center, Akashi 673-0021 (Japan); Takeuchi, T. [Department of Pathology, Kochi Medical School, Nangoku 783-8505 (Japan); Sonobe, H. [Department of Pathology, Chugoku Central Hospital, Fukuyama 720-0001 (Japan); Epstein, Alan L. [Department of Pathology, Keck School of Medicine,University of Southern California, Los Angeles,CA 90033 (United States); Akisue, T. [Department of Orthopaedic Surgery, Kobe University Graduate School of Medicine, Kobe 650-0017 (Japan); Kirihata, M. [Graduate School of Life and Environmental Sciences, Osaka Prefecture University, Sakai 599-8531 (Japan); Kurosaka, M. [Department of Orthopaedic Surgery, Kobe University Graduate School of Medicine, Kobe 650-0017 (Japan); Fukumori, Y.; Ichikawa, H. [Faculty of Pharmaceutical Sciences and Cooperative Research Center of Life Sciences, Kobe Gakuin University, Kobe 650-8586 (Japan)

    2011-12-15

    Clear cell sarcoma (CCS), a rare malignant tumor with a predilection for young adults, is of poor prognosis. Recently however, boron neutron capture therapy (BNCT) with the use of p-borono-L-phenylalanine (BPA) for malignant melanoma has provided good results. CCS also produces melanin; therefore, the uptake of BPA is the key to the application of BNCT to CCS. We describe, for the first time, the high accumulation of boron in CCS and the CCS tumor-bearing animal model generated for BNCT studies.

  19. A D-D/D-T fusion reaction based neutron generator system for liver tumor BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Koivunoro, H.; Lou, T.P.; Leung, K. N.; Reijonen, J.

    2003-04-02

    Boron-neutron capture therapy (BNCT) is an experimental radiation treatment modality used for highly malignant tumor treatments. Prior to irradiation with low energetic neutrons, a 10B compound is located selectively in the tumor cells. The effect of the treatment is based on the high LET radiation released in the {sup 10}B(n,{alpha}){sup 7}Li reaction with thermal neutrons. BNCT has been used experimentally for brain tumor and melanoma treatments. Lately applications of other severe tumor type treatments have been introduced. Results have shown that liver tumors can also be treated by BNCT. At Lawrence Berkeley National Laboratory, various compact neutron generators based on D-D or D-T fusion reactions are being developed. The earlier theoretical studies of the D-D or D-T fusion reaction based neutron generators have shown that the optimal moderator and reflector configuration for brain tumor BNCT can be created. In this work, the applicability of 2.5 MeV neutrons for liver tumor BNCT application was studied. The optimal neutron energy for external liver treatments is not known. Neutron beams of different energies (1eV < E < 100 keV) were simulated and the dose distribution in the liver was calculated with the MCNP simulation code. In order to obtain the optimal neutron energy spectrum with the D-D neutrons, various moderator designs were performed using MCNP simulations. In this article the neutron spectrum and the optimized beam shaping assembly for liver tumor treatments is presented.

  20. Multiphysics Analysis of the 2.5 MeV BNCT RFQ Accelerator

    CERN Document Server

    Xiaowen, Zhu; Kun, Zhu

    2016-01-01

    Boron Neutron Capture Therapy (BNCT), is an advanced cancer therapy that destroys the cancer tumors using the well-known Li(p,n)Be . Because of the highly selectively reaction between a boron and a neutron, BNCT is effective for rapidly spreading cancer, invasive carcinoma, such as head and neck cancer, melanoma, malignant brain tumors and so on. The PKU RFQ group proposes an RFQ based neutron source for BNCT application. The 162.5 MHz four-vane RFQ will accelerate 20-mA H+ from 35.0 keV to 2.50 MeV in CW mode, and delivers a neutron yield of 1.73*10^13 n/sec/cm^2. The thermal management will become the most important issues. The detailed multiphysics analysis of the BNCT RFQ will be studied, and the RFQ frequency shift during nominal operating condition is also predicted. The multiphysics analysis is performed by using the CST Multiphysics Model and verified with ANSYS Multiphysics.

  1. Power Burst Facility/Boron Neutron Capture Therapy Program for cancer treatment

    Energy Technology Data Exchange (ETDEWEB)

    Ackermann, A.L. (ed.); Dorn, R.V. III.

    1990-08-01

    This report discusses monthly progress in the Power Boron Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program for Cancer Treatment. Highlights of the PBF/BNCT Program during August 1990 include progress within the areas of: Gross Boron Analysis in Tissue, Blood, and Urine, boron microscopic (subcellular) analytical development, noninvasive boron quantitative determination, analytical radiation transport and interaction modeling for BNCT, large animal model studies, neutron source and facility preparation, administration and common support and PBF operations.

  2. Preliminary evaluations of the undesirable patient dose from a BNCT treatment at the ENEA-TAPIRO reactor.

    Science.gov (United States)

    Ferrari, P; Gualdrini, G; Nava, E; Burn, K W

    2007-01-01

    Boron neutron capture therapy (BNCT) is an experimental technique for the treatment of certain kinds of tumors. Research in BNCT is performed utilizing both thermal and epithermal neutron beams. Epithermal neutrons (0.4 eV-10 keV) penetrate more deeply into tissue and are thus used in non-superficial clinical applications such as the brain glioma. In the last few years, the fast reactor TAPIRO (ENEA-Casaccia Rome) has been employed as a neutron source for research into BNCT applications. Recently, an 'epithermal therapeutic column' has been designed and its construction has been completed. The Monte Carlo code MCNPX was employed to optimize the design of the column and to evaluate the dose profiles and the therapeutic parameters in the cranium of the anthropomorphic phantom ADAM. In the same context, some preliminary evaluations of the undesirable doses to the patient were performed with MCNPX. A hermaphrodite phantom derived from ADAM and EVA was employed to evaluate the energy deposition in some organs during a standard BNCT treatment. The total dose consists of the contributions from the primary neutron beam, the neutron interactions with boron and the neutron induced photons generated in the epithermal column structures and in the patient's tissues. The paper summarizes the computational procedure and provides a general dosimetric framework of the patient radiological protection aspects related to a BNCT treatment scenario at the TAPIRO reactor.

  3. An Accelerator Neutron Source for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Blue, Thomas, E

    2006-03-14

    The overall goal of this project was to develop an accelerator-based neutron source (ABNS) for Boron Neutron Capture Therapy (BNCT). Specifically, our goals were to design, and confirm by measurement, a target assembly and a moderator assembly that would fulfill the design requirements of the ABNS. These design requirements were 1) that the neutron field quality be as good as the neutron field quality for the reactor-based neutron sources for BNCT, 2) that the patient treatment time be reasonable, 3) that the proton current required to treat patients in reasonable times be technologially achievable at reasonable cost with good reliability, and accelerator space requirements which can be met in a hospital, and finally 4) that the treatment be safe for the patients.

  4. INEL BNCT Research Program annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R. [ed.

    1995-11-01

    This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1994. Contributions from the principal investigators about their individual projects are included, specifically, chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, ICP-AES analysis of biological samples), physics (treatment planning software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (small and large animal models tissue studies and efficacy studies). Information on the potential toxicity of BSH and BPA is presented and results of 21 spontaneous tumor bearing dogs that have been treated with BNCT at Brookhaven National Laboratory (BNL) are discussed. Several boron carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Highlights from the First International Workshop on Accelerator-Based Neutron Sources for BNCT are included. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  5. High-Explosives Applications Facility (HEAF)

    Science.gov (United States)

    Morse, J. L.; Weingart, R. C.

    1989-03-01

    This Safety Analysis Report (SAR) reviews the safety and environmental aspects of the High Explosives Applications Facility (HEAF). Topics covered include the site selected for the HEAF, safety design criteria, operations planned within the facility, and the safety and environmental analyses performed on this project to date. Provided in the Summary section is a review of hazards and the analyses, conclusions, and operating limits developed in this SAR. Appendices provide supporting documents relating to this SAR. This SAR is required by the LLNL Health and Safety Manual and DOE Order 5481.1B(2) to document the safety analysis efforts. The SAR was assembled by the Hazards Control Department, B-Division, and HEAF project personnel. This document was reviewed by B Division, the Chemistry Department, the Hazards Control Department, the Laboratory Associate Director for Administration and Operations, and the Associate Directors ultimately responsible for HEAF operations.

  6. Investigating a multi-purpose target for electron linac based photoneutron sources for BNCT of deep-seated tumors

    Energy Technology Data Exchange (ETDEWEB)

    Masoudi, S. Farhad, E-mail: masoudi@kntu.ac.ir; Rasouli, Fatemeh S.

    2015-08-01

    Recent studies in BNCT have focused on investigating appropriate neutron sources as alternatives for nuclear reactors. As the most prominent facilities, the electron linac based photoneutron sources benefit from two consecutive reactions, (e, γ) and (γ, n). The photoneutron sources designed so far are composed of bipartite targets which involve practical problems and are far from the objective of achieving an optimized neutron source. This simulation study deals with designing a compact, optimized, and geometrically simple target for a photoneutron source based on an electron linac. Based on a set of MCNPX simulations, tungsten is found to have the potential of utilizing as both photon converter and photoneutron target. Besides, it is shown that an optimized dimension for such a target slows-down the produced neutrons toward the desired energy range while keeping them economy, which makes achieving the recommended criteria for BNCT of deep-tumors more available. This multi-purpose target does not involve complicated designing, and can be considered as a significant step toward finding application of photoneutron sources for in-hospital treatments. In order to shape the neutron beam emitted from such a target, the beam is planned to pass through an optimized arrangement of materials composed of moderators, filters, reflector, and collimator. By assessment with the recommended in-air parameters, it is shown that the designed beam provides high intensity of desired neutrons, as well as low background contamination. The last section of this study is devoted to investigate the performance of the resultant beam in deep tissue. A typical simulated liver tumor, located within a phantom of human body, was subjected to the irradiation of the designed spectrum. The dosimetric results, including evaluated depth-dose curves and carried out in-phantom parameters show that the proposed configuration establishes acceptable agreement between the appropriate neutron intensity, and

  7. TIDBIT - the INEL database of BNCT information and treatment

    Energy Technology Data Exchange (ETDEWEB)

    Mancuso, C.A.

    1995-11-01

    The INEL Database of BNCT Information and Treatment (TIDBIT) has been under development for several years. Late in 1993, a new software development team took over the project and did and assessment of the current implementation status, and determined that the user interface was unsatisfactory for the expected users and that the data structures were out of step with the current state of reality. The team evaluated several tools that would improve the user interface to make the system easier to use. Uniface turned out to be the product of choice. During 1994, TIDBIT got its name, underwent a complete change of appearance, had a major overhaul to the data structures that support the application, and system documentation was begun. A prototype of the system was demonstrated in September 1994.

  8. Concept of a BNCT line with in-pool fission converter at MARIA reactor in Swierk

    Science.gov (United States)

    Pytel, Krzysztof; Andrzejewski, Krzysztof; Golnik, Natalia; Osko, Jakub

    2009-01-01

    BNCT facility in the Institute of Atomic Energy in Otwock-Swierk is under construction at the horizontal channel H2 of the research reactor MARIA. Measurements of the neutron energy spectrum performed at the front of the H2 experimental channel, have shown that flux of epithermal neutrons (above 10 keV) at the BNCT irradiation port was below 109 n cm-2 s-1 i.e. it was too low to be directly used for the BNCT treatment. Therefore, a fission converter will be placed between the reactor core and the periphery of the graphite reflector of MARIA reactor. The uranium converter will be powered by the densely packed EK-10 fuel elements with 10% enrichment. Preliminary calculations have shown that the total neutron flux in the converter will be about 1013 n cm-2 s-1 and flux of epithermal neutrons at the entrance to the filter/moderator of the beam will be about 2·1013 n cm-2 s-1.

  9. INEL BNCT Research Program annual report, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R. [ed.

    1993-05-01

    This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1992. Contributions from all the principal investigators about their individual projects are included, specifically, chemistry (pituitary tumor targeting compounds, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, inductively coupled plasma-atomic emission spectroscopy (ICP-AES) analysis of biological samples), physics (radiation dosimetry software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (small and large animal models tissue studies and efficacy studies). Information on the potential toxicity of borocaptate sodium and boronophenylalanine is presented, results of 21 spontaneous-tumor-bearing dogs that have been treated with BNCT at the Brookhaven National Laboratory (BNL) Medical Research Reactor (BMRR) are discussed, and predictions for an epithermal-neutron beam at the Georgia Tech Research Reactor (GTRR) are shown. Cellular-level boron detection and localization by secondary ion mass spectrometry, sputter-initiated resonance ionization spectroscopy, low atomization resonance ionization spectroscopy, and alpha track are presented. Boron detection by ICP-AES is discussed in detail. Several boron carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors with BNCT is presented. Measurement of the epithermal-neutron flux at BNL and comparison to predictions are shown. Calculations comparing the GTRR and BMRR epithermal-neutron beams are also presented. Individual progress reports described herein are separately abstracted and indexed for the database.

  10. Carborane-containing metalloporphyrins for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Miura, Michiko; Joel, D.D.; Nawrocky, M.M.; Micca, P.L. [and others

    1996-12-31

    For BNCT of malignant brain tumors, it is crucial that there be relatively high boron concentrations in tumor compared with normal tissues within the neutron-irradiated treatment volume. Fairchild and Bond estimated that major advances in BNCT should be possible if ratios of {sup 10}B concentrations in tumor to those in normal tissue (e.g. brain and blood) were at least 5: 1. Given that the only current boron carrier being tested clinically in the U.S., p-boronophenyl-alanine[BPA], yields tumor blood and tumor brain ratios of about 3:1, the criteria for new boronated compounds should be to at least match these ratios and maintain tumor boron concentrations greater than 30 {mu}g B/g. Although previously tested boronated porphyrins have not only matched but surpassed these ratios, it was at a cost of greater toxicity. Chemical and hematological assays of blood analytes; showed marked thrombocytopenia, a decrease to about one-tenth the normal concentration of platelets circulating in the blood, in addition to abnormalities in concentrations of circulating enzymes, that indicated liver toxicity. The physical appearance and behavior of the affected mice were different from those of mice injected with solvent only. Although thrombocytopenia and other toxic effects had disappeared after a few days, previously tested porphyrins would not be safe to infuse into patients for BNCT of potentially hemorrhagic malignant tumors in the brain such as glioblastoma multiforme and metastatic melanoma. We synthesized a different boronated porphyrin, tetracarboranylphenylporphyrin, [TCP] and inserted nickel, copper, or manganese into its coordination center. Biological studies of NiTCP in mice and of CuTCP in rats show that these compounds elicit little or no toxicity when given at potentially therapeutic doses.

  11. Design of photon converter and photoneutron target for High power electron accelerator based BNCT.

    Science.gov (United States)

    Rahmani, Faezeh; Seifi, Samaneh; Anbaran, Hossein Tavakoli; Ghasemi, Farshad

    2015-12-01

    An electron accelerator, ILU-14, with current of 10 mA and 100 kW in power has been considered as one of the options for neutron source in Boron Neutron Capture Therapy (BNCT). The final design of neutron target has been obtained using MCNPX to optimize the neutron production. Tungsten in strip shape and D2O in cylindrical form have been proposed as the photon converter and the photoneutron target, respectively. In addition calculation of heat deposition in the photon target design has been considered to ensure mechanical stability of target. The results show that about 8.37×10(12) photoneutron/s with average energy of 615 keV can be produced by this neutron source design. In addition, using an appropriate beam shaping assembly an epithermal neutron flux of the order of 1.24×10(8) cm(-2) s(-1) can be obtained for BNCT applications.

  12. American brain tumor patients treated with BNCT in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Laramore, G.E.; Griffin, B.R.; Spence, A.

    1995-11-01

    The purpose of this work is to establish and maintain a database for patients from the United States who have received BNCT in Japan for malignant gliomas of the brain. This database will serve as a resource for the DOE to aid in decisions relating to BNCT research in the United States, as well as assisting the design and implementation of clinical trials of BNCT for brain cancer patients in this country. The database will also serve as an information resource for patients with brain tumors and their families who are considering this form of therapy.

  13. An accelerator-based epithermal photoneutron source for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Nigg, D.W.; Mitchell, H.E.; Harker, Y.D.; Yoon, W.Y. [and others

    1995-11-01

    Therapeutically-useful epithermal-neutron beams for BNCT are currently generated by nuclear reactors. Various accelerator-based neutron sources for BNCT have been proposed and some low intensity prototypes of such sources, generally featuring the use of proton beams and beryllium or lithium targets have been constructed. This paper describes an alternate approach to the realization of a clinically useful accelerator-based source of epithermal neutrons for BNCT that reconciles the often conflicting objectives of target cooling, neutron beam intensity, and neutron beam spectral purity via a two stage photoneutron production process.

  14. Epithermal neutron beam for BNCT research at the Washington State University TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nigg, D.W.; Venhuizen, J.R.; Wheeler, F.J.; Wemple, C.A. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Tripard, G.E.; Gavin, P.R. [Washington State University, Pullman, WA (United States)

    2000-10-01

    A new epithermal-neutron beam facility for BNCT (Boron Neutron Capture Therapy) research and boronated agent screening in animal models is in the final stages of construction at Washington State University (WSU). A key distinguishing feature of the design is the incorporation of a new, high-efficiency, neutron moderating and filtering material, Fluental, developed by the Technical Research Centre of Finland. An additional key feature is the provision for adjustable filter-moderator thickness to systematically explore the radiobiological consequences of increasing the fast-neutron contamination above the nominal value associated with the baseline system. (author)

  15. A plastic scintillator-based 2D thermal neutron mapping system for use in BNCT studies.

    Science.gov (United States)

    Ghal-Eh, N; Green, S

    2016-06-01

    In this study, a scintillator-based measurement instrument is proposed which is capable of measuring a two-dimensional map of thermal neutrons within a phantom based on the detection of 2.22MeV gamma rays generated via nth+H→D+γ reaction. The proposed instrument locates around a small rectangular water phantom (14cm×15cm×20cm) used in Birmingham BNCT facility. The whole system has been simulated using MCNPX 2.6. The results confirm that the thermal flux peaks somewhere between 2cm and 4cm distance from the system entrance which is in agreement with previous studies.

  16. 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...

  17. INEL BNCT Program: Bulletin, Volume 5, No. 7

    Energy Technology Data Exchange (ETDEWEB)

    Ackermann, A.L. (ed.)

    1991-07-01

    This Bulletin presents a summary of accomplishments and highlights in the Idaho National Engineering Laboratory's (INEL) Boron Neutron Capture Therapy (BNCT) Program for June, 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and animal data charts. Specific highlights include: final-dosage-form BSH samples were analyzed for purity, with the sample from Centronic Ltd the most free from contamination and oxidation products; MRI spectroscopy will be upgraded to provide a potential for boron resolution of 0.75 cm/pixel; neutron and gamma measurements were made for the HFR epithermal neutron beam; the current status of six spontaneous brain-tumor dogs; production of MoAbs against the pituitary CRF receptor; growth of BL6 in low Phe/Tyr medium; an altered synthetic pathway for carboranyl alanine; and encapsulation of {ital i}-B{sub 20}H{sub 18}{sup 2-} into liposomes for baseline murine studies. 2 figs., 4 tabs. (MHB)

  18. Feasibility study on the utilization of boron neutron capture therapy (BNCT) in a rat model of diffuse lung metastases

    Energy Technology Data Exchange (ETDEWEB)

    Bakeine, G.J. [Department of Clinical Medicine and Neurology, Cattinara Hospital, University of Trieste (Italy)], E-mail: jamesbakeine1@yahoo.com; Di Salvo, M. [Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6, Pavia (Italy); Bortolussi, S.; Stella, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6, Pavia (Italy); National Institute of Nuclear Physics (INFN) Section of Pavia, Via Bassi 6, Pavia (Italy); Bruschi, P. [Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6, Pavia (Italy); Bertolotti, A.; Nano, R. [Department of Animal Biology University of Pavia, Piazza Botta, Pavia (Italy); Clerici, A.; Ferrari, C.; Zonta, C. [Department of Surgery University of Pavia, Piazza Botta, Pavia (Italy); Marchetti, A. [Scientific Research Office, Fondazione San Matteo University Policlinic, Pavia (Italy); Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6, Pavia (Italy); National Institute of Nuclear Physics (INFN) Section of Pavia, Via Bassi 6, Pavia (Italy)

    2009-07-15

    In order for boron neutron capture therapy (BNCT) to be eligible for application in lung tumour disease, three fundamental criteria must be fulfilled: there must be selective uptake of boron in the tumour cells with respect to surrounding healthy tissue, biological effectiveness of the radiation therapy and minimal damage or collateral effects of the irradiation on the surrounding tissues. In this study, we evaluated the biological effectiveness of BNCT by in vitro irradiation of rat colon-carcinoma cells previously incubated in boron-enriched medium. One part of these cells was re-cultured in vitro while the other was inoculated via the inferior vena cava to induce pulmonary metastases in a rat model. We observed a post-irradiation in vitro cell viability of 0.05% after 8 days of cell culture. At 4 months follow-up, all animal subjects in the treatment group that received irradiated boron-containing cells were alive. No animal survived beyond 1 month in the control group that received non-treated cells (p<0.001 Kaplan-Meier). These preliminary findings strongly suggest that BNCT has a significant lethal effect on tumour cells and post irradiation surviving cells lose their malignant capabilities in vivo. This radio-therapeutic potential warrants the investigation of in vivo BNCT for lung tumour metastases.

  19. Organisation and management of the first clinical trial of BNCT in Europe (EORTC protocol 11961).EORTC BNCT study group.

    Science.gov (United States)

    Sauerwein, W; Moss, R; Rassow, J; Stecher-Rasmussen, F; Hideghéty, K; Wolbers, J G; Sack, H

    1999-06-01

    Boron Neutron Capture Therapy is based on the ability of the isotope 10B to capture thermal neutrons and to disintegrate instantaneously producing high LET particles. The only neutron beam available in Europe for such a treatment is based at the European High Flux Reactor HFR at Petten (The Netherlands). The European Commission, owners of the reactor, decided that the potential benefit of the facility should be opened to all European citizens and therefore insisted on a multinational approach to perform the first clinical trial in Europe on BNCT. This precondition had to be respected as well as the national laws and regulations. Together with the Dutch authorities actions were undertaken to overcome the obvious legal problems. Furthermore, the clinical trial at Petten takes place in a nuclear research reactor, which apart from being conducted in a non-hospital environment, is per se known to be dangerous. It was therefore of the utmost importance that special attention is given to safety, beyond normal rules, and to the training of staff. In itself, the trial is an unusual Phase I study, introducing a new drug with a new irradiation modality, with really an unknown dose-effect relationship. This trial must follow optimal procedures, which underscore the quality and qualified manner of performance.

  20. 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.

  1. Design and construction of a thermal neutron beam for BNCT at Tehran Research Reactor.

    Science.gov (United States)

    Kasesaz, Yaser; Khalafi, Hossein; Rahmani, Faezeh; Ezzati, Arsalan; Keyvani, Mehdi; Hossnirokh, Ashkan; Shamami, Mehrdad Azizi; Amini, Sepideh

    2014-12-01

    An irradiation facility has been designed and constructed at Tehran Research Reactor (TRR) for the treatment of shallow tumors using Boron Neutron Capture Therapy (BNCT). TRR has a thermal column which is about 3m in length with a wide square cross section of 1.2×1.2m(2). This facility is filled with removable graphite blocks. The aim of this work is to perform the necessary modifications in the thermal column structure to meet thermal BNCT beam criteria recommended by International Atomic Energy Agency. The main modifications consist of rearranging graphite blocks and reducing the gamma dose rate at the beam exit. Activation foils and TLD700 dosimeter have been used to measure in-air characteristics of the neutron beam. According to the measurements, a thermal flux is 5.6×10(8) (ncm(-2)s(-1)), a cadmium ratio is 186 for gold foils and a gamma dose rate is 0.57Gy h(-1).

  2. Development and characteristics of the HANARO ex-core neutron irradiation facility for applications in the boron neutron capture therapy field

    CERN Document Server

    Kim, M S; Jun, B J; Kim, H; Lee, B C; Hwang, Sung-Yul; Jun, Byung-Jin; Kim, Heonil; Kim, Myong-Seop; Lee, Byung-Chul

    2006-01-01

    The HANARO ex-core neutron irradiation facility was developed for various applications in the boron neutron capture therapy (BNCT) field, and its characteristics have been investigated. In order to obtain a sufficient thermal neutron flux with a low level contamination of fast neutrons and gamma-rays, a radiation filtering method is adopted. The radiation filter has been designed by using a silicon single crystal cooled by liquid nitrogen and a bismuth crystal. The installation of the main components of the irradiation facility and the irradiation room are finished. Experimental measurements of the neutron beam characteristics have been performed by using bare and cadmium covered gold foils and wires. The in-phantom neutron flux distribution was measured for a flux mapping inside the phantom. The gamma-ray dose was determined by using TLD-700 thermoluminescence dosimeters. The thermal and fast neutron fluxes and the gamma-ray dose were calculated by using the MCNP code, and they were compared with experimenta...

  3. Computational dosimetry of a simulated combined standard X-Rays and BNCT treatment

    Energy Technology Data Exchange (ETDEWEB)

    Casal, M.R., E-mail: mcasal@cnea.gov.ar [Instituto de Oncologia ' Angel H. Roffo' , Universidad de Buenos Aires, Av. San Martin 5481, Bs.As. (Argentina)] [Comision Nacional de Energia Atomica, Av. General Paz 1499, San Martin, Buenos Aires (Argentina); Herrera, M.S., E-mail: mariettaherrera@gmail.com [Comision Nacional de Energia Atomica, Av. General Paz 1499, San Martin, Buenos Aires (Argentina)] [Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET) Av. Rivadavia 191, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad de General San Martin, 25 de Mayo and M. de Irigoyen, San Martin (Argentina); Gonzalez, S.J., E-mail: srgonzal@cnea.gov.ar [Comision Nacional de Energia Atomica, Av. General Paz 1499, San Martin, Buenos Aires (Argentina)] [Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET) Av. Rivadavia 191, Buenos Aires (Argentina)

    2011-12-15

    There has been increasing interest in combining Boron Neutron Capture Therapy (BNCT) with standard radiotherapy, either concomitantly or as a BNCT treatment of a recurrent tumor that was previously irradiated with a medical electron linear accelerator (LINAC). In this work we report the simulated dosimetry of treatments combining X-rays and BNCT

  4. Monte Carlo based protocol for cell survival and tumour control probability in BNCT

    Science.gov (United States)

    Ye, Sung-Joon

    1999-02-01

    A mathematical model to calculate the theoretical cell survival probability (nominally, the cell survival fraction) is developed to evaluate preclinical treatment conditions for boron neutron capture therapy (BNCT). A treatment condition is characterized by the neutron beam spectra, single or bilateral exposure, and the choice of boron carrier drug (boronophenylalanine (BPA) or boron sulfhydryl hydride (BSH)). The cell survival probability defined from Poisson statistics is expressed with the cell-killing yield, the (n, ) reaction density, and the tolerable neutron fluence. The radiation transport calculation from the neutron source to tumours is carried out using Monte Carlo methods: (i) reactor-based BNCT facility modelling to yield the neutron beam library at an irradiation port; (ii) dosimetry to limit the neutron fluence below a tolerance dose (10.5 Gy-Eq); (iii) calculation of the (n, ) reaction density in tumours. A shallow surface tumour could be effectively treated by single exposure producing an average cell survival probability of - for probable ranges of the cell-killing yield for the two drugs, while a deep tumour will require bilateral exposure to achieve comparable cell kills at depth. With very pure epithermal beams eliminating thermal, low epithermal and fast neutrons, the cell survival can be decreased by factors of 2-10 compared with the unmodified neutron spectrum. A dominant effect of cell-killing yield on tumour cell survival demonstrates the importance of choice of boron carrier drug. However, these calculations do not indicate an unambiguous preference for one drug, due to the large overlap of tumour cell survival in the probable ranges of the cell-killing yield for the two drugs. The cell survival value averaged over a bulky tumour volume is used to predict the overall BNCT therapeutic efficacy, using a simple model of tumour control probability (TCP).

  5. Effectiveness of BNCT for recurrent head and neck malignancies

    Energy Technology Data Exchange (ETDEWEB)

    Kato, Itsuro E-mail: katoitsu@dent.osaka-u.ac.jp; Ono, Koji; Sakurai, Yoshinori; Ohmae, Masatoshi; Maruhashi, Akira; Imahori, Yoshio; Kirihata, Mitsunori; Nakazawa, Mitsuhiro; Yura, Yoshiaki

    2004-11-01

    Recurrent head and neck malignancies (HNM) are often radio-/chemo-resistant and show extensive growth, necessitating a wide resection including surrounding tissues. To avoid severe impairment of oro-facial structures and functions, it is necessary to explore new treatments for HNM. Boron neutron capture therapy (BNCT) is tumor-cell targeted radiotherapy that has significant superiority over conventional radiotherapies in principle. We report here, first in the world, six patients with a recurrent HNM who have been treated with BNCT. The BNCT in combination with boronophenylalanine (BPA) and borocaptate sodium (BSH) was performed using the epithermal neutrons with Kyoto University Research Reactor (KUR). The results of BNCT were as follows: (1) {sup 10}B concentration of tumor/normal tissue ratios (T/N ratio) of PET studies were SCC:1.8-4.4, sarcoma:3.1-4.0, parotid tumor:3.5. (2) Relative volume (%) of each tumor to the prior were 6-46%. (3) Remarkable reduction (46-100%) of huge tumor such as 40-675 cm{sup 3} (average: 315 cm{sup 3}), improvement of QOL and very mild side effects were recognized in all cases. These results indicate that BNCT represents a new and promising treatment approach even for a huge or far advanced HNM.

  6. Dose masking feature for BNCT radiotherapy planning

    Science.gov (United States)

    Cook, Jeremy L.; Wessol, Daniel E.; Wheeler, Floyd J.

    2000-01-01

    A system for displaying an accurate model of isodoses to be used in radiotherapy so that appropriate planning can be performed prior to actual treatment on a patient. The nature of the simulation of the radiotherapy planning for BNCT and Fast Neutron Therapy, etc., requires that the doses be computed in the entire volume. The "entire volume" includes the patient and beam geometries as well as the air spaces in between. Isodoses derived from the computed doses will therefore extend into the air regions between the patient and beam geometries and thus depict the unrealistic possibility that radiation deposition occurs in regions containing no physical media. This problem is solved by computing the doses for the entire geometry and then masking the physical and air regions along with the isodose contours superimposed over the patient image at the corresponding plane. The user is thus able to mask out (remove) the contour lines from the unwanted areas of the image by selecting the appropriate contour masking region from the raster image.

  7. Cyclotron-based neutron source for BNCT

    Science.gov (United States)

    Mitsumoto, T.; Yajima, S.; Tsutsui, H.; Ogasawara, T.; Fujita, K.; Tanaka, H.; Sakurai, Y.; Maruhashi, A.

    2013-04-01

    Kyoto University Research Reactor Institute (KURRI) and Sumitomo Heavy Industries, Ltd. (SHI) have developed a cyclotron-based neutron source for Boron Neutron Capture Therapy (BNCT). It was installed at KURRI in Osaka prefecture. The neutron source consists of a proton cyclotron named HM-30, a beam transport system and an irradiation & treatment system. In the cyclotron, H- ions are accelerated and extracted as 30 MeV proton beams of 1 mA. The proton beams is transported to the neutron production target made by a beryllium plate. Emitted neutrons are moderated by lead, iron, aluminum and calcium fluoride. The aperture diameter of neutron collimator is in the range from 100 mm to 250 mm. The peak neutron flux in the water phantom is 1.8×109 neutrons/cm2/sec at 20 mm from the surface at 1 mA proton beam. The neutron source have been stably operated for 3 years with 30 kW proton beam. Various pre-clinical tests including animal tests have been done by using the cyclotron-based neutron source with 10B-p-Borono-phenylalanine. Clinical trials of malignant brain tumors will be started in this year.

  8. Cyclotron-based neutron source for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Mitsumoto, T.; Yajima, S.; Tsutsui, H.; Ogasawara, T.; Fujita, K. [Sumitomo Heavy Industries, Ltd (Japan); Tanaka, H.; Sakurai, Y.; Maruhashi, A. [Kyoto University Research Reactor Institute (Japan)

    2013-04-19

    Kyoto University Research Reactor Institute (KURRI) and Sumitomo Heavy Industries, Ltd. (SHI) have developed a cyclotron-based neutron source for Boron Neutron Capture Therapy (BNCT). It was installed at KURRI in Osaka prefecture. The neutron source consists of a proton cyclotron named HM-30, a beam transport system and an irradiation and treatment system. In the cyclotron, H- ions are accelerated and extracted as 30 MeV proton beams of 1 mA. The proton beams is transported to the neutron production target made by a beryllium plate. Emitted neutrons are moderated by lead, iron, aluminum and calcium fluoride. The aperture diameter of neutron collimator is in the range from 100 mm to 250 mm. The peak neutron flux in the water phantom is 1.8 Multiplication-Sign 109 neutrons/cm{sup 2}/sec at 20 mm from the surface at 1 mA proton beam. The neutron source have been stably operated for 3 years with 30 kW proton beam. Various pre-clinical tests including animal tests have been done by using the cyclotron-based neutron source with {sup 10}B-p-Borono-phenylalanine. Clinical trials of malignant brain tumors will be started in this year.

  9. Design of a beam shaping assembly and preliminary modelling of a treatment room for accelerator-based BNCT at CNEA

    Energy Technology Data Exchange (ETDEWEB)

    Burlon, A.A.; Girola, S. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, San Martin (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin, San Martin (Argentina); Valda, A.A., E-mail: valda@tandar.cnea.gov.ar [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, San Martin (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin, San Martin (Argentina); Minsky, D.M.; Kreiner, A.J. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, San Martin (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin, San Martin (Argentina)] [CONICET, Buenos Aires (Argentina); Sanchez, G. [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin, San Martin (Argentina)

    2011-12-15

    This work reports on the characterisation of a neutron beam shaping assembly (BSA) prototype and on the preliminary modelling of a treatment room for BNCT within the framework of a research programme for the development and construction of an accelerator-based BNCT irradiation facility in Buenos Aires, Argentina. The BSA prototype constructed has been characterised by means of MCNP simulations as well as a set of experimental measurements performed at the Tandar accelerator at the National Atomic Energy Commission of Argentina. - Highlights: Black-Right-Pointing-Pointer Characterisation of a neutron beam shaping assembly for accelerator-based BNCT. Black-Right-Pointing-Pointer Measurements: total and epi-cadmium neutron fluxes and beam homogeneity. Black-Right-Pointing-Pointer Calculations: Monte Carlo simulations with the MCNP code. Black-Right-Pointing-Pointer Measured and calculated figure-of-merit parameters in agreement with those of IAEA. Black-Right-Pointing-Pointer Initial MCNP dose calculations for a treatment room to define future design actions.

  10. Protocols for BNCT of glioblastoma multiforme at Brookhaven: Practical considerations

    Energy Technology Data Exchange (ETDEWEB)

    Chanana, A.D.; Coderre, J.A.; Joel, D.D.; Slatkin, D.N.

    1996-12-31

    In this report we discuss some issues considered in selecting initial protocols for boron neutron capture therapy (BNCT) of human glioblastoma multiforme. First the tolerance of normal tissues, especially the brain, to the radiation field. Radiation doses limits were based on results with human and animal exposures. Estimates of tumor control doses were based on the results of single-fraction photon therapy and single fraction BNCT both in humans and experimental animals. Of the two boron compounds (BSH and BPA), BPA was chosen since a FDA-sanctioned protocol for distribution in humans was in effect at the time the first BNCT protocols were written and therapy studies in experimental animals had shown it to be more effective than BSH.

  11. The filter/moderator arrangement-optimisation for the boron-neutron capture therapy (BNCT).

    Science.gov (United States)

    Tracz, G; Dabkowski, L; Dworak, D; Pytel, K; Woźnicka, U

    2004-01-01

    The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for the boron neutron capture therapy (BNCT) facility to be located at the Polish research nuclear reactor MARIA at Swierk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised to moderate fission neutrons to epithermal energies and to remove both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both high epithermal neutron flux and suitably low level of beam contamination. Photons originating from the reactor core are almost eliminated what is the exceptional advantage of the proposed design. It yields one order of magnitude lower gamma radiation dose than the maximum allowed dose in such a type of therapeutic facility. The MCNP code has been used for the computations.

  12. PET pharmacokinetic analysis to estimate boron concentration in tumor and brain as a guide to plan BNCT for malignant cerebral glioma

    Energy Technology Data Exchange (ETDEWEB)

    Nariai, Tadashi [Department of Neurosurgery, Tokyo Medical and Dental University, 1-5-45 Yushima, Bunkyo-ku, Tokyo (Japan)], E-mail: nariai.nsrg@tmd.ac.jp; Ishiwata, Kiichi [Positron Medical Center, Tokyo Metropolitan Institute of Gerontology, 1-1, Nakacho, Itabashi-ku, Tokyo (Japan); Kimura, Yuichi [Molecular Imaging Center, National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage-ku, Chiba (Japan); Inaji, Motoki; Momose, Toshiya [Department of Neurosurgery, Tokyo Medical and Dental University, 1-5-45 Yushima, Bunkyo-ku, Tokyo (Japan); Yamamoto, Tetsuya; Matsumura, Akira [Department of Neurosurgery, University of Tsukuba, Tennodai, Tsukuba, Igaraki (Japan); Ishii, Kenji [Positron Medical Center, Tokyo Metropolitan Institute of Gerontology, 1-1, Nakacho, Itabashi-ku, Tokyo (Japan); Ohno, Kikuo [Department of Neurosurgery, Tokyo Medical and Dental University, 1-5-45 Yushima, Bunkyo-ku, Tokyo (Japan)

    2009-07-15

    Introduction: To plan the optimal BNCT for patients with malignant cerebral glioma, estimation of the ratio of boron concentration in tumor tissue against that in the surrounding normal brain (T/N ratio of boron) is important. We report a positron emission tomography (PET) imaging method to estimate T/N ratio of tissue boron concentration based on pharmacokinetic analysis of amino acid probes. Methods: Twelve patients with cerebral malignant glioma underwent 60 min dynamic PET scanning of brain after bolus injection of {sup 18}F-borono-phenyl-alanine (FBPA) with timed arterial blood sampling. Using kinetic parameter obtained by this scan, T/N ratio of boron concentration elicited by one-hour constant infusion of BPA, as performed in BNCT, was simulated on Runge-Kutta algorithm. {sup 11}C-methionine (MET) PET scan, which is commonly used in worldwide PET center as brain tumor imaging tool, was also performed on the same day to compare the image characteristics of FBPA and that of MET. Result: PET glioma images obtained with FBPA and MET are almost identical in all patients by visual inspection. Estimated T/N ratio of tissue boron concentration after one-hour constant infusion of BPA, T/N ratio of FBPA on static condition, and T/N ratio of MET on static condition showed significant linear correlation between each other. Conclusion: T/N ratio of boron concentration that is obtained by constant infusion of BPA during BNCT can be estimated by FBPA PET scan. This ratio can also be estimated by MET-PET imaging. As MET-PET study is available in many clinical PET center, selection of candidates for BNCT may be possible by MET-PET images. Accurate planning of BNCT may be performed by static images of FBPA PET. Use of PET imaging with amino acid probes may contribute very much to establish an appropriate application of BNCT for patients with malignant glioma.

  13. Resumption of JRR-4 and characteristics of neutron beam for BNCT.

    Science.gov (United States)

    Nakamura, T; Horiguchi, H; Kishi, T; Motohashi, J; Sasajima, F; Kumada, H

    2011-12-01

    The clinical trials of Boron Neutron Capture Therapy (BNCT) have been conducted using Japan Research Reactor No. 4 (JRR-4) at Japan Atomic Energy Agency (JAEA). On December 28th, 2007, a crack of a graphite reflector in the reactor core was found on the weld of the aluminum cladding. For this reason, specifications of graphite reflectors were renewed; dimensions of the graphite were reduced and gaps of water were increased. All existing graphite reflectors of JRR-4 were replaced by new graphite reflectors. In February 2010 the resumption of JRR-4 was carried out with new graphite reflectors. We measured the characteristics of neutron beam at the JRR-4 Neutron Beam Facility. A cylindrical water phantom of 18.6 cm diameter and 24 cm depth was set in front of the beam port with 1cm gap. TLDs and gold wires were inserted within the phantom when the phantom was irradiated. The results of the measured thermal neutron flux and the gamma dose in water were compared with that of MCNP calculation. The neutron energy spectrum of the calculation model with new reflector had little variation compared to that with old reflector, but intensities of the neutron flux and gamma dose with new reflector were rather smaller than those with old reflector. The calculated results showed the same tendency as that of the experimental results. Therefore, the clinical trials of BNCT in JRR-4 could be restarted.

  14. Experimental and theoretical evaluation of accelerator based epithermal neutron yields for BNCT

    Science.gov (United States)

    Wielopolski, L.; Ludewig, H.; Powell, J. R.; Raparia, D.; Alessi, J. G.; Alburger, D. E.; Zucker, M. S.; Lowenstein, D. I.

    1999-06-01

    At BNL, we have evaluated the beam current required to produce a clinical neutron beam for Boron Neutron Capture Therapy (BNCT) with an epithermal neutron flux of 1012n/cm2/hr. Experiments were carried out on a Van de Graaff accelerator at the Radiological Research Accelerator Facility (RARAF) at Columbia University. A thick Li target was irradiated by protons with energies from 1.8 to 2.5 MeV. The neutron spectra resulting from the 7Li(p,n)7Be reaction, followed by various filter configurations, were determined by measuring pulse height distributions with a gas filled proton recoil spectrometer. These distributions were unfolded into neutron energy spectra using the PSNS code, from which the required beam currents were estimated to be about 5 mA. Results are in good agreement with calculations using the MCNP-4A transport code. In addition comparison was also made between the neutron flux obtained at the Brookhaven Medical Research Reactor (where clinical trials of BNCT are ongoing), and measurements at RARAF, using a 10BF3 detector in a phantom. These results also support the requirement for about 5 mA beam current.

  15. Feasibility of the Utilization of BNCT in the Fast Neutron Therapy Beam at Fermilab

    Science.gov (United States)

    Langen, Katja; Lennox, Arlene J.; Kroc, Thomas K.; DeLuca, Jr., Paul M.

    2000-06-01

    The Neutron Therapy Facility at Fermilab has treated cancer patients since 1976. Since then more than 2,300 patients have been treated and a wealth of clinical information accumulated. The therapeutic neutron beam at Fermilab is produced by bombarding a beryllium target with 66 MeV protons. The resulting continuous neutron spectrum ranges from thermal to 66 MeV in neutron energy. It is clear that this spectrum is not well suited for the treatment of tumors with boron neutron capture therapy (BNCT) only However, since this spectrum contains thermal and epithermal components the authors are investigating whether BNCT can be used in this beam to boost the tumor dose. There are clinical scenarios in which a selective tumor dose boost of 10 - 15% could be clinically significant. For these cases the principal treatment would still be fast neutron therapy but a tumor boost could be used either to deliver a higher dose to the tumor tissue or to reduce the dose to the normal healthy tissue while maintaining the absorbed dose level in the tumor tissue.

  16. Measurements of gamma dose and thermal neutron fluence in phantoms exposed to a BNCT epithermal beam with TLD-700.

    Science.gov (United States)

    Gambarini, G; Magni, D; Regazzoni, V; Borroni, M; Carrara, M; Pignoli, E; Burian, J; Marek, M; Klupak, V; Viererbl, L

    2014-10-01

    Gamma dose and thermal neutron fluence in a phantom exposed to an epithermal neutron beam for boron neutron capture therapy (BNCT) can be measured by means of a single thermoluminescence dosemeter (TLD-700). The method exploits the shape of the glow curve (GC) and requires the gamma-calibration GC (to obtain gamma dose) and the thermal-neutron-calibration GC (to obtain neutron fluence). The method is applicable for BNCT dosimetry in case of epithermal neutron beams from a reactor because, in most irradiation configurations, thermal neutrons give a not negligible contribution to the TLD-700 GC. The thermal neutron calibration is not simple, because of the impossibility of having thermal neutron fields without gamma contamination, but a calibration method is here proposed, strictly bound to the method itself of dose separation.

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

    Energy Technology Data Exchange (ETDEWEB)

    Price, S.M., Westinghouse Hanford

    1996-07-29

    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 General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Documentation included in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units. A checklist indicating where information is contained in the General Information Portion, in relation to the Washington State Department of Ecology guidance documentation, is located in the Contents Section. The intent of the General Information Portion is: (1) to provide an overview of the Hanford Facility; and (2) to assist in streamlining efforts associated with treatment, storage, and/or disposal unit-specific Part B permit application, preclosure work plan, closure work plan, closure plan, closure/postclosure plan, or postclosure permit application documentation development, and the `Hanford Facility Resource Conservation and Recovery Act Permit` modification process. Revision 2 of the General Information Portion of the `Hanford Facility Dangerous Waste Permit Application` contains information current as of May 1, 1996. This document is a complete submittal and supersedes Revision 1.

  18. Boron Neutron Capture Therapy at the TRIGA Mark II of Pavia, Italy - The BNCT of the diffuse tumours

    Energy Technology Data Exchange (ETDEWEB)

    Altieri, S.; Bortolussi, S.; Stella, S.; Bruschi, P.; Gadan, M.A. [University of Pavia (Italy); INFN - National Institute for Nuclear Physics, of Pavia (Italy)

    2008-10-29

    The selectivity based on the B distribution rather than on the irradiation field makes Boron neutron Capture Therapy (BNCT) a valid option for the treatment of the disseminated tumours. As the range of the high LET particles is shorter than a cell diameter, the normal cells around the tumour are not damaged by the reactions occurring in the tumoral cells. PAVIA 2001: first treatment of multiple hepatic metastases from colon ca by BNCT and auto-transplantation technique: TAOrMINA project. The liver was extracted after BPA infusion, irradiated in the Thermal Column of the Pavia TRIGA Mark II reactor, and re-implanted in the patient. Two patients were treated, demonstrating the feasibility of the therapy and the efficacy in destroying the tumoral nodules sparing the healthy tissues. In the last years, the possibility of applying BNCT to the lung tumours using epithermal collimated neutron beams and without explanting the organ, is being explored. The principal obtained results of the BNCT research are presented, with particular emphasis on the following aspects: a) the project of a new thermal column configuration to make the thermal neutron flux more uniform inside the explanted liver, b) the Monte Carlo study by means of the MCNP code of the thermal neutron flux distribution inside a patient's thorax irradiated with epithermal neutrons, and c) the measurement of the boron concentration in tissues by (n,{alpha}) spectroscopy and neutron autoradiography. The dose distribution in the thorax are simulated using MCNP and the anthropomorphic model ADAM. To have a good thermal flux distribution inside the lung epithermal neutrons must be used, which thermalize crossing the first tissue layers. Thermal neutrons do not penetrate and the obtained uniformity is poor. In the future, the construction of a PGNAA facility using a horizontal channel of the TRIGA Mark II is planned. With this method the B concentration can be measured also in liquid samples (blood, urine) and

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

    Energy Technology Data Exchange (ETDEWEB)

    Hays, C.B.

    1998-05-19

    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).

  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. Selected Applications of Planar Imaging Velocimetry in Combustion Test Facilities

    Science.gov (United States)

    Willert, Christian; Stockhausen, Guido; Voges, Melanie; Klinner, Joachim; Schodl, Richard; Hassa, Christoph; Schürmans, Bruno; Güthe, Felix

    This chapter provides an overview on the application of particle image velocimetry (PIV) and Doppler global velocimetry (DGV) in combustion test facilities that are operated at pressures of up to 10 bar. Emphasis is placed on the experimental aspects of each application rather than the interpretation of the acquired flow-field data because many of the encountered problems and chosen solution strategies are unique to this area of velocimetry application. In particular, imaging configurations, seeding techniques, data-acquisition strategies as well as pre- and postprocessing methodologies are outlined.

  2. New irradiation facility for biomedical applications at the RA-3 reactor thermal column.

    Science.gov (United States)

    Miller, M; Quintana, J; Ojeda, J; Langan, S; Thorp, S; Pozzi, E; Sztejnberg, M; Estryk, G; Nosal, R; Saire, E; Agrazar, H; Graiño, F

    2009-07-01

    A new irradiation facility has been developed in the RA-3 reactor in order to perform trials for the treatment of liver metastases using boron neutron capture therapy (BNCT). RA-3 is a production research reactor that works continuously five days a week. It had a thermal column with a small cross section access tunnel that was not accessible during operation. The objective of the work was to perform the necessary modifications to obtain a facility for irradiating a portion of the human liver. This irradiation facility must be operated without disrupting the normal reactor schedule and requires a highly thermalized neutron spectrum, a thermal flux of around 10(10) n cm(-2)s(-1) that is as isotropic and uniform as possible, as well as on-line instrumentation. The main modifications consist of enlarging the access tunnel inside the thermal column to the suitable dimensions, reducing the gamma dose rate at the irradiation position, and constructing properly shielded entrance gates enabled by logical control to safely irradiate and withdraw samples with the reactor at full power. Activation foils and a neutron shielded graphite ionization chamber were used for a preliminary in-air characterization of the irradiation site. The constructed facility is very practical and easy to use. Operational authorization was obtained from radioprotection personnel after confirming radiation levels did not significantly increase after the modification. A highly thermalized and homogenous irradiation field was obtained. Measurements in the empty cavity showed a thermal flux near 10(10) n cm(-2)s(-1), a cadmium ratio of 4100 for gold foils and a gamma dose rate of approximately 5 Gy h(-1).

  3. Analysis of accelerator based neutron spectra for BNCT using proton recoil spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Wielopolski, L.; Ludewig, H.; Powell, J.R.; Raparia, D.; Alessi, J.G.; Lowenstein, D.I.

    1999-03-01

    Boron Neutron Capture Therapy (BNCT) is a promising binary treatment modality for high-grade primary brain tumors (glioblastoma multiforme, GM) and other cancers. BNCT employs a boron-10 containing compound that preferentially accumulates in the cancer cells in the brain. Upon neutron capture by {sup 10}B energetic alpha particles and triton released at the absorption site kill the cancer cell. In order to gain penetration depth in the brain Fairchild proposed, for this purpose, the use of energetic epithermal neutrons at about 10 keV. Phase 1/2 clinical trials of BNCT for GM are underway at the Brookhaven Medical Research Reactor (BMRR) and at the MIT Reactor, using these nuclear reactors as the source for epithermal neutrons. In light of the limitations of new reactor installations, e.g. cost, safety and licensing, and limited capability for modulating the reactor based neutron beam energy spectra, alternative neutron sources are being contemplated for wider implementation of this modality in a hospital environment. For example, accelerator based neutron sources offer the possibility of tailoring the neutron beams, in terms of improved depth-dose distributions, to the individual and offer, with relative ease, the capability of modifying the neutron beam energy and port size. In previous work new concepts for compact accelerator/target configuration were published. In this work, using the Van de Graaff accelerator the authors have explored different materials for filtering and reflecting neutron beams produced by irradiating a thick Li target with 1.8 to 2.5 MeV proton beams. However, since the yield and the maximum neutron energy emerging from the Li-7(p,n)Be-7 reaction increase with increase in the proton beam energy, there is a need for optimization of the proton energy versus filter and shielding requirements to obtain the desired epithermal neutron beam. The MCNP-4A computer code was used for the initial design studies that were verified with benchmark

  4. ANALYSIS OF ACCELERATOR BASED NEUTRON SPECTRA FOR BNCT USING PROTON RECOIL SPECTROSCOPY

    Energy Technology Data Exchange (ETDEWEB)

    WIELOPOLSKI,L.; LUDEWIG,H.; POWELL,J.R.; RAPARIA,D.; ALESSI,J.G.; LOWENSTEIN,D.I.

    1998-11-06

    Boron Neutron Capture Therapy (BNCT) is a promising binary treatment modality for high-grade primary brain tumors (glioblastoma multiforme, GM) and other cancers. BNCT employs a boron-10 containing compound that preferentially accumulates in the cancer cells in the brain. Upon neutron capture by {sup 10}B energetic alpha particles and triton released at the absorption site kill the cancer cell. In order to gain penetration depth in the brain Fairchild proposed, for this purpose, the use of energetic epithermal neutrons at about 10 keV. Phase I/II clinical trials of BNCT for GM are underway at the Brookhaven Medical Research Reactor (BMRR) and at the MIT Reactor, using these nuclear reactors as the source for epithermal neutrons. In light of the limitations of new reactor installations, e.g. cost, safety and licensing, and limited capability for modulating the reactor based neutron beam energy spectra alternative neutron sources are being contemplated for wider implementation of this modality in a hospital environment. For example, accelerator based neutron sources offer the possibility of tailoring the neutron beams, in terms of improved depth-dose distributions, to the individual and offer, with relative ease, the capability of modifying the neutron beam energy and port size. In previous work new concepts for compact accelerator/target configuration were published. In this work, using the Van de Graaff accelerator the authors have explored different materials for filtering and reflecting neutron beams produced by irradiating a thick Li target with 1.8 to 2.5 MeV proton beams. However, since the yield and the maximum neutron energy emerging from the Li-7(p,n)Be-7 reaction increase with increase in the proton beam energy, there is a need for optimization of the proton energy versus filter and shielding requirements to obtain the desired epithermal neutron beam. The MCNP-4A computer code was used for the initial design studies that were verified with benchmark

  5. Dose factor entry and display tool for BNCT radiotherapy

    Science.gov (United States)

    Wessol, Daniel E.; Wheeler, Floyd J.; Cook, Jeremy L.

    1999-01-01

    A system for use in Boron Neutron Capture Therapy (BNCT) radiotherapy planning where a biological distribution is calculated using a combination of conversion factors and a previously calculated physical distribution. Conversion factors are presented in a graphical spreadsheet so that a planner can easily view and modify the conversion factors. For radiotherapy in multi-component modalities, such as Fast-Neutron and BNCT, it is necessary to combine each conversion factor component to form an effective dose which is used in radiotherapy planning and evaluation. The Dose Factor Entry and Display System is designed to facilitate planner entry of appropriate conversion factors in a straightforward manner for each component. The effective isodose is then immediately computed and displayed over the appropriate background (e.g. digitized image).

  6. Treatment Planning Systems for BNCT Requirements and Peculiarities

    CERN Document Server

    Daquino, G G

    2003-01-01

    The main requirements and peculiarities expected from the BNCT-oriented treatment planning system (TPS) are summarized in this paper. The TPS is a software, which can be integrated or composed by several auxiliary programs. It plays important roles inside the whole treatment planning of the patient's organ in BNCT. However, the main goal is the simulation of the irradiation, in order to obtain the optimal configuration, in terms of neutron spectrum, patient positioning and dose distribution in the tumour and healthy tissues. The presence of neutrons increases the level of complexity, because much more nuclear reactions need to be monitored and properly calculated during the simulation of the patient's treatment. To this purposes several 3D geometry reconstruction techniques, generally based on the CT scanning data, are implemented and Monte Carlo codes are normally used. The TPSs are expected to show also the results (basically doses and fluences) in a proper format, such as isocurves (or isosurfaces) along t...

  7. Smart facility application: exploiting space technology for smart city solution

    Science.gov (United States)

    Termizi, A. A. A.; Ahmad, N.; Omar, M. F.; Wahap, N. A.; Zainal, D.; Ismail, N. M.

    2016-06-01

    Facilities and amenities management is amongst the core functionalities of local government. Considering the vast area that local government has to manage, a smart solution is extremely inevitable to solve issues such as inefficient maintenance of public parks, drainage system and so forth. Therefore, this paper aims to offer a smart city solution which exploits the benefit of space technology. This proposed solution is one of the modules developed in Spatial Smart City Service Delivery Engine (SSC SDE) Project undertaken by Agensi Angkasa Negara (ANGKASA). Various levels of local government have been chosen to understand real issues faced by them. Based on this data, a Smart Facility application has been developed with the aim to enhance the service delivery by the local government hence improving citizens’ satisfaction. Since this project is still in progress, this paper will merely discussing the concept of this application.

  8. Measurement and simulation of the TRR BNCT beam parameters

    Science.gov (United States)

    Bavarnegin, Elham; Sadremomtaz, Alireza; Khalafi, Hossein; Kasesaz, Yaser; Golshanian, Mohadeseh; Ghods, Hossein; Ezzati, Arsalan; Keyvani, Mehdi; Haddadi, Mohammad

    2016-09-01

    Recently, the configuration of the Tehran Research Reactor (TRR) thermal column has been modified and a proper thermal neutron beam for preclinical Boron Neutron Capture Therapy (BNCT) has been obtained. In this study, simulations and experimental measurements have been carried out to identify the BNCT beam parameters including the beam uniformity, the distribution of the thermal neutron dose, boron dose, gamma dose in a phantom and also the Therapeutic Gain (TG). To do this, the entire TRR structure including the reactor core, pool, the thermal column and beam tubes have been modeled using MCNPX Monte Carlo code. To measure in-phantom dose distribution a special head phantom has been constructed and foil activation techniques and TLD700 dosimeter have been used. The results show that there is enough uniformity in TRR thermal BNCT beam. TG parameter has the maximum value of 5.7 at the depth of 1 cm from the surface of the phantom, confirming that TRR thermal neutron beam has potential for being used in treatment of superficial brain tumors. For the purpose of a clinical trial, more modifications need to be done at the reactor, as, for example design, and construction of a treatment room at the beam exit which is our plan for future. To date, this beam is usable for biological studies and animal trials. There is a relatively good agreement between simulation and measurement especially within a diameter of 10 cm which is the dimension of usual BNCT beam ports. This relatively good agreement enables a more precise prediction of the irradiation conditions needed for future experiments.

  9. Measurement and simulation of the TRR BNCT beam parameters

    Energy Technology Data Exchange (ETDEWEB)

    Bavarnegin, Elham [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of); Department of Physics, University of Guilan, Rasht (Iran, Islamic Republic of); Sadremomtaz, Alireza [Department of Physics, University of Guilan, Rasht (Iran, Islamic Republic of); Khalafi, Hossein [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of); Kasesaz, Yaser, E-mail: ykasesaz@aeoi.org.ir [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of); Golshanian, Mohadeseh; Ghods, Hossein; Ezzati, Arsalan; Keyvani, Mehdi; Haddadi, Mohammad [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of)

    2016-09-11

    Recently, the configuration of the Tehran Research Reactor (TRR) thermal column has been modified and a proper thermal neutron beam for preclinical Boron Neutron Capture Therapy (BNCT) has been obtained. In this study, simulations and experimental measurements have been carried out to identify the BNCT beam parameters including the beam uniformity, the distribution of the thermal neutron dose, boron dose, gamma dose in a phantom and also the Therapeutic Gain (TG). To do this, the entire TRR structure including the reactor core, pool, the thermal column and beam tubes have been modeled using MCNPX Monte Carlo code. To measure in-phantom dose distribution a special head phantom has been constructed and foil activation techniques and TLD700 dosimeter have been used. The results show that there is enough uniformity in TRR thermal BNCT beam. TG parameter has the maximum value of 5.7 at the depth of 1 cm from the surface of the phantom, confirming that TRR thermal neutron beam has potential for being used in treatment of superficial brain tumors. For the purpose of a clinical trial, more modifications need to be done at the reactor, as, for example design, and construction of a treatment room at the beam exit which is our plan for future. To date, this beam is usable for biological studies and animal trials. There is a relatively good agreement between simulation and measurement especially within a diameter of 10 cm which is the dimension of usual BNCT beam ports. This relatively good agreement enables a more precise prediction of the irradiation conditions needed for future experiments.

  10. Clinical results of BNCT for malignant brain tumors in children

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Yoshinobu [Department of Neurosurgery, Kagawa National Children' s Hospital, Kagawa 765-8501 (Japan)], E-mail: ynakagawa0517@yahoo.co.jp; Kageji, Teruyoshi; Mizobuchi, Yoshifumi [Department of Neurosurgery, University of Tokushima, Tokushima 770-8503 (Japan); Kumada, Hiroaki [Department of Research Reactor, Japan Atomic Energy Research Institute, Ibaragi 319-1195 (Japan); Nakagawa, Yoshiaki [Department of Medical Informatics, Post Graduated School, Kyoto University, Kyoto (Japan)

    2009-07-15

    It is very difficult to treat the patients with malignant brain tumor in children, especially under 3 years, because the conventional irradiation cannot be applied due to the damage of normal brain tissue. However, boron neutron capture therapy (BNCT) has tumor selectivity such that it can make damage only in tumor cells. We evaluated the clinical results and courses in patients with malignant glioma under 15 years. Among 183 patients with brain tumors treated by our group using BSH-based intra-operative BNCT, 23 patients were under 15 years. They included 4 patients under 3 years. There were 3 glioblastomas (GBM), 6 anaplastic astrocytomas(AAS), 7 primitive neuroectodermal tumors (PNET), 6 pontine gliomas and 1 anaplastic ependymoma. All GBM and PNET patients died due to CSF and/or CNS dissemination without local tumor regrowth. All pontine glioma patients died due to regrowth of the tumor. Four of 6 anaplastic astrocytoma and 1 anaplastic ependymoma patients alive without tumor recurrence. BNCT can be applied to malignant brain tumors in children, especially under 3 years instead of conventional radiation. Although it can achieve the local control in the primary site, it cannot prevent CSF dissemination in patients with glioblastoma.

  11. Hanford Facility dangerous waste permit application, general information. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Price, S.M.

    1997-09-08

    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.

  13. Boron neutron capture therapy (BNCT) for liver metastasis: therapeutic efficacy in an experimental model

    Energy Technology Data Exchange (ETDEWEB)

    David W. Nigg

    2012-08-01

    Boron neutron capture therapy (BNCT) was proposed for untreatable colorectal liver metastases. The present study evaluates tumor control and potential radiotoxicity of BNCT in an experimental model of liver metastasis. BDIX rats were inoculated with syngeneic colon cancer cells DHD/K12/TRb. Tumor-bearing animals were divided into three groups: BPA–BNCT, boronophenylalanine (BPA) ? neutron irradiation; Beam only, neutron irradiation; Sham, matched manipulation. The total absorbed dose administered with BPA–BNCT was 13 ± 3 Gy in tumor and 9 ± 2 Gy in healthy liver. Three weeks posttreatment, the tumor surface area post-treatment/pre-treatment ratio was 0.46 ± 0.20 for BPA–BNCT, 2.7 ± 1.8 for Beam only and 4.5 ± 3.1 for Sham. The pre-treatment tumor nodule mass of 48 ± 19 mgfell significantly to 19 ± 16 mg for BPA–BNCT, but rose significantly to 140 ± 106 mg for Beam only and to 346 ± 302 mg for Sham. For both end points, the differences between the BPA–BNCT group and each of the other groups were statistically significant (ANOVA). No clinical, macroscopic or histological normal liver radiotoxicity was observed. It is concluded that BPA– BNCT induced a significant remission of experimental colorectal tumor nodules in liver with no contributory liver toxicity.

  14. Biodistribution of phenylboric acid derivative entrapped lipiodol and 4-borono-2-{sup 18}F-fluoro-L-phenylalanine-fructose in GP7TB liver tumor bearing rats for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Liao, A.H. [Department of Biomedical Imaging and Radiological Sciences, National Yang-Ming University, No. 155, Sec. 2, Li-Nong St., Bei-tou, 112 Taipei, Taiwan (China); Chou, F.I. [Institute of Nuclear Engineering and Science, National Tsing-Hua University, Hsinchu, Taiwan (China); Kuo, Y.C. [Department of Biomedical Imaging and Radiological Sciences, National Yang-Ming University, No. 155, Sec. 2, Li-Nong St., Bei-tou, 112 Taipei, Taiwan (China); Department of Radiation Oncology, China Medical University Hospital, Taichung, Taiwan (China); Chen, H.W. [Department of Radiation Oncology and Hospice Center, Mackay Memorial Hospital, Taipei, Taiwan (China); Kai, J.J. [Institute of Nuclear Engineering and Science, National Tsing-Hua University, Hsinchu, Taiwan (China); Chang, C.W. [Department of Nuclear Medicine, Veterans General Hospital, Taipei, Taiwan (China); Chen, F.D. [Department of Biomedical Imaging and Radiological Sciences, National Yang-Ming University, No. 155, Sec. 2, Li-Nong St., Bei-tou, 112 Taipei, Taiwan (China); Hwang, J.J. [Department of Biomedical Imaging and Radiological Sciences, National Yang-Ming University, No. 155, Sec. 2, Li-Nong St., Bei-tou, 112 Taipei, Taiwan (China)], E-mail: jjhwang@ym.edu.tw

    2010-03-15

    A new phenylboric acid derivative entrapped lipiodol (PBAD-lipiodol) was developed as a boron carrier for the boron neutron capture therapy (BNCT) of hepatoma in Taiwan. The biodistribution of both PBAD-lipiodol and BPA-fructose was assayed in GP7TB hepatoma-bearing rat model. The highest uptake of PBAD-lipiodol was found at 2 h post injection. The application of BNCT for the hepatoma treatment in tumor-bearing rats is suggested to be 2-4 h post PBAD-lipiodol injection.

  15. Confirmation of a realistic reactor model for BNCT dosimetry at the TRIGA Mainz

    Energy Technology Data Exchange (ETDEWEB)

    Ziegner, Markus, E-mail: Markus.Ziegner.fl@ait.ac.at [AIT Austrian Institute of Technology GmbH, Vienna A-1220, Austria and Institute of Atomic and Subatomic Physics, Vienna University of Technology, Vienna A-1020 (Austria); Schmitz, Tobias; Hampel, Gabriele [Institut für Kernchemie, Johannes Gutenberg-Universität, Mainz DE-55128 (Germany); Khan, Rustam [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Islamabad PK-44000 (Pakistan); Blaickner, Matthias [AIT Austrian Institute of Technology GmbH, Vienna A-1220 (Austria); Palmans, Hugo [Acoustics and Ionising Radiation Division, National Physical Laboratory, Teddington TW11 0LW, United Kingdom and Medical Physics Group, EBG MedAustron GmbH, Wiener Neustadt A-2700 (Austria); Sharpe, Peter [Acoustics and Ionising Radiation Division, National Physical Laboratory, Teddington TW11 0LW (United Kingdom); Böck, Helmuth [Institute of Atomic and Subatomic Physics, Vienna University of Technology, Vienna A-1020 (Austria)

    2014-11-01

    Purpose: In order to build up a reliable dose monitoring system for boron neutron capture therapy (BNCT) applications at the TRIGA reactor in Mainz, a computer model for the entire reactor was established, simulating the radiation field by means of the Monte Carlo method. The impact of different source definition techniques was compared and the model was validated by experimental fluence and dose determinations. Methods: The depletion calculation code ORIGEN2 was used to compute the burn-up and relevant material composition of each burned fuel element from the day of first reactor operation to its current core. The material composition of the current core was used in a MCNP5 model of the initial core developed earlier. To perform calculations for the region outside the reactor core, the model was expanded to include the thermal column and compared with the previously established ATTILA model. Subsequently, the computational model is simplified in order to reduce the calculation time. Both simulation models are validated by experiments with different setups using alanine dosimetry and gold activation measurements with two different types of phantoms. Results: The MCNP5 simulated neutron spectrum and source strength are found to be in good agreement with the previous ATTILA model whereas the photon production is much lower. Both MCNP5 simulation models predict all experimental dose values with an accuracy of about 5%. The simulations reveal that a Teflon environment favorably reduces the gamma dose component as compared to a polymethyl methacrylate phantom. Conclusions: A computer model for BNCT dosimetry was established, allowing the prediction of dosimetric quantities without further calibration and within a reasonable computation time for clinical applications. The good agreement between the MCNP5 simulations and experiments demonstrates that the ATTILA model overestimates the gamma dose contribution. The detailed model can be used for the planning of structural

  16. Improvement of the boron neutron capture therapy (BNCT) by the previous administration of the histone deacetylase inhibitor sodium butyrate for the treatment of thyroid carcinoma.

    Science.gov (United States)

    Perona, M; Rodríguez, C; Carpano, M; Thomasz, L; Nievas, S; Olivera, M; Thorp, S; Curotto, P; Pozzi, E; Kahl, S; Pisarev, M; Juvenal, G; Dagrosa, A

    2013-08-01

    We have shown that boron neutron capture therapy (BNCT) could be an alternative for the treatment of poorly differentiated thyroid carcinoma (PDTC). Histone deacetylase inhibitors (HDACI) like sodium butyrate (NaB) cause hyperacetylation of histone proteins and show capacity to increase the gamma irradiation effect. The purpose of these studies was to investigate the use of the NaB as a radiosensitizer of the BNCT for PDTC. Follicular thyroid carcinoma cells (WRO) and rat thyroid epithelial cells (FRTL-5) were incubated with 1 mM NaB and then treated with boronophenylalanine ¹⁰BPA (10 μg ¹⁰B ml⁻¹) + neutrons, or with 2, 4-bis (α,β-dihydroxyethyl)-deutero-porphyrin IX ¹⁰BOPP (10 μg ¹⁰B ml⁻¹) + neutrons, or with a neutron beam alone. The cells were irradiated in the thermal column facility of the RA-3 reactor (flux = (1.0 ± 0.1) × 10¹⁰ n cm⁻² s⁻¹). Cell survival decreased as a function of the physical absorbed dose in both cell lines. Moreover, the addition of NaB decreased cell survival (p < 0.05) in WRO cells incubated with both boron compounds. NaB increased the percentage of necrotic and apoptotic cells in both BNCT groups (p < 0.05). An accumulation of cells in G2/M phase at 24 h was observed for all the irradiated groups and the addition of NaB increased this percentage. Biodistribution studies of BPA (350 mg kg⁻¹ body weight) 24 h after NaB injection were performed. The in vivo studies showed that NaB treatment increases the amount of boron in the tumor at 2-h post-BPA injection (p < 0.01). We conclude that NaB could be used as a radiosensitizer for the treatment of thyroid carcinoma by BNCT.

  17. A design study for an accelerator-based epithermal neutron beam for BNCT.

    Science.gov (United States)

    Allen, D A; Beynon, T D

    1995-05-01

    An achievable design concept for a boron neutron capture therapy (BNCT) facility, based on a high-current, low-energy proton accelerator, is described. Neutrons are produced within a thick natural lithium target, under bombardment from protons with an initial energy between 2.5 and 3.0 MeV. The proton current will be up to 10 mA. After gamma-ray filtering, the neutrons are partially moderated to epithermal energies within a heavy-water moderator, poisoned with 6Li to remove thermal neutrons. Monte Carlo modelling has been used to predict system performance in terms of neutron fluence rate and neutron and gamma-ray dose at the patient position. The relationship between the system performance and key parameters, such as proton energy, moderator depth and 6Li concentration, has been investigated. With a proton current of 10 mA, the facility is capable of providing a therapy beam with a useful neutron fluence rate of 10(9) cm-2 s-1 and a neutron dose per unit fluence of less than 6 x 10(-13) Gy cm2, with a gamma-ray contamination of the therapy beam of about 10(-13) Gy cm2.

  18. 40 CFR 60.730 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ... Performance for Calciners and Dryers in Mineral Industries § 60.730 Applicability and designation of affected facility. (a) The affected facility to which the provisions of this subpart apply is each calciner...

  19. A micro-PET/CT approach using O-(2-[{sup 18}F]fluoroethyl)-L-tyrosine in an experimental animal model of F98 glioma for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Menichetti, L., E-mail: luca.menichetti@ifc.cnr.it [CNR Institute of Clinical Physiology, Pisa (Italy); Petroni, D.; Panetta, D. [CNR Institute of Clinical Physiology, Pisa (Italy); Burchielli, S. [Fondazione CNR/Regione Toscana G. Monasterio, Pisa (Italy); Bortolussi, Silva [Dept. Theoretical and Nuclear Physics, University of Pavia, Pavia (Italy); Matteucci, M. [Scuola Superiore Sant' Anna, Pisa (Italy); Pascali, G.; Del Turco, S. [CNR Institute of Clinical Physiology, Pisa (Italy); Del Guerra, A. [Department of Physics, University of Pisa, Pisa (Italy); Altieri, S. [Dept. Theoretical and Nuclear Physics, University of Pavia, Pavia (Italy); Salvadori, P.A. [CNR Institute of Clinical Physiology, Pisa (Italy)

    2011-12-15

    The present study focuses on a micro-PET/CT application to be used for experimental Boron Neutron Capture Therapy (BNCT), which integrates, in the same frame, micro-CT derived anatomy and PET radiotracer distribution. Preliminary results have demonstrated that {sup 18}F-fluoroethyl-tyrosine (FET)/PET allows the identification of the extent of cerebral lesions in F98 tumor bearing rat. Neutron autoradiography and {alpha}-spectrometry on axial tissues slices confirmed the tumor localization and extraction, after the administration of fructose-boronophenylalanine (BPA). Therefore, FET-PET approach can be used to assess the transport, the net influx, and the accumulation of FET, as an aromatic amino acid analog of BPA, in experimental animal model. Coregistered micro-CT images allowed the accurate morphological localization of the radiotracer distribution and its potential use for experimental BNCT.

  20. Potential of boron neutron capture therapy (BNCT) for malignant peripheral nerve sheath tumors (MPNST).

    Science.gov (United States)

    Fujimoto, Takuya; Andoh, Tooru; Sudo, Tamotsu; Fujita, Ikuo; Fukase, Naomasa; Takeuchi, Tamotsu; Sonobe, Hiroshi; Inoue, Masayoshi; Hirose, Tkanori; Sakuma, Toshiko; Moritake, Hiroshi; Sugimoto, Tohru; Kawamoto, Teruya; Fukumori, Yoshinobu; Yamamoto, Satomi; Atagi, Shinji; Sakurai, Yoshinori; Kurosaka, Masahiro; Ono, Koji; Ichikawa, Hideki; Suzuki, Minoru

    2015-12-01

    Malignant peripheral nerve sheath tumors (MPNST) are relatively rare neoplasms with poor prognosis. At present there is no effective treatment for MPNST other than surgical resection. Nonetheless, the anti-tumor effect of boron neutron capture therapy (BNCT) was recently demonstrated in two patients with MPNST. Subsequently, tumor-bearing nude mice subcutaneously transplanted with a human MPNST cell line were injected with p-borono-L-phenylalanine (L-BPA) and subjected to BNCT. Pathological studies then revealed that the MPNST cells were selectively destroyed by BNCT.

  1. Correlation of clinical outcome to the estimated radiation dose from Boron Neutron Capture Therapy (BNCT)

    Energy Technology Data Exchange (ETDEWEB)

    Chadha, M. [Beth Israel Medical Center, NY (United States). Dept. of Radiation Oncology; Coderre, J.A.; Chanana, A.D. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1996-12-31

    A phase I/II trial delivering a single fraction of BNCT using p-Boronophenylalanine-Fructose and epithermal neutrons at the the Brookhaven Medical Research Reactor was initiated in September 1994. The primary endpiont of the study was to evaluate the feasibility and safety of a given BNCT dose. The clinical outcome of the disease was a secondary endpoint of the study. The objective of this paper is to evaluate the correlation of the clinical outcome of patients to the estimated radiation dose from BNCT.

  2. SCARF - The Swarm Satellite Constellation Application and Research Facility

    DEFF Research Database (Denmark)

    Olsen, Nils

    2014-01-01

    Swarm, a three-satellite constellation to study the dynamics of the Earth's magnetic field and its interactions with the Earth system, has been launched in November 2013. The objective of the Swarm mission is to provide the best ever survey of the geomagnetic field and its temporal evolution, which...... will bring new insights into the Earth system by improving our understanding of the Earth's interior and environment. In order to take advantage of the unique constellation aspect of Swarm, considerably advanced data analysis tools have been developed. Scientific users will also benefit significantly from...... derived products, the so-called Level-2 products, that take into account the features of the constellation. The Swarm SCARF (Satellite Constellation Application and Research Facility), a consortium of several research institutions, has been established with the goal of deriving Level-2 products...

  3. Application of chlorine dioxide as an oilfield facilities treatment fluid

    Energy Technology Data Exchange (ETDEWEB)

    Romaine, J.; Strawser, T.G.; Knippers, M.L.

    1995-11-01

    Both mechanical and chemical treatments are used to clean water flood injection distribution systems whose efficiency has been reduced as a result of plugging material such as iron sulfide sludge. Most mechanical treatments rely on uniform line diameter to be effective, while chemical treatments require good contact with the plugging material for efficient removal. This paper describes the design and operation of a new innovative application using chlorine dioxide for the removal of iron sulfide sludge from water flood injection distribution systems. This technology has evolved from the use of chlorine dioxide in well stimulation applications. The use of chlorine dioxide for continuous treatment of injection brines will also be discussed. Exxon USA`s Hartzog Draw facility in Gillette, Wyoming was the site for the application described. 4,500 barrels of chlorine dioxide was pumped in three phases to clean sixty-six miles of the water flood distribution system. Results indicate that chlorine dioxide was effective in cleaning the well guard screens, the injection lines, frac tanks used to collect the treatment fluids and the injection wells.

  4. 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.

  5. Voxel model in BNCT treatment planning: performance analysis and improvements

    Science.gov (United States)

    González, Sara J.; Carando, Daniel G.; Santa Cruz, Gustavo A.; Zamenhof, Robert G.

    2005-02-01

    In recent years, many efforts have been made to study the performance of treatment planning systems in deriving an accurate dosimetry of the complex radiation fields involved in boron neutron capture therapy (BNCT). The computational model of the patient's anatomy is one of the main factors involved in this subject. This work presents a detailed analysis of the performance of the 1 cm based voxel reconstruction approach. First, a new and improved material assignment algorithm implemented in NCTPlan treatment planning system for BNCT is described. Based on previous works, the performances of the 1 cm based voxel methods used in the MacNCTPlan and NCTPlan treatment planning systems are compared by standard simulation tests. In addition, the NCTPlan voxel model is benchmarked against in-phantom physical dosimetry of the RA-6 reactor of Argentina. This investigation shows the 1 cm resolution to be accurate enough for all reported tests, even in the extreme cases such as a parallelepiped phantom irradiated through one of its sharp edges. This accuracy can be degraded at very shallow depths in which, to improve the estimates, the anatomy images need to be positioned in a suitable way. Rules for this positioning are presented. The skin is considered one of the organs at risk in all BNCT treatments and, in the particular case of cutaneous melanoma of extremities, limits the delivered dose to the patient. Therefore, the performance of the voxel technique is deeply analysed in these shallow regions. A theoretical analysis is carried out to assess the distortion caused by homogenization and material percentage rounding processes. Then, a new strategy for the treatment of surface voxels is proposed and tested using two different irradiation problems. For a parallelepiped phantom perpendicularly irradiated with a 5 keV neutron source, the large thermal neutron fluence deviation present at shallow depths (from 54% at 0 mm depth to 5% at 4 mm depth) is reduced to 2% on average

  6. INEEL BNCT research program. Annual report, January 1, 1996--December 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R. [ed.

    1997-04-01

    This report is a summary of the progress and research produced for the Idaho National Engineering and Environmental Laboratory (INEEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1996. Contributions from the individual investigators about their projects are included, specifically, physics: treatment planning software, real-time neutron beam measurement dosimetry, measurement of the Finnish research reactor epithermal neutron spectrum, BNCT accelerator technology; and chemistry: analysis of biological samples and preparation of {sup 10}B enriched decaborane.

  7. Complexion of Boric Acid with 2-Deoxy-D-glucose (DG) as a novel boron carrier for BNCT

    OpenAIRE

    Akan, Zafer; Demiroglu, Hasan; Avcibasi, Ugur; Oto, Gokhan; Ozdemir, Hulya; Deniz, Sabahattin; Basak, Ali Sadi

    2014-01-01

    Objective: Boron neutron capture therapy (BNCT) is an intensive research area for cancer researchers. Especially the side effects and inabilities of conventional therapies in some cases, directs researchers to find out a new cancer therapy methods such as BNCT. One of three important problem of BNCT is targeting of boron to tumor tissue. Borono Phenyl Alanine (BPA) and Borono Sodium Borocaptate (BSH) are already using in clinical studies as boron carriers. New boron carriers are searching fo...

  8. INEL BNCT research program, July--August 1992

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R.

    1992-10-01

    This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

  9. INEL BNCT Research Program, May/June 1992

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R.

    1992-09-01

    This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (IBPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

  10. INEL BNCT Research Program, March/April 1992

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R.

    1992-09-01

    This report presents summaries for two months of current research for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murino screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronopheoylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

  11. INEL BNCT Research Program, September--October 1992

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R.

    1992-12-01

    This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotain. carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophonylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

  12. INEL BNCT Research Program, January/February 1993

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R. [ed.

    1993-04-01

    This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

  13. 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

  14. Boron neutron capture therapy (BNCT) for glioblastoma multiforme using the epithermal neutron beam at the Brookhaven Medical Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Capala, J. [Brookhaven National Lab., Upton, NY (United States); Diaz, A.Z.; Chadha, M. [Univ. Hospital, State Univ. of New York, NY (United States)] [and others

    1997-12-31

    The abstract describes evaluation of boron neutron capture therapy (BNCT) for two groups of glioblastoma multiforme patients. From September 1994 to February 1996 15 patients have been treated. In September 1997 another 34 patients were examined. Authors determined a safe starting dose for BNCT using epithermal neutrons and BPA-F. They have also evaluated adverse effects of BNCT at this starting dose. Therapeutic effectiveness of this starting dose has been evaluated. No significant side effects from BPA-F infusion or BNCT treatment were observed in normal brains.

  15. 42 CFR 488.56 - Temporary waivers applicable to skilled nursing facilities.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Temporary waivers applicable to skilled nursing... PROCEDURES Special Requirements § 488.56 Temporary waivers applicable to skilled nursing facilities. (a... skilled nursing facility to engage the services of a registered nurse more than 40 hours a week,...

  16. 30 CFR 75.1712-8 - Application for waiver of location requirements for underground sanitary facilities.

    Science.gov (United States)

    2010-07-01

    ... underground sanitary facilities. Applications for waivers of the location requirements of § 75.1712-6 shall be... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Application for waiver of location requirements for underground sanitary facilities. 75.1712-8 Section 75.1712-8 Mineral Resources MINE SAFETY...

  17. 76 FR 65544 - Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities

    Science.gov (United States)

    2011-10-21

    ... issuance of the guide (74 FR 36780). The comment period closed on September 21, 2009. The staff's responses... COMMISSION Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities... Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities.'' This...

  18. Monte Carlo model of the Studsvik BNCT clinical beam: description and validation.

    Science.gov (United States)

    Giusti, Valerio; Munck af Rosenschöld, Per M; Sköld, Kurt; Montagnini, Bruno; Capala, Jacek

    2003-12-01

    The neutron beam at the Studsvik facility for boron neutron capture therapy (BNCT) and the validation of the related computational model developed for the MCNP-4B Monte Carlo code are presented. Several measurements performed at the epithermal neutron port used for clinical trials have been made in order to validate the Monte Carlo computational model. The good general agreement between the MCNP calculations and the experimental results has provided an adequate check of the calculation procedure. In particular, at the nominal reactor power of 1 MW, the calculated in-air epithermal neutron flux in the energy interval between 0.4 eV-10 keV is 3.24 x 10(9) n cm(-2) s(-1) (+/- 1.2% 1 std. dev.) while the measured value is 3.30 x 10(9) n cm(-20 s(-1) (+/- 5.0% 1 std. dev.). Furthermore, the calculated in-phantom thermal neutron flux, equal to 6.43 x 10(9) n cm(-2) s(-1) (+/- 1.0% 1 std. dev.), and the corresponding measured value of 6.33 X 10(9) n cm(-2) s(-1) (+/- 5.3% 1 std. dev.) agree within their respective uncertainties. The only statistically significant disagreement is a discrepancy of 39% between the MCNP calculations of the in-air photon kerma and the corresponding experimental value. Despite this, a quite acceptable overall in-phantom beam performance was obtained, with a maximum value of the therapeutic ratio (the ratio between the local tumor dose and the maximum healthy tissue dose) equal to 6.7. The described MCNP model of the Studsvik facility has been deemed adequate to evaluate further improvements in the beam design as well as to plan experimental work.

  19. Biodistribution of sodium borocaptate (BSH) for boron neutron capture therapy (BNCT) in an oral cancer model.

    Science.gov (United States)

    Garabalino, Marcela A; Heber, Elisa M; Monti Hughes, Andrea; González, Sara J; Molinari, Ana J; Pozzi, Emiliano C C; Nievas, Susana; Itoiz, Maria E; Aromando, Romina F; Nigg, David W; Bauer, William; Trivillin, Verónica A; Schwint, Amanda E

    2013-08-01

    Boron neutron capture therapy (BNCT) is based on selective accumulation of ¹⁰B carriers in tumor followed by neutron irradiation. We previously proved the therapeutic success of BNCT mediated by the boron compounds boronophenylalanine and sodium decahydrodecaborate (GB-10) in the hamster cheek pouch oral cancer model. Based on the clinical relevance of the boron carrier sodium borocaptate (BSH) and the knowledge that the most effective way to optimize BNCT is to improve tumor boron targeting, the specific aim of this study was to perform biodistribution studies of BSH in the hamster cheek pouch oral cancer model and evaluate the feasibility of BNCT mediated by BSH at nuclear reactor RA-3. The general aim of these studies is to contribute to the knowledge of BNCT radiobiology and optimize BNCT for head and neck cancer. Sodium borocaptate (50 mg ¹⁰B/kg) was administered to tumor-bearing hamsters. Groups of 3-5 animals were killed humanely at nine time-points, 3-12 h post-administration. Samples of blood, tumor, precancerous pouch tissue, normal pouch tissue and other clinically relevant normal tissues were processed for boron measurement by optic emission spectroscopy. Tumor boron concentration peaked to therapeutically useful boron concentration values of 24-35 ppm. The boron concentration ratio tumor/normal pouch tissue ranged from 1.1 to 1.8. Pharmacokinetic curves showed that the optimum interval between BSH administration and neutron irradiation was 7-11 h. It is concluded that BNCT mediated by BSH at nuclear reactor RA-3 would be feasible.

  20. Spectromicroscopy of boron for the optimization of boron neutron capture therapy (BNCT) for cancer

    Science.gov (United States)

    Gilbert, B.; Redondo, J.; Baudat, P.-A.; Lorusso, G. F.; Andres, R.; Van Meir, E. G.; Brunet, J.-F.; Hamou, M.-F.; Suda, T.; Mercanti, Delio; Ciotti, M. Teresa; Droubay, T. C.; Tonner, B. P.; Perfetti, P.; Margaritondo, M.; DeStasio, Gelsomina

    1998-10-01

    We used synchrotron spectromicroscopy to study the microscopic distribution of boron in rat brain tumour and healthy tissue in the field of boron neutron capture therapy (BNCT). The success of this experimental cancer therapy depends on the preferential uptake of ? in tumour cells after injection of a boron compound (in our case ?, or BSH). With the Mephisto (microscope à emission de photoélectrons par illumination synchrotronique de type onduleur) spectromicroscope, high-magnification imaging and chemical analysis was performed on brain tissue sections from a rat carrying an implanted brain tumour and the results were compared with inductively coupled plasma-atomic emission spectroscopy (ICP-AES) detection of boron in bulk tissue. Boron was found to have been taken up more favourably by regions of tumour rather than healthy tissue, but the resulting boron distribution in the tumour was inhomogeneous. The results demonstrate that Mephisto can perform microchemical analysis of tissue sections, detect and localize the presence of boron with submicron spatial resolution. The application of this technique to boron in brain tissue can therefore be used to evaluate the current efforts to optimize BNC therapy.

  1. Spectromicroscopy of boron for the optimization of boron neutron capture therapy (BNCT) for cancer

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, B.; Redondo, J.; Baudat, P-A. [Institut de Physique Appliquee, Ecole Polytechnique Federale, Lausanne (Switzerland)] [and others

    1998-10-07

    We used synchrotron spectromicroscopy to study the microscopic distribution of boron in rat brain tumour and healthy tissue in the field of boron neutron capture therapy (BNCT). The success of this experimental cancer therapy depends on the preferential uptake of {sup 10}B in tumour cells after injection of a boron compound (in our case B{sub 12}H{sub 11}SH, or BSH). With the Mephisto (microscope a emission de photoelectrons par illumination synchrotronique de type onduleur) spectromicroscope, high-magnification imaging and chemical analysis was performed on brain tissue sections from a rat carrying an implanted brain tumour and the results were compared with inductively coupled plasma-atomic emission spectroscopy (ICP-AES) detection of boron in bulk tissue. Boron was found to have been taken up more favourably by regions of tumour rather than healthy tissue, but the resulting boron distribution in the tumour was inhomogeneous. The results demonstrate that Mephisto can perform microchemical analysis of tissue sections, detect and localize the presence of boron with submicron spatial resolution. The application of this technique to boron in brain tissue can therefore be used to evaluate the current efforts to optimize BNC therapy. (author)

  2. 24 CFR 960.205 - Drug use by applicants: Obtaining information from drug treatment facility.

    Science.gov (United States)

    2010-04-01

    ... information from drug treatment facility. 960.205 Section 960.205 Housing and Urban Development Regulations... Admission § 960.205 Drug use by applicants: Obtaining information from drug treatment facility. (a) Purpose. This section addresses a PHA's authority to request and obtain information from drug abuse...

  3. Neutron-photon mixed field dosimetry by TLD-700 glow curve analysis and its implementation in dose monitoring for Boron Neutron Capture Therapy (BNCT) treatments

    Energy Technology Data Exchange (ETDEWEB)

    Boggio, E. F.; Longhino, J. M. [Centro Atomico Bariloche, Departamento de Fisica de Reactores y Radiaciones / CNEA, Av. E. Bustillo Km 9.5, R8402AGP San Carlos de Bariloche (Argentina); Andres, P. A., E-mail: efboggio@cab.cnea.gov.ar [Centro Atomico Bariloche, Division Proteccion Radiologica / CNEA, Av. E. Bustillo Km 9.5, R8402AGP San Carlos de Bariloche (Argentina)

    2015-10-15

    BNCT is a cancerous cells selective, non-conventional radiotherapy modality to treat malignant tumors such as glioblastoma, melanoma and recurrent head and neck cancer. It consists of a two-step procedure: first, the patient is injected with a tumor localizing drug containing a non-radioactive isotope (Boron-10) with high slow neutron capture cross-section. In a second step, the patient is irradiated with neutrons, which are absorbed by the Boron-10 agent with the subsequently nuclear reaction B- 10(n,a)Li-7, thereby resulting in dose at cellular level due to the high-Let particles. The neutron fields suitable for BNCT are characterized by high neutron fluxes and low gamma dose. Determination of each component is not an easy task, especially when the volume of measurement is quite small or inaccessible for a miniature ionization chamber, for example. A method of measuring the photon and slow neutron dose(mainly by N-14 and B-10) from the glow curve (GC) analysis of a single {sup 7}LiF thermoluminescence detector is evaluated. This method was suggested by the group headed by Dr. Grazia Gambarini. The dosemeters used were TLD-600 ({sup 6}LiF:Mg,Ti with 95.6% {sup 6}Li) and TLD-700 ({sup 7}LiF:Mg,Ti with 99.9% {sup 7}LiF) from Harshaw. Photon dose measurement using the GC analysis method with TLD-700 in mixed fields requires the relation of the two main peaks of a TLD-600 GC shape obtained from an exposition to the same neutron field, and a photon calibrated GC with TLD-700. The requirements for slow neutron dose measurements are similar. In order to properly apply the GC analysis method at the Ra-6 Research Reactor BNCT facility, measurements were carried out in a standard water phantom, fully characterized on the BNCT beam by conventional techniques (activation detectors and paired ionization chambers technique). Next, the method was implemented in whole body dose monitoring of a patient undergoing a BNCT treatment, using a Bo MAb (Bottle Manikin Absorption) phantom

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

    Science.gov (United States)

    2013-07-05

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

  5. Characterisation of an accelerator-based neutron source for BNCT versus beam energy

    CERN Document Server

    Agosteo, S; D'Errico, F; Nath, R; Tinti, R

    2002-01-01

    Neutron capture in sup 1 sup 0 B produces energetic alpha particles that have a high linear energy transfer in tissue. This results in higher cell killing and a higher relative biological effectiveness compared to photons. Using suitably designed boron compounds which preferentially localize in cancerous cells instead of healthy tissues, boron neutron capture therapy (BNCT) has the potential of providing a higher tumor cure rate within minimal toxicity to normal tissues. This clinical approach requires a thermal neutron source, generally a nuclear reactor, with a fluence rate sufficient to deliver tumorcidal doses within a reasonable treatment time (minutes). Thermal neutrons do not penetrate deeply in tissue, therefore BNCT is limited to lesions which are either superficial or otherwise accessible. In this work, we investigate the feasibility of an accelerator-based thermal neutron source for the BNCT of skin melanomas. The source was designed via MCNP Monte Carlo simulations of the thermalization of a fast ...

  6. BNCT of 3 cases of spontaneous head and neck cancer in feline patients

    Energy Technology Data Exchange (ETDEWEB)

    Rao, M.; Trivillin, V.A.; Heber, E.M.; Angeles Cantarelli, Maria de los; Itoiz, M.E.; Nigg, D.W.; Rebagliati, R.J.; Batistoni, Daniel; Schwint, A.E. E-mail: schwint@cnea.gov.ar

    2004-11-01

    Having demonstrated BPA-BNCT induced control of experimental squamous cell carcinomas (SCC) of the hamster cheek pouch mucosa with no damage to normal tissue we explored the feasibility and safety of treating spontaneous head and neck tumors, with particular focus on SCC, of terminal feline patients with low dose BPA-BNCT employing the thermal beam of the RA-1 Reactor within a preclinical context. The biodistribution studies showed that, in all three cases evaluated, BPA delivered absolute boron values to tumor in the range that proved therapeutically useful in the experimental model of SCC. BPA-BNCT studies showed no radiotoxic effects, partial tumor control in terms of impaired growth and partial necrosis, an improvement in clinical condition and prolonged survival beyond the terminal condition of the feline patients at the time of recruitment.

  7. Subcellular boron and fluorine distributions with SIMS ion microscopy in BNCT and cancer research

    Energy Technology Data Exchange (ETDEWEB)

    Subhash Chandra

    2008-05-30

    The development of a secondary ion mass spectrometry (SIMS) based technique of Ion Microscopy in boron neutron capture therapy (BNCT) was the main goal of this project, so that one can study the subcellular location of boron-10 atoms and their partitioning between the normal and cancerous tissue. This information is fundamental for the screening of boronated drugs appropriate for neutron capture therapy of cancer. Our studies at Cornell concentrated mainly on studies of glioblastoma multiforme (GBM). The early years of the grant were dedicated to the development of cryogenic methods and correlative microscopic approaches so that a reliable subcellular analysis of boron-10 atoms can be made with SIMS. In later years SIMS was applied to animal models and human tissues of GBM for studying the efficacy of potential boronated agents in BNCT. Under this grant the SIMS program at Cornell attained a new level of excellence and collaborative SIMS studies were published with leading BNCT researchers in the U.S.

  8. Boron neutron capture therapy (BNCT): implications of neutron beam and boron compound characteristics.

    Science.gov (United States)

    Wheeler, F J; Nigg, D W; Capala, J; Watkins, P R; Vroegindeweij, C; Auterinen, I; Seppälä, T; Bleuel, D

    1999-07-01

    The potential efficacy of boron neutron capture therapy (BNCT) for malignant glioma is a significant function of epithermal-neutron beam biophysical characteristics as well as boron compound biodistribution characteristics. Monte Carlo analyses were performed to evaluate the relative significance of these factors on theoretical tumor control using a standard model. The existing, well-characterized epithermal-neutron sources at the Brookhaven Medical Research Reactor (BMRR), the Petten High Flux Reactor (HFR), and the Finnish Research Reactor (FiR-1) were compared. Results for a realistic accelerator design by the E. O. Lawrence Berkeley National Laboratory (LBL) are also compared. Also the characteristics of the compound p-Boronophenylaline Fructose (BPA-F) and a hypothetical next-generation compound were used in a comparison of the BMRR and a hypothetical improved reactor. All components of dose induced by an external epithermal-neutron beam fall off quite rapidly with depth in tissue. Delivery of dose to greater depths is limited by the healthy-tissue tolerance and a reduction in the hydrogen-recoil and incident gamma dose allow for longer irradiation and greater dose at a depth. Dose at depth can also be increased with a beam that has higher neutron energy (without too high a recoil dose) and a more forward peaked angular distribution. Of the existing facilities, the FiR-1 beam has the better quality (lower hydrogen-recoil and incident gamma dose) and a penetrating neutron spectrum and was found to deliver a higher value of Tumor Control Probability (TCP) than other existing beams at shallow depth. The greater forwardness and penetration of the HFR the FiR-1 at greater depths. The hypothetical reactor and accelerator beams outperform at both shallow and greater depths. In all cases, the hypothetical compound provides a significant improvement in efficacy but it is shown that the full benefit of improved compound is not realized until the neutron beam is fully

  9. Calibration and Testing Facility for Silicon Microseismometers for Planetary Applications

    Science.gov (United States)

    Irshad, Ranah; Teanby, N. A.; Calcutt, S. B.; Pike, W. T.; Bowles, N. E.; Flynn, W.; Temple, J. M.

    2009-09-01

    A calibration and test facility has been developed for microseismometers designed to measure seismic data on planetary or lunar surfaces. The set-up allows the testing of microseismometers under vacuum, at temperatures from 300K down to 70K. In addition, the facility is designed for calibration of the microseismometers using a commercial broad-band seismometer as a reference, that remains at a constant temperature of 300K. The facility consists of a solid granite block which acts as a support for both the commercial seismometer and the microseismometers to be tested. The entire set-up is isolated from ambient seismic noise by a 10 ton seismic mass and pneumatic isolators that are part of an existing calibration facility in a class 100 cleanroom at Oxford. The commercial seismometer sits on top of the horizontal granite slab and the microseismometers are mounted directly opposite, underneath the granite, on thermally isolated supports in a vacuum chamber and surrounded by a radiative cooling system. A small oscillating mass will be coupled to the granite in such a way as to provide identical vibrations to both seismometers. The performance of the microseismometers may thus be characterised as a function of temperature and pressure. The facility also incorporates a dual fibre-optic laser vibrometer system which can measure the surface vibrations of the microseismometer accommodation relative to the base of the granite. This allows the characterisation of the mechanical transfer function of the thermally isolating legs supporting the microseismometers, as well as the absolute motion recorded on each instrument. This work is supported by the STFC.

  10. Might iodomethyl-{alpha}-tyrosine be a surrogate for BPA in BNCT?

    Energy Technology Data Exchange (ETDEWEB)

    Miura, Michiko; Micca, P.L.; Nawrocky, M.M.; Slatkin, D.N.

    1996-12-31

    A single-photon emission computed tomography [SPECT] imaging agent that is an analogue of a boron carrier for boron neutron-capture therapy [BNCT] of cerebral gliomas would be useful for assessing the kinetics of boron uptake in tumors and in the surrounding brain tissues noninvasively. BNCT is based on the interaction of thermalized neutrons with {sup 10}B nuclei in the targeted tumor. For BNCT of brain tumors, it is crucial that {sup 10}B concentrations in radiosensitive regions of the brain be minimal since malignant cells and vital brain tissues are often inter-mingled at the margins of the tumor. Currently, boronophenylalanine [BPA]-mediated BNCT is undergoing preliminary clinical study for postoperative radiotherapy of glioblastorna multiforme at Brookhaven National Laboratory. Investigators in Japan are developing {sup 18}F-fluoroboronophenylaianine [FBPA] as a positron {sup 18}F (T{sub 1/2} = 110 min), which is usually emission tomography [PET] surrogate for BPA. generated at a cyclotron dedicated to PET, is generally a minimally perturbing substitute for the 2-H on the aromatic ring because of its small size and the strong covalent bond it forms with carbon. However, SPECT has potential advantages over PET: (1) SPECT is clinically more widely available at lower cost; (2) most radioisotopes for the synthesis of SPECT agents can be purchased; (3) SPECT is less difficult to implement. It is thought that the quality of images derived from the two techniques would each be sufficiently informative for BNCT treatment planning purposes, provided that the SPECT and PET agents being considered were both pharmacokinetic surrogates for BPA. This study evaluated the use of {sup 123}I alpha methyltyrosine as a surrogate for BPA in BNCT.

  11. 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.

  12. Benefits of explosive cutting for nuclear-facility applications

    Energy Technology Data Exchange (ETDEWEB)

    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. (DLC)

  13. Boron biodistribution for BNCT in the hamster cheek pouch oral cancer model: combined administration of BSH and BPA.

    Science.gov (United States)

    Garabalino, Marcela A; Heber, Elisa M; Monti Hughes, Andrea; Pozzi, Emiliano C C; Molinari, Ana J; Nigg, David W; Bauer, William; Trivillin, Verónica A; Schwint, Amanda E

    2014-06-01

    Sodium mercaptoundecahydro-closo-dodecaborate (BSH) is being investigated clinically for BNCT. We examined the biodistribution of BSH and BPA administered jointly in different proportions in the hamster cheek pouch oral cancer model. The 3 assayed protocols were non-toxic, and showed preferential tumor boron uptake versus precancerous and normal tissue and therapeutic tumor boron concentration values (70-85ppm). All 3 protocols warrant assessment in BNCT studies to contribute to the knowledge of (BSH+BPA)-BNCT radiobiology for head and neck cancer and optimize therapeutic efficacy.

  14. Application for the On-line Isotope Mass Separator ISOLDE Facility: the Target Heater

    CERN Document Server

    Sánchez-Conejo, Jorge

    2003-01-01

    The purpose of the Heater Application is to heat and cool the target and line used on the On-Line Isotope Mass Separator ISOLDE facility up to a desired temperature selected by the user. The application has been developed in Java, making use of the Java Development Kit 1.4 and the PS Java environment.

  15. Application for the On-line Isotope Mass Separator ISOLDE Facility: the Mass Scan

    CERN Document Server

    Sánchez-Conejo, Jorge

    2003-01-01

    The purpose of the Mass Scan Application is to scan the mass of the ion beam that passes through the GPS (General Purpose Separator) on the On-Line Isotope Mass Separator ISOLDE facility. The application has been developed in Java, making use of the Java Development Kit 1.4 and the PS Java environment.

  16. Synthesis and evaluation of boron folates for Boron-Neutron-Capture-Therapy (BNCT)

    Energy Technology Data Exchange (ETDEWEB)

    Kettenbach, Kathrin; Schieferstein, Hanno; Grunewald, Catrin; Hampel, Gabriele; Schuetz, Christian L. [Mainz Univ. (Germany). Inst. of Nuclear Chemistry; Iffland, Dorothee; Bings, Nicolas H. [Mainz Univ. (Germany). Inst. of Inorganic Chemistry and Analytical Chemistry; Reffert, Laura M. [Hannover Medical School (Germany). Radiopharmaceutical Chemistry; Ross, Tobias L. [Mainz Univ. (Germany). Inst. of Nuclear Chemistry; Hannover Medical School (Germany). Radiopharmaceutical Chemistry

    2015-07-01

    Boron neutron capture therapy (BNCT) employs {sup 10}B-pharmaceuticals administered for the treatment of malignancies, and subsequently irradiated with thermal neutrons. So far, clinical established pharmaceuticals like boron phenylalanine (BPA) or sodium boron mercaptate (BSH) use imperfect (BPA) or passive (BSH) targeting for accumulation at target sites. Due to the need of a selective transportation of boron drugs into cancer cells and sparing healthy tissues, we combined the BNCT approach with the specific and effective folate receptor (FR) targeting concept. The FR is overexpressed on many human carcinomas and provides a selective and specific target for molecular imaging as well as for tumor therapy. We synthesized and characterized a carborane-folate as well as a BSH-folate to study their in vitro characteristics and their potential as new boron-carriers for BNCT. Uptake studies were carried out using human KB cells showing a significant increase of the boron content in cells and demonstrating the successful combination of active FR-targeting and BNCT.

  17. 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.

  18. A methodology for assessing computer software applicability to inventory and facility management

    OpenAIRE

    Paul, Debashis

    1989-01-01

    Computer applications have become popular and widespread in architecture and other related fields. While the architect uses a computer for design and construction of a building, the user takes the advantage of computer for maintenance of the building. Inventory and facility management are two such fields where computer applications have become predominant. The project has investigated the use and application of different commercially available computer software in the above men...

  19. 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).

  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

    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.

  2. A clinical trial protocol for second line treatment of malignant brain tumors with BNCT at University of Tsukuba

    Energy Technology Data Exchange (ETDEWEB)

    Aiyama, H. [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan); Nakai, K., E-mail: knakai@Neurosurg-tsukuba.com [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan); Yamamoto, T. [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan)] [Department of Radiation Oncology, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan); Nariai, T. [Department of Neurosurgery, Tokyo Medical and Dental University, 1-5-45 Yushima, Bunkyouku (Japan); Kumada, H. [Department of Radiation Oncology, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan); Ishikawa, E. [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan); Isobe, T. [Department of Radiation Oncology, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan); Endo, K.; Takada, T.; Yoshida, F.; Shibata, Y.; Matsumura, A. [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, 1-1-1 Tennodai, Tsukuba (Japan)

    2011-12-15

    We have evaluated the efficacy and safety of boron neutron capture therapy (BNCT) for recurrent glioma and malignant brain tumor using a new protocol. One of the two patients enrolled in this trial is a man with recurrent glioblastoma and the other is a woman with anaplastic meningioma. Both are still alive and no severe adverse events have been observed. Our findings suggest that NCT will be safe as a palliative therapy for malignant brain tumors. - Highlights: Black-Right-Pointing-Pointer Boron neutron capture therapy (BNCT) for recurrent glioma and malignant brain tumor. Black-Right-Pointing-Pointer Two cases with recurrent glioblastoma and anaplastic meningioma. Black-Right-Pointing-Pointer No severe adverse events have been observed using BNCT. Black-Right-Pointing-Pointer BNCT has a possibility of a safe palliative therapy for malignant brain tumors.

  3. Study on the characterization of the neutron radiography facility in HANARO for two-phase flow research

    Energy Technology Data Exchange (ETDEWEB)

    Lim, I. C.; Seo, C. G.; Jeong, J. H.; Lee, B. H.; Choi, Y. S

    2001-01-01

    For the application of dynamic neutron radiography to the two-phase flow research using HANARO, several experimental items to which the radiography technique is beneficial were identified through the review of the outputs from the related researches and the discussions with experts. Also, the investigation of the equipments including the beam port, camera and converter was made and a hardware and a software for image processing were equipped. It was confirmed that the calibration curve for the attenuation of neutron beam in fluid which is required for the two-phase flow experiment could be obtained by the computer code calculation. Based on the investigation results on the equipment and the results from the measurement of BNCT beam characteristics, a high speed camera and an image intensifier will be purchased. Then, the high speed dynamic neutron radiography facility for two-phase flow experiments will be fully equipped.

  4. 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

  5. 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.

  6. RAFT-HDA Chemistry - Conception, Development and Application of a Facile Tool for Precision Macromolecular Engineering

    OpenAIRE

    Inglis, Andrew

    2010-01-01

    The conceptualization, development and application of the herein named RAFT-HDA Chemistry is reported. This chemistry is presented as a facile conjugation method (falling within the field of click chemistry) whereby synthetic polymeric materials may be covalently linked to other species, including other polymers with high efficiency.

  7. 40 CFR 60.380 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ... Performance for Metallic Mineral Processing Plants § 60.380 Applicability and designation of affected facility... mineral processing plants: Each crusher and screen in open-pit mines; each crusher, screen, bucket... underground mines are exempted from the provisions of this subpart. At uranium ore processing plants,...

  8. 75 FR 10395 - Attestation Applications by Facilities Temporarily Employing H-1C Nonimmigrant Foreign Workers as...

    Science.gov (United States)

    2010-03-05

    ...-1A registered nurse temporary visa program created by the Immigration Nursing Relief Act of 1989... NRDAA, and that of the Nursing Relief Act establishing the H-1A program, support an interpretation that... Administration 20 CFR Part 655 Attestation Applications by Facilities Temporarily Employing H-1C...

  9. 18 CFR 157.18 - Applications to abandon facilities or service; exhibits.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Applications to abandon facilities or service; exhibits. 157.18 Section 157.18 Conservation of Power and Water Resources FEDERAL..., Concerning Any Operation, Sales, Service, Construction, Extension, Acquisition or Abandonment §...

  10. Experimental Investigation of Radio Signal Propagation in Scientific Facilities for Telerobotic Applications

    OpenAIRE

    Ramviyas Parasuraman; Keith Kershaw(CERN); Manuel Ferre

    2013-01-01

    Understanding the radio signal transmission characteristics in the environment where the telerobotic application is sought is a key part of achieving a reliable wireless communication link between a telerobot and a control station. In this paper, wireless communication requirements and a case study of a typical telerobotic application in an underground facility at CERN are presented. Then, the theoretical and experimental characteristics of radio propagation are investigated with respect to t...

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

    Energy Technology Data Exchange (ETDEWEB)

    Seidensticker, R.W.; Chang, Y.W. (Argonne National Lab., IL (United States). Reactor Analysis and Safety Div.)

    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. This paper reviews the 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.

  12. The Swedish facility for boron neutron capture therapy

    Energy Technology Data Exchange (ETDEWEB)

    Skoeld, K.; Capala, J. [Studsvik Medical AB (Sweden); Kierkegaard, J.; Haakansson, R. [Studsvik Nuclear AB (Sweden); Gudowska, I. [Karolinska Institute (Sweden)

    2000-10-01

    A BNCT (Boron Neutron Capture Therapy) facility has been constructed at the R2-0 reactor at Studsvik, Sweden. R2-0 is a 1 MW, open core, pool reactor. The reactor core is suspended on a movable tower and can be positioned anywhere in the pool. The BNCT facility includes two adjacent, parallel filter/moderator configurations and the reactor core is positioned in front of any of them as appropriate. One of the resulting neutron beams has been optimized for clinical irradiations with a filter/moderator system that allows easy variation of the neutron spectrum from the thermal to the epithermal energy range and with an extended collimator for convenient patient positioning. The other beam has been designed for radiobiological research and is equipped with a heavy water moderator and a large irradiation cavity with a uniform field of thermal neutrons. (author)

  13. Lithium target for accelerator based BNCT neutron source: Influence by the proton irradiation on lithium

    Science.gov (United States)

    Fujii, R.; Imahori, Y.; Nakakmura, M.; Takada, M.; Kamada, S.; Hamano, T.; Hoshi, M.; Sato, H.; Itami, J.; Abe, Y.; Fuse, M.

    2012-12-01

    The neutron source for Boron Neutron Capture Therapy (BNCT) is in the transition stage from nuclear reactor to accelerator based neutron source. Generation of low energy neutron can be achieved by 7Li (p, n) 7Be reaction using accelerator based neutron source. Development of small-scale and safe neutron source is within reach. The melting point of lithium that is used for the target is low, and durability is questioned for an extended use at a high current proton beam. In order to test its durability, we have irradiated lithium with proton beam at the same level as the actual current density, and found no deterioration after 3 hours of continuous irradiation. As a result, it is suggested that lithium target can withstand proton irradiation at high current, confirming suitability as accelerator based neutron source for BNCT.

  14. Near threshold ⁷Li(p,n) ⁷Be reaction as neutron source for BNCT.

    Science.gov (United States)

    Minsky, D M; Kreiner, A J

    2015-12-01

    (7)Li(p,n)(7)Be is an endothermic reaction and working near its threshold (1.88 MeV) has the advantage of neutron spectra with maximum energies of about 100 keV, considerably lower than at higher beam energies, or than using other neutron-producing reactions or as for the uranium fission spectrum, relevant for BNCT based on nuclear reactors. With this primary energy it is much easier to obtain the energies needed for treating deep seated tumors by BNCT (about 10 keV). This work studies bombarding energies up to 2.05 MeV, different beam incidence angles and the effect of the undesirable gamma production via the (7)Li(p,γp') (7)Li reaction.

  15. Hyaluronic acid as a potential boron carrier for BNCT: Preliminary evaluation.

    Science.gov (United States)

    Zaboronok, A; Yamamoto, T; Nakai, K; Yoshida, F; Uspenskii, S; Selyanin, M; Zelenetskii, A; Matsumura, Akira

    2015-12-01

    Hyaluronic acid (HA), a nonimmunogenic, biocompatible polymer found in different biological tissues, has the potential to attach to CD44 receptors on the surface of certain cancer cells, where the receptor is overexpressed compared with normal cells. Boron-hyaluronic acid (BHA) was tested for its feasibility as a potential agent for BNCT. BHA with low-viscosity 30 kDa HA could be administered by intravenous injection. The compound showed a certain degree of cytotoxicity and accumulation in C6 rat glioma cells in vitro. Instability of the chelate bonds between boron and HA and/or insufficient specificity of CD44 receptors on C6 cells to BHA could account for the insufficient in vitro accumulation. To ensure the future eligibility of BHA for BNCT experiments, using alternative tumor cell lines and chemically securing the chelate bonds or synthesizing BHA with boron covalently attached to HA might be required.

  16. Designing of the 14 MeV neutron moderator for BNCT

    Institute of Scientific and Technical Information of China (English)

    CHENG Dao-Wen; LU Jing-Bin; YANG Dong; LIU Yu-Min; WANG Hui-Dong; MA Ke-Yan

    2012-01-01

    In boron neutron capture therapy (BNCT),the ratio of the fast neutron flux to the neutron flux in the tumor (RFNT) must be less than 3%.If a D-T neutron generator is used in BNCT,the 14 MeV neutron moderator must be optimized to reduce the RFNT.Based on the neutron moderation theory and the simulation results,tungsten,lead and diamond were used to moderate the 14 MeV neutrons.Satisfying RFNT of less than 3%,the maximum neutron flux in the tumor was achieved with a three-layer moderator comprised of a 3 cm thick tungsten layer,a 14 cm thick lead layer and a 21 cm thick diamond layer.

  17. 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.

  18. A feasibility design study on a neutron spectrometer for BNCT with liquid moderator.

    Science.gov (United States)

    Tamaki, S; Sato, F; Murata, I

    2015-12-01

    Neutrons generated by accelerators have various energy spectra. However, only limited methods are available to measure the whole neutron energy spectrum, especially when including the epithermal region that is normally used in BNCT. In the present study, we carried out the design study on a new neutron spectrometer that can measure such a neutron spectrum more accurately, precisely and with higher energy resolution, using an unfolding technique and a liquid moderator.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-01-26

    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.

  20. 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.

  1. 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.

  2. Characterisation of an accelerator-based neutron source for BNCT versus beam energy

    Science.gov (United States)

    Agosteo, S.; Curzio, G.; d'Errico, F.; Nath, R.; Tinti, R.

    2002-01-01

    Neutron capture in 10B produces energetic alpha particles that have a high linear energy transfer in tissue. This results in higher cell killing and a higher relative biological effectiveness compared to photons. Using suitably designed boron compounds which preferentially localize in cancerous cells instead of healthy tissues, boron neutron capture therapy (BNCT) has the potential of providing a higher tumor cure rate within minimal toxicity to normal tissues. This clinical approach requires a thermal neutron source, generally a nuclear reactor, with a fluence rate sufficient to deliver tumorcidal doses within a reasonable treatment time (minutes). Thermal neutrons do not penetrate deeply in tissue, therefore BNCT is limited to lesions which are either superficial or otherwise accessible. In this work, we investigate the feasibility of an accelerator-based thermal neutron source for the BNCT of skin melanomas. The source was designed via MCNP Monte Carlo simulations of the thermalization of a fast neutron beam, generated by 7 MeV deuterons impinging on a thick target of beryllium. The neutron field was characterized at several deuteron energies (3.0-6.5 MeV) in an experimental structure installed at the Van De Graaff accelerator of the Laboratori Nazionali di Legnaro, in Italy. Thermal and epithermal neutron fluences were measured with activation techniques and fast neutron spectra were determined with superheated drop detectors (SDD). These neutron spectrometry and dosimetry studies indicated that the fast neutron dose is unacceptably high in the current design. Modifications to the current design to overcome this problem are presented.

  3. In-phantom dosimetry for BNCT with Fricke and normoxic-polymer gels

    Science.gov (United States)

    Gambarini, G.; Agosteo, S.; Carrara, M.; Gay, S.; Mariani, M.; Pirola, L.; Vanossi, E.

    2006-05-01

    Measurements of in-phantom dose distributions and images are important for Boron Neutron Capture Therapy treatment planning. The method for spatial determination of absorbed doses in thermal or epithermal neutron fields, based on Fricke-xylenol-orange-infused gel dosimeters in form of layers, has revealed to be very reliable, as gel layer dosimeters give the possibility of obtaining spatial dose distributions and measurements of each dose contribution in neutron fields, by means of a properly studied procedure. Quite recently, BNCT has been applied to treat liver metastases; in this work the results of in-phantom dosimetry for explanted liver in BNCT treatments are described. Moreover, polyacrylamide gel (PAG) dosimeters in which a polymerization process appears as a consequence of absorbed dose, have been recently tested, because of their characteristic absence of diffusion. In fact, due to the diffusion of ferric ions, Fricke-gel dosimeters require prompt analysis after exposure to avoid spatial information loss. In this work the preliminary results of a study about the reliability of polymer gel in BNCT dosimetry are also discussed. Gel layers have been irradiated in a phantom exposed in the thermal column of the TRIGA MARK II reactor (Pavia). The results obtained with the two kinds of gel dosimeter have been compared.

  4. Effective dose evaluation for BNCT brain tumor treatment based on voxel phantoms.

    Science.gov (United States)

    Wang, Jeng-Ning; Lee, Kuo-Wei; Jiang, Shiang-Huei

    2014-06-01

    For BNCT treatments, in addition to tumor target doses, non-negligible doses will result in all the remaining organs of the body. This work aims to evaluate the effective dose as well as the average absorbed doses of each of organs of patients with brain tumor treated in the BNCT epithermal neutron beam at THOR. The effective doses were evaluated according to the definitions of ICRP Publications 60 and 103 for the reference male and female computational phantoms developed in ICRP Publication 110 by using the MCNP5 Monte Carlo code with the THOR-Y09 beam source. The effective dose acquired in this work was compared with the results of our previous work calculated for an adult hermaphrodite mathematical phantom. It was found that the effective dose for the female voxel phantom is larger than that for the male voxel phantom by a factor of 1.2-1.5 and the effective dose for the voxel phantom is larger than that for the mathematical phantom by a factor of 1.3-1.6. For a typical brain tumor BNCT, the effective dose was calculated to be 1.51Sv and the average absorbed dose for eye lenses was 1.07Gy.

  5. Boron neutron capture therapy (BNCT) for the treatment of spontaneous nasal planum squamous cell carcinoma in felines.

    Science.gov (United States)

    Trivillin, Verónica A; Heber, Elisa M; Rao, Monica; Cantarelli, María A; Itoiz, Maria E; Nigg, David W; Calzetta, Osvaldo; Blaumann, Herman; Longhino, Juan; Schwint, Amanda E

    2008-02-01

    Recently, Boron neutron capture therapy (BNCT) was successfully applied to treat experimental squamous cell carcinomas (SCC) of the hamster cheek pouch mucosa, with no damage to normal tissue. It was also shown that treating spontaneous nasal planum SCC in terminal feline patients with low dose BNCT is safe and feasible. In an extension of this work, the present study aimed at evaluation of the response of tumor and dose-limiting normal tissues to potentially therapeutic BNCT doses. Biodistribution studies with (10)B-boronophenylalanine (BPA enriched in (10)B) as a (10)B carrier were performed on three felines that showed advanced nasal planum SCC without any standard therapeutic option. Following the biodistribution studies, BNCT mediated by (10)BPA was done using the thermalized epithermal neutron beam at the RA-6 Nuclear Reactor. Follow-up included clinical evaluation, assessment of macroscopic tumor and normal tissue response and biopsies for histopathological analysis. The treated animals did not show any apparent radiation-induced toxicity. All three animals exhibited partial tumor control and an improvement in clinical condition. Enhanced therapeutic efficacy was associated with a high (10)B content of the tumor and a small tumor size. BNCT is therefore believed to be potentially effective in the treatment of spontaneous SCC. However, improvement in targeting (10)B into all tumor cells and delivering a sufficient dose at a greater depth are still required for the treatment of deep-seated, large tumors. Future studies are needed to evaluate the potential efficacy of the dual mode cellular (e.g. BPA-BNCT) and vascular (e.g. GB-10-BNCT) targeting protocol in a preclinical scenario, employing combinations of (10)B compounds with different properties and complementary uptake mechanisms.

  6. Development of cancer therapy facility of HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Byung Jin; Hwang, S. Y.; Kim, M. J. and others

    2000-04-01

    Facilities of the research and clinical treatments of neutron capture therapy using HANARO are developed, and they are ready to install. They are BNCT irradiation facility and prompt gamma neutron activatiion analysis facility. Since every horizontal neutron facility of HANARO is long and narrow tangential beam tube, it is analysed that sufficient epithermal neutrons for the BNCT cannot be obtained but sufficient thermal neutrons can be obtained by a filter composed of silicon and bismuth single crystals. Since the thermal neutron penetaration increases significantly when the crystals are cooled, a filter cooled by liquid nitrogen is developed. So as to avoid interference with the reactor operation, a water shutter is developed. The irradiation room is designed for the temporary surgical operation as well. Handling tools to remove activated beam port plug and to install water shutter and filter are developed. The basic structure of the irradiation room is already installed and most of other parts are ready to install. Since no free beam port is available for the prompt gamma neutron activation analysis, a method obtaining almost pure thermal neutrons by the vertical diffraction of extra beam for the polarized neutron spectrometer is developed. This method is confirmed by analysis and experiments to give high enough neutron beam. Equipment and devices are provided to install this facility.

  7. Application of Nuclear Regulatory Commission Regulation Equivalency to Construction of New Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    BISHOP, G.E.

    1999-06-02

    The Spent Nuclear Fuels Project (SNFP) Office of the Department of Energy (DOE), Richland Operations Office, is charged with moving 2.100 metric tons of spent nuclear fuel elements left over from plutonium production into semi-permanent storage at DOE'S Hanford site in Washington state. In anticipation of eventual NRC regulation, the DOE decided to impose NRC requirements on new SNFP facility design and construction, specifically for the Cold Vacuum Drying Facility (CVDF) and the Canister Storage Building (CSB). The SNFP implemented this policy of ''NRC equivalency'' with the goal of achieving a level of nuclear safety equivalent to that of NRC-licensed fuel processing facilities. Appropriate features of the NRC licensing process were adopted. However, the SNFP maintained applicable DOE requirements in tandem with the NRC regulations. Project work is continuing, with the first fuel movement scheduled for November, 2000.

  8. Experimental Investigation of Radio Signal Propagation in Scientific Facilities for Telerobotic Applications

    Directory of Open Access Journals (Sweden)

    Ramviyas Parasuraman

    2013-10-01

    Full Text Available Understanding the radio signal transmission characteristics in the environment where the telerobotic application is sought is a key part of achieving a reliable wireless communication link between a telerobot and a control station. In this paper, wireless communication requirements and a case study of a typical telerobotic application in an underground facility at CERN are presented. Then, the theoretical and experimental characteristics of radio propagation are investigated with respect to time, distance, location and surrounding objects. Based on analysis of the experimental findings, we show how a commercial wireless system, such as Wi-Fi, can be made suitable for a case study application at CERN.

  9. Neutron medical treatment of tumours — a survey of facilities

    Science.gov (United States)

    Wagner, F. M.; Loeper-Kabasakal, B.; Breitkreutz, H.

    2012-03-01

    Neutron therapy has two branches: Fast Neutron Therapy (FNT) and Boron Neutron Capture Therapy (BNCT). The mean neutron energies used for FNT range from 2 MeV to 25 MeV whereas the maximum energy for BNCT is about 10 keV. Neutron generators for FNT have been cyclotrons, accelerators and reactors, whereas BNCT is so far bound to reactors. Both therapies use the effects of high-LET radiation (secondary recoil protons and alpha particles, respectively) and can attack otherwise radioresistant tumours, however, with the hazard of adverse effects for irradiated healthy tissue. FNT has been administered to about 30,000 patients world-wide. From formerly 40 facilities, only eight are operational or stand-by today. The reasons for this development have been, on the one hand, related to technical and economical conditions; on the other hand, strong side effects and insufficient proof of clinical results in the early years as well as increasing competition with new clinical methods have reduced patient numbers. In fact, strict observations of indications, appropriate therapy-planning including low-LET radiation, and consequent treatment of side effects have lead to remarkable results in the meantime. BNCT initially was developed for the treatment of extremely aggressive forms of brain tumour, taking advantage of the action of the blood-brain-barrier which allows for a boronated compound to be selectively enriched in tumour cells. Meanwhile, also malignant melanoma (MM) and Head-and-Neck (H&T) tumours are treated because of their relative radioresistance. At present, epithermal beams with sufficient flux are available only at two facilities. Existing research reactors were indispensable in the development of BNCT, but are to be replaced by hospital-based epithermal neutron sources. Clinical results indicate significantly increased survival times, but the number of patients ever treated is still below 1,000. 3D-dose calculation systems have been developed at several facilities

  10. Creation and Application of Expert System Framework in Granting the Credit Facilities

    Directory of Open Access Journals (Sweden)

    Somaye Hoseini

    2013-09-01

    Full Text Available This study investigated the development of a knowledge base for expert system for credit risk assessment of bank’s legal customers. It analyzed the customers’ credit risk based on experts’ financial ratio analysis. Financial ratios were derived from financial statements of customers; however, the knowledge that helps banking experts to determine the relationship between customers’ credit risk and financial situation has been derived from these laws. In this study, expert system considered customer financial ratios as input and prediction of credit risk level as the output. This study was a descriptive-case study research. The population consisted of credit experts of Tejarat bank who were the member of bank’s credit Committee and had the right to vote for facilities approval and the individuals whose main task was providing reports for granting facilities and monitoring the use of facilities. After an initial interview and determining the evaluation criteria for facilities and determining the items for each of the criteria, a questionnaire was designed using Likert scale. Data normality test was conducted to ensure the accuracy of the collected data. T-test was performed to realize the selected criteria are important. Then, experts were asked to determine the minimum score for providing the facility to the applicant in each section of the questionnaire. The laws of expert system were provided based on determined minimum scores.

  11. Medical Applications of Gadolinium and/or Boron-Labeled Pharmaceuticals

    Energy Technology Data Exchange (ETDEWEB)

    Coderre, J A; Spielvogel, B

    1997-10-01

    Boron neutron capture therapy (BNCT) is a binary treatment modality that can selectively irradiate tumor tissue. The key to effective BNCT is the preferential accumulation of 10B in the tumor relative to the surrounding normal tissues. A screening procedure was developed under this CRADA that is an improvement over previously reported techniques. This method was used to evaluate the two compounds produced by BBI, the amino acid p-boronophenylalanine (BPA)and the sulfhydryl boroane N2B12H11SH (BSH), for clinically useful accumulation in a panel of human tumor cell lines. BPA showed selective accumulation in: squamous cell carcinoma of the lung; small cell carcinoma of the lung; osteosarcoma; prostate carcinoma; and ovarian carcinoma. Of these it was decided to pursue application of BPA-based BNCT to lung tumors. BPA distribution in nude mice bearing subcutaneous human lung tumor xenografts showed very favorable results. At 3 hours post-injection, the tumor/blood boron concentration ratio was 5:1, the tumorflung ratio was 6:1. The treatment planning sofiware, already in use for the glioblastoma BNCT clinical trial underway at BNL, was used for simulation of a human lung tumor treatment using BNCT. Input data for this simulation included the nude mouse biodistribution data, human lung tumor CT geometry, and the same assumptions about relative biological effectiveness of the BNCT dose components currently in use for the human brain tumor trial. The results of this lung tumor simulation indicate significant sparing of normal lung compared to tumor. We conclude that the BBI product BPA has potential applications in BNCT of other tumor sites. BPA-based BNCT for human small cell carcinoma of the lung looks promising. Further studies into the radiation biology of the normal lung will be required prior to clinical BNCT for lung tumors.

  12. 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

  13. 77 FR 73060 - Standard Review Plan for Review of Fuel Cycle Facility License Applications

    Science.gov (United States)

    2012-12-07

    ...The U.S. Nuclear Regulatory Commission (NRC) is planning to revise NUREG-1520, Revision 1, ``Standard Review Plan (SRP) for the Review of a License Application for a Fuel Cycle Facility.'' The staff proposes to revise NUREG-1520 to provide guidance and further clarify several technical areas. In addition to revising NUREG-1520, the staff is also planning to issue Interim Staff Guidance (ISG)......

  14. Project for the development of the linac based NCT facility in University of Tsukuba.

    Science.gov (United States)

    Kumada, H; Matsumura, A; Sakurai, H; Sakae, T; Yoshioka, M; Kobayashi, H; Matsumoto, H; Kiyanagi, Y; Shibata, T; Nakashima, H

    2014-06-01

    A project team headed by University of Tsukuba launched the development of a new accelerator based BNCT facility. In the project, we have adopted Radio-Frequency Quadrupole (RFQ)+Drift Tube Linac (DTL) type linac as proton accelerators. Proton energy generated from the linac was set to 8MeV and average current was 10mA. The linac tube has been constructed by Mitsubishi Heavy Industry Co. For neutron generator device, beryllium is selected as neutron target material; high intensity neutrons are generated by the reaction with beryllium and the 80kW proton beam. Our team chose beryllium as the neutron target material. At present beryllium target system is being designed with Monte-Carlo estimations and heat analysis with ANSYS. The neutron generator consists of moderator, collimator and shielding. It is being designed together with the beryllium target system. We also acquired a building in Tokai village; the building has been renovated for use as BNCT treatment facility. It is noteworthy that the linac tube had been installed in the facility in September 2012. In BNCT procedure, several medical devices are required for BNCT treatment such as treatment planning system, patient positioning device and radiation monitors. Thus these are being developed together with the linac based neutron source. For treatment planning system, we are now developing a new multi-modal Monte-Carlo treatment planning system based on JCDS. The system allows us to perform dose estimation for BNCT as well as particle radiotherapy and X-ray therapy. And the patient positioning device can navigate a patient to irradiation position quickly and properly. Furthermore the device is able to monitor movement of the patient׳s position during irradiation.

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

    KAUST Repository

    Lim, Yee-Fun

    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.

  16. The National Shipbuilding Research Program. Automated Process Application in Steel Fabrication and Subassembly Facilities; Phase I (Process Analysis)

    Science.gov (United States)

    1999-05-01

    6 Automated Process Application in Steel Fabrication and Subassembly Facilities; Phase I ( Process Analysis ) U.S. DEPARTMENT OF THE NAVY CARDEROCK...Subassembly Facilities; Phase I ( Process Analysis ) 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) 5d. PROJECT NUMBER 5e

  17. Cationized gelatin-HVJ envelope with sodium borocaptate improved the BNCT efficacy for liver tumors in vivo

    Directory of Open Access Journals (Sweden)

    Ono Koji

    2011-01-01

    Full Text Available Abstract Background Boron neutron capture therapy (BNCT is a cell-selective radiation therapy that uses the alpha particles and lithium nuclei produced by the boron neutron capture reaction. BNCT is a relatively safe tool for treating multiple or diffuse malignant tumors with little injury to normal tissue. The success or failure of BNCT depends upon the 10B compound accumulation within tumor cells and the proximity of the tumor cells to the body surface. To extend the therapeutic use of BNCT from surface tumors to visceral tumors will require 10B compounds that accumulate strongly in tumor cells without significant accumulation in normal cells, and an appropriate delivery method for deeper tissues. Hemagglutinating Virus of Japan Envelope (HVJ-E is used as a vehicle for gene delivery because of its high ability to fuse with cells. However, its strong hemagglutination activity makes HVJ-E unsuitable for systemic administration. In this study, we developed a novel vector for 10B (sodium borocaptate: BSH delivery using HVJ-E and cationized gelatin for treating multiple liver tumors with BNCT without severe adverse events. Methods We developed cationized gelatin conjugate HVJ-E combined with BSH (CG-HVJ-E-BSH, and evaluated its characteristics (toxicity, affinity for tumor cells, accumulation and retention in tumor cells, boron-carrying capacity to multiple liver tumors in vivo, and bio-distribution and effectiveness in BNCT therapy in a murine model of multiple liver tumors. Results CG-HVJ-E reduced hemagglutination activity by half and was significantly less toxic in mice than HVJ-E. Higher 10B concentrations in murine osteosarcoma cells (LM8G5 were achieved with CG-HVJ-E-BSH than with BSH. When administered into mice bearing multiple LM8G5 liver tumors, the tumor/normal liver ratios of CG-HVJ-E-BSH were significantly higher than those of BSH for the first 48 hours (p . In suppressing the spread of tumor cells in mice, BNCT treatment was as

  18. Navigation Facility for High Accuracy Offline Trajectory and Attitude Estimation in Airborne Applications

    Directory of Open Access Journals (Sweden)

    A. Renga

    2013-01-01

    Full Text Available The paper focuses on a navigation facility, relying on commercial-off-the-shelf (COTS technology, developed to generate high-accuracy attitude and trajectory measurements in postprocessing. Target performance is cm-level positioning with tenth of degree attitude accuracy. The facility is based on the concept of GPS-aided inertial navigation but comprises carrier-phase differential GPS (CDGPS processing and attitude estimation based on multiantenna GPS configurations. Expected applications of the system include: (a performance assessment of integrated navigation systems, developed for general aviation aircraft and medium size unmanned aircraft systems (UAS; (b generation of reference measurements to evaluate the flight performance of airborne sensors (e.g., radar or laser; and (c generation of reference trajectory and attitude for improving imaging quality of airborne remote sensing data. The paper describes system architecture, selected algorithms for data processing and integration, and theoretical performance evaluation. Experimental results are also presented confirming the effectiveness of the implemented approach.

  19. High power accelerator-based boron neutron capture with a liquid lithium target and new applications to treatment of infectious diseases.

    Science.gov (United States)

    Halfon, S; Paul, M; Steinberg, D; Nagler, A; Arenshtam, A; Kijel, D; Polacheck, I; Srebnik, M

    2009-07-01

    A new conceptual design for an accelerator-based boron neutron capture therapy (ABNCT) facility based on the high-current low-energy proton beam driven by the linear accelerator at SARAF (Soreq Applied Research Accelerator Facility) incident on a windowless forced-flow liquid-lithium target, is described. The liquid-lithium target, currently in construction at Soreq NRC, will produce a neutron field suitable for the BNCT treatment of deep-seated tumor tissues, through the reaction (7)Li(p,n)(7)Be. The liquid-lithium target is designed to overcome the major problem of solid lithium targets, namely to sustain and dissipate the power deposited by the high-intensity proton beam. Together with diseases conventionally targeted by BNCT, we propose to study the application of our setup to a novel approach in treatment of diseases associated with bacterial infections and biofilms, e.g. inflammations on implants and prosthetic devices, cystic fibrosis, infectious kidney stones. Feasibility experiments evaluating the boron neutron capture effectiveness on bacteria annihilation are taking place at the Soreq nuclear reactor.

  20. High power accelerator-based boron neutron capture with a liquid lithium target and new applications to treatment of infectious diseases

    Energy Technology Data Exchange (ETDEWEB)

    Halfon, S. [Soreq NRC, Yavne 81800 (Israel); Racah Institute of Physics, Hebrew University, Jerusalem 91904 (Israel)], E-mail: halfon@phys.huji.ac.il; Paul, M. [Racah Institute of Physics, Hebrew University, Jerusalem 91904 (Israel); Steinberg, D. [Biofilm Laboratory, Institute of Dental Sciences, Faculty of Dentistry, Hebrew University-Hadassah (Israel); Nagler, A.; Arenshtam, A.; Kijel, D. [Soreq NRC, Yavne 81800 (Israel); Polacheck, I. [Clinical Microbiology and Infectious Diseases, Hadassah-Hebrew University Medical Center (Israel); Srebnik, M. [Department of Medicinal Chemistry and Natural Products, School of Pharmacy, Hebrew University, Jerusalem 91120 (Israel)

    2009-07-15

    A new conceptual design for an accelerator-based boron neutron capture therapy (ABNCT) facility based on the high-current low-energy proton beam driven by the linear accelerator at SARAF (Soreq Applied Research Accelerator Facility) incident on a windowless forced-flow liquid-lithium target, is described. The liquid-lithium target, currently in construction at Soreq NRC, will produce a neutron field suitable for the BNCT treatment of deep-seated tumor tissues, through the reaction {sup 7}Li(p,n){sup 7}Be. The liquid-lithium target is designed to overcome the major problem of solid lithium targets, namely to sustain and dissipate the power deposited by the high-intensity proton beam. Together with diseases conventionally targeted by BNCT, we propose to study the application of our setup to a novel approach in treatment of diseases associated with bacterial infections and biofilms, e.g. inflammations on implants and prosthetic devices, cystic fibrosis, infectious kidney stones. Feasibility experiments evaluating the boron neutron capture effectiveness on bacteria annihilation are taking place at the Soreq nuclear reactor.

  1. Electrostatic design and beam transport for a folded tandem electrostatic quadrupole accelerator facility for accelerator-based boron neutron capture therapy

    Energy Technology Data Exchange (ETDEWEB)

    Thatar Vento, V., E-mail: Vladimir.ThatarVento@gmail.com [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral. Paz 1499 (1650), San Martin, Buenos Aires (Argentina)] [CONICET, Av. Rivadavia 1917 (1033), Ciudad Autonoma de Buenos Aires (Argentina); Bergueiro, J.; Cartelli, D. [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral. Paz 1499 (1650), San Martin, Buenos Aires (Argentina)] [CONICET, Av. Rivadavia 1917 (1033), Ciudad Autonoma de Buenos Aires (Argentina); Valda, A.A. [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral. Paz 1499 (1650), San Martin, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, UNSAM, M. Irigoyen 3100 (1650), San Martin, Buenos Aires (Argentina); Kreiner, A.J. [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral. Paz 1499 (1650), San Martin, Buenos Aires (Argentina)] [CONICET, Av. Rivadavia 1917 (1033), Ciudad Autonoma de Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, UNSAM, M. Irigoyen 3100 (1650), San Martin, Buenos Aires (Argentina)

    2011-12-15

    Within the frame of an ongoing project to develop a folded Tandem-Electrostatic-Quadrupole (TESQ) accelerator facility for Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT), we discuss here the electrostatic design of the machine, including the accelerator tubes with electrostatic quadrupoles and the simulations for the transport and acceleration of a high intensity beam.

  2. Filter/moderator system for a BNCT beam of epithermal neutrons at nuclear reactor MARIA

    Science.gov (United States)

    Tyminska, Katarzyna

    2009-01-01

    Boron Neutron Capture Therapy is a very promising form of cancer therapy, consisting in irradiating a stable isotope of boron (10B) concentrated in tumor cells with a low energy neutron beam. This technique makes it possible to destroy tumor cells, leaving healthy tissues practically unaffected. In order to carry out the therapy in the proper way, the proper range of the neutron beam energy has to be chosen. In this paper we present a filter/moderator system modeled with MCNP code in order to obtain an epithermal neutron beam for BNCT post at MARIA reactor in Swierk.

  3. Synthesis and evaluation of a novel liposome containing BPA-peptide conjugate for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Shirakawa, Makoto [Department of Graduate School of Comprehensive Human Sciences, Faculty of Functional and Regulatory Medical Sciences, University of Tsukuba (Japan)], E-mail: m0720347@md.tsukuba.ac.jp; Yamamto, Tetsuya; Nakai, Kei [Department of Graduate School of Comprehensive Human Sciences, Faculty of Functional and Regulatory Medical Sciences, University of Tsukuba (Japan); Aburai, Kenichi [Department of Pure and Applied Chemistry, Faculty of Science and Technology, Tokyo University of Science (Japan); Kawatobi, Sho [Faculty of Pharmaceutical Sciences, Toho University (Japan); Tsurubuchi, Takao; Yamamoto, Yohei [Department of Graduate School of Comprehensive Human Sciences, Faculty of Functional and Regulatory Medical Sciences, University of Tsukuba (Japan); Yokoyama, Yuusaku; Okuno, Hiroaki [Faculty of Pharmaceutical Sciences, Toho University (Japan); Matsumura, Akira [Department of Graduate School of Comprehensive Human Sciences, Faculty of Functional and Regulatory Medical Sciences, University of Tsukuba (Japan)

    2009-07-15

    We aimed at securing sufficient concentrations of {sup 10}B in boron neutron capture therapy (BNCT) by developing a new drug delivery system. We have designed and developed a novel lipid analog and succeeded in using it to develop the new boron component liposome. It consisted of three different kinds of amino acid derivatives and two fatty acids, and could react directly with the peptide synthesized first on resin by Fmoc solid-phase synthesis. In this study, lipid analog conjugated with HIV-TAT peptide (domain of human immunodeficiency virus TAT protein) and boronophenylalanine (BPA) was synthesized and successfully incorporated into liposomes.

  4. The optimization study of Bonner sphere in the epi-thermal neutron irradiation field for BNCT.

    Science.gov (United States)

    Ueda, H; Tanaka, H; Maruhashi, A; Ono, K; Sakurai, Y

    2011-12-01

    The optimization study on the Bonner sphere in the epi-thermal neutron irradiation field for BNCT was done for the moderator material, moderator size, and activation foils as a neutron detector in the sphere. The saturated activity for the activation foil was obtained from the calculated response, and the effective energy range for each Bonner sphere was determined from the saturated activity. We can see that boric acid solution moderator is suitable for the spectrum measurement of a epi-thermal neutron irradiation field.

  5. Facility Environment Thermal Control Technology and Facility Application%设施环境热调控技术及设施应用

    Institute of Scientific and Technical Information of China (English)

    吕桂菊

    2012-01-01

    Based on the thermal characteristics of horticultural facilities,causes and ways of research and analysis of heat loss,on the production of the thermal environment in the regulation of different purposes,focus on temperature keep,temperature increase,temperature change three kinds of measures,involving the facilities and technology application,to guide the production facilities.%通过对园艺设施内热变化特点、产生原因以及热量损失途径的研究与分析,对生产中热环境调控目的不同,重点进行保温、增温、变温三种措施介绍,涉及设施及技术应用,对设施生产进行指导。

  6. A facile TiO2/PVDF composite membrane synthesis and their application in water purification

    Science.gov (United States)

    Zhang, Wei; Zhang, Yiming; Fan, Rong; Lewis, Rosmala

    2016-01-01

    In this work, we have demonstrated a facile wet chemical method to synthesise TiO2/PVDF composite membranes as alternative water purification method to traditional polymer-based membrane. For the first time, hydrothermally grown TiO2 nanofibers under alkali conditions were successfully inserted into PVDF membranes matrix. The structure, permeability and anti-fouling performance of as-prepared PVDF/TiO2 composite membranes were studied systematically. The TiO2/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.

  7. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-10-01

    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 US 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.

  9. 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.

  10. Development and application of PIE apparatuses in Tokai hot cell facilities

    Energy Technology Data Exchange (ETDEWEB)

    Amano, Hidetoshi; Kodaira, Tsuneo; Sukegawa, Tomohide [Department of Hot Laboratories, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

    1999-08-01

    The Department of Hot Laboratories (DHL) operates three hot cell facilities, which are the Reactor Fuel Examination Facility (RFEF), the Research Hot Laboratory (RHL) and the Waste Safety Testing Facility (WASTEF). The RFEF is especially examining the reliability of actual power reactor fuel assemblies for PWR and BWR. The RHL is established to perform post irradiation examinations (PIEs) for fuels and materials irradiated in research and test reactors. In the WASTEF, Synroc and new ceramic waste forms were prepared and investigated for the safety disposal of high level radioactive waste. At present, one of concentrated works is the PIE of high burnup fuels, for which the RFEF improved and developed several apparatuses such as thermal properties measurement and microscopic analysis. The other is the PIE concerning with studies of component aging and structural reliability, for which the charpy impact-testing machine is instrumented and a low-cycle and high-cycle fatigue test apparatus is now under developing in the RHL. This paper describes these development and application of PIE apparatuses in DHL. (author)

  11. 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.

  12. 124Sb-Be photo-neutron source for BNCT: Is it possible?

    Science.gov (United States)

    Golshanian, Mohadeseh; Rajabi, Ali Akbar; Kasesaz, Yaser

    2016-11-01

    In this research a computational feasibility study has been done on the use of 124SbBe photo-neutron source for Boron Neutron Capture Therapy (BNCT) using MCNPX Monte Carlo code. For this purpose, a special beam shaping assembly has been designed to provide an appropriate epithermal neutron beam suitable for BNCT. The final result shows that using 150 kCi of 124Sb, the epithermal neutron flux at the designed beam exit is 0.23×109 (n/cm2 s). In-phantom dose analysis indicates that treatment time for a brain tumor is about 40 min which is a reasonable time. This high activity 124Sb could be achieved using three 50 kCi rods of 124Sb which can be produced in a research reactor. It is clear, that as this activity is several hundred times the activity of a typical cobalt radiotherapy source, issues related to handling, safety and security must be addressed.

  13. The contractor`s role in low-level waste disposal facility application review and licensing

    Energy Technology Data Exchange (ETDEWEB)

    Serie, P.J.; Dressen, A.L. [Environmental Issues Management, Inc., Seattle, WA (United States)

    1991-12-31

    The California Department of Health Services will soon reach a licensing decision on the proposed Ward Valley low-level radioactive waste disposal facility. As the first regulatory agency in the country to address the 10 CFR Part 61 requirements for a new disposal facility, California`s program has broken new ground in its approach. Throughout the review process, the Department has relied on contractor support to augment its technical and administrative staff. A team consisting of Roy F. Weston, Inc., supported by ERM-Program Management Corp., Environmental Issues Management, Inc., and Rogers and Associates Engineering Corporation, has worked closely with the Department in a staff extension role. The authors have been involved with the project in contractor project management roles since 1987, and continue to support the Department`s program as it proceeds to finalize its licensing process. This paper describes the selection process used to identify a contractor team with the needed skills and experience, and the makeup of team capabilities. It outlines the management, communication, and technical approaches used to assure a smooth agency-contractor function and relationship. It describes the techniques used to ensure that decisions and documents represented the Department credibly in its role as the regulatory and licensing agency under the Nuclear Regulatory Commission (NRC) Agreement State program. The paper outlines the license application review process and activities, through preparation of licensing documentation and responses to public comments. Lessons learned in coordination of an agency-contractor team effort to review and license a low-level waste disposal facility are reviewed and suggestions made for approaching a similar license application review and licensing situation.

  14. Quantitative evaluation of boron neutron capture therapy (BNCT) drugs for boron delivery and retention at subcellular-scale resolution in human glioblastoma cells with imaging secondary ion mass spectrometry (SIMS).

    Science.gov (United States)

    Chandra, S; Ahmad, T; Barth, R F; Kabalka, G W

    2014-06-01

    Boron neutron capture therapy (BNCT) of cancer depends on the selective delivery of a sufficient number of boron-10 ((10)B) atoms to individual tumour cells. Cell killing results from the (10)B (n, α)(7) Li neutron capture and fission reactions that occur if a sufficient number of (10)B atoms are localized in the tumour cells. Intranuclear (10)B localization enhances the efficiency of cell killing via damage to the DNA. The net cellular content of (10)B atoms reflects both bound and free pools of boron in individual tumour cells. The assessment of these pools, delivered by a boron delivery agent, currently cannot be made at subcellular-scale resolution by clinically applicable techniques such as positron emission tomography and magnetic resonance imaging. In this study, a secondary ion mass spectrometry based imaging instrument, a CAMECA IMS 3f ion microscope, capable of 500 nm spatial resolution was employed. Cryogenically prepared cultured human T98G glioblastoma cells were evaluated for boron uptake and retention of two delivery agents. The first, L-p-boronophenylalanine (BPA), has been used clinically for BNCT of high-grade gliomas, recurrent tumours of the head and neck region and melanomas. The second, a boron analogue of an unnatural amino acid, 1-amino-3-borono-cyclopentanecarboxylic acid (cis-ABCPC), has been studied in rodent glioma and melanoma models by quantification of boron in the nucleus and cytoplasm of individual tumour cells. The bound and free pools of boron were assessed by exposure of cells to boron-free nutrient medium. Both BPA and cis-ABCPC delivered almost 70% of the pool of boron in the free or loosely bound form to the nucleus and cytoplasm of human glioblastoma cells. This free pool of boron could be easily mobilized out of the cell and was in some sort of equilibrium with extracellular boron. In the case of BPA, the intracellular free pool of boron also was affected by the presence of phenylalanine in the nutrient medium. This

  15. 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.

  16. Design, properties and application of a facile fluorescence switch for Cu(II)

    Science.gov (United States)

    Diao, Haipeng; Niu, Weiping; Liu, Wen; Feng, Liheng; Xie, Jun

    2017-01-01

    A facile fluorescence switch based on Schiff base 2,2‧-[1,3-phenylenbis- (methylidynenitrilo)]bis[benzenethiol] (PMBB) has been developed and used to sensing metal ions. UV-vis absorption and fluorescence emission spectra show that the PMBB receptor has high selectivity and sensitivity for Cu(II) ions. Based on the photoinduced electron transfer (PET) and chelation enhanced fluorescence (CHEF) mechanisms, the receptor exhibits an fluorescence "turn-on" switch signal for Cu(II). The 1:1 binding mode of PMBB and Cu (II) ions can be obtained by the Job-plot and ESI-Mass spectra data. Noticeably, the color changes (from colorless to yellow) of PMBB solutions for Cu(II) sensing can be observed by naked eyes in the sunlight. The detection limit of the receptor for Cu(II) may reach 10- 7 mol/L with a good linear relation in the lower concentrations of Cu(II). To develop the practical application, the Cu(II) ions in swimming pool water samples were detected. Results show that PMBB receptor as a fluorescent probe can use to detect the trace level of Cu(II) in the environmental samples. This work contributes to providing a facile strategy for designing efficient probes and developing their practical application value.

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

    Energy Technology Data Exchange (ETDEWEB)

    Batandjieva, B.; Metcalf, P.

    2003-02-25

    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. 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.

  19. In-vivo measurements with TLD detectors for BNCT of glioblastoma patients at the high-flux research reactor petten/NL

    Energy Technology Data Exchange (ETDEWEB)

    Finke, E.; Hideghety, K.; Rassow, J.; Sauerwein, W. [Universitaetsklinikum, Essen (Germany); Kessler, C. [Comision Nacional de Energia Atomica, Laboratorio Secundario de Calibracion Dosimetricqa, Buenos Aires (Argentina); Morrissey, J.; Moss, R. [JRC Joint Research Center, Petten (Netherlands); Stecher-Rasmussen, F.; Verhagen, H.W. [NRG (an ECN Kema Company), Petten (Netherlands)

    2000-10-01

    Base of this investigation is an experimental test, which TLD detector material is best suited for indication of a representative dose component for in-vivo measurements at BNCT patients treated with epithermal neutrons of a constant energy spectrum. In-vivo measurements with Thermoluminescence detectors CaF{sub 2}:Tm (TLD 300) were carried out during irradiation of four BNCT-patients. (author)

  20. A phantom experiment for the evaluation of whole body exposure during BNCT using cyclotron-based epithermal neutron source (C-BENS)

    Energy Technology Data Exchange (ETDEWEB)

    Tsukamoto, T., E-mail: t.tsukamoto@ft5.ecs.kyoto-u.ac.jp [Graduate School of Engineering, Kyoto University, Yoshida Honmachi, Sakyo-ku, Kyoto 606-8501 (Japan); Tanaka, H.; Yoshinaga, H. [Research Reactor Institute, Kyoto University, Asashiro-nishi 2-1010, Kumatori-cho, Osaka 590-0494 (Japan); Mitsumoto, T. [Sumitomo Heavy Industries, Ltd., Osaki 2-1-1, Shinagawa, Tokyo 141-6025 (Japan); Maruhashi, A.; Ono, K.; Sakurai, Y. [Research Reactor Institute, Kyoto University, Asashiro-nishi 2-1010, Kumatori-cho, Osaka 590-0494 (Japan)

    2011-12-15

    At Kyoto University Research Reactor Institute (KURRI), cyclotron-based epithermal neutron source was installed in December 2008, and the supplementary construction works have been performed. As of December 2010, the various irradiation characteristics important for BNCT were mostly evaluated. The whole body exposure during BNCT medical irradiation is one of the important characteristics. In this article, measurements of absorbed dose for thermal and fast neutrons and gamma-ray at ten positions corresponding to important organs are reported.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-07-01

    This report describes the EG&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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-07-01

    This report describes the EG 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.

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

    CERN Document Server

    Wahl, U

    2011-01-01

    The ISOLDE isotope separator facility at CERN provides a variety of radioactive ion beams, currently more than 800 different isotopes from ~65 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 ~15%) of the delivered beam time, requested by 18 different experiments. The ISOLDE materials science and biophysics community currently consists of ~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 i...

  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. Potential applications of the dielectric wakefield accelerators in the SINBAD facility at DESY

    Energy Technology Data Exchange (ETDEWEB)

    Nie, Y.C., E-mail: yuancun.nie@desy.de [Deutsches Elektronen-Synchrotron DESY, 22607 Hamburg (Germany); Assmann, R.; Dorda, U.; Marchetti, B. [Deutsches Elektronen-Synchrotron DESY, 22607 Hamburg (Germany); Weikum, M. [Deutsches Elektronen-Synchrotron DESY, 22607 Hamburg (Germany); University of Strathclyde, G1 1XQ Glasgow (United Kingdom); Zhu, J.; Hüning, M. [Deutsches Elektronen-Synchrotron DESY, 22607 Hamburg (Germany)

    2016-09-01

    Short, high-brightness relativistic electron bunches can drive ultra-high wakefields in the dielectric wakefield accelerators (DWFAs). This effect can be used to generate high power THz coherent Cherenkov radiation, accelerate a witness bunch with gradient two or three orders of magnitude larger than that in the conventional RF linear accelerators, introduce energy modulation within the driving bunch itself, etc. The paper studies potential applications of the DWFAs in the SINBAD facility at DESY. The simulations show that the ultra-short relativistic bunches from the SINBAD injector ARES can excite accelerating wakefields with peak amplitudes as high as GV/m at THz frequencies in proper DWFA structures. In addition, it illustrates that the DWFA structure can serve as a dechirper to compensate the correlated energy spread of the bunches accelerated by the laser plasma wakefield accelerator.

  6. Facile synthesis of SiO{sub 2} nanoparticles for biomedical applications

    Energy Technology Data Exchange (ETDEWEB)

    Scano, A., E-mail: alescano80@tiscali.it; Pilloni, M., E-mail: alescano80@tiscali.it; Cabras, V., E-mail: alescano80@tiscali.it; Ennas, G. [Università di Cagliari, Dipartimento di Scienze Chimiche e Geologiche and Research Unit of the National Consortium of Materials Science and Technology (INSTM), Cittadella Universitaria di Monserrato- 09042 Monserrato (Canada) (Italy); Vazquez-Vazquez, C. [Departamento de Química Física, Facultad de Química, Universidad de Santiago de Compostela, Santiago de Compostela, 15782 Galicia (Spain)

    2014-10-21

    Silica nanoparticles (SiO{sub 2} NPs) for biomedical applications have been prepared by using a facile modified Stöber-synthesis. Potassium borohydride (KBH{sub 4}) has been introduced in the synthesis procedure in order to control NP size. Several samples have been prepared varying tetraethylorthosilicate (TEOS) concentration, and using different process conditions (temperature, reaction time and atmosphere). In order to study the influence of the process conditions on the NP size, morphology and properties, several characterization techniques were used. Size and morphology of the as-prepared SiO{sub 2} NPs have been studied by using Transmission Electron Microscope (TEM) and Dynamic Light Scattering (DLS) techniques. Structural characterization was carried out by X-ray powder diffraction. To investigate the SiO{sub 2} NP fluorescence emission properties the fluorescence spectroscopy was also used.

  7. Applications of SU-8 in the development of a Single Ion Hit Facility

    Energy Technology Data Exchange (ETDEWEB)

    Arteaga-Marrero, N. [Division of Nuclear Physics, Department of Physics, Lund University, Professorsgatan 1, Box 118, SE-22100 Lund (Sweden)], E-mail: natalia.arteaga@nuclear.lu.se; Astromskas, G. [Division of Solid State Physics, Department of Physics, Lund University, Professorsgatan 1, Box 118, SE-22100 Lund (Sweden); Olsson, M.G. [Department of Infection Medicine, Lund University, Soelvegatan 19, B14, SE-22184 Lund (Sweden); Elfman, M.; Kristiansson, P.; Nilsson, E.J.C.; Nilsson, C.; Pallon, J. [Division of Nuclear Physics, Department of Physics, Lund University, Professorsgatan 1, Box 118, SE-22100 Lund (Sweden)

    2009-06-15

    The Lund Nuclear Microprobe (LNM) has been adapted to be used as a Single Ion Hit Facility (SIHF) for proton cell irradiation experiments at low dose. In order to test the capabilities of the system, Ni dot arrays and artificial cells have been fabricated with the photopolymer SU-8 and common lithographic techniques. The primary purpose of the Ni dot arrays was to determine the targeting accuracy of the beam in vacuum and in air. Additionally, this sample was employed to evaluate the system performance during cell target irradiation experiments. The Ni dot arrays were also used for beam characterization. The artificial cells were originally fabricated to test the software for cell recognition and localization, developed and implemented at the LNM. However, this sample became very functional to make small adjustments at the irradiation chamber for cell irradiation experiments. A description of the samples, fabrication procedure and applications are presented in this paper.

  8. Facile hydrothermal preparation of niobium pentaoxide decorated reduced graphene oxide nanocomposites for supercapacitor applications

    Science.gov (United States)

    Murugan, M.; Kumar, R. Mohan; Alsalme, Ali; Alghamdi, Abdulaziz; Jayavel, R.

    2016-04-01

    Facile synthesis of graphene-Nb2O5 composite has been reported. Graphene oxide was prepared by the modified Hummer's method. The metal oxide (Nb2O5) was introduced to the graphene to form the composite by the hydrothermal method. The prepared samples were characterized by X-ray diffraction, scanning electron microscopy, high resolution transmission electron microscopy, Fourier transform infrared (FTIR) and thermo gravimetric analysis (TGA). SEM and TEM results revealed that the metal oxide particles are uniformly dispersed on the surface of thin sheets of well-defined multilayered graphene structure. Thermal stability of the graphene metal oxide nanocomposites was also investigated. The CV measurements reveal a significant enhancement in the specific capacitance reaching 321 Fg-1 at a scan rate of 10 mV s-1. With promising electrochemical characteristics, Nb2O5 decorated graphene nanocomposite are explored as potential electrode material for supercapacitor applications.

  9. 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)

  10. Development of tritiated vapor absorbent applicable to the atmospheric detritiation system in a nuclear facility.

    Science.gov (United States)

    Iwai, Yasunori; Yamanishi, Toshihiko

    2010-09-01

    The combination of hydrogen oxidation reactor packed noble metal catalysts and water vapor absorber has been applied to the atmospheric detritiation system of the tritium handling facility. Commercial synthetic zeolite such as molecular sieve 5A has been used as an adsorbent of ADS absorber. In the case of application of molecular sieve 5A to the ADS absorber of a large-scale tritium handling facility such as a future fusion plant, an absorber becomes huge due mainly to the difficulty in dehydration from molecular sieve 5A. Hence, application of CaY Faujasite-type zeolite with a high framework silica-to-alumina ratio to the adsorbent for atmospheric detritiation system was investigated. It was clear that the dehydration behavior at room temperature was significantly improved using CaY zeolite. In contrast, detritiation factor for CaY zeolite with a high framework silica-to-alumina ratio depended strongly on the space velocity through the absorber. To apply CaY zeolite with a high framework SiO(2)/Al(2)O(3) ratio to the ADS absorbent, the space velocity less than 250h(-1) was recommended to maintain the detritiation factor more than 1000. The steep increase in water adsorption at the relative pressure lower than 0.05 is a feature of synthetic zeolite with calcium cation. However, such an increase was not observed in water adsorption on CaY zeolite with a framework SiO(2)/Al(2)O(3) ratio more than 7.0. Consequently, the CaY zeolite with the framework SiO(2)/Al(2)O(3) ratio of 5.0 is a promising candidate as absorbent of ADS absorber.

  11. Tetrakis(p-Carboranylthio-Tetrafluorophenyl)Chlorin (TPFC): Application for Photodynamic Therapy and Boron Neutron Capture Therapy

    Science.gov (United States)

    HIRAMATSU, RYO; KAWABATA, SHINJI; TANAKA, HIROKI; SAKURAI, YOSHINORI; SUZUKI, MINORU; ONO, KOJI; MIYATAKE, SHIN-ICHI; KUROIWA, TOSHIHIKO; HAO, ERHONG; VICENTE, M. GRAÇA H.

    2015-01-01

    Carboranyl-containing chlorins have emerged as promising dual sensitizers for use in both photodynamic therapy (PDT) and boron neutron capture therapy (BNCT), by virtue of their known tumor affinity, low cytotoxicity in dark conditions, and their strong absorptions in the red region of the optical spectrum. Tetrakis(p-carboranylthio-tetrafluorophenyl)chlorin (TPFC) is a new synthetic carboranyl-containing chlorin of high boron content (24% by weight). To evaluate TPFC’s applicability as sensitizer for both PDT and BNCT, we performed an in vitro and in vivo study using F98 rat glioma cells and F98 rat glioma-bearing brain tumor models. For the in vivo BNCT study, we used boronophenylalanine (BPA), which is currently used in clinical BNCT studies, via intravenous administration (i.v.) and/or used TPFC via convection-enhanced delivery (CED), a method for local drug infusion directly into the brain. In the in vitro PDT study, the cell surviving fraction following laser irradiation (9 J/cm2) was 0.035 whereas in the in vitro BNCT study, the cell surviving fraction following neutron irradiation (thermal neutron = 1.73 × 1012 n/cm2) was 0.04. In the in vivo BNCT study, the median survival time following concomitant administration of BPA (i.v.) and TPFC (CED) was 42 days (95% confidence interval; 37–43 days). PMID:25546823

  12. Tetrakis(p-carboranylthio-tetrafluorophenyl)chlorin (TPFC): application for photodynamic therapy and boron neutron capture therapy.

    Science.gov (United States)

    Hiramatsu, Ryo; Kawabata, Shinji; Tanaka, Hiroki; Sakurai, Yoshinori; Suzuki, Minoru; Ono, Koji; Miyatake, Shin-ichi; Kuroiwa, Toshihiko; Hao, Erhong; Vicente, M Graça H

    2015-03-01

    Carboranyl-containing chlorins have emerged as promising dual sensitizers for use in both photodynamic therapy (PDT) and boron neutron capture therapy (BNCT), by virtue of their known tumor affinity, low cytotoxicity in dark conditions, and their strong absorptions in the red region of the optical spectrum. Tetrakis(p-carboranylthio-tetrafluorophenyl)chlorin (TPFC) is a new synthetic carboranyl-containing chlorin of high boron content (24% by weight). To evaluate TPFC's applicability as sensitizer for both PDT and BNCT, we performed an in vitro and in vivo study using F98 rat glioma cells and F98 rat glioma-bearing brain tumor models. For the in vivo BNCT study, we used boronophenylalanine (BPA), which is currently used in clinical BNCT studies, via intravenous administration (i.v.) and/or used TPFC via convection-enhanced delivery (CED), a method for local drug infusion directly into the brain. In the in vitro PDT study, the cell surviving fraction following laser irradiation (9 J/cm(2) ) was 0.035 whereas in the in vitro BNCT study, the cell surviving fraction following neutron irradiation (thermal neutron = 1.73 × 10(12) n/cm(2) ) was 0.04. In the in vivo BNCT study, the median survival time following concomitant administration of BPA (i.v.) and TPFC (CED) was 42 days (95% confidence interval; 37-43 days).

  13. Boron neutron capture therapy (BNCT) for liver metastasis in an experimental model: dose–response at five-week follow-up based on retrospective dose assessment in individual rats

    Energy Technology Data Exchange (ETDEWEB)

    Emiliano C. C. Pozzi; Veronica A. Trivilin; Lucas L. Colombo; Andrea Monti Hughes; Silvia I. Thorp; Jorge E. Cardoso; Marcel A. Garabalino; Ana J. Molinari; Elisa M. Heber; Paula Curotto; Marcelo Miller; Maria E. Itoiz; Romina F. Aromando; David W. Nigg; Amanda E. Schwint

    2013-11-01

    Boron neutron capture therapy (BNCT) was proposed for untreatable colorectal liver metastases. Employing an experimental model of liver metastases in rats, we recently demonstrated that BNCT mediated by boronophenylalanine (BPA-BNCT) at 13 Gy prescribed to tumor is therapeutically useful at 3-week follow-up. The aim of the present study was to evaluate dose–response at 5-week follow-up, based on retrospective dose assessment in individual rats. BDIX rats were inoculated with syngeneic colon cancer cells DHD/K12/TRb. Tumor-bearing animals were divided into three groups: BPA-BNCT (n = 19), Beam only (n = 8) and Sham (n = 7) (matched manipulation, no treatment). For each rat, neutron flux was measured in situ and boron content was measured in a pre-irradiation blood sample for retrospective individual dose assessment. For statistical analysis (ANOVA), individual data for the BPA-BNCT group were pooled according to absorbed tumor dose, BPA-BNCT I: 4.5–8.9 Gy and BPA-BNCT II: 9.2–16 Gy. At 5 weeks post-irradiation, the tumor surface area post-treatment/pre-treatment ratio was 12.2 +/- 6.6 for Sham, 7.8 +/- 4.1 for Beam only, 4.4 +/- 5.6 for BPA-BNCT I and 0.45 +/- 0.20 for BPA-BNCT II; tumor nodule weight was 750 +/- 480 mg for Sham, 960 +/- 620 mg for Beam only, 380 +/- 720 mg for BPA-BNCT I and 7.3 +/- 5.9 mg for BPA-BNCT II. The BPA-BNCT II group exhibited statistically significant tumor control with no contributory liver toxicity. Potential threshold doses for tumor response and significant tumor control were established at 6.1 and 9.2 Gy, respectively.

  14. (9)Be(d,n)(10)B-based neutron sources for BNCT.

    Science.gov (United States)

    Capoulat, M E; Herrera, M S; Minsky, D M; González, S J; Kreiner, A J

    2014-06-01

    In the frame of accelerator-based BNCT, the (9)Be(d,n)(10)B reaction was investigated as a possible source of epithermal neutrons. In order to determine the configuration in terms of bombarding energy, target thickness and Beam Shaping Assembly (BSA) design that results in the best possible beam quality, a systematic optimization study was carried out. From this study, the optimal configuration resulted in tumor doses ≥40Gy-Eq, with a maximum value of 51Gy-Eq at a depth of about 2.7cm, in a 60min treatment. The optimal configuration was considered for the treatment planning assessment of a real Glioblastoma Multiforme case. From this, the resulted dose performances were comparable to those obtained with an optimized (7)Li(p,n)-based neutron source, under identical conditions and subjected to the same clinical protocol.

  15. A novel design of beam shaping assembly to use D-T neutron generator for BNCT.

    Science.gov (United States)

    Kasesaz, Yaser; Karimi, Marjan

    2016-12-01

    In order to use 14.1MeV neutrons produced by d-T neutron generators, two special and novel Beam Shaping Assemblies (BSA), including multi-layer and hexagonal lattice have been suggested and the effect of them has been investigated by MCNP4C Monte Carlo code. The results show that the proposed BSA can provide the qualified epithermal neutron beam for BNCT. The final epithermal neutron flux is about 6e9 n/cm2.s. The final proposed BSA has some different advantages: 1) it consists of usual and well-known materials (Pb, Al, Fluental and Cd); 2) it has a simple geometry; 3) it does not need any additional gamma filter; 4) it can provide high flux of epithermal neutrons. As this type of neutron source is under development in the world, it seems that they can be used clinically in a hospital considering the proposed BSA.

  16. Gel dosimeters as useful dose and thermal-fluence detectors in Boron Neutron Capture Therapy (BNCT)

    Energy Technology Data Exchange (ETDEWEB)

    Gambarini, G.; Valente, M. [Department of Physics of the University and INFN, Via Celoria 16, I-20133 Milan (Italy); Moss, R.L.; Daquino, G.G.; Nievaart, V.A. [Joint Research Centre, Institute for Energy, P.O. Box 2, NL-1755ZG Petten, The Netherlands (Netherlands); Mariani, M.; Vanossi, E. [Department of Nuclear Engineering of Polytechnic, CESNEF, Via Ponzio, 34/3 - I-20133 Milan (Italy); Carrara, M. [Medical Physics Department, National Cancer Institute, Via Venezian 1, I-20131, Milan (Italy)

    2006-07-01

    The dosimetry method based on Fricke-Xylenol-Orange-infused gels in form of layers has shown noticeable potentiality for in-phantom or in-free-beam dose and thermal flux profiling and imaging in the high fluxes of thermal or epithermal neutrons utilised for boron neutron capture therapy (BNCT). Gel-dosimeters in form of layers give the possibility not only of obtaining spatial dose distributions but also of achieving measurements of each dose contribution in neutron fields. The discrimination of the various dose components is achieved by means of pixel-to-pixel manipulations of pairs of images obtained with gel-dosimeters having different isotopic composition. It is possible to place large dosimeters, detecting in such a way large dose images, because the layer geometry of dosimeters avoids sensitive variation of neutron transport due to the gel isotopic composition. Some results obtained after the last improvements of the method are reported. (Author)

  17. Neutron spectra measurement and comparison of the HFR and THOR BNCT beams.

    Science.gov (United States)

    Liu, Yuan-Hao; Nievaart, Sander; Tsai, Pi-En; Liu, Hong-Ming; Moss, Ray; Jiang, Shiang-Huei

    2009-07-01

    This paper aims to measure the spectra of HB11 (high flux reactor, HFR) and the Tsing Hua open-pool reactor (THOR) boron neutron capture therapy (BNCT) beams by multiple activation foils. The self-shielding corrections were made with the aid of MCNP calculations. The initial spectra were adjusted by a sophisticated process named coarse-scaling adjustment using SAND-EX, which can adjust a given coarse-group spectrum into a fine-group structure, i.e. 640 groups, with excellent continuity. The epithermal neutron flux of the THOR beam is about three times of HB11. The thermal neutron flux, boron and gold reaction rates along the central axis of a PMMA phantom are calculated for both adjusted spectra for comparison.

  18. Synthesis of optically active dodecaborate-containing L-amino acids for BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Kusaka, Shintaro [Department of Bioscience and Informatics, Graduate School of Life and Environmental Sciences, Osaka Prefecture University, 1-1 Gakuen-cho, Nakaku, Sakai (Japan); Hattori, Yoshihide, E-mail: y0shi_hattori@riast.osakafu-u.ac.jp [Department of Bioscience and Informatics, Graduate School of Life and Environmental Sciences, Osaka Prefecture University, 1-1 Gakuen-cho, Nakaku, Sakai (Japan); Uehara, Kouki; Asano, Tomoyuki [Stella Pharma Corporation, ORIX Kouraibashi Bldg. 5F 3-2-7 Kouraibashi, Chuo-ku, Osaka (Japan); Tanimori, Shinji; Kirihata, Mitsunori [Department of Bioscience and Informatics, Graduate School of Life and Environmental Sciences, Osaka Prefecture University, 1-1 Gakuen-cho, Nakaku, Sakai (Japan)

    2011-12-15

    A convenient and simple synthetic method of dodecaboratethio-L-amino acid, a new class of tumor-seeking boron carrier for BNCT, was accomplished from S-cyanoethylthioundecahydro-closo-dodecaborate (S-cyanoethyl-{sup 10}BSH, [{sup 10}B{sub 12}H{sub 11}]{sup 2-}SCH{sub 2}CH{sub 2}CN) and bromo-L-{alpha}-amino acids by nearly one step S-alkylation. An improved synthesis of S-cyanoethyl-{sup 10}BSH, a key starting compound for S-alkylation, was also performed by Michael addition of {sup 10}BSH with acryronitrile in high yield. Four kinds of new dodecaboratethio-L-amino acids were obtained in optically pure form without the need for any optical resolution.

  19. 40 CFR 60.560 - Applicability and designation of affected facilities.

    Science.gov (United States)

    2010-07-01

    ... (including expandable polystyrene) manufacturing processes, the affected facilities are each group of... apply to affected facilities involved in the manufacture of polypropylene, polyethylene, polystyrene, or... that are emitted intermittently. (2) For process emissions from polystyrene manufacturing...

  20. Neutron generator for BNCT based on high current ECR ion source with gyrotron plasma heating.

    Science.gov (United States)

    Skalyga, V; Izotov, I; Golubev, S; Razin, S; Sidorov, A; Maslennikova, A; Volovecky, A; Kalvas, T; Koivisto, H; Tarvainen, O

    2015-12-01

    BNCT development nowadays is constrained by a progress in neutron sources design. Creation of a cheap and compact intense neutron source would significantly simplify trial treatments avoiding use of expensive and complicated nuclear reactors and accelerators. D-D or D-T neutron generator is one of alternative types of such sources for. A so-called high current quasi-gasdynamic ECR ion source with plasma heating by millimeter wave gyrotron radiation is suggested to be used in a scheme of D-D neutron generator in the present work. Ion source of that type was developed in the Institute of Applied Physics of Russian Academy of Sciences (Nizhny Novgorod, Russia). It can produce deuteron ion beams with current density up to 700-800 mA/cm(2). Generation of the neutron flux with density at the level of 7-8·10(10) s(-1) cm(-2) at the target surface could be obtained in case of TiD2 target bombardment with deuteron beam accelerated to 100 keV. Estimations show that it is enough for formation of epithermal neutron flux with density higher than 10(9) s(-1) cm(-2) suitable for BNCT. Important advantage of described approach is absence of Tritium in the scheme. First experiments performed in pulsed regime with 300 mA, 45 kV deuteron beam directed to D2O target demonstrated 10(9) s(-1) neutron flux. This value corresponds to theoretical estimations and proofs prospects of neutron generator development based on high current quasi-gasdynamic ECR ion source.

  1. Dynamic infrared imaging of cutaneous melanoma and normal skin in patients treated with BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Santa Cruz, G.A. [Dpto. de Instrumentacion y Control, Comision Nacional de Energia Atomica, Av. del Libertador 8250 (1429), Buenos Aires (Argentina)], E-mail: santacr@cnea.gov.ar; Bertotti, J.; Marin, J. [Universidad Favaloro, Solis 453 (1078), Buenos Aires (Argentina); Gonzalez, S.J. [Dpto. de Instrumentacion y Control, Comision Nacional de Energia Atomica, Av. del Libertador 8250 (1429), Buenos Aires (Argentina); CONICET, Avda. Rivadavia 1917 (1033), Buenos Aires (Argentina); Gossio, S. [FCEyN, Pabellon II, Ciudad Universitaria (1428), Buenos Aires (Argentina); Alvarez, D. [Fundacion Favaloro, Av. Belgrano 1746 (1093), Buenos Aires (Argentina); Roth, B.M.C.; Menendez, P. [Instituto de Oncologia Angel H. Roffo, Av. San Martin 5481 (1417), Buenos Aires (Argentina); Pereira, M.D. [Agencia Nacional de Promocion Cientifica y Tecnologica, PAV 22393 (Argentina); Albero, M.; Cubau, L.; Orellano, P. [INVAP S.E., F.P. Moreno 1089 (R8400AMU), S.C. de Bariloche, Rio Negro (Argentina); Liberman, S.J. [Dpto. de Instrumentacion y Control, Comision Nacional de Energia Atomica, Av. del Libertador 8250 (1429), Buenos Aires (Argentina)

    2009-07-15

    We recently initiated a program aimed to investigate the suitability of dynamic infrared imaging for following-up nodular melanoma patients treated with BNCT. The reason that makes infrared imaging attractive is the fact that it constitutes a functional and non-invasive imaging method, providing information on the normal and abnormal physiologic response of the nervous and vascular systems, as well as the local metabolic rate and inflammatory processes that ultimately appear as differences in the skin temperature. An infrared camera, with a focal plane array of 320x240 uncooled ferroelectric detectors is employed, which provides a video stream of the infrared emission in the 7-14 {mu}m wavelength band. A double blackbody is used as reference for absolute temperature calibration. After following a protocol for patient preparation and acclimatization, a basal study is performed. Subsequently, the anatomic region of interest is subjected to a provocation test (a cold stimulus), which induces an autonomic vasoconstriction reflex in normal structures, thus enhancing the thermal contrast due to the differences in the vasculature of the different skin regions. Radiation erythema reactions and melanoma nodules possess typically a faster temperature recovery than healthy, non-irradiated skin. However, some other non-pathological structures are also detectable by infrared imaging, (e.g. scars, vessels, arteriovenous anastomoses and injuries), thus requiring a multi-study comparison in order to discriminate the tumor signal. Besides the superficial nodules, which are readily noticeable by infrared imaging, we have detected thermal signals that are coincident with the location of non-palpable nodules, which are observable by CT and ultrasound. Diffuse regions of fast temperature recovery after a cold stimulus were observed between the third and sixth weeks post-BNCT, concurrent with the clinical manifestation of radiation erythema. The location of the erythematous visible and

  2. APPLICATION OF LINEAR PROGRAMMING TO FACILITY MAINTENANCE PROBLEMS IN THE NAVY SHORE ESTABLISHMENT.

    Science.gov (United States)

    LINEAR PROGRAMMING ), (*NAVAL SHORE FACILITIES, MAINTENANCE), (*MAINTENANCE, COSTS, MATHEMATICAL MODELS, MANAGEMENT PLANNING AND CONTROL, MANPOWER, FEASIBILITY STUDIES, OPTIMIZATION, MANAGEMENT ENGINEERING.

  3. 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.

  4. 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...

  5. Application of chlorine dioxide as an oilfield-facilities-treatment fluid

    Energy Technology Data Exchange (ETDEWEB)

    Romaine, J. [Rio Linda Chemical Co., Inc., Sugar Land, TX (United States); Strawser, T.J. [Exxon Co. USA, Gillette, WY (United States); Knippers, M.L. [Nalco/Exxon Energy Chemicals L.P., Sugar Land, TX (United States)

    1996-02-01

    Both mechanical and chemical treatments are used to clean waterflood-injection distribution systems whose efficiency has been reduced as a result of plugging material, such as iron sulfide (FeS) containing sludge. Most mechanical treatments rely on uniform-line diameter to be effective, while chemical treatments require good contact with the plugging material for efficient removal. This paper describes the design and operation of a new innovative application using chlorine dioxide (ClO{sub 2}) for the removal of FeS sludge from waterflood-injection distribution systems. The use of ClO{sub 2} for continuous treatment of injection brines will also be discussed. Exxon USA`s Hartzog Draw facility in Gillette, WY, was the site for the application described. A total of 4,500 bbl of ClO{sub 2} was pumped in three phases to clean 66 miles of the waterflood-distribution system. Results indicated that ClO{sub 2} was effective in cleaning the well guard screens, the injection lines, and the injection wells. The addition of excess ClO{sub 2} to the frac tanks used to collect the treatment fluids also reduced waste handling and disposal costs.

  6. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; O' Kelly, D S

    2006-05-08

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

  8. Microdosimetric evaluation of the neutron field for BNCT at Kyoto University reactor by using the PHITS code.

    Science.gov (United States)

    Baba, H; Onizuka, Y; Nakao, M; Fukahori, M; Sato, T; Sakurai, Y; Tanaka, H; Endo, S

    2011-02-01

    In this study, microdosimetric energy distributions of secondary charged particles from the (10)B(n,α)(7)Li reaction in boron-neutron capture therapy (BNCT) field were calculated using the Particle and Heavy Ion Transport code System (PHITS). The PHITS simulation was performed to reproduce the geometrical set-up of an experiment that measured the microdosimetric energy distributions at the Kyoto University Reactor where two types of tissue-equivalent proportional counters were used, one with A-150 wall alone and another with a 50-ppm-boron-loaded A-150 wall. It was found that the PHITS code is a useful tool for the simulation of the energy deposited in tissue in BNCT based on the comparisons with experimental results.

  9. Feasibility of sealed D-T neutron generator as neutron source for liver BNCT and its beam shaping assembly.

    Science.gov (United States)

    Liu, Zheng; Li, Gang; Liu, Linmao

    2014-04-01

    This paper involves the feasibility of boron neutron capture therapy (BNCT) for liver tumor with four sealed neutron generators as neutron source. Two generators are placed on each side of the liver. The high energy of these emitted neutrons should be reduced by designing a beam shaping assembly (BSA) to make them useable for BNCT. However, the neutron flux decreases as neutrons pass through different materials of BSA. Therefore, it is essential to find ways to increase the neutron flux. In this paper, the feasibility of using low enrichment uranium as a neutron multiplier is investigated to increase the number of neutrons emitted from D-T neutron generators. The neutron spectrum related to our system has a proper epithermal flux, and the fast and thermal neutron fluxes comply with the IAEA recommended values.

  10. AB-BNCT beam shaping assembly based on {sup 7}Li(p,n){sup 7}Be reaction optimization

    Energy Technology Data Exchange (ETDEWEB)

    Minsky, D.M., E-mail: minsky@tandar.cnea.gov.ar [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral Paz 1499 (B1650KNA), San Martin, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, UNSAM, M. de Irigoyen 3100 (1650), San Martin (Argentina)] [CONICET, Av. Rivadavia 1917 (C1033AAJ), Buenos Aires (Argentina); Kreiner, A.J. [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral Paz 1499 (B1650KNA), San Martin, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, UNSAM, M. de Irigoyen 3100 (1650), San Martin (Argentina)] [CONICET, Av. Rivadavia 1917 (C1033AAJ), Buenos Aires (Argentina); Valda, A.A. [Gerencia de Investigacion y Aplicaciones, CNEA, Av. Gral Paz 1499 (B1650KNA), San Martin, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, UNSAM, M. de Irigoyen 3100 (1650), San Martin (Argentina)

    2011-12-15

    A numerical optimization of a Beam Shaping Assembly (BSA) for Accelerator Based-Boron Neutron Capture Therapy (AB-BNCT) has been performed. The reaction {sup 7}Li(p,n){sup 7}Be has been considered using a proton beam on a lithium fluoride target. Proton energy and the dimensions of a simple BSA geometry have been varied to obtain a set of different configurations. The optimal configuration of this set is shown.

  11. Considerations for boron neutron capture therapy studies; Consideracoes sobre o estudo da BNCT (terapia de captura neutronica por boro)

    Energy Technology Data Exchange (ETDEWEB)

    Faria Gaspar, P. de

    1994-12-31

    Radiotherapy is indispensable as a mean to eradicate deeply or infiltrating tumor tissue that can not be removed surgically. Therefore, it is not selective and may also kill the surrounding health tissue. The principle of BNCT (Boron Neutron Capture Therapy) consist in targeting a tumor selectively with a boron-10 compound. This nuclide has a large capture cross section for thermal neutrons and the nuclear reaction and the delivered energy in locus will selective the tumor. Since its initial proposal in 1963 BNCT has made much progress, however it is not used in a routine treatment. In this work it was approached some complex procedures, as the obtention of selective boron compounds, the adequate set up of neutron beams, the biodistribution, the in vivo and in vitro studies, and also human patients treatments. This work provide fundamentals about BNCT to professional of different areas of knowledge since it comprises multidisciplinary study. It includes appendixes for the ones not related to the field for a better comprehension of the many aspects involved. It is also presented a glossary containing technical and basic aspects involved. It is also presented a glossary containing technical and basic terms referred in the work. (author). 174 refs, 1 fig, 12 apps.

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

    Energy Technology Data Exchange (ETDEWEB)

    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 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 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 D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs.

  13. Sources and potential application of waste heat utilization at a gas processing facility

    Science.gov (United States)

    Alshehhi, Alyas Ali

    Waste heat recovery (WHR) has the potential to significantly improve the efficiency of oil and gas plants, chemical and other processing facilities, and reduce their environmental impact. In this Thesis a comprehensive energy audit at Abu Dhabi Gas Industries Ltd. (GASCO) ASAB gas processing facilities is undertaken to identify sources of waste heat and evaluate their potential for on-site recovery. Two plants are considered, namely ASAB0 and ASAB1. Waste heat evaluation criteria include waste heat grade (i.e., temperature), rate, accessibility (i.e., proximity) to potential on-site waste heat recovery applications, and potential impact of recovery on installation performance and safety. The operating parameters of key waste heat source producing equipment are compiled, as well as characteristics of the waste heat streams. In addition, potential waste heat recovery applications and strategies are proposed, focusing on utilities, i.e., enhancement of process cooling/heating, electrical/mechanical power generation, and steam production. The sources of waste heat identified at ASAB facilities consist of gas turbine and gas generator exhaust gases, flared gases, excess propane cooling capacity, excess process steam, process gas air-cooler heat dissipation, furnace exhaust gases and steam turbine outlet steam. Of the above waste heat sources, exhaust gases from five gas turbines and one gas generator at ASAB0 plant, as well as from four gas turbines at ASAB1 plant, were found to meet the rate (i.e., > 1 MW), grade (i.e., > 180°C), accessibility (i.e., absorption refrigeration unit for gas turbine inlet air cooling, which would result in additional electric or mechanical power generation, and pre-cooling of process gas, which could reduce the need for or eliminate air coolers, as well as reduce propane chiller load, and ii) serve for heating of lean gas, which would reduce furnace load. At ASAB1, it is proposed that exhaust gases from all four gas turbines be used to

  14. Microdosimetric measurements in the thermal neutron irradiation facility of LENA reactor.

    Science.gov (United States)

    Colautti, P; Moro, D; Chiriotti, S; Conte, V; Evangelista, L; Altieri, S; Bortolussi, S; Protti, N; Postuma, I

    2014-06-01

    A twin TEPC with electric-field guard tubes has been constructed to be used to characterize the BNCT field of the irradiation facility of LENA reactor. One of the two mini TEPC was doped with 50ppm of (10)B in order to simulate the BNC events occurring in BNCT. By properly processing the two microdosimetric spectra, the gamma, neutron and BNC spectral components can be derived with good precision (~6%). However, direct measurements of (10)B in some doped plastic samples, which were used for constructing the cathode walls, point out the scarce accuracy of the nominal (10)B concentration value. The influence of the Boral(®) door, which closes the irradiation channel, has been measured. The gamma dose increases significantly (+51%) when the Boral(®) door is closed. The crypt-cell-regeneration weighting function has been used to measure the quality, namely the RBEµ value, of the radiation field in different conditions. The measured RBEµ values are only partially consistent with the RBE values of other BNCT facilities.

  15. Application of an Optimized Entropy-TOPSIS Multicriteria Decision Making Model to Facilities Management

    Institute of Scientific and Technical Information of China (English)

    WANG Zhao-hong; ZHAN Wei; QIU Wan-hua

    2006-01-01

    Performance evaluation of facilities management plays a key role in the facilities management process. This paper proposes an optimized multicriteria decision making model to evaluate the performance of facilities management in schools in Hong Kong. In this model, entropy weights acted as weight coefficients for evaluated criteria in order to avoid uncertainty and randomicity of subjective judgments. Besides, the TOPSIS method was incorporated in this model. Then this model was employed to evaluate the performance of facilities management in classrooms, offices and laboratories and satisfying results were obtained. Moreover, findings indicated that one of the schools could be rehabilitated rather than removed.

  16. 40 CFR 60.260 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ..., silicomanganese, ferromanganese silicon, or calcium carbide; and dust-handling equipment. (b) Any facility under... submerged arc furnaces which produce silicon metal, ferrosilicon, calcium silicon, silicomanganese...

  17. A Study on Applicability of Distributed Energy Generation, Storage and Consumption within Small Scale Facilities

    Directory of Open Access Journals (Sweden)

    Jesús Rodríguez-Molina

    2016-09-01

    Full Text Available Distributed generation and storage of energy, conceived as one of the prominent applications of the Smart Grid, has become one of the most popular ways for generation and usage of electricity. Not only does it offer environmental advantages and a more decentralized way to produce energy, but it also enables former consumers to become producers (thus turning them into prosumers. Alternatively, regular power production and consumption is still widely used in most of the world. Unfortunately, accurate business models representations and descriptive use cases for small scale facilitates, either involved in distributed energy or not, have not been provided in a descriptive enough manner. What is more, the possibilities that electricity trade and its storage and consumption activities offer for small users to obtain profits are yet to be addressed and offered to the research community in a thorough manner, so that small consumers will use them to their advantage. This paper puts forward a study on four different business models for small scale facilities and offers an economical study on how they can be deployed as a way to offer profitability for end users and new companies, while at the same time showing the required technological background to have them implemented.

  18. Facile synthesis of PdSx/C porous nanospheres and their applications for ethanol oxidation reaction

    Science.gov (United States)

    Zhang, Qiang; Zhang, Fuhua; Ma, Xuemei; Zheng, Yiqun; Hou, Shifeng

    2016-12-01

    We report a facile approach for the synthesis of carbon-supported palladium polysulphide porous nanospheres (PdSx/C) and their applications for ethanol oxidation reaction. Typical synthesis started with generation of palladium/poly (3,4-ethylenedioxythiophene)(Pd/PEDOT) nanospheres, followed by a calcination process at an optimized temperature to form PdSx/C, with an average size of 2.47 ± 0.60 and 50 nm of PdSx nanoparticles and carbon porous nanospheres, respectively. Various techniques, such as scanning electron microscopy (SEM), transmission electron microscopy (TEM), X-ray diffraction (XRD), Raman spectroscopy, X-ray photoelectron spectroscopy (XPS), and electrochemical techniques were performed to characterize their morphologies, compositions and structures. In contrary to most Pd-based electrochemical catalysts that could be easily poised with trace sulfur during the catalytic oxidation process, the as-prepared PdSx/C porous nanospheres exhibited high electrocatalytic activities and stabilities for the electrochemical catalytic oxidation of ethanol in alkaline medium. In particular, the forward peak current intensity achieved 162.1 mA mg-1 and still maintained at 46.7 mA mg-1 even after 1000 cycles. This current work not only offers a novel type of fuel-cell catalyst for ethanol oxidation reaction, but also provides a possible route for solving the sulfur-poisoning problem in catalysis.

  19. 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.

  20. 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...

  1. 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

  2. A discussion of regulatory requirements and air dispersion modeling approaches applicable to U.S. chemical demilitarization facilities.

    Science.gov (United States)

    Higgins, B W; Robbins, L B; Litynski, J

    1998-09-01

    Owners of hazardous waste treatment, storage, and disposal facilities, and certain major air pollution sources, must conduct several separate ambient air dispersion modeling analyses before beginning construction of new facilities or modifying existing facilities. These analyses are critical components of the environmental permitting and facility certification processes and must be completed to the satisfaction of federal, state, and local regulatory authorities. The U.S. Army has conducted air dispersion modeling for its proposed chemical agent disposal facilities to fulfill the following environmental regulatory and risk management requirements: (1) Resource Conservation and Recovery Act human health and ecological risk assessment analysis for the hazardous waste treatment and storage permit applications, (2) Quantitative Risk Assessment to support the site-specific risk management programs, and (3) Prevention of Significant Deterioration ambient air impact analysis for the air permit applications. The purpose of these air dispersion modeling studies is to show that the potential impacts on human health and the environment, due to operation of the chemical agent disposal facilities, are acceptable. This paper describes and compares the types of air dispersion models, modeling input data requirements, modeling algorithms, and approaches used to satisfy the three environmental regulatory and risk management requirements listed above. Although this paper discusses only one industry (i.e., chemical demilitarization), the information it contains could help those in other industries who need to communicate to the public the purpose and objectives of each modeling analysis. It may also be useful in integrating the results of each analysis into an overarching summary of compliance and potential risks.

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

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minhwan; Jeong, Ji-Young; Kim, Jongman [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    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.

  4. Development of particle induced X-ray emission facility at cyclotron laboratory and its prospective applications

    Energy Technology Data Exchange (ETDEWEB)

    Puri, N.K. [Department of Applied Physics, Delhi Technological Universily (Formerly Delhi College of Engineering, DCE), Delhi (India); Garg, M.L. [Department of Bio-Physics, Panjab Universily, Chandigarh (India); Govil, I.M. [Department of Physics, Panjab University, Chandigarh (India)

    2013-07-01

    Full text: We are presenting here a description of modifications in the Variable Energy Cyclotron (VEC) Chandigarh along with the installation of Proton Induced X-ray Emission (PIXE) setup. The installation of new main magnet power supply of 400A/125V out put with 10 ppm stability (model 853 M/S Danfysik, Denmark) and a new stabilized solid state power supply for RF oscillator gave the beam characteristics substantially good enough for PIXE work. A new chamber [1] was designed to cater for Proton Induced Gamma Emission (PIGE) and Rutherford Back Scattering (RBS) analysis along with PIXE measurements. The HPGe X-ray detector, the Ge(Li) -ray detector and a Silicon Surface Barrier (SSB) detector could be mounted simultaneously in the chamber. A Turbo-Molecular vacuum pump was provided to produce a clean vacuum of the order of 10{sup -7} torr in PIXE chamber. A remotely controlled stepper motor could move the 12/24-position target holder. Beam size optimization along with the minimization of background was done with the help of graphite collimators, thus making the setup suitable for practical applications. We attempted to address some of the limitations using PIXE facility of Institute of Physics (IOP), India [2] and incorporated modifications (e.g. chamber design, sample holder etc.) in our set-up. Preliminary experiments for the PIXE analysis of aerosol samples, gunshot residues samples and bone samples were presented. The aerosol samples were collected using aerosol sampling kit which involves Millipore diaphragmatic vacuum pump and Sequential Filter Unit (SFU) with coarse pored Nucleo pore polycarbonate filter in such a manner that the particles passing through the 8m pore size filter were collected on the 0.4m pore size filter. Two different pistols viz. 7.65mm Indian made and 7.63mm Germany made were used to fire at a filter paper target with card board and cotton wool backing from a distance of 3 feet. Two sheets of Whatman filter paper were used to form the

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

    Directory of Open Access Journals (Sweden)

    J. Schulz

    2008-05-01

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

  6. Dose calculation and in-phantom measurement in BNCT using response matrix method.

    Science.gov (United States)

    Rahmani, Faezeh; Shahriari, Majid

    2011-12-01

    In-phantom measurement of physical dose distribution is very important for Boron Neutron Capture Therapy (BNCT) planning validation. If any changes take place in therapeutic neutron beam due to the beam shaping assembly (BSA) change, the dose will be changed so another group of simulations should be carried out for dose calculation. To avoid this time consuming procedure and speed up the dose calculation to help patients not wait for a long time, response matrix method was used. This procedure was performed for neutron beam of the optimized BSA as a reference beam. These calculations were carried out using the MCNPX, Monte Carlo code. The calculated beam parameters were measured for a SNYDER head phantom placed 10 cm away from beam the exit of the BSA. The head phantom can be assumed as a linear system and neutron beam and dose distribution can be assumed as an input and a response of this system (head phantom), respectively. Neutron spectrum energy was digitized into 27 groups. Dose response of each group was calculated. Summation of these dose responses is equal to a total dose of the whole neutron/gamma spectrum. Response matrix is the double dimension matrix (energy/dose) in which each parameter represents a depth-dose resulted from specific energy. If the spectrum is changed, response of each energy group may be differed. By considering response matrix and energy vector, dose response can be calculated. This method was tested for some BSA, and calculations show statistical errors less than 10%.

  7. BDTPS The BNCT Treatment Planning System jointly developed at DIMNP and JRC/IE

    CERN Document Server

    Daquino, G G; Mazzini, M; Moss, R; Muzi, L; International Workshop on "Neutron Capture Therapy: State of the art"

    2003-01-01

    The idea to couple the Treatment Planning System (TPS) to the information on the real boron distribution in the patient is the main added value of the new methodology set-up at DIMNP of University of Pisa, in collaboration with the JRC of Petten (NL). The methodology has been implemented in the new TPS, called BDTPS (Boron Distribution Treatment Planning System), which takes into account the actual boron distribution in the patient brain, while the standard TPS assumes a uniform boron distribution, absolutely far from the reality. Nowadays, Positron Emission Tomography (PET) is able to provide this in vivo information. The new TPS, based on the Monte Carlo technique, has been validated comparing the main BNCT parameters (thermal flux, boron dose, etc.) as measured during the irradiation of a special heterogeneous boron phantom (HEBOM), ad hoc designed, as calculated by the BDTPS and by the standard TPS SERA. An evident SERA overestimation of the thermal neutron flux, as well as the boron dose, has been detect...

  8. An optimized neutron-beam shaping assembly for accelerator-based BNCT.

    Science.gov (United States)

    Burlon, A A; Kreiner, A J; Valda, A A; Minsky, D M

    2004-11-01

    Different materials and proton beam energies have been studied in order to search for an optimized neutron production target and beam shaping assembly for accelerator-based BNCT. The solution proposed in this work consists of successive stacks of Al, polytetrafluoroethylene, commercially known as Teflon, and LiF as moderator and neutron absorber, and Pb as reflector. This assembly is easy to build and its cost is relatively low. An exhaustive Monte Carlo simulation study has been performed evaluating the doses delivered to a Snyder model head phantom by a neutron production Li-metal target based on the (7)Li(p,n)(7)Be reaction for proton bombarding energies of 1.92, 2.0, 2.3 and 2.5 MeV. Three moderator thicknesses have been studied and the figures of merit show the advantage of irradiating with near-resonance-energy protons (2.3 MeV) because of the relatively high neutron yield at this energy, which at the same time keeps the fast neutron healthy tissue dose limited and leads to the lowest treatment times. A moderator of 34 cm length has shown the best performance among the studied cases.

  9. An optimized neutron-beam shaping assembly for accelerator-based BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Burlon, A.A. E-mail: burlon@tandar.cnea.gov.ar; Kreiner, A.J.; Valda, A.A.; Minsky, D.M

    2004-11-01

    Different materials and proton beam energies have been studied in order to search for an optimized neutron production target and beam shaping assembly for accelerator-based BNCT. The solution proposed in this work consists of successive stacks of Al, polytetrafluoroethylene, commercially known as Teflon[reg ], and LiF as moderator and neutron absorber, and Pb as reflector. This assembly is easy to build and its cost is relatively low. An exhaustive Monte Carlo simulation study has been performed evaluating the doses delivered to a Snyder model head phantom by a neutron production Li-metal target based on the {sup 7}Li(p,n){sup 7}Be reaction for proton bombarding energies of 1.92, 2.0, 2.3 and 2.5 MeV. Three moderator thicknesses have been studied and the figures of merit show the advantage of irradiating with near-resonance-energy protons (2.3 MeV) because of the relatively high neutron yield at this energy, which at the same time keeps the fast neutron healthy tissue dose limited and leads to the lowest treatment times. A moderator of 34 cm length has shown the best performance among the studied cases.

  10. Practice on Application of TPM Facility Management Mode%TPM设备管理模式导入实践

    Institute of Scientific and Technical Information of China (English)

    曹玉芬

    2014-01-01

    介绍TPM管理模式的内容,具体分析导入过程及取得成效,指出TPM管理模式导入有利于企业综合竞争力的提升。%The paper describes what TPM management is and How it is applied specifically as well as what effect it brings. The application of TPM facility management mode can improve the comprehensive competitiveness of an enterprise.

  11. 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.

  12. 40 CFR 60.120 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ...: Pot furnaces of more than 250 kg (550 lb) charging capacity, blast (cupola) furnaces, and reverberatory furnaces. (b) Any facility under paragraph (a) of this section that commences construction...

  13. Medical gamma processing facility in Riyadh, Saudi Arabia, and radiation applications

    Energy Technology Data Exchange (ETDEWEB)

    Grecz, N.; Hahn, E.W.; Jouris, W.E.

    1985-09-01

    A medical cobalt-60 facility was opened at King Faisal Specialist Hospital and Research Center in 1984. Features of the facility are that it can be heated to 120-190F during irradiation and has an on-line 30 kw microwave oven. It can be used for small scale batch irradiation or large scale conveyor irradiation. Programs under development are the sterilization of hospital supplies, radiation processing of Saudi foods and radiation of infectious hospital wastes.

  14. Neutron field characterization in the installation for BNCT study in the IEA-R1 reactor; Caracterizacao do campo de neutrons na instalacao para estudo em BNCT no reator IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Carneiro Junior, Valdeci

    2008-07-01

    This work aims to characterize the mixed neutron and gamma field, in the sample irradiation position, in a research installation for Boron Neutron Capture Therapy (BNCT), in the IPEN IEA-R1 reactor. The BNCT technique has been studied as a safe and selective option in the treatment of resistant cancerigenous tumors or considered non-curable by the conventional techniques, for example, the Glioblastoma Multiform - a brain cancerigenous tumor. Neutron flux measurements were carried out: thermal, resonance and fast, as well as neutron and gamma rays doses, in the sample position, using activation foils detectors and thermoluminescent dosimeters. For the determination of the neutron spectrum and intensity, a set of different threshold activation foils and gold foils covered and uncovered with cadmium irradiated in the installation was used, analyzed by a high Pure Germanium semiconductor detector, coupled to an electronic system suitable for gamma spectrometry. The results were processed with the SAND-BP code. The doses due to gamma and neutron rays were determined using thermoluminescent dosimeters TLD 400 and TLD 700 sensitive to gamma and TLD 600, sensitive to neutrons. The TLDs were selected and used for obtaining the calibration curves - dosimeter answer versus dose - from each of the TLD three types, which were necessary to calculate the doses due to neutron and gamma, in the sample position. The radiation field, in the sample irradiation position, was characterized flux for thermal neutrons of 1.39.10{sup 8} {+-} 0,12.10{sup 8} n/cm{sup 2}s the doses due to thermal neutrons are three times higher than those due to gamma radiation and confirm the reproducibility and consistency of the experimental findings obtained. Considering these results, the neutron field and gamma radiation showed to be appropriated for research in BNCT. (author)

  15. The ERA2 facility: towards application of a fiber-based astronomical spectrograph for imaging spectroscopy in life sciences

    CERN Document Server

    Roth, Martin M; Tarcea, Nicolae; Popp, Jürgen; Adelhelm, Silvia; Stolz, Marvin; Kelz, Andreas; Sandin, Christer; Bauer, Svend-Marian; Fechner, Thomas; Jahn, Thomas; Popow, Emil; Roth, Bernhard; Singh, Paul; Srivastava, Mudit; Wolter, Dieter

    2012-01-01

    Astronomical instrumentation is most of the time faced with challenging requirements in terms of sensitivity, stability, complexity, etc., and therefore leads to high performance developments that at first sight appear to be suitable only for the specific design application at the telescope. However, their usefulness in other disciplines and for other applications is not excluded. The ERA2 facility is a lab demonstrator, based on a high-performance astronomical spectrograph, which is intended to explore the innovation potential of fiber-coupled multi-channel spectroscopy for spatially resolved spectroscopy in life science, material sciences, and other areas of research.

  16. Toward a clinical application of ex situ boron neutron capture therapy for lung tumors at the RA-3 reactor in Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Farías, R. O.; Trivillin, V. A.; Portu, A. M.; Schwint, A. E.; González, S. J., E-mail: srgonzal@cnea.gov.ar [Comisión Nacional de Energía Atómica (CNEA), San Martín 1650, Argentina and Consejo Nacional de Investigaciones Científicas y Técnicas (CONICET), Buenos Aires 1033 (Argentina); Garabalino, M. A.; Monti Hughes, A.; Pozzi, E. C. C.; Thorp, S. I.; Curotto, P.; Miller, M. E.; Santa Cruz, G. A.; Saint Martin, G. [Comisión Nacional de Energía Atómica (CNEA), San Martín 1650 (Argentina); Ferraris, S.; Santa María, J.; Rovati, O.; Lange, F. [CIDME, Universidad Maimónides, Buenos Aires 1405 (Argentina); Bortolussi, S. [Istituto Nazionale di Fisica Nucleare, Sezione di Pavia 27100 (Italy); Altieri, S. [Istituto Nazionale di Fisica Nucleare, Sezione di Pavia 27100, Italy and Dipartimento di Fisica, Università di Pavia, Pavia 27100 (Italy)

    2015-07-15

    Purpose: Many types of lung tumors have a very poor prognosis due to their spread in the whole organ volume. The fact that boron neutron capture therapy (BNCT) would allow for selective targeting of all the nodules regardless of their position, prompted a preclinical feasibility study of ex situ BNCT at the thermal neutron facility of RA-3 reactor in the province of Buenos Aires, Argentina. (L)-4p-dihydroxy-borylphenylalanine fructose complex (BPA-F) biodistribution studies in an adult sheep model and computational dosimetry for a human explanted lung were performed to evaluate the feasibility and the therapeutic potential of ex situ BNCT. Methods: Two kinds of boron biodistribution studies were carried out in the healthy sheep: a set of pharmacokinetic studies without lung excision, and a set that consisted of evaluation of boron concentration in the explanted and perfused lung. In order to assess the feasibility of the clinical application of ex situ BNCT at RA-3, a case of multiple lung metastases was analyzed. A detailed computational representation of the geometry of the lung was built based on a real collapsed human lung. Dosimetric calculations and dose limiting considerations were based on the experimental results from the adult sheep, and on the most suitable information published in the literature. In addition, a workable treatment plan was considered to assess the clinical application in a realistic scenario. Results: Concentration-time profiles for the normal sheep showed that the boron kinetics in blood, lung, and skin would adequately represent the boron behavior and absolute uptake expected in human tissues. Results strongly suggest that the distribution of the boron compound is spatially homogeneous in the lung. A constant lung-to-blood ratio of 1.3 ± 0.1 was observed from 80 min after the end of BPA-F infusion. The fact that this ratio remains constant during time would allow the blood boron concentration to be used as a surrogate and indirect

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

    Energy Technology Data Exchange (ETDEWEB)

    Seidensticker, R.W. (Argonne National Lab., IL (USA))

    1991-06-01

    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. The level of assurance of performance for such isolation systems for a nuclear power plant will be much greater than that required for non-nuclear facilities. The question is to what extent can R and D for non-nuclear use of seismic isolation be applied to a nuclear power plant. Experience shows that considerable effort is needed to adapt any technology to nuclear power facilities. This paper reviews the 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. (orig.).

  18. Biodistribution of the boron carriers boronophenylalanine (BPA) and/or decahydrodecaborate (GB-10) for Boron Neutron Capture Therapy (BNCT) in an experimental model of lung metastases

    Energy Technology Data Exchange (ETDEWEB)

    D.W. Nigg; Various Others

    2014-06-01

    BNCT was proposed for the treatment of diffuse, non-resectable tumors in the lung. We performed boron biodistribution studies with 5 administration protocols employing the boron carriers BPA and/or GB-10 in an experimental model of disseminated lung metastases in rats. All 5 protocols were non-toxic and showed preferential tumor boron uptake versus lung. Absolute tumor boron concentration values were therapeutically useful (25–76 ppm) for 3 protocols. Dosimetric calculations indicate that BNCT at RA-3 would be potentially therapeutic without exceeding radiotolerance in the lung.

  19. The status of Tsukuba BNCT trial: BPA-based boron neutron capture therapy combined with X-ray irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, T., E-mail: tetsu_tsukuba@yahoo.co.jp [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, Tennodai 1-1-1, Tsukuba (Japan)] [Department of Radiation Oncology, Graduate School of Comprehensive Human Science, University of Tsukuba, Tennodai 1-1-1, Tsukuba (Japan); Nakai, K. [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, Tennodai 1-1-1, Tsukuba (Japan); Nariai, T. [Department of Neurosurgery, Tokyo Medical and Dental University, Yushima 1-5-45, Bunkyo-ku, Tokyo (Japan); Kumada, H.; Okumura, T.; Mizumoto, M.; Tsuboi, K. [Department of Radiation Oncology, Graduate School of Comprehensive Human Science, University of Tsukuba, Tennodai 1-1-1, Tsukuba (Japan); Zaboronok, A.; Ishikawa, E.; Aiyama, H.; Endo, K.; Takada, T.; Yoshida, F.; Shibata, Y.; Matsumura, A. [Department of Neurosurgery, Graduate School of Comprehensive Human Science, University of Tsukuba, Tennodai 1-1-1, Tsukuba (Japan)

    2011-12-15

    The phase II trial has been prepared to assess the effectiveness of BPA (250 mg/kg)-based NCT combined with X-ray irradiation and temozolomide (75 mg/m{sup 2}) for the treatment of newly diagnosed GBM. BPA uptake is determined by {sup 18}F-BPA-PET and/or {sup 11}C-MET-PET, and a tumor with the lesion to normal ratio of 2 or more is indicated for BNCT. The maximum normal brain point dose prescribed was limited to 13.0 Gy or less. Primary end point is overall survival.

  20. 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.

  1. Global Daily Sea Ice Concentration Reprocessing Data Set for 1978-2007 from the EUMETSAT Ocean and Sea Ice Satellite Application Facility (NCEI 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...

  2. Design study of multi-imaging plate system for BNCT irradiation field at Kyoto university reactor.

    Science.gov (United States)

    Tanaka, Kenichi; Sakurai, Yoshinori; Kajimoto, Tsuyoshi; Tanaka, Hiroki; Takata, Takushi; Endo, Satoru

    2016-09-01

    The converter configuration for a multi-imaging plate system was investigated for the application of quality assurance in the irradiation field profile for boron neutron capture therapy. This was performed by the simulation calculation using the PHITS code in the fields at the Heavy Water Neutron Irradiation Facility of Kyoto University Reactor. The converter constituents investigated were carbon for gamma rays, and polyethylene with and without LiF at varied (6)Li concentration for thermal, epithermal, and fast neutrons. Consequently, potential combinations of the converters were found for two components, gamma rays and thermal neutrons, for the standard thermal neutron mode and three components of gamma rays, epithermal neutrons, and thermal or fast neutrons, for the standard mixed or epithermal neutron modes, respectively.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  4. 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

  5. Real Estate Site Selection: An Application of Artificial Intelligence for Military Retail Facilities

    Science.gov (United States)

    2006-09-01

    Information and Spatial Analysis (SCGISA), University of Sheffield. Kotler , P . (1984). Marketing Management: Analysis, Planning, and Control...Spatial Distribution of Retail Sales. Journal of Real Estate Finance and Economics, Vol. 31 Iss. 1, 53. Lilien, G., & Kotler , P . (1983). Marketing ...commissaries). The current business model for military retail facilities may not be optimized based upon current trends market data. Optimizing

  6. 76 FR 64388 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses; Involving No...

    Science.gov (United States)

    2011-10-18

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

  7. 40 CFR 60.740 - Applicability and designation of affected facility.

    Science.gov (United States)

    2010-07-01

    ... for sale to another company for use in an affected facility (coating operation); (2) Coating mix... fraction; (3) Web coating operations that print an image on the surface of the substrate or any coating applied on the same printing line that applies the image....

  8. 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.

  9. 75 FR 62592 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2010-10-12

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

  10. 45 CFR 1309.10 - Applications for the purchase, construction and major renovation of facilities.

    Science.gov (United States)

    2010-10-01

    ... available for a playground and for parking). If incidental alterations and renovations or major renovations...)(C)) and its implementing regulations (40 CFR parts 1500 through 1508), as well as a report showing the results of tests for environmental hazards present in the facility, ground water, and soil...

  11. 40 CFR 60.100a - Applicability, designation of affected facility, and reconstruction.

    Science.gov (United States)

    2010-07-01

    ... facility, provided it processes gases produced within a petroleum refinery. (b) Except for flares, the...: (1) Any new piping from a refinery process unit or fuel gas system is physically connected to the... of Performance for Petroleum Refineries for Which Construction, Reconstruction, or...

  12. 40 CFR 60.100 - Applicability, designation of affected facility, and reconstruction.

    Science.gov (United States)

    2010-07-01

    ... petroleum refineries: fluid catalytic cracking unit catalyst regenerators, fuel gas combustion devices, and... boundaries of a petroleum refinery to be an affected facility, provided it processes gases produced within a petroleum refinery. (b) Any fluid catalytic cracking unit catalyst regenerator or fuel gas combustion...

  13. 75 FR 70032 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-11-16

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

  14. 75 FR 76041 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-12-07

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

  15. 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.

  16. 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

  17. 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.

  18. The pulsed beam facility at the 3 MV Van de Graaff accelerator in Florence: Overview and examples of applications

    Science.gov (United States)

    Taccetti, N.; Giuntini, L.; Casini, G.; Stefanini, A. A.; Chiari, M.; Fedi, M. E.; Mandò, P. A.

    2002-04-01

    An electrostatic chopper has been installed at the KN 3000 accelerator in Florence to obtain short beam pulses with a number of particles per pulse whose average value can be chosen by varying the current intensity at the deflector plates input. Beam pulses can be obtained containing an average number of particles per pulse from less than one to thousands. The transmitted beam pulses can be as short as 200 ps FWHM, at a repetition rate up to about 100 kHz. Among the many applications of the facility, the direct measurement of energy loss and straggling of protons in Kapton and aluminium is reported. In this measurement, the facility has been tuned for transmission of mainly single-proton pulses; the beam energy is directly measured downstream with a good energy-resolution detector, without and with absorbers in front. In general, measurements of this kind can be directed both to study the basic processes of charged particles interactions in materials, or more practically to obtain the effective values of energy parameters useful in many IBA applications, avoiding the need to rely on simulations or theoretical estimates. Also briefly described is an application to Si-detector testing. In this case, the facility has been tuned for transmission of pulses containing many hundreds of protons of energy Ep=2.5 MeV and the detector is directly exposed to the pulses. Spectra containing equally spaced peaks at energies multiple of Ep are obtained and the response linearity of the detector plus electronics system can thus be checked.

  19. The pulsed beam facility at the 3 MV Van de Graaff accelerator in Florence: Overview and examples of applications

    Energy Technology Data Exchange (ETDEWEB)

    Taccetti, N.; Giuntini, L. E-mail: giuntini@fi.infn.it; Casini, G.; Stefanini, A.A.; Chiari, M.; Fedi, M.E.; Mando, P.A

    2002-04-01

    An electrostatic chopper has been installed at the KN 3000 accelerator in Florence to obtain short beam pulses with a number of particles per pulse whose average value can be chosen by varying the current intensity at the deflector plates input. Beam pulses can be obtained containing an average number of particles per pulse from less than one to thousands. The transmitted beam pulses can be as short as 200 ps FWHM, at a repetition rate up to about 100 kHz. Among the many applications of the facility, the direct measurement of energy loss and straggling of protons in Kapton and aluminium is reported. In this measurement, the facility has been tuned for transmission of mainly single-proton pulses; the beam energy is directly measured downstream with a good energy-resolution detector, without and with absorbers in front. In general, measurements of this kind can be directed both to study the basic processes of charged particles interactions in materials, or more practically to obtain the effective values of energy parameters useful in many IBA applications, avoiding the need to rely on simulations or theoretical estimates. Also briefly described is an application to Si-detector testing. In this case, the facility has been tuned for transmission of pulses containing many hundreds of protons of energy E{sub p}=2.5 MeV and the detector is directly exposed to the pulses. Spectra containing equally spaced peaks at energies multiple of E{sub p} are obtained and the response linearity of the detector plus electronics system can thus be checked.

  20. Optimization of Neutron Spectrum in Northwest Beam Tube of Tehran Research Reactor for BNCT, by MCNP Code

    Energy Technology Data Exchange (ETDEWEB)

    Zamani, M. [National Radiation Protection Department - NRPD, Atomic Energy Organization of Iran - AEOI, Tehran (Iran, Islamic Republic of); End of North Kargar st, Atomic Energy Organization of Iran, P.O. Box: 14155-1339, Tehran (Iran, Islamic Republic of); Kasesaz, Y.; Khalafi, H.; Shayesteh, M. [Radiation Application School, Nuclear Science and Technology Research Institute, AEOI, Tehran (Iran, Islamic Republic of)

    2015-07-01

    In order to gain the neutron spectrum with proper components specification for BNCT, it is necessary to design a Beam Shape Assembling (BSA), include of moderator, collimator, reflector, gamma filter and thermal neutrons filter, in front of the initial radiation beam from the source. According to the result of MCNP4C simulation, the Northwest beam tube has the most optimized neuron flux between three north beam tubes of Tehran Research Reactor (TRR). So, it has been chosen for this purpose. Simulation of the BSA has been done in four above mentioned phases. In each stage, ten best configurations of materials with different length and width were selected as the candidates for the next stage. The last BSA configuration includes of: 78 centimeters of air as an empty space, 40 centimeters of Iron plus 52 centimeters of heavy-water as moderator, 30 centimeters of water or 90 centimeters of Aluminum-Oxide as a reflector, 1 millimeters of lithium (Li) as thermal neutrons filter and finally 3 millimeters of Bismuth (Bi) as a filter of gamma radiation. The result of Calculations shows that if we use this BSA configuration for TRR Northwest beam tube, then the best neutron flux and spectrum will be achieved for BNCT. (authors)

  1. Evaluation of D(d,n)3 He reaction neutron source models for BNCT irradiation system design

    Institute of Scientific and Technical Information of China (English)

    YAO Ze'en; LUO Peng; Tooru KOBAYASHI; Gerard BENGUA

    2007-01-01

    A mathematical method was developed to calculatc the yield.energy spectrum and angular distribution of neutrons from D(d,n)3 He(D-D)reaction in a thick deuterium-titanium target for incident deuterons in energies lower than 1.0MeV.The data of energy spectrum and angular distribution wefe applied to set up the neutron source model for the beam-shaping-assembly(BSA)design of Boron-Neutron-Capture-Therapy(BNCT)using MCNP-4C code.Three cases of D-D neutron source corresponding to incident deuteron energy of 1000.400 and 150 kaV were investigated.The neutron beam characteristics were compared with the model of a 2.45 MeV mono-energetic and isotropic neutron source using an example BSA designed for BNCT irradiation.The results show significant differences in the neutron beam characteristics,particularly the fast neutron component and fast neutron dose in air,between the non-isotropic neutron source model and the 2.5 MeV mono-energetic and isotropic neutron source model.

  2. An evaluation on the design of beam shaping assembly based on the D-T reaction for BNCT

    Science.gov (United States)

    Asnal, M.; Liamsuwan, T.; Onjun, T.

    2015-05-01

    Boron Neutron Capture Therapy (BNCT) can be achieved by using a compact neutron generator such as a compact D-T neutron source, in which neutron energy must be in the epithermal energy range with sufficient flux. For these requirements, a Beam Shaping Assembly (BSA) is needed. In this paper, three BSA designs based on the D-T reaction for BNCT are discussed. It is found that the BSA configuration designed by Rasouli et al. satisfies all of the International Atomic Energy Agency (IAEA) criteria. It consists of 14 cm uranium as multiplier, 23 cm TiF3 and 36 cm Fluental as moderator, 4 cm Fe as fast neutron filter, 1 mm Li as thermal neutron filter, 2.6 cm Bi as gamma ray filter, and Pb as collimator and reflector. It is also found that use of specific filters is important for removing the fast and thermal neutrons and gamma contamination. Moreover, an appropriate neutron source plays a key role in providing a proper epithermal flux.

  3. Comparative dosimetry in intracavitary balloon catheter brachytherapy with I-125 and in Cf-252 brachytherapy combined with BNCT for brain tumors

    Energy Technology Data Exchange (ETDEWEB)

    Brandao, Samia de Freitas, E-mail: samiabrandao@gmail.com [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Campos, Tarcisio Passos Ribeiro de [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil)

    2013-06-15

    Objective: comparative analysis of dosimetry in intracavitary balloon catheter brachytherapy with I-125 and in Cf-252 brachytherapy combined with BNCT for treatment of brain tumors. Materials and methods: simulations of intracavitary balloon catheter brachytherapy with I-125 and in Cf-252 brachytherapy combined with BNCT were performed with the MCNP5 code, modeling the treatment of a brain tumor on a voxel computational phantom representing a human head. Absorbed dose rates were converted into biologically weighted dose rates. Results: intracavitary balloon catheter brachytherapy with I-125 produced biologically weighted mean dose rates of 3.2E-11, 1.3E-10, 1.9E-11 and 6.9E-13 RBE.Gy.h{sup -1}.p{sup -1}.s, respectively, on the healthy tissue, on the balloon periphery and on the /{sub 1} and /{sub 2} tumor infiltration zones. On the other hand, Cf-252 brachytherapy combined with BNCT produced a biologically weighted mean dose rate of 5.2E-09, 2.3E-07, 8.7E-09 and 2.4E-09 RBE.Gy.h{sup -1}.p{sup -1}.s, respectively on the healthy tissue, on the target tumor and on the /{sub 1} and /{sub 2} infiltration zones. Conclusion: Cf-252 brachytherapy combined with BNCT delivered a selective irradiation to the target tumor and to infiltration zones, while intracavitary balloon catheter brachytherapy with I-125 delivered negligible doses on the tumor infiltration zones. (author)

  4. 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

  5. EV Charging Facilities and Their Application in LV Feeders with Photovoltaics

    DEFF Research Database (Denmark)

    Marra, Francesco; Yang, Guangya; Træholt, Chresten

    2013-01-01

    for the different locations in the feeder. With time-series simulations, we quantify the energy size required for a station ESS. A Belgian LV residential grid, modeled using real PV generation and load profiles, is used as case study. The method and simulation results show the effectiveness of using public EV...... charging facilities with the additional function of voltage regulation in feeders with PV....

  6. Recent developments and applications for the University of Texas Thermal Neutron Imaging Facility.

    Science.gov (United States)

    Dorsey, D J; Charlton, W S

    2004-10-01

    The Thermal Neutron Imaging Facility (UT-TNIF) at the University of Texas at Austin is being modified to begin work with the non-destructive evaluation of carbon fiber composite materials intended for use in space. The use of high-resolution borated micro channel plate (MCP) detectors has been investigated. MCNP calculations to redesign the external radiation shielding to allow UT-TNIF operation at higher reactor powers and to minimize internal neutron scattering have been performed.

  7. Development and Application of Radiation Heating Facility%辐射加热设备的开发及运用

    Institute of Scientific and Technical Information of China (English)

    陈连忠; 张友华; 陈海群; 林国胜; 欧东斌

    2011-01-01

    介绍了中国航天空气动力技术研究院辐射加热设备的开发及运用情况.设备包括0-150 kW的石英灯加热器,试验舱,真空系统以及控制系统.在辐射加热设备上对低密度隔热材料在不同低压下的隔热性能进行了研究,所用模型横截面积为100 mmx100 mm,最长运行时间2000 s,低密度隔热材料的表面温度高达1000 K,试验舱最低压力为10 Pa.%This paper reports the development and application of radiation heating facility in China Academy of Aerospace Aerodynamics (CAAA). The facility includes 0 to 150 kW quartz lamps heater,test chamber,vacuum system and control system. The performances of low density thermal insulation materials in deferent low pressures have been studied on the radiation heating facility. The model cross size is 100 mm x 100 mm. The maximum running time is 2 000 s. The surface temperature of low density thermal insulation materials is up to 1 000 K. The minimum pressure in the test chamber is 10 Pa.

  8. 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...

  9. Facile and Gram-scale Synthesis of Metal-free Catalysts: Toward Realistic Applications for Fuel Cells

    Science.gov (United States)

    Kim, Ok-Hee; Cho, Yong-Hun; Chung, Dong Young; Kim, Min Jeong; Yoo, Ji Mun; Park, Ji Eun; Choe, Heeman; Sung, Yung-Eun

    2015-03-01

    Although numerous reports on nonprecious metal catalysts for replacing expensive Pt-based catalysts have been published, few of these studies have demonstrated their practical application in fuel cells. In this work, we report graphitic carbon nitride and carbon nanofiber hybrid materials synthesized by a facile and gram-scale method via liquid-based reactions, without the use of toxic materials or a high pressure-high temperature reactor, for use as fuel cell cathodes. The resulting materials exhibited remarkable methanol tolerance, selectivity, and stability even without a metal dopant. Furthermore, these completely metal-free catalysts exhibited outstanding performance as cathode materials in an actual fuel cell device: a membrane electrode assembly with both acidic and alkaline polymer electrolytes. The fabrication method and remarkable performance of the single cell produced in this study represent progressive steps toward the realistic application of metal-free cathode electrocatalysts in fuel cells.

  10. Facile and gram-scale synthesis of metal-free catalysts: toward realistic applications for fuel cells.

    Science.gov (United States)

    Kim, Ok-Hee; Cho, Yong-Hun; Chung, Dong Young; Kim, Min Jeong; Yoo, Ji Mun; Park, Ji Eun; Choe, Heeman; Sung, Yung-Eun

    2015-03-02

    Although numerous reports on nonprecious metal catalysts for replacing expensive Pt-based catalysts have been published, few of these studies have demonstrated their practical application in fuel cells. In this work, we report graphitic carbon nitride and carbon nanofiber hybrid materials synthesized by a facile and gram-scale method via liquid-based reactions, without the use of toxic materials or a high pressure-high temperature reactor, for use as fuel cell cathodes. The resulting materials exhibited remarkable methanol tolerance, selectivity, and stability even without a metal dopant. Furthermore, these completely metal-free catalysts exhibited outstanding performance as cathode materials in an actual fuel cell device: a membrane electrode assembly with both acidic and alkaline polymer electrolytes. The fabrication method and remarkable performance of the single cell produced in this study represent progressive steps toward the realistic application of metal-free cathode electrocatalysts in fuel cells.

  11. 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.

  12. An application of the IMC software to controller design for the JPL LSCL Experiment Facility

    Science.gov (United States)

    Zhu, Guoming; Skelton, Robert E.

    1993-01-01

    A software package which Integrates Model reduction and Controller design (The IMC software) is applied to design controllers for the JPL Large Spacecraft Control Laboratory Experiment Facility. Modal Cost Analysis is used for the model reduction, and various Output Covariance Constraints are guaranteed by the controller design. The main motivation is to find the controller with the 'best' performance with respect to output variances. Indeed it is shown that by iterating on the reduced order design model, the controller designed does have better performance than that obtained with the first model reduction.

  13. Facile synthesis of porous Co3O4 nanoplates for supercapacitor applications

    Indian Academy of Sciences (India)

    Tao Geng; Li Zhang; Hongyan Wang; Keying Zhang; Xia Zhou

    2015-09-01

    Porous tricobalt tetraoxide (Co3O4) nanoplates with large aspect ratio have been obtained by annealing Co(OH)2 precursor nanoplates synthesized by a facile reflux method without the need for any template or surfactant. After the heat treatment, the as-obtained phase-pure Co3O4 nanoplates with a wellretained structure were applied as the electrode material for supercapacitors, and the sample exhibits excellent performance with a high specific capacitance of 225 F g–1 after 2000 charge–discharge cycles at 2 A g–1, corresponding to a retention of 97% of the initial capacitance.

  14. 75 FR 37471 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-06-29

    ... license amendment application, see the application for amendment which is available for public inspection..., which include the cooling water, starting air, lubrication, intake and exhaust, and fuel oil systems... boiling (DNBR) limits, heat flux hot channel factor (F Q (Z)) limits, nuclear enthalpy rise hot...

  15. 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.

  16. Application of a conic glass monocapillary in Beijing synchrotron radiation facility

    Energy Technology Data Exchange (ETDEWEB)

    Li, Yude, E-mail: liyude@bnu.edu.cn [Key Laboratory of Beam Technology and Material Modification of the Ministry of Education, Beijing 100875 (China); College of Nuclear Science and Technology, Beijing Normal University, Beijing 100875 (China); Beijing Radiation Center, Beijing 100875 (China); Lin, Xiaoyan; Guo, Fei; Liu, Shigang; He, JinLong; Zhao, Weilin; Sun, Tianxi [Key Laboratory of Beam Technology and Material Modification of the Ministry of Education, Beijing 100875 (China); College of Nuclear Science and Technology, Beijing Normal University, Beijing 100875 (China); Beijing Radiation Center, Beijing 100875 (China); Zheng, Lirong; Gao, Zengqiang; Chang, Guangcai [Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049 (China)

    2014-08-01

    A conic glass monocapillary was developed and used at the Biological Macromolecules Station (BMS) in Beijing Synchrotron Radiation Facility (BSRF). The structure and transmission property of this optics is reported here in details. The experiments have shown that the value of full width at the half maximum (FWHM) of the X-ray beams transmitted through this optics was nearly unchanged within a short distance. This is very convenient for further measurement of samples. The power diffraction experiments of CeO{sub 2} revealed that the Debye rings are much clearer in the case of applying this optics. The ratio of error in the diffraction peak position is reduced significantly to the value as less as 0.042%.

  17. Co$_9$S$_8$ nanotubes: facile synthesis and application in the catalytic reduction of 4-nitrophenol

    Indian Academy of Sciences (India)

    TAO GENG; YONGHONG NI; HONGYAN WANG; XIA ZHOU

    2016-10-01

    Co$_9$S$_8$ nanotubes have been successfully synthesized via a facile two-step solvothermal method without the assistance of any template or surfactant, using cobalt sulphate (CoSO$_4$·7H$_2$O), urea and sodium sulphide (Na$_2$S·9H$_2$O) as starting reactants, and deionized water and glycol as the reactive medium. The phase and the morphologyof the as-obtained product were characterized by means of powder X-ray diffraction, energy dispersive spectrometry and scanning electron microscopy. The result displays that the Co9S8 nanotubes have hexagonal crosssections,the diameter of the nanotubes is about 200 nm and the wall thickness is of 50 nm. The experiments showed that the Co$_9$S$_8$ nanotubes could be used as new-type catalysts for the reduction of 4-nitrophenol. It was found thatthe as-obtained Co$_9$S$_8$ nanotubes contributed to the best catalytic activity.

  18. Application of a conic glass monocapillary in Beijing synchrotron radiation facility

    Science.gov (United States)

    Li, Yude; Lin, Xiaoyan; Guo, Fei; Liu, Shigang; He, JinLong; Zhao, Weilin; Sun, Tianxi; Zheng, Lirong; Gao, Zengqiang; Chang, Guangcai

    2014-08-01

    A conic glass monocapillary was developed and used at the Biological Macromolecules Station (BMS) in Beijing Synchrotron Radiation Facility (BSRF). The structure and transmission property of this optics is reported here in details. The experiments have shown that the value of full width at the half maximum (FWHM) of the X-ray beams transmitted through this optics was nearly unchanged within a short distance. This is very convenient for further measurement of samples. The power diffraction experiments of CeO2 revealed that the Debye rings are much clearer in the case of applying this optics. The ratio of error in the diffraction peak position is reduced significantly to the value as less as 0.042%.

  19. Development of a Tandem-Electrostatic-Quadrupole facility for Accelerator-Based Boron Neutron Capture Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Kreiner, A.J., E-mail: kreiner@tandar.cnea.gov.ar [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, Av. Gral Paz 1499, 1650 San Martin, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin (Argentina)] [CONICET, Buenos Aires (Argentina); Castell, W. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, Av. Gral Paz 1499, 1650 San Martin, Buenos Aires (Argentina); Di Paolo, H. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, Av. Gral Paz 1499, 1650 San Martin, Buenos Aires (Argentina)] [Escuela de Ciencia y Tecnologia, Universidad Nacional de San Martin (Argentina); Baldo, M. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, Av. Gral Paz 1499, 1650 San Martin, Buenos Aires (Argentina); Bergueiro, J. [Gerencia de Investigacion y Aplicaciones, Comision Nacional de Energia Atomica, Av. Gral Paz 1499, 1650 San Martin, Buenos Aires (Argentina)] [CONICET, Buenos Aires (Argentina)

    2011-12-15

    We describe the present status of an ongoing project to develop a Tandem-ElectroStatic-Quadrupole (TESQ) accelerator facility for Accelerator-Based (AB)-BNCT. The project final goal is a machine capable of delivering 30 mA of 2.4 MeV protons to be used in conjunction with a neutron production target based on the {sup 7}Li(p,n){sup 7}Be reaction. The machine currently being constructed is a folded TESQ with a high-voltage terminal at 0.6 MV. We report here on the progress achieved in a number of different areas.

  20. Design of a rotating facility for extracorporal treatment of an explanted liver with disseminated metastases by boron neutron capture therapy with an epithermal neutron beam.

    Science.gov (United States)

    Nievaart, V A; Moss, R L; Kloosterman, J L; van der Hagen, T H J J; van Dam, H; Wittig, A; Malago, M; Sauerwein, W

    2006-07-01

    In 2001, at the TRIGA reactor of the University of Pavia (Italy), a patient suffering from diffuse liver metastases from an adenocarcinoma of the sigmoid was successfully treated by boron neutron capture therapy (BNCT). The procedure involved boron infusion prior to hepatectomy, irradiation of the explanted liver at the thermal column of the reactor, and subsequent reimplantation. A complete response was observed. This encouraging outcome stimulated the Essen/Petten BNCT group to investigate whether such an extracorporal irradiation could be performed at the BNCT irradiation facility at the HFR Petten (The Netherlands), which has very different irradiation characteristics than the Pavia facility. A computational study has been carried out. A rotating PMMA container with a liver, surrounded by PMMA and graphite, is simulated using the Monte Carlo code MCNP. Due to the rotation and neutron moderation of the PMMA container, the initial epithermal neutron beam provides a nearly homogeneous thermal neutron field in the liver. The main conditions for treatment as reported from the Pavia experiment, i.e. a thermal neutron fluence of 4 x 10(12) +/- 20% cm(-2), can be closely met at the HFR in an acceptable time, which, depending on the defined conditions, is between 140 and 180 min.

  1. MASS DEFLECTOR APPLICATION FOR CERN’s ON-LINE ISOTOPE SEPARATOR FACILITY 077

    CERN Document Server

    Sánchez-Conejo, J

    2004-01-01

    The mass deflector application for the General Purpose Separator GPS allows splitting a beam of particles, characterized by a central mass, into two particle beams, which are sent to a high-mass and low-mass beam lines.

  2. MASS DEFLECTOR APPLICATION FOR CERN’s ON-LINE ISOTOPE SEPARATOR FACILITY 073

    CERN Document Server

    Sánchez-Conejo, J

    2004-01-01

    The mass deflector application for the General Purpose Separator GPS allows splitting a beam of particles, characterized by a central mass, into two particle beams, which are sent to a high-mass and low-mass beam lines.

  3. An Application for the On-Line Isotope Mass Separator ISOLDE facility: the Mass Control

    CERN Document Server

    Ovalle Gonzalez, E

    2003-01-01

    The Mass Control Application will calculate the magnetic field for both the HRS and GPS separators. The calculation will be carry out according to parameters either entered by the user or taken from other sources.

  4. Engineering on abolishment measure of nuclear fuel facilities. Application of 3D-CAD to abolishment measure of nuclear fuel facilities

    Energy Technology Data Exchange (ETDEWEB)

    Annen, Sotonori; Sugitsue, Noritake [Japan Nuclear Cycle Development Inst., Ningyo Toge Environmental Engineering Center, Kamisaibara, Okayama (Japan)

    2001-12-01

    The Japan Nuclear Cycle Development Institute (JNC) progresses some advancing R and Ds required for establishment of the nuclear fuel cycle under considering on safety, economical efficiency, environmental compatibility, and so on. An important item among them is a technology on safe abolishment of a nuclear energy facility ended its role, which is called the abolishment measure technique. Here was introduced at a center of viewpoint called on use of three dimensional CAD (3D-CAD), on outlines of engineering system for abolishment measure (subdivision engineering system) under an object of nuclear fuel facilities, constructed through subdivision and removal of refinement conversion facilities, by the Ningyo-toge Environmental Engineering Center of JNC. (G.K.)

  5. Investigation on the reflector/moderator geometry and its effect on the neutron beam design in BNCT.

    Science.gov (United States)

    Kasesaz, Y; Rahmani, F; Khalafi, H

    2015-12-01

    In order to provide an appropriate neutron beam for Boron Neutron Capture Therapy (BNCT), a special Beam Shaping Assembly (BSA) must be designed based on the neutron source specifications. A typical BSA includes moderator, reflector, collimator, thermal neutron filter, and gamma filter. In common BSA, the reflector is considered as a layer which covers the sides of the moderator materials. In this paper, new reflector/moderator geometries including multi-layer and hexagonal lattice have been suggested and the effect of them has been investigated by MCNP4C Monte Carlo code. It was found that the proposed configurations have a significant effect to improve the thermal to epithermal neutron flux ratio which is an important neutron beam parameter.

  6. Dosimetric performance evaluation regarding proton beam incident angles of a lithium-based AB-BNCT design.

    Science.gov (United States)

    Lee, Pei-Yi; Liu, Yuan-Hao; Jiang, Shiang-Huei

    2014-10-01

    The (7)Li(p,xn)(7)Be nuclear reaction, based on the low-energy protons, could produce soft neutrons for accelerator-based boron neutron capture therapy (AB-BNCT). Based on the fact that the induced neutron field is relatively divergent, the relationship between the incident angle of proton beam and the neutron beam quality was evaluated in this study. To provide an intense epithermal neutron beam, a beam-shaping assembly (BSA) was designed. And a modified Snyder head phantom was used in the calculations for evaluating the dosimetric performance. From the calculated results, the intensity of epithermal neutrons increased with the increase in proton incident angle. Hence, either the irradiation time or the required proton current can be reduced. When the incident angle of 2.5-MeV proton beam is 120°, the required proton current is ∼13.3 mA for an irradiation time of half an hour.

  7. Exploring new labelling strategies for boronated compounds: towards fast development and efficient assessment of BNCT drug candidates

    OpenAIRE

    Gona, Kiran Babu

    2015-01-01

    208 p. La terapia por captura de neutrones (BNCT o Boron Neutron Capture Therapy), fue descrita por primera vez por Locher en 1936 y es una modalidad terapéutica binaria para el tratamiento del cáncer que se basa en la captura de neutrones térmicos por medio de átomos de 10B, previamente acumulados en las células tumorales. La captura del neutrón térmico resulta en la formación de un núcleo de 11B, que fisiona para generar dos iones altamente energéticos: 4He2+ y 7Li3+. El daño y la poster...

  8. Spectral performance of a composite single-crystal filtered thermal neutron beam for BNCT research at the University of Missouri.

    Science.gov (United States)

    Brockman, J; Nigg, D W; Hawthorne, M F; McKibben, C

    2009-07-01

    Parameter studies, design calculations and initial neutronic performance measurements have been completed for a new thermal neutron beamline to be used for neutron capture therapy cell and small-animal radiobiology studies at the University of Missouri Research Reactor. The beamline features the use of single-crystal silicon and bismuth sections for neutron filtering and for reduction of incident gamma radiation. The calculated and measured thermal neutron fluxes produced at the irradiation location are 9.6 x 10(8) and 8.8 x 10(8)neutrons/cm(2)s, respectively. Calculated and measured cadmium ratios (Au foils) are 217 and 132. These results indicate a well-thermalized neutron spectrum with sufficient thermal neutron flux for a variety of small animal BNCT studies.

  9. 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.

  10. 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

  11. 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.

  12. Facile synthesis of nickel–cobalt double hydroxide nanosheets with high rate capability for application in supercapacitor

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Minmin; Xue, Junying; Zhang, Fangming; Ma, Wenle; Cui, Hongtao, E-mail: htcui@ytu.edu.cn [Yantai University, Shandong Provincial Engineering Research Center for Comprehensive Utilization of Light Hydrocarbons, College of Chemistry and Chemical Engineering (China)

    2015-02-15

    In this work, nickel–cobalt double hydroxide nanosheets with high rate capability are prepared by a facile epoxide precipitation route. The synthetic procedure includes an oxidization step using ammonium persulfate as oxidant and a precipitation step using propylene oxide as precipitation agent. As shown in the results of electrochemical characterization, high specific capacitance of 2548 F g{sup −1} for this material can be obtained at current density of 0.9 A g{sup −1} in aqueous solution of 3 mol L{sup −1 }KOH. It is surprising to notice that the capacitance of material still remains 1587 F g{sup −1} at high current density of 35.7 A g{sup −1}. These results demonstrate that the as-prepared nickel–cobalt double hydroxide nanosheets are promising electrode material for supercapacitor application as a primary power source.

  13. 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.

  14. Understanding the application of knowledge management to the safety critical facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ilina, Elena

    2010-07-01

    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

  15. Graphenized pencil lead fiber: facile preparation and application in solid-phase microextraction.

    Science.gov (United States)

    Liu, Qian; Cheng, Mengting; Long, Yanmin; Yu, Miao; Wang, Thanh; Jiang, Guibin

    2014-01-17

    Graphenized pencil lead fiber was facilely prepared by in situ chemical exfoliation of graphite in pencil lead fiber to few-layered graphene sheets via a one-pot, one-step pressurized oxidation reaction for the first time. This new fiber was characterized and demonstrated to be a highly efficient but low-cost solid-phase microextraction (SPME) fiber. The extraction performance of the fiber was evaluated with four bisphenol analogs [bisphenol A (BPA), bisphenol S (BPS), bisphenol AF (BPAF), and tetrabromobisphenol A (TBBPA)] as model analytes in direct SPME mode. Unlike commercially available fibers, the graphenized pencil lead fiber showed an excellent chemical stability in highly saline, acidic, alkaline and organic conditions due to its coating-free configuration. The fiber also showed a very long lifespan. Furthermore, high extraction efficiency and good selectivity for the analytes with a wide polarity range could be obtained due to the exceptional properties of graphene. The detection limits (LODs) for the analytes were in the range of 1.1-25ng/L. The fiber was successfully applied in the analysis of tap water and effluent samples from a waste water treatment plant with spike recoveries ranging from 68.5 to 105.1%. Therefore, the graphenized pencil lead fiber provides a high performance, cheap, robust, and reliable tool for SPME.

  16. 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.

  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. Neutron flux assessment of a neutron irradiation facility based on inertial electrostatic confinement fusion.

    Science.gov (United States)

    Sztejnberg Gonçalves-Carralves, M L; Miller, M E

    2015-12-01

    Neutron generators based on inertial electrostatic confinement fusion were considered for the design of a neutron irradiation facility for explanted organ Boron Neutron Capture Therapy (BNCT) that could be installed in a health care center as well as in research areas. The chosen facility configuration is "irradiation chamber", a ~20×20×40 cm(3) cavity near or in the center of the facility geometry where samples to be irradiated can be placed. Neutron flux calculations were performed to study different manners for improving scattering processes and, consequently, optimize neutron flux in the irradiation position. Flux distributions were assessed through numerical simulations of several models implemented in MCNP5 particle transport code. Simulation results provided a wide spectrum of combinations of net fluxes and energy spectrum distributions. Among them one can find a group that can provide thermal neutron fluxes per unit of production rate in a range from 4.1·10(-4) cm(-2) to 1.6·10(-3) cm(-2) with epithermal-to-thermal ratios between 0.3% and 13% and fast-to-thermal ratios between 0.01% to 8%. Neutron generators could be built to provide more than 10(10) n s(-1) and, consequently, with an arrangement of several generators appropriate enough neutron fluxes could be obtained that would be useful for several BNCT-related irradiations and, eventually, for clinical practice.

  19. 75 FR 57521 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-09-21

    ... applicable acceptance criteria. The safety analyses for these accidents have been performed at the EPU power... is consistent with the safety analysis assumptions. The proposed RPS and ESFAS Limiting Safety System... (CST),'' resulting from (1) modifications to the AFW system to support requirements for transients...

  20. 76 FR 56483 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-09-13

    ... MWt. Nuclear steam supply system and balance-of-plant systems, components and analyses that could be... applicable analysis acceptance criteria are still met with the proposed changes. Power level is an input assumption to equipment design and accident analyses, but it is not a transient or accident...

  1. 77 FR 75676 - Standard Review Plan for Review of Fuel Cycle Facility License Applications

    Science.gov (United States)

    2012-12-21

    ... Regulatory Commission. ACTION: NUREG revision; extension of comment period. SUMMARY: On December 7, 2012 (77... to NUREG- 1520, Revision 1, ``Standard Review Plan (SRP) for the Review of a License Application for... document is available in ADAMS) is provided the first time that a document is referenced....

  2. 77 FR 8288 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2012-02-14

    ... value shall be added to the cycle-specific SLMCPR value. This adder is applicable to SLO , which is.... The proposed change to the MCPR SLs accounts for the 0.02 adder specified in the NRC Safety Evaluation... revision to the MCPR SLs accounts for the 0.02 adder specified in the NRC Safety Evaluation limitations...

  3. 77 FR 43374 - Biweekly Notice, Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-07-24

    ... of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii). For further details with respect to this...) purification loop interface. This change would only be applicable for the next two fuel cycles. Basis for... an accident that has previously been evaluated? Response: No. The SFP Purification Loop is...

  4. 75 FR 4111 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-01-26

    ... resistance to tube pullout due to the pressure induced forces, with applicable safety factors applied... revises testing acceptance criteria for the existing Indian Point 2 Control Room filtration system in... criteria for the existing Control Room filtration system. The proposed change does not involve...

  5. 75 FR 52039 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-24

    ... application for amendment which is available for public inspection at the Commission's PDR, located at One..., ``Both Isolation Actuation Instrument Channels Inoperable'' (Agencywide Documents Access and Management... restricts the maximum fuel rod average burnup. Deletion of this condition would allow the maximum fuel...

  6. 77 FR 65720 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-10-30

    ..., see the application for amendment which is available for public inspection at the NRC's PDR, located... of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel... hot channel factor, nuclear enthalpy rise hot channel factor, loss of coolant accident peak...

  7. 75 FR 32509 - Notice Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-06-08

    ... amendment action, see the application for amendment which is available for public inspection at the... and channel surveillance requirements associated with average power range monitor simulated thermal... the RPV head is removed, any gaseous release due to fuel damage from any accident or transient...

  8. 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.

  9. 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

  10. 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.

  11. Facility Location Using Maximum Covering Model: An Application In Retail Sector

    Directory of Open Access Journals (Sweden)

    Çiğdem Alabaş Uslu

    2012-06-01

    Full Text Available In this study, a store location problem has been addressed for service sector, and a real application problem for a leading firm in modern retail sector in Turkey has been solved by modeling with mathematical programming. Since imitating a store location in retail sector is hard and provides an important competitive edge, determining accurate store locations becomes a critical issue for the management. Application problem solved in this study is to choose appropriate areas for opening stores with different capacities and quantities in Umraniye, Istanbul. The problem has been converted to a maximum set covering model by considering after sales forecasts and also by taking into account several decision criteria foreseen by the management. Optimum solutions of the developed model for different scenarios has been obtained using a package program and presented to the firm management.

  12. Immobilized graphene-based composite from asphalt: facile synthesis and application in water purification.

    Science.gov (United States)

    Sreeprasad, Theruvakkattil Sreenivasan; Gupta, Soujit Sen; Maliyekkal, Shihabudheen Mundampra; Pradeep, Thalappil

    2013-02-15

    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(-1) and 1345 cm(-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.

  13. Neutron beam optimization based on a 7Li(p,n)7Be reaction for treatment of deep-seated brain tumors by BNCT

    Science.gov (United States)

    Zahra Ahmadi, Ganjeh; S. Farhad, Masoudi

    2014-10-01

    Neutron beam optimization for accelerator-based Boron Neutron Capture Therapy (BNCT) is investigated using a 7Li(p,n)7Be reaction. Design and optimization have been carried out for the target, cooling system, moderator, filter, reflector, and collimator to achieve a high flux of epithermal neutron and satisfy the IAEA criteria. Also, the performance of the designed beam in tissue is assessed by using a simulated Snyder head phantom. The results show that the optimization of the collimator and reflector is critical to finding the best neutron beam based on the 7Li(p,n)7Be reaction. Our designed beam has 2.49×109n/cm2s epithermal neutron flux and is suitable for BNCT of deep-seated brain tumors.

  14. Laboratory Astrophysics Studies with the COSmIC Facility: Interstellar and Planetary Applications.

    Science.gov (United States)

    Salama, Farid; Contreras, Cesar S.; Sciamma-O'Brien, Ella; Bejaoui, Salma

    2015-08-01

    We present and discuss the characteristics and the capabilities of the laboratory facility, COSmIC, that was developed at NASA Ames to generate, process and analyze interstellar, circumstellar and planetary analogs in the laboratory [1]. COSmIC stands for “Cosmic Simulation Chamber” and is dedicated to the study of neutral and ionized molecules and nano particles under the low temperature and high vacuum conditions that are required to simulate space environments. COSmIC integrates a variety of state-of-the-art instruments that allow forming, processing and monitoring simulated space conditions for planetary, circumstellar and interstellar materials in the laboratory. COSmIC is composed of a Pulsed Discharge Nozzle (PDN) expansion that generates a plasma in free supersonic jet expansion coupled to two high-sensitivity, complementary in situ diagnostics: a Cavity Ring Down Spectroscopy (CRDS) and laser induced fluorescence (LIF) systems for photonic detection and a Reflectron Time-Of-Flight Mass Spectrometer (ReTOF-MS) for mass detection [2].Recent laboratory astrophysics results that were obtained using COSmIC will be presented, in particular the progress that has been achieved in the domain of the diffuse interstellar bands (DIBs) and in monitoring, in the laboratory, the formation of dust grains and aerosols from their gas-phase molecular precursors in environments as varied as stellar/circumstellar outflows [3] and planetary atmospheres [4]. Plans for future, next generation, laboratory experiments on cosmic molecules and grains in the growing field of laboratory astrophysics will also be addressed as well as the implications of the current studies for astronomy.References:[1] Salama F., In Organic Matter in Space, IAU Symposium 251, Kwok & Sandford Eds.Cambridge University Press, Vol. 4, S251, p. 357 (2008) and references therein.[2] Ricketts C., Contreras C., Walker, R., Salama F., Int. J. Mass Spec, 300, 26 (2011)[3] Cesar Contreras and Farid Salama, The

  15. Application of Tomo-PIV in a large-scale supersonic jet flow facility

    Science.gov (United States)

    Wernet, Mark P.

    2016-09-01

    Particle imaging velocimetry (PIV) has been used extensively at NASA GRC over the last 15 years to build a benchmark data set of hot and cold jet flow measurements in an effort to understand acoustic noise sources in high-speed jets. Identifying the noise sources in high-speed jets is critical for ultimately modifying the nozzle hardware design/operation and therefore reducing the jet noise. Tomographic PIV (Tomo-PIV) is an innovative approach for acquiring and extracting velocity information across extended volumes of a flow field, enabling the computation of additional fluid mechanical properties not typically available using traditional PIV techniques. The objective of this work was to develop and implement the Tomo-PIV measurement capability and apply it in a large-scale outdoor test facility, where seeding multiple flow streams and operating in the presence of daylight presents formidable challenges. The newly developed Tomo-PIV measurement capability was applied in both a subsonic M 0.9 flow and an under-expanded M 1.4 heated jet flow field. Measurements were also obtained using traditional two-component (2C) PIV and stereo PIV in the M 0.9 flow field for comparison and validation of the Tomo-PIV results. In the case of the M 1.4 flow, only the 2C PIV was applied to allow a comparison with the Tomo-PIV measurement. The Tomo-PIV fields-of-view covered 180 × 180 × 10 mm, and the reconstruction domains were 3500 × 3500 × 200 voxels. These Tomo-PIV measurements yielded all three components of vorticity across entire planes for the first time in heated supersonic jet flows and provided the first full 3D reconstruction of the Mach disk and oblique shock intersections inside of the barrel shocks. Measuring all three components of vorticity across multiple planes in the flow, potentially reduces the number of measurement configurations (streamwise and cross-stream PIV) required to fully characterize the mixing-enhanced nozzle flows routinely studied in

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

    DEFF Research Database (Denmark)

    2014-01-01

    The Wind Atlas Analysis and Application Program (WAsP) is a PC-program for horizontal and vertical extrapolation of wind climates. The program contains a complete set of models to calculate the effects on the wind of sheltering obstacles, surface roughness changes and terrain height variations....... The analysis part consists of a transformation of an observed wind climate (wind speed and direction distributions) to a generalised wind climate (wind atlas data set). The generalised wind climate can subsequently be applied for estimation of the wind climate and wind power potential, as well as for siting...

  17. Monte Carlo Calculation of Core Reactivity and Fluxes for the Development of the BNCT Neutron Source at the Kyiv Research Reactor

    Science.gov (United States)

    Gritzay, Olena; Kalchenko, Oleksandr; Klimova, Nataliya; Razbudey, Volodymyr; Sanzhur, Andriy; Binney, Stephen

    2005-05-01

    The presented results show our consecutive steps in developing a neutron source with parameters required by Boron Neutron Capture Therapy (BNCT) at the Kyiv Research Reactor (KRR). The main goal of this work was to analyze the influence of installation of different types of uranium converters close to the reactor core on neutron beam characteristics and on level of reactor safety. The general Monte Carlo radiation transport code MCNP, version 4B, has been used for these calculations.

  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. 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.

  20. Facile preparation of multifunctional superparamagnetic PHBV microspheres containing SPIONs for biomedical applications

    Science.gov (United States)

    Li, Wei; Jan Zaloga; Ding, Yaping; Liu, Yufang; Janko, Christina; Pischetsrieder, Monika; Alexiou, Christoph; Boccaccini, Aldo R.

    2016-03-01

    The promising potential of magnetic polymer microspheres in various biomedical applications has been frequently reported. However, the surface hydrophilicity of superparamagnetic iron oxide nanoparticles (SPIONs) usually leads to poor or even failed encapsulation of SPIONs in hydrophobic polymer microspheres using the emulsion method. In this study, the stability of SPIONs in poly(3-hydroxybutyrate-co-3-hydroxyvalerate) (PHBV) solution was significantly increased after surface modification with lauric acid. As a result, magnetic PHBV microspheres with high encapsulation efficiencies (71.0-87.4%) were prepared using emulsion-solvent extraction/evaporation method. Magnetic resonance imaging (MRI) showed significant contrast for the magnetic PHBV microspheres. The toxicity of these magnetic PHBV microspheres towards human T-lymphoma suspension cells and adherent colon carcinoma HT-29 cells was investigated using flow cytometry, and they were shown to be non-toxic in a broad concentration range. A model drug, tetracycline hydrochloride, was used to demonstrate the drug delivery capability and to investigate the drug release behavior of the magnetic PHBV microspheres. The drug was successfully loaded into the microspheres using lauric acid-coated SPIONs as drug carrier, and was released from the microspheres in a diffusion controlled manner. The developed magnetic PHBV microspheres are promising candidates for biomedical applications such as targeted drug delivery and MRI.

  1. 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.

  2. 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...

  3. 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.

  4. Facile Synthesis of Electroconductive AZO@TiO2 Whiskers and Their Application in Textiles

    Directory of Open Access Journals (Sweden)

    Hui Ma

    2016-01-01

    Full Text Available The electroconductive AZO@TiO2 whiskers have been successfully prepared via coating Al doped ZnO onto TiO2 whisker. The orthogonal tests were employed to optimize the synthetic conditions. The crystallographic structure and the morphology of the AZO@TiO2 whiskers and the polypropylene nonwoven fabrics modified with AZO@TiO2 whiskers were characterized by X-ray photoelectron spectroscopy, X-ray diffraction, scanning electron microscope, four-probe meter, and electrometer. The results showed the AZO@TiO2 whiskers exhibited good electroconductive performance. Moreover, the polypropylene nonwoven fabrics modified with AZO@TiO2 whiskers revealed excellent antistatic performance indicating wide application of AZO@TiO2 whiskers in the antistatic textiles.

  5. 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...

  6. Facile 3D Metal Electrode Fabrication for Energy Applications via Inkjet Printing and Shape Memory Polymer

    Science.gov (United States)

    Roberts, R. C.; Wu, J.; Hau, N. Y.; Chang, Y. H.; Feng, S. P.; Li, D. C.

    2014-11-01

    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/cm2 with stable metal performance.

  7. Accelerator Stewardship Test Facility Program - Elliptical Twin Cavity for Accelerator Applications

    Energy Technology Data Exchange (ETDEWEB)

    Hutton, Andrew [TJNAF; Areti, Hari [TJNAF

    2015-08-01

    Funding is being requested pursuant to the proposals entitled Elliptical Twin Cavity for Accelerator Applications that was submitted and reviewed through the Portfolio Analysis and Management System (PAMS). The PAMS proposal identifier number is 0000219731. The proposed new type of superconducting cavity, the Elliptical Twin Cavity, is capable of accelerating or decelerating beams in two separate beam pipes. This configuration is particularly effective for high-current, low energy electron beams that will be used for bunched beam cooling of high-energy protons or ions. Having the accelerated beam physically separated from the decelerated beam, but interacting with the same RF mode, means that the low energy beam from the gun can be injected into to the superconducting cavity without bends enabling a small beam emittance to be maintained. A staff engineer who has been working with non-standard complicated cavity structures replaces the senior engineer (in the original budget) who is moving on to be a project leader. This is reflected in a slightly increased engineer time and in reduced costs. The Indirect costs for FY16 are lower than the previous projection. As a result, there is no scope reduction.

  8. Facile preparation and applications of graphitic carbon nitride coating in solid-phase microextraction.

    Science.gov (United States)

    Xu, Na; Wang, Yiru; Rong, Mingcong; Ye, Zhifeng; Deng, Zhuo; Chen, Xi

    2014-10-17

    In this study, graphitic carbon nitride (g-C3N4) was used as a coating material for solid-phase microextraction (SPME) applications. Coupled to gas chromatography (GC), the extraction ability of the SPME fiber was investigated and compared with the commercial fibers of 100 μm PDMS and 85 μm CAR/PDMS using six target analytes including deltamethrin, nerolidol, amphetamine, dodecane, ametryn and acrylamide. The g-C3N4 coating revealed excellent extraction ability and durability comparing with those of the commercial fibers due to its loose structure and unique physicochemical properties. The repeatability for each single fiber was found to be 3.46% and reproducibility for fiber to fiber was 8.53%. The g-C3N4 SPME fiber was applied to the determination of acrylamide in potato chips, the linearity and detection limit was 0.5-250 μg g(-1) and 0.018 μg g(-1), respectively.

  9. Facile synthesis of cobalt oxide/reduced graphene oxide composites for electrochemical capacitor and sensor applications

    Science.gov (United States)

    Nguyen, Thi Toan; Nguyen, Van Hoa; Deivasigamani, Ranjith Kumar; Kharismadewi, Dian; Iwai, Yoshio; Shim, Jae-Jin

    2016-03-01

    Reduced graphene oxide sheets decorated with cobalt oxide nanoparticles (Co3O4/rGO) were produced using a hydrothermal method without surfactants. Both the reduction of GO and the formation of Co3O4 nanoparticles occurred simultaneously under this condition. At the same current density of 0.5 A g-1, the Co3O4/rGO nanocomposites exhibited much a higher specific capacitance (545 F g-1) than that of bare Co3O4 (100 F g-1). On the other hand, for the detection of H2O2, the peak current of Co3O4/rGO was 4 times higher than that of Co3O4. Moreover, the resulting composite displayed a low detection limit of 0.62 μM and a high sensitivity of 28,500 μA mM-1cm-2 for the H2O2 sensor. These results suggest that the Co3O4/rGO nanocomposite is a promising material for both supercapacitor and non-enzymatic H2O2 sensor applications.

  10. 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.

  11. 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

  12. 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.

  13. Facile sonochemical synthesis of nanostructured NiO with different particle sizes and its electrochemical properties for supercapacitor application.

    Science.gov (United States)

    Duraisamy, Navaneethan; Numan, Arshid; Fatin, Saiha Omar; Ramesh, K; Ramesh, S

    2016-06-01

    In this work, we demonstrate the influence of nickel oxides with divergent particle sizes as the working electrodes for supercapacitor application. The nanostructured nickel oxide (NiO) is synthesized via facile sonochemical method, followed by calcination process. The crystallinity and surface purity of prepared samples are clearly examined by X-ray diffraction and Raman analysis. NiO crystallinity is significantly increased with increasing calcination temperatures. The surface analysis confirmed that the calcination at 250°C exhibited nanoclutser like NiO with average particle size of ∼6nm. While increasing the calcination temperature beyond 250°C, hexagonal shaped NiO is observed with enhanced particle sizes. The electrochemical performance confirmed the good redox behavior of NiO electrodes. Moreover, NiO with average particle size of ∼6nm exhibited high specific capacitance of 449F/g at a scan rate of 5mV/s compared to other samples with particle sizes of ∼21nm (323F/g) and ∼41nm (63F/g). This is due to the good ion transfer mechanism and effective electrochemical utilization of the working electrode.

  14. Facile synthesis of nitrogen-doped carbon dots and its application as sensing probes for serum iron

    Science.gov (United States)

    Wang, Long; Hou, Juan; Li, Huiyu; Zhao, Qi; Zhang, Fengshuang; Zhao, Jiahui; Ding, Hong; Ding, Lan

    2015-11-01

    In this paper, nitrogen-doped carbon dots (N-CDs) with a quantum yield of 23.6 % were successfully synthesized by microwave pyrolysis of urea using diethylene glycol as the high boiling point reaction medium. The N-CDs were spherical and monodisperse with a size distribution between 1.5 and 5.5 nm. The N-CDs exhibited excellent water-soluble property and remarkable stability under extreme ionic strengths and light illumination. The fluorescence of the N-CDs could be quenched by Fe3+ through the static quenching mechanism, but not by other common metal ions. On this basis, the N-CDs can be used as a facile sensing platform for label-free sensitive and selective detection of Fe3+ in a linear range of 1.6-333.3 μmol L-1, and the detection limit was 0.45 μmol L-1 obtained at a signal-to-noise ratio of 3. Importantly, the N-CDs-based fluorescent probe was successfully applied to the direct analysis of iron contents in human serum samples, which demonstrated potential applications in biological and clinical analysis.

  15. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    Energy Technology Data Exchange (ETDEWEB)

    Tom Elicson; Bentley Harwood; Richard Yorg; Heather Lucek; Jim Bouchard; Ray Jukkola; Duan Phan

    2011-03-01

    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.

  16. Facile, Low-Cost, UV-Curing Approach to Prepare Highly Conductive Composites for Flexible Electronics Applications

    Science.gov (United States)

    Li, Fucheng; Chen, Shilong; Wei, Yong; Liu, Konghua; Lin, Yong; Liu, Lan

    2016-07-01

    We present a facile approach to prepare high-performance ultraviolet (UV)-curable polyurethane-acrylate-based flexible electrical conductive adhesive (PUA-FECA) for flexible electronics applications. PUA is employed as the polymer matrix so that the ECA is flexible and UV-curable at room temperature in just a few minutes. The effects of the PUA-FECA formulation and curing procedure on the electrical properties have been studied. Very low volume resistivity (5.08 × 10-4 Ω cm) is obtained by incorporating 70 wt.% microsized Ag-coated Cu flakes. Moreover, by simply standing the PUA-FECA paste for 4 h before exposure to UV light, the bulk resistivity of the PUA-FECA is dramatically decreased to 3.62 × 10-4 Ω cm. This can be attributed to rearrangement of Ag-coated Cu flakes in the matrix while standing. PUA-FECA also presents stable electrical conductivity during rolling and compression, excellent adhesion, and good processability, making it easily scalable to large-scale fabrication and enabling screen-printing on various low-cost flexible substrates such as office paper and polyethylene terephthalate film.

  17. 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

    2015-03-01

    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.

  18. The precipitation products generation chain for the EUMETSAT Hydrological Satellite Application Facility at C.N.M.C.A.

    Science.gov (United States)

    Biron, Daniele; Melfi, Davide; Zauli, Francesco

    2008-08-01

    The EUMETSAT Satellite Application Facility in support to Hydrology (H-SAF) focuses on 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, carried on 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 architectural status of the H-SAF precipitation group and stress the component of operations. It is shown the full correspondence with the EUMETSAT approved H-SAF documents, in particular the Algorithm Theoretical Design Document (ATDD), where products characteristics are referenced. Are also reported the first results, produced during the first H-SAF Workshop, held in Rome in October 2007, of validation activities performed on version 1 products, and last results of products distribution to beta-users in preparation of distributing version 2.

  19. Si-doped carbon quantum dots: a facile and general preparation strategy, bioimaging application, and multifunctional sensor.

    Science.gov (United States)

    Qian, Zhaosheng; Shan, Xiaoyue; Chai, Lujing; Ma, Juanjuan; Chen, Jianrong; Feng, Hui

    2014-05-14

    Heteroatom doping of carbon quantum dots not only enables great improvement of fluorescence efficiency and tunability of fluorescence emission, but also provides active sites in carbon dots to broaden their application in sensor. Silicon as a biocompatible element offers a promising direction for doping of carbon quantum dots. Si-doped carbon quantum dots (SiCQDs) were synthesized through a facile and effective approach. The as-prepared Si-doped carbon quantum dots possess visible fluorescence with high quantum yield up to 19.2%, owing to fluorescence enhancement effect of introduced silicon atoms into carbon dots. The toxicity test on human Hela cells showed that SiCQDs have lower cellular toxicity than common CQDs, and bioimaging experiments clearly demonstrated their excellent biolabelling ability and outstanding performance in resistance to photobleaching. Strong fluorescence quenching effect of Fe(III) on SiCQDs can be used for its selective detection among general metal ions. Specific electron transfer between SiCQDs and hydrogen peroxide enables SiCQDs as a sensitive fluorescence sensing platform for hydrogen peroxide. The subsequent fluorescence recovery induced by removal of hydrogen peroxide from SiCQDs due to formation of the stable adducts between hydrogen peroxide and melamine was taken advantage of to construct effective sensor for melamine.

  20. Facile synthesis of nitrogen-doped carbon dots and its application as sensing probes for serum iron

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Long; Hou, Juan; Li, Huiyu; Zhao, Qi; Zhang, Fengshuang; Zhao, Jiahui [Jilin University, College of Chemistry (China); Ding, Hong [Jilin University, State Key Laboratory of Inorganic Synthesis and Preparative Chemistry, College of Chemistry (China); Ding, Lan, E-mail: dinglan@jlu.edu.cn [Jilin University, College of Chemistry (China)

    2015-11-15

    In this paper, nitrogen-doped carbon dots (N-CDs) with a quantum yield of 23.6 % were successfully synthesized by microwave pyrolysis of urea using diethylene glycol as the high boiling point reaction medium. The N-CDs were spherical and monodisperse with a size distribution between 1.5 and 5.5 nm. The N-CDs exhibited excellent water-soluble property and remarkable stability under extreme ionic strengths and light illumination. The fluorescence of the N-CDs could be quenched by Fe{sup 3+} through the static quenching mechanism, but not by other common metal ions. On this basis, the N-CDs can be used as a facile sensing platform for label-free sensitive and selective detection of Fe{sup 3+} in a linear range of 1.6–333.3 μmol L{sup −1}, and the detection limit was 0.45 μmol L{sup −1} obtained at a signal-to-noise ratio of 3. Importantly, the N-CDs-based fluorescent probe was successfully applied to the direct analysis of iron contents in human serum samples, which demonstrated potential applications in biological and clinical analysis.

  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. Urban Test Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — RTTC has access to various facilities for use in urban testing applications,including an agreement with the Hazardous Devices School (HDS): a restrictedaccess Urban...

  3. Study of the measurement of critical parameters in an electron beam radiation facility. Application to the case of the first accelerator dedicated to radiation in Tunisia

    Energy Technology Data Exchange (ETDEWEB)

    M' Garrech, S. [Laboratoire de Radio-traitement, Centre National des Sciences et Technologies Nucleaires, 2020 Sidi-Thabet (Tunisia)], E-mail: mgslah@yahoo.fr; Ezzouch, A. [Institut National des Sciences Appliquees et de Technologie, 1080 Tunis (Tunisia)

    2009-02-15

    The Tunisian National Center for Nuclear Sciences and Technologies will acquire the first North African Radio Frequency linear accelerator of electrons in 2009. The facility will be designed primarily for sterilization of medical devices and preservation of foodstuff. The first part of this paper is dedicated to a description of the facility. In order to adjust the treatment conditions and to control the good operation of the accelerator, it is necessary to find out several electron beam parameters. The second part of the paper is devoted to the presentation of the system dedicated to determining several key parameters of the electron beam. The performances and advantages of the diagnostic system cited in this report make it quite suitable for process control application at an electron beam radiation processing facility.

  4. Coarse-scaling adjustment of fine-group neutron spectra for epithermal neutron beams in BNCT using multiple activation detectors

    Science.gov (United States)

    Liu, Yuan-Hao; Nievaart, Sander; Tsai, Pi-En; Liu, Hong-Ming; Moss, Ray; Jiang, Shiang-Huei

    2009-01-01

    In order to provide an improved and reliable neutron source description for treatment planning in boron neutron capture therapy (BNCT), a spectrum adjustment procedure named coarse-scaling adjustment has been developed and applied to the neutron spectrum measurements of both the Tsing Hua Open-pool Reactor (THOR) epithermal neutron beam in Taiwan and the High Flux Reactor (HFR) in The Netherlands, using multiple activation detectors. The coarse-scaling adjustment utilizes a similar idea as the well-known two-foil method, which adjusts the thermal and epithermal neutron fluxes according to the Maxwellian distribution for thermal neutrons and 1/ E distribution over the epithermal neutron energy region. The coarse-scaling adjustment can effectively suppress the number of oscillations appearing in the adjusted spectrum and provide better smoothness. This paper also presents a sophisticated 9-step process utilizing twice the coarse-scaling adjustment which can adjust a given coarse-group spectrum into a fine-group structure, i.e. 640 groups, with satisfactory continuity and excellently matched reaction rates between measurements and calculation. The spectrum adjustment algorithm applied in this study is the same as the well-known SAND-II.

  5. Investigating a cyclotron HM-30 based neutron source for BNCT of deep-seated tumors by using shifting method

    Science.gov (United States)

    Suharyana; Riyatun; Octaviana, E. F.

    2016-11-01

    We have successfully proposed a simulation of a neutron beam-shaping assembly using MCNPX Code. This simulation study deals with designing a compact, optimized, and geometrically simple beam shaping assembly for a neutron source based on a proton cyclotron for BNCT purpose. Shifting method was applied in order to lower the fast neutron energy to the epithermal energy range by choosing appropriate materials. Based on a set of MCNPX simulations, it has been found that the best materials for beam shaping assembly are 3 cm Ni layered with 7 cm Pb as the reflector and 13 cm AlF3 the moderator. Our proposed beam shaping assembly configuration satisfies 2 of 5 of the IAEA criteria, namely the epithermal neutron flux 1.25 × 109 n.cm-2 s-1 and the gamma dose over the epithermal neutron flux is 0.18×10 -13 Gy.cm 2 n -1. However, the ratio of the fast neutron dose rate over neutron epithermal flux is still too high. We recommended that the shifting method must be accompanied by the filter method to reduce the fast neutron flux.

  6. 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

  7. Fabrication Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — The Fabrication Facilities are a direct result of years of testing support. Through years of experience, the three fabrication facilities (Fort Hood, Fort Lewis, and...

  8. Facility Microgrids

    Energy Technology Data Exchange (ETDEWEB)

    Ye, Z.; Walling, R.; Miller, N.; Du, P.; Nelson, K.

    2005-05-01

    Microgrids are receiving a considerable interest from the power industry, partly because their business and technical structure shows promise as a means of taking full advantage of distributed generation. This report investigates three issues associated with facility microgrids: (1) Multiple-distributed generation facility microgrids' unintentional islanding protection, (2) Facility microgrids' response to bulk grid disturbances, and (3) Facility microgrids' intentional islanding.

  9. Operational generation of AVHRR-based cloud products for Europe and the Arctic at EUMETSAT's Satellite Application Facility on Climate Monitoring (CM-SAF

    Directory of Open Access Journals (Sweden)

    F. Kaspar

    2009-04-01

    Full Text Available The Satelite Application Facility on Climate Monitoring has implemented a new processing environment for AVHRR-based climate monitoring products. AVHRR measurements from NOAA-17, NOAA-18 and MetOp-A are utilized to generate daily and monthly means of several cloud parameters for Europe and the Inner Arctic: Cloud fraction, cloud types, cloud phase, cloud top height, cloud optical thickness and cloud liquid water path.

  10. An evaluation of the various aspects of the progress in clinical applications of laser driven ionizing radiation

    Science.gov (United States)

    Hideghéty, K.; Szabó, E. R.; Polanek, R.; Szabó, Z.; Ughy, B.; Brunner, S.; Tőkés, T.

    2017-03-01

    There has been a vast development of laser-driven particle acceleration (LDPA) using high power lasers. This has initiated by the radiation oncology community to use the dose distribution and biological advantages of proton/heavy ion therapy in cancer treatment with a much greater accessibility than currently possible with cyclotron/synchrotron acceleration. Up to now, preclinical experiments have only been performed at a few LDPA facilities; technical solutions for clinical LDPA have been theoretically developed but there is still a long way to go for the clinical introduction of LDPA. Therefore, to explore the further potential bio-medical advantages of LDPA has pronounced importance. The main characteristics of LDPA are the ultra-high beam intensity, the flexibility in beam size reduction and the potential particle and energy selection whilst conventional accelerators generate single particle, quasi mono-energetic beams. There is a growing number of studies on the potential advantages and applications of Energy Modulated X-ray Radiotherapy, Modulated Electron Radiotherapy and Very High Energy Electron (VHEE) delivery system. Furthermore, the ultra-high space and/or time resolution of super-intense beams are under intensive investigation at synchrotrons (microbeam radiation and very high dose rate (> 40 Gy/s) electron accelerator flash irradiation) with growing evidence of significant improvement of the therapeutic index. Boron Neutron Capture Therapy (BNCT) is an advanced cell targeted binary treatment modality. Because of the high linear energy transfer (LET) of the two particles (7Li and 4He) released by 10BNC reaction, all of the energy is deposited inside the tumour cells, killing them with high probability, while the neighbouring cells are not damaged. The limited availability of appropriate neutron sources, prevent the more extensive exploration of clinical benefit of BNCT. Another boron-based novel binary approach is the 11B-Proton Fusion, which result in

  11. Application of Biogas Manure in Facility Agriculture%沼肥在设施农业大棚中的应用

    Institute of Scientific and Technical Information of China (English)

    李红霞

    2014-01-01

    The paper described the situation and problems of the application of biogas manure in facility agriculture ,analyzed the nutritional contents of biogas slurry and biogas residue ,and put forward the application method of biogas manure .%笔者分析了沼肥在设施农业中应用的现状及普遍存在的问题,对沼液、沼渣的营养成分进行了分析,提出了沼肥(沼液、沼渣等)的施用方法。

  12. Bystander effect-induced mutagenicity in HPRT locus of CHO cells following BNCT neutron irradiation: Characteristics of point mutations by sequence analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kinashi, Yuko [Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka (Japan)], E-mail: kinashi@rri.kyoto-u.ac.jp; Suzuki, Minoru; Masunaga, Shinichiro; Ono, Koji [Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka (Japan)

    2009-07-15

    To investigate bystander mutagenic effects induced by alpha particles during boron neutron capture therapy (BNCT), we mixed cells that were electroporated with borocaptate sodium (BSH), which led to the accumulation of {sup 10}B inside the cells, with cells that did not contain the boron compound. BSH-containing cells were irradiated with {alpha} particles produced by the {sup 10}B(n,{alpha}){sup 7}Li reaction, whereas cells without boron were only affected by the {sup 1}H(n,{gamma}){sup 2}H and {sup 14}N(n,{rho}){sup 14}C reactions. The frequency of mutations induced in the hypoxanthine-guanine phosphoribosyltransferase (HPRT) locus was examined in Chinese hamster ovary (CHO) cells irradiated with neutrons (Kyoto University Research Reactor: 5 MW). Neutron irradiation of 1:1 mixtures of cells with and without BSH resulted in a survival fraction of 0.1, and the cells that did not contain BSH made up 99.4% of the surviving cell population. Using multiplex polymerase chain reactions (PCRs), molecular structural analysis indicated that most of the mutations induced by the bystander effect were point mutations and that the frequencies of total and partial deletions induced by the bystander effect were lower than those resulting from the {alpha} particles produced by the {sup 10}B(n,{alpha}){sup 7}Li reaction or the neutron beam from the {sup 1}H(n,{gamma}){sup 2}H and {sup 14}N(n,{rho}){sup 14}C reactions. The types of point mutations induced by the BNCT bystander effect were analyzed by cloning and sequencing methods. These mutations were comprised of 65.5% base substitutions, 27.5% deletions, and 7.0% insertions. Sequence analysis of base substitutions showed that transversions and transitions occurred in 64.7% and 35.3% of cases, respectively. G:C{yields}T:A transversion induced by 8-oxo-guanine in DNA occurred in 5.9% of base substitution mutants in the BNCT bystander group. The characteristic mutations seen in this group, induced by BNCT {alpha} particles

  13. 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.

  14. 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.)

  15. RADIATION DOSIMETRY IN THE BNCT PATIENT TREATMENT ROOM AT THE BMRR.

    Energy Technology Data Exchange (ETDEWEB)

    HOLDEN, N.E.; RECINIELLO, R.N.; HU, J.-P.

    2005-05-08

    The Medical Research Reactor at the Brookhaven National Laboratory (BMRR) was a heterogeneous, tank type, light water cooled and moderated, graphite reflected reactor, which was operated on demand at a power level up to 3 mega-watts (MW) for medical and biological research [1]. The reactor first went critical on March 15, 1959, with 17 fresh fuel elements (2.52 kg uranium-235 in a total of 2.7 kg uranium) in the center core. The BMRR had two treatment rooms on opposite sides of the core. It had a predominately thermal neutron beam in the Thermal Neutron Irradiation Facility (TNE) on the west side of the core. By early 1990, a redesigned beam line had a predominately epithermal neutron beam in the Epithermal Neutron Irradiation Facility (ENIF) on the east side of the core [2]. The ENP was approximately 11 feet by 21 feet in size with its focal point consisting of a bismuth plate mounted in the wall adjacent to the reactor shield about 36 inches above the floor. The beam originated at a shutter constructed of 0.75 inch steel filled with concrete and weighing {approx}21 tons. Access to the ENIF was through a pair of hand operated steel shielding doors, each 42 inches wide, 84 inches high and 5 inches thick. The inner door had a 4-inch thick layer of paraffin on the side facing the reactor. The doors 5000 pounds weighed each. Additional shielding material had been added to the entire beam port at reactor wall within the ENIF. The shielding material consisted of 2-inch thick polyethylene sheets, which were impregnated with 95%-enriched {sup 6}Li in lithium carbonate (Li{sub 2}CO{sub 3}). The shielding sheets around the port face were designed to allow the insertion of a variety of different beam collimators.

  16. 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

  17. Development and calculation of an energy dependent normal brain tissue neutron RBE for evaluating neutron fields for BNCT.

    Science.gov (United States)

    Woollard, J E; Blue, T E; Gupta, N; Gahbauer, R A

    2001-06-01

    In Boron Neutron Capture Therapy (BNCT) of malignant brain tumors, the energy dependence of a clinically relevant Relative Biological Effectiveness (RBE) for epithermal neutrons, RBE(En), is important in neutron field design. In the first half of this paper, we present the development of an expression for the energy dependent normal-tissue RBE, RBE(En). We then calculate a reasonable estimate for RBE(En) for adult brain tissue. In the second half of the paper, two separate RBE expressions are developed, one for the RBE of the neutrons that interact in tissue via the 14N(n,p)14C reaction, denoted RBE(N), and one for the RBE of the neutrons which interact in tissue via the 1H(n,n')1H reaction, denoted RBE(H). The absorbed-dose-averaged values of these expressions are calculated for the neutron flux spectrum in phantom for the Brookhaven Medical Research Reactor (BMRR) epithermal neutron beam. The calculated values, [RBE(norm)N] = 3.4 and [RBE(norm)H] = 3.2, are within 6% of being equal, and support the use of equal values for RBEN and RBE(H) by researchers at Brookhaven National Laboratory (BNL). Finally, values of [RBE(norm)N] and [RBE(norm)H], along with the absorbed-dose-averaged RBE for brain, [RBE(norm)b], were calculated as a function of depth along the centerline of an ellipsoidal head phantom using flux spectra calculated for our Accelerator-Based Neutron Source (ABNS). These values remained essentially constant with depth, supporting the use of constant values for RBE, as is done at BNL.

  18. Regulatory facility guide for Ohio

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

    1994-02-28

    The Regulatory Facility Guide (RFG) has been developed for the DOE and contractor facilities located in the state of Ohio. It provides detailed compilations of international, federal, and state transportation-related regulations applicable to shipments originating at destined to Ohio facilities. This RFG was developed as an additional resource tool for use both by traffic managers who must ensure that transportation operations are in full compliance with all applicable regulatory requirements and by oversight personnel who must verify compliance activities.

  19. Development and laboratory testing of a thermal emission velocimeter for application to an erosion nose tip test facility

    Science.gov (United States)

    Trolinger, J. D.; Houser, M. J.

    1981-08-01

    A thermal emission velocimeter concept was explored and a system was developed for use in measuring particle velocities up to 5,000 meters per second in a reentry erosion facility. The particles, ranging from 10 to 100 micrometers in diameter, are generated to study reentry nose tip erosion and ablation. The approach passively utilizes optical components of a laser transit anemometer coupled to a microprocessor data management system. The system was laboratory tested and has inherent characteristics which should produce quality data in the severe and noisy environment of a reentry test facility. The system sensitivity has been calculated to measure velocity of micrometer sized particles whose temperature are minimally 1700 K.

  20. Application of reactive compensation method in thermal facilities%无功补偿方法在热力设施中的应用

    Institute of Scientific and Technical Information of China (English)

    袁银生

    2012-01-01

    简要介绍了有功功率和无功功率的概念,阐述了无功补偿的意义,对无功补偿的原理和补偿方法的发展进行了论述,对热力设施用电特性进行分析,并对热力设施用电的无功补偿方法及具体应用提出一定见解,以指导实践。%This paper briefly introduces the definition of active power and reactive power,describes the meaning of reactive compensation,discusses reactive compensation principles and compensation methods,analyzes the power supply characteristics of thermal facilities,and then puts forward specific application and some views on the reactive compensation method in the power supply of thermal facilities,so as to guide practice.

  1. Feasibility analysis of a Plasma Focus neutron source for BNCT treatment of transplanted human liver

    Science.gov (United States)

    Benzi, V.; Mezzetti, F.; Rocchi, F.; Sumini, M.

    2004-01-01

    Boron Neutron Capture Therapy preliminary treatments on transplanted human liver have been recently conducted at Pavia University. The need of high fluences of thermal neutrons imposed the use of the available thermal channel of a TRIGA reactor properly modified for this application. We analyse the possibility of using the Plasma Focus (PF) machine as a pulsed neutron source for this medical application instead of a nuclear reactor. Thermalization of the fast (2.45 MeV for D-D reactions) neutrons produced by the PF is gained with a paraffin or polyethylene moderator which contains both the neutron source and the irradiation chamber. The design parameters of a PF optimized for such an application are discussed, as well as other considerations on the advantages that this machine can bring to this kind of cancer therapy.

  2. Bioactive Encapsulation for Military Food Applications: Request for Enhanced Nano and Micro Particle Fabrication and Characterization Facilities

    Science.gov (United States)

    2016-01-25

    SECURITY CLASSIFICATION OF: The purpose of this project was to establish state-of-the art facilities to develop nanoparticle and microparticle...McClements, D. J. (2014). Encapsulation, protection, and re- lease of polyunsaturated lipids using biopolymer-based hydrogel particles. Food Research Inter

  3. Calculation of Absorbed Dose in Target Tissue and Equivalent Dose in Sensitive Tissues of Patients Treated by BNCT Using MCNP4C

    Science.gov (United States)

    Zamani, M.; Kasesaz, Y.; Khalafi, H.; Pooya, S. M. Hosseini

    Boron Neutron Capture Therapy (BNCT) is used for treatment of many diseases, including brain tumors, in many medical centers. In this method, a target area (e.g., head of patient) is irradiated by some optimized and suitable neutron fields such as research nuclear reactors. Aiming at protection of healthy tissues which are located in the vicinity of irradiated tissue, and based on the ALARA principle, it is required to prevent unnecessary exposure of these vital organs. In this study, by using numerical simulation method (MCNP4C Code), the absorbed dose in target tissue and the equiavalent dose in different sensitive tissues of a patiant treated by BNCT, are calculated. For this purpose, we have used the parameters of MIRD Standard Phantom. Equiavelent dose in 11 sensitive organs, located in the vicinity of target, and total equivalent dose in whole body, have been calculated. The results show that the absorbed dose in tumor and normal tissue of brain equal to 30.35 Gy and 0.19 Gy, respectively. Also, total equivalent dose in 11 sensitive organs, other than tumor and normal tissue of brain, is equal to 14 mGy. The maximum equivalent doses in organs, other than brain and tumor, appear to the tissues of lungs and thyroid and are equal to 7.35 mSv and 3.00 mSv, respectively.

  4. Are high energy proton beams ideal for AB-BNCT? A brief discussion from the viewpoint of fast neutron contamination control.

    Science.gov (United States)

    Lee, Pei-Yi; Liu, Yuan-Hao; Jiang, Shiang-Huei

    2014-06-01

    High energy proton beam (>8MeV) is favorable for producing neutrons with high yield. However, the produced neutrons are of high energies. These high energy neutrons can cause severe fast neutron contamination and degrade the BNCT treatment quality if they are not appropriately moderated. Hence, this study aims to briefly discuss the issue, from the viewpoint of fast neutron contamination control, whether high energy proton beam is ideal for AB-BNCT or not. In this study, D2O, PbF4, CaF2, and Fluental(™) were used standalone as moderator materials to slow down 1-, 6-, and 10-MeV parallelly incident neutrons. From the calculated results, we concluded that neutrons produced by high energy proton beam could not be easily moderated by a single moderator to an acceptable contamination level and still with reasonable epithermal neutron beam intensity. Hence, much more complicated and sophisticated designs of beam shaping assembly have to be developed when using high energy proton beams.

  5. 物联网关键技术在设施农业中应用探讨%Application of key internet of thing technologies in facility agriculture

    Institute of Scientific and Technical Information of China (English)

    贾文珅; 李孟楠; 李雨; 孟蕾; 卢娜; 韩平; 潘立刚; 王纪华

    2016-01-01

    Agriculture Internet of Things (IoT) refers to using a large number of sensor nodes to constitute a monitoring network and use sensors to collect information so that problems can be found and located accurately. Therefore, agriculture IoT makes extensive use of various automated, intelligent, and remote-control production devices. Facility agriculture is a concrete embodiment and symbol of modern agriculture and can generate high efficiency and high profits for agriculture. Therefore, the application of agriculture IoT into facility agriculture will shift the agricultural production mode centered on manual labor and dependent on isolated machines to one centered on information and software. According to the architecture of IoT, facility agriculture IoT is divided into three parts:the perception layer, the transmission layer, and the application layer which corresponds to information perception technology, information transmission technology, and information application technology respectively. Based on the investigation and analysis of the latest developments in Chinese and foreign facility agriculture IoT technologies, this paper summarized the research progress of facility agriculture IoT in information perception technology, information transmission technology, and information application technology, as well as big data and Iot facilities agriculture, etc. Based on the developments in facility agriculture IoT technologies, some constructive suggestions from the aspects of the perception layer, transmission layer, and application layer were put forward.%农业物联网是将大量的传感器节点构成监控网络,通过各种传感器采集信息,以便发现问题,并且准确地确定发生问题的位置,从而大量使用各种自动化、智能化、远程控制的生产设备。而设施农业是现代化农业的具体体现和标志,可以获取农业生产高效率与高收益,因此将农业物联网应用到设施农业中,将突破

  6. Application of Cycloaddition Reactions to the Syntheses of Novel Boron Compounds

    OpenAIRE

    Maguire, John A.; Hosmane, Narayan S; Yinghuai Zhu; Xiao Siwei

    2010-01-01

    This review covers the application of cycloaddition reactions in forming the boron-containing compounds such as symmetric star-shaped boron-enriched dendritic molecules, nano-structured boron materials and aromatic boronic esters. The resulting boron compounds are potentially important reagents for both materials science and medical applications such as in boron neutron capture therapy (BNCT) in cancer treatment and as drug delivery agents and synthetic intermediates for carbon-carbon cross-c...

  7. 10 CFR 55.46 - Simulation facilities.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Simulation facilities. 55.46 Section 55.46 Energy NUCLEAR... Simulation facilities. (a) General. This section addresses the use of a simulation facility for the... applicants for operator and senior operator licenses. (b) Commission-approved simulation facilities...

  8. R D activities at Argonne National Laboratory for the application of base seismic isolation in nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Seidensticker, R.W.

    1991-01-01

    Argonne National Laboratory (ANL) has been deeply involved in the development of seismic isolation for use in nuclear facilities for the past decade. Initial focus of these efforts has been on the use of seismic isolation for advanced liquid metal reactors (LMR). Subsequent efforts in seismic isolation at ANL included a lead role in an accelerated development program for possible use of seismic isolation for the DOE's New Production reactors (NPR). Under funding provided by the National Science Foundation (NSF) Argonne is currently working with Shimizu in a joint United States-Japanese program on response of seismically-isolated buildings to actual earthquakes. The results of recent work in the seismic isolation program elements are described in this paper. The current Status of these programs is presented along with an assessment of work still needed to bring the benefits of this emerging technology to full potential in nuclear reactors and other nuclear facilities. 38 refs., 3 figs.

  9. Design, development and characterization of multi-functionalized gold nanoparticles for biodetection and targeted boron delivery in BNCT applications.

    NARCIS (Netherlands)

    Mandal, S.; Bakeine, G.J.; Krol, S.; Ferrari, C.; Clerici, A.M.; Zonta, C.; Cansolino, L.; Ballarini, F.; Bortolussi, S.; Stella, S.; Protti, N.; Bruschi, P.; Altieri, S.

    2011-01-01

    The aim of this study is to optimize targeted boron delivery to cancer cells and its tracking down to the cellular level. To this end, we describe the design and synthesis of novel nanovectors that double as targeted boron delivery agents and fluorescent imaging probes. Gold nanoparticles were coate

  10. Design, development and characterization of multi-functionalized gold nanoparticles for biodetection and targeted boron delivery in BNCT applications

    Energy Technology Data Exchange (ETDEWEB)

    Mandal, Subhra [Department of Tumor Immunology, Radboud University Nijmegen Medical Centre (Netherlands); Bakeine, Gerald J., E-mail: Jamesbakeine1@yahoo.com [Department of Internal Medicine and Therapeutics-Section of Clinical Toxicology, University of Pavia, Piazza Botta 10, 27100 Pavia (Italy); Krol, Silke [Institute of Neurology, Fondazione IRCCS Carlo Besta, Milan (Italy); Ferrari, Cinzia; Clerici, Anna M.; Zonta, Cecilia; Cansolino, Laura [Department of Surgery, Laboratory of Experimental Surgery, University of Pavia (Italy); Ballarini, Francesca [Department of Nuclear and Theoretical Physics, University of Pavia (Italy); Bortolussi, Silva [Department of Nuclear and Theoretical Physics, University of Pavia (Italy)] [National Institute of Nuclear Physics (INFN), Section of Pavia (Italy); Stella, Subrina; Protti, Nicoletta [Department of Nuclear and Theoretical Physics, University of Pavia (Italy); Bruschi, Piero [National Institute of Nuclear Physics (INFN), Section of Pavia (Italy); Altieri, Saverio [Department of Nuclear and Theoretical Physics, University of Pavia (Italy)] [National Institute of Nuclear Physics (INFN), Section of Pavia (Italy)

    2011-12-15

    The aim of this study is to optimize targeted boron delivery to cancer cells and its tracking down to the cellular level. To this end, we describe the design and synthesis of novel nanovectors that double as targeted boron delivery agents and fluorescent imaging probes. Gold nanoparticles were coated with multilayers of polyelectrolytes functionalized with the fluorescent dye (FITC), boronophenylalanine and folic acid. In vitro confocal fluorescence microscopy demonstrated significant uptake of the nanoparticles in cancer cells that are known to overexpress folate receptors. - Highlights: Black-Right-Pointing-Pointer Synthesis of multi-labeled gold nanoparticles for selective boron delivery to tumor cells. Black-Right-Pointing-Pointer Tumor selectivity is achieved through folic acid receptor targeting. Black-Right-Pointing-Pointer Optical fluorescent microscopy allows tracking of cellular uptake of the gold nanoparticle. Black-Right-Pointing-Pointer In vitro tests demonstrate selective nanoparticle up in folate receptor positive tumor cells.

  11. 医院手卫生设施的临床应用进展%Progress in the clinical application of hand hygiene facilities in the hospital

    Institute of Scientific and Technical Information of China (English)

    官素琼; 李岸英; 韦瑞敏

    2014-01-01

    手卫生是预防医院感染最简单、最方便、最有效、最便宜的方法。提高医务人员洗手的依从性,确保手卫生是预防医院感染的重要环节。而提供方便实用的手卫生设施,是提高医务人员洗手依从性的主要措施之一。手卫生设施在不断改进应用,本文对手卫生设施,包括洗手池、水龙头、流动水、清洁剂、干手用品、手消毒剂等临床应用情况进行综述。%Hand hygiene is the most simple,the most convenient,the most effective,the most expensive method of hospital infection prevention. To improve the medical staff hand washing compliance to ensure hand hygiene is an important link in prevention of hospital infection.And providing a convenient and practical hand hygiene facilities, is one of the main measures to improve the medical staff hand washing compliance.Hand hygiene facilities in the continuous improvement of application.The text is to review hand hygiene facilities,including the sink,water tap,flowing water,cleaning agents,dry hand supplies,hand antiseptic agent and other clinical applications.

  12. Canyon Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — B Plant, T Plant, U Plant, PUREX, and REDOX (see their links) are the five facilities at Hanford where the original objective was plutonium removal from the uranium...

  13. Mammography Facilities

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Mammography Facility Database is updated periodically based on information received from the four FDA-approved accreditation bodies: the American College of...

  14. Health Facilities

    Science.gov (United States)

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, such as birthing centers and psychiatric care centers. When you ...

  15. The alanine detector in BNCT dosimetry: Dose response in thermal and epithermal neutron fields

    Energy Technology Data Exchange (ETDEWEB)

    Schmitz, T., E-mail: schmito@uni-mainz.de [Institute for nuclear chemistry, Johannes Gutenberg-University, Mainz D-55128 (Germany); Bassler, N. [Department of Physics and Astronomy, Aarhus University, Ny Munkegade 120, Aarhus C, Aarhus 8000 (Denmark); Blaickner, M. [AIT Austrian Institute of Technology GmbH, Vienna A-1220 (Austria); Ziegner, M. [AIT Austrian Institute of Technology GmbH, Vienna A-1220, Austria and TU Wien, Vienna University of Technology, Vienna A-1020 (Austria); Hsiao, M. C. [Insitute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu 30013, Taiwan (China); Liu, Y. H. [Nuclear Science and Technology Development Center, National Tsing Hua University, Hsinchu 30013, Taiwan (China); Koivunoro, H. [Department of Physics, University of Helsinki, POB 64, FI-00014, Finland and HUS Medical Imaging Center, Helsinki University Central Hospital, FI-00029 HUS (Finland); Auterinen, I.; Serén, T.; Kotiluoto, P. [VTT Technical Research Centre of Finland, Espoo (Finland); Palmans, H. [National Physical Laboratory, Acoustics and Ionising Radiation Division, Teddington TW11 0LW, United Kingdom and Medical Physics Group, EBG MedAustron GmbH, Wiener Neustadt A-2700 (Austria); Sharpe, P. [National Physical Laboratory, Acoustics and Ionising Radiation Division, Teddington TW11 0LW (United Kingdom); Langguth, P. [Department of Pharmacy and Toxicology, University of Mainz, Mainz D-55128 (Germany); Hampel, G. [Institut für Kernchemie, Johannes Gutenberg-Universität, Mainz D-55128 (Germany)

    2015-01-15

    Purpose: The response of alanine solid state dosimeters to ionizing radiation strongly depends on particle type and energy. Due to nuclear interactions, neutron fields usually also consist of secondary particles such as photons and protons of diverse energies. Various experiments have been carried out in three different neutron beams to explore the alanine dose response behavior and to validate model predictions. Additionally, application in medical neutron fields for boron neutron capture therapy is discussed. Methods: Alanine detectors have been irradiated in the thermal neutron field of the research reactor TRIGA Mainz, Germany, in five experimental conditions, generating different secondary particle spectra. Further irradiations have been made in the epithermal neutron beams at the research reactors FiR 1 in Helsinki, Finland, and Tsing Hua open pool reactor in HsinChu, Taiwan ROC. Readout has been performed with electron spin resonance spectrometry with reference to an absorbed dose standard in a {sup 60}Co gamma ray beam. Absorbed doses and dose components have been calculated using the Monte Carlo codes FLUKA and MCNP. The relative effectiveness (RE), linking absorbed dose and detector response, has been calculated using the Hansen and Olsen alanine response model. Results: The measured dose response of the alanine detector in the different experiments has been evaluated and compared to model predictions. Therefore, a relative effectiveness has been calculated for each dose component, accounting for its dependence on particle type and energy. Agreement within 5% between model and measurement has been achieved for most irradiated detectors. Significant differences have been observed in response behavior between thermal and epithermal neutron fields, especially regarding dose composition and depth dose curves. The calculated dose components could be verified with the experimental results in the different primary and secondary particle fields. Conclusions: The

  16. Use of international data sets to evaluate and validate pathway assessment models applicable to exposure and dose reconstruction at DOE facilities. Progress report, August 1993--January 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, S.M. [ed.] [Lawrence Livermore National Lab., CA (United States); Hoffman, F.O. [Senes Oak Ridge, Inc., TN (United States). Center for Risk Analysis

    1994-03-01

    This project, ``Use of International Data Sets to Evaluate and Validate Pathway Assessment Models Applicable to Exposure and Dose Reconstruction at DOE Facilities,`` grew out of several activities being conducted by the Principal Investigator Dr. F Owen Hoffman. One activity was originally part of the Chernobyl Studies Project and began as Task 7.1D, ``Internal Dose From Direct Contamination of Terrestrial Food Sources.`` The objective of Task 7.1D was to (1) establish a collaborative US USSR effort to improve and validate our methods of forecasting doses and dose commitments from the direct contamination of food sources, and (2) perform experiments and validation studies to improve our ability to predict rapidly and accurately the long-term internal dose from the contamination of agricultural soil. The latter was to include the consideration of remedial measures to block contamination of food grown on contaminated soil. The current objective of this project is to evaluate and validate pathway-assessment models applicable to exposure and dose reconstruction at DOE facilities through use of international data sets. This project incorporates the activity of Task 7.1D into a multinational effort to evaluate data used for the prediction of radionuclide transfer through agricultural and aquatic systems to humans. It also includes participation in two multinational studies, BIOMOVS (BIOspheric MOdel Validation Study) with the Swedish National Institute for Radiation Protection and VAMP (VAlidation of Model Predictions) with the International Atomic Energy Agency, that address testing the performance of models of radionuclide transport through foodchains.

  17. Evaluation of Quantitative Exposure Assessment Method for Nanomaterials in Mixed Dust Environments: Application in Tire Manufacturing Facilities.

    Science.gov (United States)

    Kreider, Marisa L; Cyrs, William D; Tosiano, Melissa A; Panko, Julie M

    2015-11-01

    Current recommendations for nanomaterial-specific exposure assessment require adaptation in order to be applied to complicated manufacturing settings, where a variety of particle types may contribute to the potential exposure. The purpose of this work was to evaluate a method that would allow for exposure assessment of nanostructured materials by chemical composition and size in a mixed dust setting, using carbon black (CB) and amorphous silica (AS) from tire manufacturing as an example. This method combined air sampling with a low pressure cascade impactor with analysis of elemental composition by size to quantitatively assess potential exposures in the workplace. This method was first pilot-tested in one tire manufacturing facility; air samples were collected with a Dekati Low Pressure Impactor (DLPI) during mixing where either CB or AS were used as the primary filler. Air samples were analyzed via scanning transmission electron microscopy (STEM) coupled with energy dispersive spectroscopy (EDS) to identify what fraction of particles were CB, AS, or 'other'. From this pilot study, it was determined that ~95% of all nanoscale particles were identified as CB or AS. Subsequent samples were collected with the Dekati Electrical Low Pressure Impactor (ELPI) at two tire manufacturing facilities and analyzed using the same methodology to quantify exposure to these materials. This analysis confirmed that CB and AS were the predominant nanoscale particle types in the mixing area at both facilities. Air concentrations of CB and AS ranged from ~8900 to 77600 and 400 to 22200 particles cm(-3), respectively. This method offers the potential to provide quantitative estimates of worker exposure to nanoparticles of specific materials in a mixed dust environment. With pending development of occupational exposure limits for nanomaterials, this methodology will allow occupational health and safety practitioners to estimate worker exposures to specific materials, even in scenarios

  18. Variable gravity research facility

    Science.gov (United States)

    Allan, Sean; Ancheta, Stan; Beine, Donna; Cink, Brian; Eagon, Mark; Eckstein, Brett; Luhman, Dan; Mccowan, Daniel; Nations, James; Nordtvedt, Todd

    1988-01-01

    Spin and despin requirements; sequence of activities required to assemble the Variable Gravity Research Facility (VGRF); power systems technology; life support; thermal control systems; emergencies; communication systems; space station applications; experimental activities; computer modeling and simulation of tether vibration; cost analysis; configuration of the crew compartments; and tether lengths and rotation speeds are discussed.

  19. Remarks on Consistent Development of Plant Nodalizations: An Example of Application to the ROSA Integral Test Facility

    Directory of Open Access Journals (Sweden)

    J. Freixa

    2012-01-01

    Full Text Available Experimental results obtained at integral test facilities (ITFs are used in the validation process of system codes for the transient analyses of light water reactors (LWRs. The expertise and guidelines derived from this work are later applied to transient analyses of nuclear power plants (NPPs. However, the boundary conditions at the NPPs will always differ from those at the ITF, and hence, the soundness of the ITF model needs to be maximized. An unaltered ITF nodalization should prove to be able to simulate as many tests as possible, before any conclusion is derived to NPP analyses. The STARS group at the Paul Scherrer Institut (PSI actively participates in several international programs, where ITFs are being used (e.g., ROSA, PKL. Several tests carried out at the ROSA large-scale test facility operated by the Japan Atomic Energy Agency (JAEA have been simulated in recent years by using the United States Nuclear Regulatory Commission (US-NRC system code TRACE. In this paper, 5 different posttest analyses are presented, along with the evolution of the employed TRACE nodalization and the process followed to track the consistency of the nodalization modifications. The ROSA TRACE nodalization provided results in a reasonable agreement with all 5 experiments.

  20. The application of proton spectrometers at the SG-III facility for ICF implosion areal density diagnostics

    Institute of Scientific and Technical Information of China (English)

    Xing Zhang; Jianhua Zheng; Ji Yan; Zhenghua Yang; Ming Su; Yudong Pu; Pin Yang; Xufei Xie; Li Chen; Ming Chen; Tianxuan Huang; Shao’en Jiang; Shenye Liu; Jiamin Yang

    2015-01-01

    Charged particle diagnostics is one of the required techniques for implosion areal density diagnostics at the SG-III facility.Several proton spectrometers are under development, and some preliminary areal density diagnostics have been carried out. The response of the key detector, CR39, to charged particles was investigated in detail. A new track profile simulation code based on a semi-empirical model was developed. The energy response of the CR39 detector was calibrated with the accelerator protons and alphas from a241 Am source. A proton spectrometer based on the filtered CR39 detector was developed, and D–D primary proton measurements were implemented. A step range filter spectrometer was developed,and preliminary areal density diagnostics was carried out. A wedged range filter spectrometer array made of Si with a higher resolution was designed and developed at the SG-III facility. A particle response simulation code by the Monte Carlo method and a spectra unfolding code were developed. The capability was evaluated in detail by simulations.

  1. Theory of hydro-equivalent ignition for inertial fusion and its applications to OMEGA and the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Nora, R.; Betti, R.; Bose, A.; Woo, K. M.; Christopherson, A. R.; Meyerhofer, D. D. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Fusion Science Center, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Physics and/or Mechanical Engineering, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Anderson, K. S.; Shvydky, A.; Marozas, J. A.; Collins, T. J. B.; Radha, P. B.; Hu, S. X.; Epstein, R.; Marshall, F. J.; Sangster, T. C. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); McCrory, R. L. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Physics and/or Mechanical Engineering, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States)

    2014-05-15

    The theory of ignition for inertial confinement fusion capsules [R. Betti et al., Phys. Plasmas 17, 058102 (2010)] is used to assess the performance requirements for cryogenic implosion experiments on the Omega Laser Facility. The theory of hydrodynamic similarity is developed in both one and two dimensions and tested using multimode hydrodynamic simulations with the hydrocode DRACO [P. B. Radha et al., Phys. Plasmas 12, 032702 (2005)] of hydro-equivalent implosions (implosions with the same implosion velocity, adiabat, and laser intensity). The theory is used to scale the performance of direct-drive OMEGA implosions to the National Ignition Facility (NIF) energy scales and determine the requirements for demonstrating hydro-equivalent ignition on OMEGA. Hydro-equivalent ignition on OMEGA is represented by a cryogenic implosion that would scale to ignition on the NIF at 1.8 MJ of laser energy symmetrically illuminating the target. It is found that a reasonable combination of neutron yield and areal density for OMEGA hydro-equivalent ignition is 3 to 6 × 10{sup 13} and ∼0.3 g/cm{sup 2}, respectively, depending on the level of laser imprinting. This performance has not yet been achieved on OMEGA.

  2. Facile linker free growth of CdS nanoshell on 1-D ZnO: Solar cell application

    Science.gov (United States)

    Kamble, Archana; Sinha, Bhavesh; Chung, Kookchae; More, Anup; Vanalakar, Sharad; Hong, Chang Woo; Kim, Jin Hyeok; Patil, Pramod

    2015-03-01

    One dimensional type-II core/shell heterostructures are widely employed in solar cells because of their adventitious role in both light absorption and charge separation. Here we report a facile two step chemical approach to synthesizing ZnO/CdS core/shell nanorod arrays. ZnO nanorods (ZNR) with a high aspect ratio were grown using a hydrothermal technique where a uniform CdS shell was deposited using a facile, linker free, one pot, Hexamethylenetetramine (HMTA) based reflux technique for the first time. Though the reflux technique is quite similar to the chemical bath deposition technique (CBD), we obtained more uniform CdS coating and improved solar cell performance with the ZnO/CdS heterostructure compared to CBD-grown ZnO/CdS heterostructures. To obtain a conformal coating of CdS, we optimized the CdS deposition time. Formation of pure phase ZnO/CdS core/shell heterostructure was confirmed by high resolution transmission electron microscopy and X-ray photoelectron spectroscopy (XPS) depth analysis. Improved solar cell performance of 1.23% was obtained for ZnO/CdS core/shell structures with ZnS surface treatment. [Figure not available: see fulltext.

  3. Characterization of the Bnct Epithermal Column of the Fast Reactor Tapiro (enea) and Dose Measurements in Phantom Utilising Not-Conventional Detection

    Science.gov (United States)

    Gambarini, G.; Colombi, C.; Lietti, B.; Prestini, P.; Fiorani, O.; Perrone, A.; Rosi, G.; Agosteo, S.; Riva, A.

    2002-11-01

    The epithermal column of TAPIRO reactor has been characterized and in-phantom dose has been imaged, with the purpose of determining parameters and data whose knowledge will be of main importance for future experimentation regarding boron neutron capture therapy (BNCT). In-phantom measurements have been carried out mainly utilizing a recently developed method for absorbed dose imaging, based on gel-dosimeters. Gel-dosimeters have revealed to give significant support to thermal or epithermal neutron dosimetry: in fact, the modality of energy release in gel-dosimeters is very similar to that in tissue, and with proper adjustment of the isotopic composition of gel matrix, the various dose components are separated.

  4. SUPER-CAPACITOR APPLICATION IN ELECTRICAL POWER CABLE TESTING FACILITIES IN THERMAL ENDURANCE AND MECHANICAL BRACING TESTS

    Directory of Open Access Journals (Sweden)

    I. V. Oleksyuk

    2015-01-01

    Full Text Available The current-carrying cores of the electrical power cables should be resistant to effects of short-circuit currents whose values depend on the material of the core, its cross-sectional area, cable insulation properties, environment temperature, and the duration of the short-circuit current flow (1 and 3–4 sec. when tested for thermal endurance and mechanical bracing. The facilities for testing the 10 kV aluminum core cables with short-circuit current shall provide mechanical-bracing current 56,82 kA and thermal endurance current 11,16 kA. Although capacitors provide such values of the testing currents to the best advantage, utilizing conventional capacitor-units will involve large expenditures for erecting and  running a separate building. It is expedient to apply super-capacitors qua the electric power supply for testing facilities, as they are capacitors with double-electrical layer and involve the current values of tens of kilo-amperes.The insulation voltage during short-circuit current testing being not-standardized, it is not banned to apply voltages less than 10 kV when performing short-circuit thermal endurance and mechanical bracing tests for electrical power cables of 10 kV. The super-capacitor voltage variation-in-time graph consists of two regions: capacitive and resistive. The capacitive part corresponds to the voltage change consequent on the energy change in the super-capacitors. The resistive part shows the voltage variation due to the active resistance presence in the super-capacitor.The author offers the algorithm determining the number of super capacitors requisite for testing 10 kV-electrical power cables with short-circuit currents for thermal endurance and mechanical bracing. The paper shows that installation of super-capacitors in the facilities testing the cables with short-circuit currents reduces the area needed for the super-capacitors in comparison with conventional capacitors more than by one order of magnitude.

  5. SUBSURFACE FACILITY WORKER DOES ASSESSMENT

    Energy Technology Data Exchange (ETDEWEB)

    V. Arakali; E. Faillace; A. Linden

    2004-02-27

    The purpose of this design calculation is to estimate radiation doses received by personnel working in the subsurface facility of the repository performing emplacement, maintenance, and retrieval operations under normal conditions. The results of this calculation will be used to support the design of the subsurface facilities and provide occupational dose estimates for the License Application.

  6. Hierarchically macroporous silver monoliths using Pluronic F127: Facile synthesis, characterization and its application as an efficient biomaterial for pathogens

    Directory of Open Access Journals (Sweden)

    Gowhar Ahmad Naikoo

    2016-03-01

    Full Text Available Herein we report the facile synthesis of three dimensional macroporous (MP silver monoliths serving as intelligent biomaterials against Gram negative (Escherichia coli, Salmonella typhimurium and Gram positive (Bacillus subtilis bacteria with more efficacy against Gram negative bacteria. The macroporous silver monoliths were examined by Fourier transform infra red (FTIR spectroscopy, thermogravimetric analysis (TGA, X-ray diffraction (XRD study, field emission scanning electron microscopy (FESEM, energy dispersion X-ray spectroscopy analysis (EDX and Brunauer–Emmet–Teller (BET adsorption technique. From the antibacterial activity results, it was concluded that macroporous silver monoliths can serve as efficient disinfection agents. The enhanced antibacterial properties of macroporous silver monoliths was possibly due to high surface free energy of the surface Ag+ atoms leading to cell membrane damage followed by cell death.

  7. Facilities for the study of behaviour in corrosive atmospheres and their application to thermal and photovoltaic converters

    Science.gov (United States)

    Weisgerber, P.

    The various materials used for flat plate collectors and solar cells and modules for domestic use in Europe are reviewed, together with the available environmental hazards to the devices and test equipment used to verify the long-term behavior of the solar energy conversion systems. The flat plates feature coatings on the absorber surface and a fluid flow to transfer the heat. Solar cells considered consist mainly of Si materials, both polycrystalline and monocrystalline, metallic electrical contacts, and the module material encapsulating the cells. Corrosive effects on the equipment are caused by hot and humid weather, salts in the air, temperature cycling, and acid droplets formed from hydrocarbon-based fuel burning. The AT-1 test facility is described, noting its capability of simulating exposure to cyclic damp heat, SO2, salt mist, and atmospheric ozone.

  8. A facile fabrication of light diffusing film with LDP/polyacrylates composites coating for anti-glare LED application

    Science.gov (United States)

    Song, Shisen; Sun, Yaojie; Lin, Yandan; You, Bo

    2013-05-01

    In this paper, we present a facile coating technique to fabricate the light diffusing film with hemispherical surface convex micro-structure. The coating was prepared by different ratio of light-diffusing particles (LDP)/polyacrylates composites via in situ radical polymerization, with the H2SO4 and vinyl triethoxysilane (A-151) pretreatment made the LDP better dispersed and incorporated with polyacrylate polymer chains. When the mass ratio (LDP/polyacrylate) was 0.5, the film obtained the highest light-diffusing effect and more than 90% transmittance due to the formation of hemispherical surface convex micro-structure. The light diffusing films have excellent anti-glare property if applied to LED light system.

  9. Gamma residual radioactivity measurements on rats and mice irradiated in the thermal column of a TRIGA Mark II reactor for BNCT.

    Science.gov (United States)

    Protti, Nicoletta; Manera, Sergio; Prata, Michele; Alloni, Daniele; Ballarini, Francesca; di Tigliole, Andrea Borio; Bortolussi, Silva; Bruschi, Piero; Cagnazzo, Marcella; Garioni, Maria; Postuma, Ian; Reversi, Luca; Salvini, Andrea; Altieri, Saverio

    2014-12-01

    The current Boron Neutron Capture Therapy (BNCT) experiments performed at the University of Pavia, Italy, are focusing on the in vivo irradiations of small animals (rats and mice) in order to evaluate the effectiveness of BNCT in the treatment of diffused lung tumors. After the irradiation, the animals are manipulated, which requires an evaluation of the residual radioactivity induced by neutron activation and the relative radiological risk assessment to guarantee the radiation protection of the workers. The induced activity in the irradiated animals was measured by high-resolution open geometry gamma spectroscopy and compared with values obtained by Monte Carlo simulation. After an irradiation time of 15 min in a position where the in-air thermal flux is about 1.2 × 10(10) cm(-2) s(-1), the specific activity induced in the body of the animal is mainly due to 24Na, 38Cl, 42K, 56Mn, 27Mg and 49Ca; it is approximately 540 Bq g(-1) in the rat and around 2,050 Bq g(-1) in the mouse. During the irradiation, the animal body (except the lung region) is housed in a 95% enriched 6Li shield; the primary radioisotopes produced inside the shield by the neutron irradiation are 3H by the 6Li capture reaction and 18F by the reaction sequence 6Li(n,α)3H → 16O(t,n)18F. The specific activities of these products are 3.3 kBq g(-1) and 880 Bq g(-1), respectively.

  10. Facile synthesis of Pd-based bimetallic nanocrystals and their application as catalysts for methanol oxidation reaction

    Science.gov (United States)

    Xi, Pinxian; Cao, Yang; Yang, Fengchun; Ma, Cai; Chen, Fengjuan; Yu, Sha; Wang, Shuai; Zeng, Zhengzhi; Zhang, Xin

    2013-06-01

    We employed an efficient and facile route to synthesise monodisperse Pd-based bimetallic nanocrystals (MPd: M = Cu, Co and Ni) via a controlled co-reduction of Pd(ii) chloride and M(ii) nitrate at 200-230 °C in the presence of oleylamine (OAm). These monodisperse Pd-based nanocrystals have small dimensions, unique structures and homogeneous morphology, thus exhibit efficient catalytic activities for methanol oxidation in alkaline solution, which is much better than commercial Pd/C with same amount of palladium. The catalytic activities of these nanocrystals followed the order of NiPd/C > CoPd/C > CuPd/C > commercial Pd/C, due to the different synergistic effects. Our results show that these Pd-based bimetallic nanocrystals can be promising as practical catalysts for methanol oxidation reactions and other catalytic reactions in further investigations.We employed an efficient and facile route to synthesise monodisperse Pd-based bimetallic nanocrystals (MPd: M = Cu, Co and Ni) via a controlled co-reduction of Pd(ii) chloride and M(ii) nitrate at 200-230 °C in the presence of oleylamine (OAm). These monodisperse Pd-based nanocrystals have small dimensions, unique structures and homogeneous morphology, thus exhibit efficient catalytic activities for methanol oxidation in alkaline solution, which is much better than commercial Pd/C with same amount of palladium. The catalytic activities of these nanocrystals followed the order of NiPd/C > CoPd/C > CuPd/C > commercial Pd/C, due to the different synergistic effects. Our results show that these Pd-based bimetallic nanocrystals can be promising as practical catalysts for methanol oxidation reactions and other catalytic reactions in further investigations. Electronic supplementary information (ESI) available. See DOI: 10.1039/c3nr00912b

  11. Application of IOT security and protection in area of nuclear facilities%物联网安防在核设施领域中的应用

    Institute of Scientific and Technical Information of China (English)

    2013-01-01

      介绍了几种先进的物联网技术在核设施安防中的典型应用,包括控制区域防护、周界防护、用RFID技术对核燃料存储和运输的管理、无线传感器网络数据采集、基于ZigBee技术的无线传输等。提出了基于物联网技术的核设施安防实现架构,包括前端实现、通信模式和后端实现等。最后通过分析,论证了物联网技术在核设施安防中的应用有效性和可靠性。%The typical applications of several advanced IOT technology in the security and protection of nuclear facilities are introduced, such as control area protection, perimeter protection, using RFID technology to manage the storage and transportation of the nuclear fuel, the data collection of wireless sensor network, wireless transmission based on ZigBee technology and so on. The implementation architecture of the security and protection of nuclear facilities based on IOT technology is proposed, including the front-end implementation, communication mode and back-end realization etc. Through the analysis, the validity and reliability of the IOT technology applied in the security and protection of nuclear facilities is demonstrated.

  12. Regulatory Facility Guide for Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

    1994-02-28

    This guide provides detailed compilations of international, federal, and state transportation related regulations applicable to shipments originating at or destined to Tennessee facilities. Information on preferred routes is also given.

  13. Application of Heavy Oil in Incineration Facility of Hazardous Waste%重油在危险废物焚烧处理工程中的应用

    Institute of Scientific and Technical Information of China (English)

    张绍坤

    2011-01-01

    在分析重油燃烧特点的基础上,详细说明了危险废物处理项目中应用重油作为燃料的应用要点,并结合工程实例,证明了通过改进设计,重油是能够在危险废物处理中作为燃料应用的,为今后的危险废物焚烧处置项目提供了参考.%On the basis of analyzing the burning characters of heavy oil, the application key points of applying heavy oil as fuel in the incineration facility of hazardous waste were detailed explained. And combined with the case of real project, it was proved that the heavy oil could be used as fuel in the incineration facility of hazardous waste by approved designing. It provided references for future incineration disposal project of hazardous waste.

  14. The PSA Solar Furnace, A Test Facility Ready to Characterize High-ContrationSolar Devices from Solar Thermal Applications to PV Cells

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, J.; Canadas, I.; Fernandez, J.; Monterreal, R.

    2006-07-01

    The PSA solar furnace is mainly devoted to materials science research experiments. This is because, due to the high thermal flux delivered onto their focus, solar furnaces are able to obtain the maximum energy density attainable with solar devices and therefore, are very suitable tools for thermal surface treatment of materials, in which the specimens are subjected to thermal shock or high temperatures. This facility has recently been improved with the installation of new equipment and instrumentation, including a flux measuring system, spectro radiometer, high-pressure cooling system with speed regulation, high-speed circular shutter, a test bed for volumetric and rotating receivers and a new Control and Data Acquisition System. Moreover, replacement of the previous four heliostats by a single, larger one, has improved system performance. This paper presents the new PSA Solar Furnace capabilities with the new instrumentation and control, which broaden the fields of application of this facility, from materials treatments and thermal balance to solar thermal processes i.e. porous receivers with calorimetric calculus or solid waste treatments and concentrating PV cells. (Author)

  15. Heavy oil recovery process: Conceptual engineering of a downhole methanator and preliminary estimate of facilities cost for application to North Slope Alaska

    Energy Technology Data Exchange (ETDEWEB)

    Gondouin, M.

    1991-10-31

    The West Sak (Upper Cretaceous) sands, overlaying the Kuparuk field, would rank among the largest known oil fields in the US, but technical difficulties have so far prevented its commercial exploitation. Steam injection is the most successful and the most commonly-used method of heavy oil recovery, but its application to the West Sak presents major problems. Such difficulties may be overcome by using a novel approach, in which steam is generated downhole in a catalytic Methanator, from Syngas made at the surface from endothermic reactions (Table 1). The Methanator effluent, containing steam and soluble gases resulting from exothermic reactions (Table 1), is cyclically injected into the reservoir by means of a horizontal drainhole while hot produced fluids flow form a second drainhole into a central production tubing. The downhole reactor feed and BFW flow downward to two concentric tubings. The large-diameter casing required to house the downhole reactor assembly is filled above it with Arctic Pack mud, or crude oil, to further reduce heat leaks. A quantitative analysis of this production scheme for the West Sak required a preliminary engineering of the downhole and surface facilities and a tentative forecast of well production rates. The results, based on published information on the West Sak, have been used to estimate the cost of these facilities, per daily barrel of oil produced. A preliminary economic analysis and conclusions are presented together with an outline of future work. Economic and regulatory conditions which would make this approach viable are discussed. 28 figs.

  16. Completion of a large environmental application facility for testing composite materials. Fukugozai kozo shiken[prime]yo ogata kankyo fuyo sochi kansei

    Energy Technology Data Exchange (ETDEWEB)

    1992-06-01

    This paper reports a summary of the large enviromntal application facility to perform strength tests on composite materials under varying temperature environments. The facility features the capability of providing uniform temperature and humidity distributions in an environmental space of 9[times] 5[times]3 m, and covering a wide temperature range from[minus]70[degree]C to 200[degree]C. Since the environmental room temperature of 200[degree] C is not sufficiently high to meet high-temperature structural testing requirement for HOPE, an auxiliary ceramic heater was brought into the environmental room to heat only the required area up to 350[degree] C. A hydraulic actuator including the already introduced high-load loading equipment was installed in a space under the environmental room rack, and loads are induced to an extension rod attached to the load terminal in the actuator. Tests scheduled include a fatigue test on CF/thermoplastic composite filament winding beams for high-altitude unmanned spacecraft under a use temperature of [minus]60[degree]C, which is under preparation at normal temperatures, and a high-temperature strength test on polyimide CFPP structure for HOPE to follow the former test. 5 figs., 1 tab.

  17. LAMPF: a nuclear research facility

    Energy Technology Data Exchange (ETDEWEB)

    Livingston, M.S.

    1977-09-01

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies.

  18. Facile synthesis of urchin-like NiCo2O4 hollow microspheres with enhanced electrochemical properties in energy and environmentally related applications.

    Science.gov (United States)

    Yu, Xin-Yao; Yao, Xian-Zhi; Luo, Tao; Jia, Yong; Liu, Jin-Huai; Huang, Xing-Jiu

    2014-03-12

    A facile synthesis of novel urchin-like NiCo2O4 hierarchical hollow microspheres has been developed based on a template-free solvothermal and subsequent calcination method. The growth process of NiCo2O4 hollow microsphere precursors has been investigated, and a plausible mechanism was proposed. Because of their unique structure and high specific surface area, these NiCo2O4 hollow microspheres displayed enhanced electrochemical properties in methanol electrooxidation and determination of heavy-metal ions compared with solid urchin-like NiCo2O4 microspheres, Co3O4, and NiO microspheres. The good electrochemical performances suggested that these unique hierarchical NiCo2O4 hollow microspheres could be promising materials for energy and environmentally related applications.

  19. Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    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.

  20. Development and application of a multi-channel monitoring system for near real-time VOC measurement in a hazardous waste management facility.

    Science.gov (United States)

    Je, Chung-hwan; Stone, Richard; Oberg, Steven G

    2007-09-01

    This paper describes the development and application of a multi-channel monitoring system for recording, processing, and analyzing volatile organic compound (VOC) levels discharged to the atmosphere from a walk-in hood in a hazardous waste management facility. The monitoring system consists of an array of PID (photo ionization detector) sensors and a networked control program that provides operational schematic diagram, performs data analyses, and illustrates real-time graphical displays. Furthermore, the system records potential worker exposures, exhaust filtration efficiency and environmental release levels. Multi-channel continuous monitoring of VOCs is successfully implemented during chemical bulking operations. It is shown that a real-time monitoring system is effective for early warning detection of hazardous chemicals and for predicting the performance of adsorption filters used for VOC removal. In addition, a connected local weather visualization system supports efforts to minimize potential health and environmental impacts of VOC emissions to surrounding areas.

  1. [Modern problems of the application of sanitary regulations concerning sanitary protection zones and sanitary classification of enterprises, buildings and other facilities].

    Science.gov (United States)

    Lomtev, A Iu; Eremin, G B; Mozzhukhina, N A; Kombarova, M Iu; Mel'tser, A V; Giul'mamedov, É Iu

    2013-01-01

    In this paper there was performed an analysis of the application of sanitary norms and rules concerning sanitary protective zones and sanitary classification of enterprises, buildings and other facilities, including requirements for the sufficiency and accuracy of information in the performance of projects in sanitary protection zone (SPZ). There is presented an analysis of regulations that set requirements for implementation of mapping works in drafting the SPZ. The design of the SPZ was shown to be, on the one hand, the element of territorial planning subjects of the Russian Federation, on the other hand, the object of capital construction. The substantiations of requirements for graphic and text content, structure, and composition of data, sources of their obtaining, methods of data convergence are reported. There are revealed inconsistencies in Sanitary Regulations and Norms (SanPins) and in their relationship with the Town Planning and Land Code and other laws, and regulations adopted in their development.

  2. Facile preparation of highly luminescent CdTe quantum dots within hyperbranched poly(amidoamine)s and their application in bio-imaging.

    Science.gov (United States)

    Shi, Yunfeng; Liu, Lin; Pang, Huan; Zhou, Hongli; Zhang, Guanqing; Ou, Yangyan; Zhang, Xiaoyin; Du, Jimin; Xiao, Wangchuan

    2014-03-13

    A new strategy for facile preparation of highly luminescent CdTe quantum dots (QDs) within amine-terminated hyperbranched poly(amidoamine)s (HPAMAM) was proposed in this paper. CdTe precursors were first prepared by adding NaHTe to aqueous Cd2+ chelated by 3-mercaptopropionic sodium (MPA-Na), and then HPAMAM was introduced to stabilize the CdTe precursors. After microwave irradiation, highly fluorescent and stable CdTe QDs stabilized by MPA-Na and HPAMAM were obtained. The CdTe QDs showed a high quantum yield (QY) up to 58%. By preparing CdTe QDs within HPAMAM, the biocompatibility properties of HPAMAM and the optical, electrical properties of CdTe QDs can be combined, endowing the CdTe QDs with biocompatibility. The resulting CdTe QDs can be directly used in biomedical fields, and their potential application in bio-imaging was investigated.

  3. Facile synthesis of PbWO4: Applications in photoluminescence and photocatalytic degradation of organic dyes under visible light

    Science.gov (United States)

    Saraf, Rohit; Shivakumara, C.; Behera, Sukanti; Nagabhushana, H.; Dhananjaya, N.

    2015-02-01

    Stolzite polymorph of PbWO4 catalyst was prepared by the facile room temperature precipitation method. Structural parameters were refined by the Rietveld analysis using powder X-ray data. PbWO4 was crystallized in the scheelite-type tetragonal structure with space group I41/a (No. 88). Field emission scanning electron microscopy revealed leaf like morphology. Photoluminescence spectra exhibit broad blue emission (425 nm) under the excitation of 356 nm. The photocatalytic degradation of Methylene blue, Rhodamine B and Methyl orange dyes were measured under visible illumination. The 100% dye degradation was observed for MB and RhB dyes within 60 and 105 min. The rate constant was found to be in the decreasing order of MB > RhB > MO which followed the 1st order kinetic mechanism. Therefore, PbWO4 can be a potential candidate for blue component in white LEDs and also acts as a catalyst for the treatment of toxic and non-biodegradable organic pollutants in water.

  4. Fast and facile preparation of CTAB based gels and their applications in Au and Ag nanoparticles synthesis

    Energy Technology Data Exchange (ETDEWEB)

    Upadhyay, Ravi Kant, E-mail: rkupadhyay85@gmail.com [Department of Chemistry, School of Natural Sciences, Shiv Nadar University, Gautam Budh Nagar, 201314 Uttar Pradesh (India); Soin, Navneet, E-mail: n.soin@bolton.ac.uk [Knowledge Centre for Materials Chemistry (KCMC), Institute for Materials Research and Innovation (IMRI), University of Bolton, Deane Road, Bolton BL3 5AB (United Kingdom); Saha, Susmita, E-mail: ssaha@bose.res.in [Department of Condensed Matter Physics and Material Sciences, S. N. Bose National Centre for Basic Sciences, Block JD, Sector III, Salt Lake, Kolkata 700 098 (India); Barman, Anjan, E-mail: abarman@bose.res.in [Department of Condensed Matter Physics and Material Sciences, S. N. Bose National Centre for Basic Sciences, Block JD, Sector III, Salt Lake, Kolkata 700 098 (India); Sinha Roy, Susanta, E-mail: susanta.roy@snu.edu.in [Department of Physics, School of Natural Sciences, Shiv Nadar University, Gautam Budh Nagar, 201314 Uttar Pradesh (India)

    2015-04-15

    We have demonstrated that the gel-like mesophase of Cetyltrimethylammonium bromide (CTAB) can be synthesized by judicial adjustment of water to surfactant molar ratio (W{sub 0}), without using any additional salts, gelating agents or co-surfactants. Gel formation was found to be highly dependent on the water to surfactant molar ratio (W{sub 0}), with the lowest value of W{sub 0} (41.5) resulting in rapid gel formation. Environmental scanning electron microscope (ESEM) analysis revealed that the gel was comprised of interconnected cylindrical structures. The presence of hydrogen bonding in the gel-like mesophase was confirmed by Fourier Transform Infrared spectroscopy (FTIR) analysis. Rheology measurements revealed that all the gel samples were highly viscoelastic in nature. Furthermore, Au and Ag containing CTAB gels were explored as precursors for the preparation of spherical Gold (Au) and Silver (Ag) nanoparticles using Sodium borohydride (NaBH{sub 4}) as reducing agent. The effects of NaBH{sub 4} concentration on the particle size and morphology of the Au and Ag nanoparticles have also been studied. - Highlights: • A facile synthesis of CTAB based gel-like mesophase is reported. • CTAB gels were obtained by adjusting water to surfactant molar ratio (W{sub 0}). • FTIR analysis revealed that hydrogen bonding plays a key role in gel formation. • Au, Ag nanoparticles were synthesized by using CTAB gel and NaBH{sub 4}.

  5. Facile synthesis of PbWO4: applications in photoluminescence and photocatalytic degradation of organic dyes under visible light.

    Science.gov (United States)

    Saraf, Rohit; Shivakumara, C; Behera, Sukanti; Nagabhushana, H; Dhananjaya, N

    2015-02-05

    Stolzite polymorph of PbWO4 catalyst was prepared by the facile room temperature precipitation method. Structural parameters were refined by the Rietveld analysis using powder X-ray data. PbWO4 was crystallized in the scheelite-type tetragonal structure with space group I41/a (No. 88). Field emission scanning electron microscopy revealed leaf like morphology. Photoluminescence spectra exhibit broad blue emission (425 nm) under the excitation of 356 nm. The photocatalytic degradation of Methylene blue, Rhodamine B and Methyl orange dyes were measured under visible illumination. The 100% dye degradation was observed for MB and RhB dyes within 60 and 105 min. The rate constant was found to be in the decreasing order of MB>RhB>MO which followed the 1st order kinetic mechanism. Therefore, PbWO4 can be a potential candidate for blue component in white LEDs and also acts as a catalyst for the treatment of toxic and non-biodegradable organic pollutants in water.

  6. Determining the applicability of the Landauer nanoDot as a general public dosimeter in a research imaging facility.

    Science.gov (United States)

    Charlton, Michael A; Thoreson, Kelly F; Cerecero, Jennifer A

    2012-11-01

    The Research Imaging Institute (RII) building at the University of Texas Health Science Center at San Antonio (UTHSCSA) houses two cyclotron particle accelerators, positron emission tomography (PET) machines, and a fluoroscopic unit. As part of the radiation protection program (RPP) and meeting the standard for achieving ALARA (as low as reasonably achievable), it is essential to minimize the ionizing radiation exposure to the general public through the use of controlled areas and area dose monitoring. Currently, thirty-four whole body Luxel+ dosimeters, manufactured by Landauer, are being used in various locations within the RII to monitor dose to the general public. The intent of this research was to determine if the nanoDot, a single point dosimeter, can be used as a general public dosimeter in a diagnostic facility. This was tested by first verifying characteristics of the nanoDot dosimeter including dose linearity, dose rate dependence, angular dependence, and energy dependence. Then, the response of the nanoDot dosimeter to the Luxel+ dosimeter when placed in a continuous, low dose environment was investigated. Finally, the nanoDot was checked for appropriate response in an acute, high dose environment. Based on the results, the current recommendation is that the nanoDot should not replace the Luxel+ dosimeter without further work to determine the energy spectra in the RII building and without considering the limitation of the microStar reader, portable on-site OSL reader, at doses below 0.1 mGy (10 mrad).

  7. First diffraction topographic results at a third generation synchrotron radiation facility: application to crystals under an electric field

    Energy Technology Data Exchange (ETDEWEB)

    Rejmankova, P. [European Synchrotron Radiation Facility, BP 220, 38043 Grenoble Cedex (France); Baruchel, J. [European Synchrotron Radiation Facility, BP 220, 38043 Grenoble Cedex (France)

    1995-05-01

    Diffraction topographic techniques allow the observation of inhomogeneities (defects, domains,..) within a single crystal. The unique capabilities of third generation synchrotron radiation facilities, like the ESRF, add new possibilities to these techniques: (1) the exposure time to record a topograph can be reduced to similar 10{sup -2} s, i.e. a factor 10{sup 2}-10{sup 3} below the present standards; (2) an improved resolution associated with the small source size, even when setting the film far ( similar 60 cm) from the sample, allows the size of the sample environment devices to be increased; (3) high sensitivity to small ({>=}10{sup -7}) distortions (misorientations and/or lattice parameter variations); (4) investigation of thick or heavy materials, which were up to now the exclusive field of neutron diffraction. We briefly describe the future Topography and High Resolution Diffraction beamline ID 19, which is designed to optimize the required experimental conditions, and which will be operational at the end of 1995. The first topographic white beam experiments which illustrate these new possibilities were carried out on two (ID11 and D5) of the presently operational beamlines of the ESRF. In this work, particular attention is dedicated to observations performed on crystals under an electric field ({alpha}-LiIO{sub 3}, KTP, LiNbO{sub 3}). Very interesting and encouraging results were obtained, particularly when using ``section`` topography. (orig.).

  8. A Study on the Development and Application of Monitoring System for Power Transmission Facilities by using the Optical Sensors

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K.J.; Cho, H.K.; Han, M.S.; Kim, S.K.; Oh, M.T; Park, K.J.; Kim, W.K. [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center; Park, H.K.; Kim, N.; Ban, J.K.; Song, W.Y.; Park, S.K.; Lee, S.Y.; Lee, K.Y.; Lee, Y.H.; Yoon, J.H.; Kim, S.T. [Electrical Engineering and Science Research Center (Korea, Republic of)

    1993-12-31

    Corresponding to extended scope of transmission line maintenance and surveillance system, complex and long transmission line, high capacity and diversutt of monitoring information owing to bulky and high voltage of the system, there have been great demands for new measurement and communication technology on maintenance and monitoring of transmission line facilities. Henceforth in the field of large scale communication system, to overcome shortcomings that former electrical communication has, the introduction of optical communication system is actively being carried out and especially for transmission of power information such as protection, monitoring and control of electric power system operation, optical fiber composite overhead ground wire(OPGW) is increasingly built in the field. Accordingly, from formerly installed optical fibers in OPGW, by utilizing fiber`s low loss, wide bandwidth, high dielectric properties, system information for maintenance, i.e. fault information, weather information, etc. are directly sent to the maintenance department. This promotion in modernization of power transmission line maintenance will set up basis for the realization of effective management, automatic control and remote sensing in maintenance tasks. Eventually, this system can provides various information such as wind velocity and direction, state of aircraft warning lamp and fault current information ground wire etc.. (author). 38 refs., figs.

  9. Facile synthesis of Fe3O4@C hollow nanospheres and their application in polluted water treatment

    Science.gov (United States)

    Zhang, Yuanguang; Xu, Shihao; Xia, Hongyu; Zheng, Fangcai

    2016-11-01

    Nanostructured carbon-based materials, such as carbon nanotube arrays have shown respectable removal ability for heavy metal ions and organic dyes in aqueous solution. Although the carbon-based materials exhibited excellent removal ability, the separation of them from the aqueous solution is difficult and time-consuming. Here we demonstrated a novel and facile route for the large-scale fabrication of Fe3O4@C hollow nanospheres, with using ferrocene as a single reagent and SiO2 as a template. The as-prepared Fe3O4@C hollow nanospheres exhibited adsorption ability for heavy metal ions and organic dyes from aqueous solution, and can be easily separated by an external magnet. When the as-prepared Fe3O4@C hollow nanospheres were mixed with the aqueous solution of Hg2+ within 15 min, the removal efficiency was 90.3%. The as-prepared Fe3O4@C hollow nanospheres were also exhibited a high adsorption capacity (100%) as the adsorbent for methylene blue (MB). In addition, the as-prepared Fe3O4@C hollow nanospheres can be used as the recyclable sorbent for water treatment via a simple magnetic separation.

  10. NEW GUN CAPABILITY WITH INTERCHANGABLE BARRELS TO INVESTIGATE LOW VELOCITY IMPACT REGIMES AT THE LAWRENCE LIVERMORE NATIONAL LABORATORY HIGH EXPLOSIVES APPLICATIONS FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Vandersall, K S; Behn, A; Gresshoff, M; Jr., L F; Chiao, P I

    2009-09-16

    A new gas gun capability is being activated at Lawrence Livermore National Laboratories located in the High Explosives Applications Facility (HEAF). The single stage light gas (dry air, nitrogen, or helium) gun has interchangeable barrels ranging from 25.4 mm to 76.2 mm in diameter with 1.8 meters in length and is being fabricated by Physics Applications, Inc. Because it is being used for safety studies involving explosives, the gun is planned for operation inside a large enclosed firing tank, with typical velocities planned in the range of 10-300 m/s. Three applications planned for this gun include: low velocity impact of detonator or detonator/booster assemblies with various projectile shapes, the Steven Impact test that involves impact initiation of a cased explosive target, and the Taylor impact test using a cylindrical explosive sample impacted onto a rigid anvil for fracture studies of energetic materials. A highlight of the gun features, outline on work in progress for implementing this capability, and discussion of the planned areas of research will be included.

  11. Low-flow active and passive sampling of VOCs using thermal desorption tubes: theory and application at an offset printing facility.

    Science.gov (United States)

    Batterman, Stuart; Metts, Tricia; Kalliokoski, Pentti; Barnett, Emily

    2002-06-01

    While air sampling techniques using adsorbent-based collection, thermal desorption and chromatographic analysis have found a niche in ambient air sampling, occupational applications have been more limited. This paper evaluates the use of thermal desorption techniques for low flow active and passive sampling configurations which allow conveniently long duration sampling in occupational settings and other high concentration environments. The use of an orifice enables flows as low as 0.5 ml min(-1) and sampling periods up to several days without significant biases. A model is used to predict sampling rates of a passive sampler encompassing an orifice, a void space, glass wool, and the adsorbent. Laboratory and field tests conducted at a commercial offset printing facility, which contained a variety of volatile organic compounds (primarily aromatic but also a few chlorinated and terpene compounds at levels from 1 to 67,000 microg m(-3)), are used to evaluate the approach. Tenax GR and Carbosieve SIII, both singly and together, were employed as adsorbents. Side-by-side tests comparing high flow, low flow and passive samplers show excellent agreement and high linearity (r = 0.95) for concentrations spanning nearly five orders of magnitude. Active samplers were tested at flows as low as 0.5 ml min(-1), compared to typical flows up to 40 ml min(-1). Passive samplers demonstrated a linear range and agreement with predictions for adsorbate loadings from approximately 1 ng to nearly 10 microg. Using a chemical mass balance receptor model, concentrations in the facility were apportioned to solvents, inks and other indoor and outdoor sources. Overall, the use of low flow active and passive sampling approaches employing thermal desorption techniques provides good performance and tremendous flexibility that facilitates use in many applications, including workplace settings.

  12. 78 FR 144 - Application for a Presidential Permit To Operate and Maintain Pipeline Facilities on the Border...

    Science.gov (United States)

    2013-01-02

    ... 800,000 bpd of heavy crude. FOR FURTHER INFORMATION CONTACT: Office of Energy Diplomacy, Energy... States and Canada; Enbridge Energy, LP AGENCY: Department of State. ACTION: Notice of Receipt of Enbridge Energy, Limited Partnership Application for a Presidential Permit to Operate and Maintain...

  13. Establishing cause of maternal death in Malawi via facility-based review and application of the ICD-MM classification.

    Science.gov (United States)

    Owolabi, H; Ameh, C A; Bar-Zeev, S; Adaji, S; Kachale, F; van den Broek, N

    2014-09-01

    Maternal death review (MDR) is an accepted process that is implemented across Malawi and 'underlying cause of death' is assigned by healthcare providers using a standard MDR form. Mixed-methods approach. Key informant interviews with eight stakeholders involved in MDR. Secondary analysis of MDR forms for 54 maternal deaths. Comparison of assigned cause of death by healthcare providers conducting MDR at health facility level with cause assigned by researchers using the International Classification of Diseases Maternal Mortality (ICD-MM) classification. MDR teams, analysts and policymakers reported facing challenges in completing the forms, analysing and using information. The concepts of underlying (primary) and contributing (secondary) causes of death are often misunderstood. Healthcare providers using only MDR forms reported cause of death as non-obstetric complications in 39.6% and pregnancy-related infection in 11.3% of cases. For 30.2% of cases, no clear clinical cause of death was recorded. The most commonly assigned underlying cause of death using ICD-MM was obstetric haemorrhage (32.1%), non-obstetric complications (24.5%) and pregnancy-related infection (22.6%). There was poor agreement between cause(s) of maternal death assigned by healthcare providers in the field and trained researchers using the new ICD-MM classification (κ statistic; 0.219). The majority of cases could be reclassified using the ICD-MM and this provided a more specific cause of death. A more structured and user-friendly MDR form is required. Accurate classification of cause of death is important. Dissemination of, and training in the use of the new ICD-MM classification system will be helpful to healthcare providers conducting MDR in Malawi.

  14. On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Kristofova, Kristina; Tatransky, Peter; Zachar, Matej [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2007-03-15

    The presented report is focused on tentative calculations of basic decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by Intermediate storage facility for spent fuel in Studsvik, by means of calculation code OMEGA. This report continuously follows up two previous projects, which described methodology of cost estimates of decommissioning with an emphasis to derive cost functions for alpha contaminated material and implementation of the advanced decommissioning costing methodology for Intermediate Storage facility for Spent Fuel in Studsvik. The main purpose of the presented study is to demonstrate the trial application of the advanced costing methodology using OMEGA code for Intermediate Storage Facility for Spent Fuel in Studsvik. Basic work packages presented in report are as follows: 1. Analysis and validation input data on Intermediate Storage Facility for Spent Fuel and assemble a database suitable for standardised decommissioning cost calculations including radiological parameters, 2. Proposal of range of decommissioning calculations and define an extent of decommissioning activities, 3. Defining waste management scenarios for particular material waste streams from Intermediate Storage Facility for Spent Fuel, 4. Developing standardised cost calculation structure applied for Intermediate Storage Facility for Spent Fuel decommissioning calculation and 5. Performing tentative decommissioning calculations for Intermediate Storage Facility for Spent Fuel by OMEGA code. Calculated parameters of decommissioning are presented in structure according to Proposed Standardized List of Items for Costing Purposes. All parameters are documented and summed up in both table and graphic forms in text and Annexes. The presented report documents availability and applicability of methodology for evaluation of costs and other parameters of decommissioning in a form implemented

  15. 30 CFR 784.30 - Support facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Support facilities. 784.30 Section 784.30... Support facilities. Each applicant for an underground coal mining and reclamation permit shall submit a description, plans, and drawings for each support facility to be constructed, used, or maintained within...

  16. 30 CFR 780.38 - Support facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Support facilities. 780.38 Section 780.38... Support facilities. Each applicant for a surface coal mining and reclamation permit shall submit a description, plans, and drawings for each support facility to be constructed, used, or maintained within...

  17. 14 CFR 142.15 - Facilities.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Facilities. 142.15 Section 142.15... OTHER CERTIFICATED AGENCIES TRAINING CENTERS General § 142.15 Facilities. (a) An applicant for, or..., sanitation, and health codes; and (2) The facilities used for instruction are not routinely subject...

  18. Comparison of silver sorbents for application to radioiodine control at the PUREX process facility modification. [Iodine 129

    Energy Technology Data Exchange (ETDEWEB)

    Scheele, R.D.; Burger, L.L.; Halko, B.T.

    1988-09-01

    In continued support of the design of the gaseous radioiodine control system for the PUREX Process Facility Modification (PFM), the Pacific Northwest Laboratory (PNL) conducted laboratory-scale measurements of the performance of four state-of-the-art sorbents for radioiodine in the dissolver offgas (DOG) of a nuclear reprocessing plant. The PFM is a new head-end treatment plant being designed by Westinghouse Hanford Company (WHC) for the PUREX Plant at the Hanford Site. The experiments performed measured the iodine effluent concentration from Norton silver mordenite (NAgZ), Linde silver mordenite (LAgZ), Linde silver faujasite (AgX), and silver nitrate-impregnated silicic acid (AgNO/sub 3/Si) during simulated normal operating conditions in the PFM after three shutdown/startup cycles, and during standby. At normal operating conditions the input gas is expected to have a dew point of 35/degree/C to 40/degree/C and contain 0.1 ..mu..mol I/L, 1 vol% NO, and 1 vol% NO /sub 2/. The sorbent bed would be at 150/degree/C. A shutdown/startup cycle consisted of eliminating iodine and NO/sub x/ from the input gas, cooling the bed to room temperature, stopping gas flow, and restarting the system. During standby conditions the input gas contained no iodine or NO/sub x/, the dew point was at 30/degree/C to 35/degree/C, and the bed temperature remained at 150/degree/C. This experimental study showed that 20 cm beds of NAgZ, LAgZ, and 18 wt% silver AgX could load up to 0.25 mmol I/g sorbent and routinely reduce the iodine concentration in a simulated PFM DOG from 0.1 ..mu..mol I/L to less than the target level of 10/sup /minus/5/ ..mu..mol I/L. In contrast, the AgNO/sub 3/Si unexpectedly failed to achieve this required level of performance, reducing the concentration on a routine basis only to 10/sup /minus/4/ to 10/sup /minus/2/ ..mu..mol I/L. 5 refs., 14 figs., 6 tabs.

  19. Application of Biogas Slurry in Facility Tomato Cultivation%沼液在设施番茄栽培中的应用

    Institute of Scientific and Technical Information of China (English)

    程永刚; 景小兰; 曹昌林; 段冰; 李爱军; 闫建宾; 侯东辉; 王瑞刚

    2012-01-01

    为了摸清沼液在设施番茄栽培中的应用效果,将沼气池直接建在大棚内,产完沼气后,将沼渣与沼液分离,沼渣作基肥与土壤改良剂,对沼液进行净化、喷施量及浓度、喷施间隔时间试验.结果表明,在设施番茄栽培中,土壤施用沼液肥,能提高土壤肥力、改善土壤结构、提高土壤保水保肥和通气能力;沼液用松籽壳过滤后以60%的浓度,每隔6d叶面喷施一次即可起到防治病虫害的目的;在设施番茄栽培中施用沼液肥,产品符合无公害蔬菜标准,可增产22.5%,增收7.30万元/hm2.%To get application effect of biogas slurry in facility tomato cultivation, methane tank was directly built in greenhouse, and after the methane was produced, biogas residues and biogas slurry was separated, and biogas residues was made to be basic fertilizer and soil amendment, while to biogas slurry, the experiment of purification, spraying quantity, concentration, spraying interval time were carried out. The results showed that, application of biogas slurry manure in soil could improve soil fertility, soil structure, increase capacity of soil retain water and nutrients and aeration. After filtering with the pine nut shell, the biogas slurry concentration of 60%, every 6 day once leaf spraying could play a role to control plant diseases and insect pests. Application of biogas slurry manure in the facility tomato cultivation increased 22.5% of yield of per hm2 and 73 000 ¥ per hm2 income. The production of tomato comply with the standard of pollution-free vegetables.

  20. Highly photoluminescent MoO{sub x} quantum dots: Facile synthesis and application in off-on Pi sensing in lake water samples

    Energy Technology Data Exchange (ETDEWEB)

    Xiao, Sai Jin [Jiangxi Key Laboratory of Mass Spectrometry and Instrumentation, East China University of Technology (ECUT), Nanchang 330013 (China); School of Chemistry, Biology and Material Science, ECUT, Nanchang 330013 (China); Zhao, Xiao Jing; Zuo, Jun [School of Chemistry, Biology and Material Science, ECUT, Nanchang 330013 (China); Huang, Hai Qing [State Key Laboratory Breeding Base of Nuclear Resources and Environment, ECUT, Nanchang 330013 (China); Zhang, Li, E-mail: zhangli8@ncu.edu.cn [College of Chemistry, Nanchang University, Nanchang 330031 (China)

    2016-02-04

    Molybdenum oxide (MoO{sub x}) is a well-studied transition-metal semiconductor material, and has a wider band gap than MoS{sub 2} which makes it become a promising versatile probe in a variety of fields, such as gas sensor, catalysis, energy storage ect. However, few MoO{sub x} nanomaterials possessing photoluminescence have been reported until now, not to mention the application as photoluminescent probes. Herein, a one-pot method is developed for facile synthesis of highly photoluminescent MoO{sub x} quantum dots (MoO{sub x} QDs) in which commercial molybdenum disulfide powder and hydrogen peroxide (H{sub 2}O{sub 2}) are involved as the precursor and oxidant, respectively. Compared with current synthesis methods, the proposed one has the advantages of rapid, one-pot, easily prepared, environment friendly as well as strong photoluminescence. The obtained MoO{sub x} QDs is further utilized as an efficient photoluminescent probe, and a new off-on sensor has been constructed for phosphate (Pi) determination in complicated lake water samples, attributed to the fact that the binding affinity of Eu{sup 3+} ions to the oxygen atoms from Pi is much higher than that from the surface of MoO{sub x} QDs. Under the optimal conditions, a good linear relationship was found between the enhanced photoluminescence intensity and Pi concentration in the range of 0.1–160.0 μM with the detection limit of 56 nM (3σ/k). The first application of the photoluminescent MoO{sub x} nanomaterials for ion photochemical sensing will open the gate of employing MoO{sub x} nanomaterials as versatile probes in a variety of fields, such as chemi-/bio-sensor, cell imaging, biomedical and so on. - Highlights: • Though increasing effort has been devoted to MoO{sub x} nanomaterials synthesis, only a few reports mentioning its photoluminescence property are available, while even no evidence has shown its applications in chemical and biological sensing. • Herein, a one-pot method possessing the

  1. Air Dispersion Modeling for the INL Application for a Synthetic Minor Sitewide Air Quality Permit to Construct with a Facility Emission Cap Component

    Energy Technology Data Exchange (ETDEWEB)

    Sondrup, Andrus Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-10-01

    The Department of Energy Idaho Operations Office (DOE-ID) is applying for a synthetic minor, Sitewide, air quality permit to construct (PTC) with a facility emission cap (FEC) component from the Idaho Department of Environmental Quality (DEQ) for Idaho National Laboratory (INL) to limit its potential to emit to less than major facility limits for criteria air pollutants (CAPs) and hazardous air pollutants (HAPs) regulated under the Clean Air Act. This document is supplied as an appendix to the application, Idaho National Laboratory Application for a Synthetic Minor Sitewide Air Quality Permit to Construct with a Facility Emissions Cap Component, hereafter referred to as “permit application” (DOE-ID 2015). Air dispersion modeling was performed as part of the permit application process to demonstrate pollutant emissions from the INL will not cause a violation of any ambient air quality standards. This report documents the modeling methodology and results for the air dispersion impact analysis. All CAPs regulated under Section 109 of the Clean Air Act were modeled with the exception of lead (Pb) and ozone, which are not required to be modeled by DEQ. Modeling was not performed for toxic air pollutants (TAPs) as uncontrolled emissions did not exceed screening emission levels for carcinogenic and non-carcinogenic TAPs. Modeling for CAPs was performed with the EPA approved AERMOD dispersion modeling system (Version 14134) (EPA 2004a) and five years (2000-2004) of meteorological data. The meteorological data set was produced with the companion AERMET model (Version 14134) (EPA 2004b) using surface data from the Idaho Falls airport, and upper-air data from Boise International Airport supplied by DEQ. Onsite meteorological data from the Grid 3 Mesonet tower located near the center of the INL (north of INTEC) and supplied by the local National Oceanic and Atmospheric Administration (NOAA) office was used for surface wind directions and wind speeds. Surface data (i

  2. Operational Estimation of Accumulated Precipitation using Satellite Observation, by Eumetsat Satellite Application facility in Support to Hydrology (H-SAF Consortium).

    Science.gov (United States)

    di Diodato, A.; de Leonibus, L.; Zauli, F.; Biron, D.; Melfi, D.

    2009-04-01

    Operational Estimation of Accumulated Precipitation using Satellite Observation, by Eumetsat Satellite Application facility in Support to Hydrology (H-SAF Consortium). Cap. Attilio DI DIODATO(*), T.Col. Luigi DE LEONIBUS(*), T.Col Francesco ZAULI(*), Cap. Daniele BIRON(*), Ten. Davide Melfi(*) Satellite Application Facilities (SAFs) are specialised development and processing centres of the EUMETSAT Distributed Ground Segment. SAFs process level 1b data from meteorological satellites (geostationary and polar ones) in conjunction with all other relevant sources of data and appropriate models to generate services and level 2 products. Each SAF is a consortium of EUMETSAT European partners lead by a host institute responsible for the management of the complete SAF project. The Meteorological Service of Italian Air Force is the host Institute for the Satellite Application Facility on Support to Operational Hydrology and Water Management (H-SAF). HSAF has the commitment to develop and to provide, operationally after 2010, products regarding precipitation, soil moisture and snow. HSAF is going to provide information on error structure of its products and validation of the products via their impacts into Hydrological models. To that purpose it has been structured a specific subgroups. Accumulated precipitation is computed by temporal integration of the instantaneous rain rate achieved by the blended LEO/MW and GEO/IR precipitation rate products generated by Rapid Update method available every 15 minutes. The algorithm provides four outputs, consisting in accumulated precipitation in 3, 6, 12 and 24 hours, delivered every 3 hours at the synoptic hours. These outputs are our precipitation background fields. Satellite estimates can cover most of the globe, however, they suffer from errors due to lack of a direct relationship between observation parameters and precipitation, the poor sampling and algorithm imperfections. For this reason the 3 hours accumulated precipitation is

  3. A facile and low-cost length sorting of single-wall carbon nanotubes by precipitation and applications for thin-film transistors.

    Science.gov (United States)

    Gui, Hui; Chen, Haitian; Khripin, Constantine Y; Liu, Bilu; Fagan, Jeffrey A; Zhou, Chongwu; Zheng, Ming

    2016-02-14

    Semiconducting single-wall carbon nanotubes (SWCNTs) with long lengths are highly desirable for many applications such as thin-film transistors and circuits. Previously reported length sorting techniques usually require sophisticated instrumentation and are hard to scale up. In this paper, we report for the first time a general phenomenon of a length-dependent precipitation of surfactant-dispersed carbon nanotubes by polymers, salts, and their combinations. Polyelectrolytes such as polymethacrylate (PMAA) and polystyrene sulfonate (PSS) are found to be especially effective on cholate and deoxycholate dispersed SWCNTs. By adding PMAA to these nanotube dispersions in a stepwise fashion, we have achieved nanotube precipitation in a length-dependent order: first nanotubes with an average length of 650 nm, and then successively of 450 nm, 350 nm, and 250 nm. A similar effect of nanotube length sorting has also been observed for PSS. To demonstrate the utility of the length fractionation, the 650 nm-long nanotube fraction was subjected to an aqueous two-phase separation to obtain semiconducting enriched nanotubes. Thin-film transistors fabricated with the resulting semiconducting SWCNTs showed a carrier mobility up to 18 cm(2) (V s)(-1) and an on/off ratio up to 10(7). Our result sheds new light on the phase behavior of aqueous nanotube dispersions under high concentrations of polymers and salts, and offers a facile, low-cost, and scalable method to produce length sorted semiconducting nanotubes for macroelectronics applications.

  4. Application of core-shell-structured CdTe-SiO{sub 2} quantum dots synthesized via a facile solution method for improving latent fingerprint detection

    Energy Technology Data Exchange (ETDEWEB)

    Gao Feng; Han Jiaxing; Lv Caifeng; Wang Qin; Zhang Jun, E-mail: cejzhang@imu.edu.cn [Inner Mongolia University, College of Chemistry and Chemical Engineering (China); Li Qun; Bao Liru; Li Xin [Division of Science and Technology, Public Security Department of Inner Mongolia (China)

    2012-10-15

    Fingerprint detection is important in criminal investigation. This paper reports a facile powder brushing technique for improving latent fingerprint detection using core-shell-structured CdTe-SiO{sub 2} quantum dots (QDs) as fluorescent labeling marks. Core-shell-structured CdTe-SiO{sub 2} QDs are prepared via a simple solution-based approach using NH{sub 2}NH{sub 2}{center_dot}H{sub 2}O as pH adjustor and stabilizer, and their application for improving latent fingerprint detection is explored. The obtained CdTe-SiO{sub 2} QDs show spherical shapes with well-defined core-shell structures encapsulating different amounts of QDs depending on the type of the pH adjustor and stabilizer. Moreover, the fluorescence of CdTe-SiO{sub 2} QDs is largely enhanced by surface modification of the SiO{sub 2} shell. The CdTe-SiO{sub 2} QDs overcome the oxidation problem of pure CdTe QDs in air, thus affording better variability with strong adhesive ability, better resolution, and bright emission colors for practical application in latent fingerprint detection. In comparison with the conventional fluorescence powders, silver powders, and others, the effectiveness of CdTe-SiO{sub 2} QD powders for detection of latent fingerprints present on a large variety of object surfaces is greatly improved. The synthesis method for CdTe-SiO{sub 2} QDs is simple, cheap, and easy for large-scale production, and thus offers many advantages in the practical application of fingerprint detection.

  5. Conceptual design of a clinical BNCT beam in an adjacent dry cell of the Jozef Stefan Institute TRIGA reactor

    NARCIS (Netherlands)

    Maucec, M

    2000-01-01

    The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation

  6. Novel Nanocomposite of Chitosan-protected Platinum Nanoparticles Immobilized on Nickel Hydroxide: Facile Synthesis and Application as Glucose Electrochemical Sensor

    Indian Academy of Sciences (India)

    DEJIANG RAO; QINGLIN SHENG; JIANBIN ZHENG

    2016-09-01

    Novel nanocomposite of nickel hydroxide/chitosan/platinum was successfully synthesised with chitosan (CS) as a dispersing and protecting agent. Its potential application in non-enzymatic electrochemical glucose sensor was studied. Scanning electron microscopy (SEM), transmission electron microscopy (TEM)and energy-dispersive X-ray spectroscopy (EDX) were used to characterize the composition and morphology of this nanocomposite. The electrochemical investigations of this glucose sensor exhibited remarkable analyticalperformances towards the oxidation of glucose. In particular, glucose can be selectively and sensitively detected in a wide linear range from 3.0×10⁻⁶ to 1.1×10⁻² mol·L⁻¹with a detection limit of 0.56±0.03 μmol·L⁻¹ at a signal-tonoise ratio of 3 (S/N = 3). Furthermore, the Ni(OH)₂/CS/Pt nanocomposite-modified GCE also showed an acceptable anti-interference ability and stability. Importantly, the Ni(OH)₂/CS/Pt based sensor can be used to detect trace amount of glucose in serum samples. The results demonstrated that the Ni(OH)₂/CS/Pt nanocomposite can be potentially useful to construct a new glucose sensing platform.

  7. Pulsed-Plasma Physical Vapor Deposition Approach Toward the Facile Synthesis of Multilayer and Monolayer Graphene for Anticoagulation Applications.

    Science.gov (United States)

    Vijayaraghavan, Rajani K; Gaman, Cezar; Jose, Bincy; McCoy, Anthony P; Cafolla, Tony; McNally, Patrick J; Daniels, Stephen

    2016-02-01

    We demonstrate the growth of multilayer and single-layer graphene on copper foil using bipolar pulsed direct current (DC) magnetron sputtering of a graphite target in pure argon atmosphere. Single-layer graphene (SG) and few-layer graphene (FLG) films are deposited at temperatures ranging from 700 °C to 920 °C within graphene films formed. The films were characterized using atomic force microscopy (AFM), scanning electron microscopy (SEM), high-resolution transmission electron microscopy (HRTEM), Raman spectroscopy, X-ray photoelectron spectroscopy (XPS), and optical transmission spectroscopy techniques. Based on the above studies, a diffusion-controlled mechanism was proposed for the graphene growth. A single-step whole blood assay was used to investigate the anticoagulant activity of graphene surfaces. Platelet adhesion, activation, and morphological changes on the graphene/glass surfaces, compared to bare glass, were analyzed using fluorescence microscopy and SEM techniques. We have found significant suppression of the platelet adhesion, activation, and aggregation on the graphene-covered surfaces, compared to the bare glass, indicating the anticoagulant activity of the deposited graphene films. Our production technique represents an industrially relevant method for the growth of SG and FLG for various applications including the biomedical field.

  8. Cost effective facile synthesis of TiO2 nanograins for flexible DSSC application using rose bengal dye

    Science.gov (United States)

    Jambure, Supriya Bapurao; Gund, Girish Sambhaji; Dubal, Deepak Prakash; Shinde, Sujata Sureshrao; Lokhande, Chandrakant Dnyandev

    2014-09-01

    Synthesis of titanium dioxide (TiO2) nanograins using economical successive ionic layer adsorption and reaction (SILAR) method has been carried out. TiO2 thin films are studied for their structural, compositional, optical and morphological properties. A layer by layer process leads to the formation of 2.4 μm thick nanocrystalline TiO2 film. The heat treated TiO2 thin films are hydrophilic in nature with contact angle of 67°. The interconnected nanograins are employed for dye sensitized solar cells (DSSC) using inexpensive Rose Bengal (RB) dye. RB dye sensitization resulted into shifting of absorption peak from UV to visible region. The photoresponce of the dye sensitized solar cell is evaluated in the polyiodide electrolyte (0.1 M KI + 0.01 M I2) at 40 mWcm-2 illumination intensity. The TiO2 nanograins accompanied with RB sensitizer showed the conversion efficiency ( η) of 0.89%. These results depict the strong assurance of TiO2 nanograins for DSSC application.

  9. Facile and Scale Up Synthesis of Red Phosphorus-Graphitic Carbon Nitride Heterostructures for Energy and Environment Applications

    Science.gov (United States)

    Ansari, Sajid Ali; Ansari, Mohammad Omaish; Cho, Moo Hwan

    2016-06-01

    The development of heterostructured materials for efficient solar energy conversion and energy storage devices are essential for practical applications. In this study, a simple and relatively inexpensive method was used to improve the visible light-driven photocatalytic activity and electrochemical supercapacitor behavior of the graphitic carbon nitride (g-C3N4) by elemental red phosphorus (RPh). The as-prepared RPh-g-C3N4 was characterized in detail using a range of spectroscopic techniques to understand the structure, morphology, chemical interaction, and chemical state of the materials. The visible light-driven photocatalytic activity and supercapacitive electrode performance were assessed by the photodegradation of model colored, non-colored organic pollutants, and electrochemical half-cell measurements, respectively. The RPh-g-C3N4 heterostructure with 30 weight percent of RPh exhibited remarkably high photocatalytic activity for the degradation of pollutants compared to the bare constituent materials, which was further confirmed by the photoelectrochemical study under similar visible photoirradiation conditions. The RPh-g-C3N4 heterostructure supercapacitor electrode displayed a high capacitance of 465 F/g and excellent cyclic stability with capacitance retention of 90% after 1000 cycles at a current of 10 A/g. The superior performance was attributed mainly to the narrow band gap, high surface area, capacitive nature of RPh, and nitrogen-rich skeleton of g-C3N4.

  10. An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    Energy Technology Data Exchange (ETDEWEB)

    Kristofova, Kristina; Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2007-01-15

    The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA.

  11. Facility effluent monitoring plan for the tank farm facility

    Energy Technology Data Exchange (ETDEWEB)

    Crummel, G.M.

    1998-05-18

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

  12. Air Quality Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research FacilityFacilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

  13. Theme: Laboratory Facilities Improvement.

    Science.gov (United States)

    Miller, Glen M.; And Others

    1993-01-01

    Includes "Laboratory Facilities Improvement" (Miller); "Remodeling Laboratories for Agriscience Instruction" (Newman, Johnson); "Planning for Change" (Mulcahy); "Laboratory Facilities Improvement for Technology Transfer" (Harper); "Facilities for Agriscience Instruction" (Agnew et al.); "Laboratory Facility Improvement" (Boren, Dwyer); and…

  14. First application of dynamic infrared imaging in boron neutron capture therapy for cutaneous malignant melanoma

    Energy Technology Data Exchange (ETDEWEB)

    Santa Cruz, G. A.; Gonzalez, S. J.; Bertotti, J.; Marin, J. [Departamento de Instrumentacion y Control, Comision Nacional de Energia Atomica, Avenida del Libertador 8250, 1429 Buenos Aires (Argentina); Departamento de Instrumentacion y Control, Comision Nacional de Energia Atomica, Avenida del Libertador 8250, 1429 Buenos Aires (Argentina) and CONICET, Avenida Rivadavia 1917, 1033 Buenos Aires (Argentina); Universidad Favaloro, Solis 453, 1078 Buenos Aires (Argentina)

    2009-10-15

    Purpose: The purpose of this study is to assess the potential of dynamic infrared imaging (DIRI) as a functional, noninvasive technique for evaluating the skin acute toxicity and tumor control within the framework of the Argentine boron neutron capture therapy (BNCT) program for cutaneous malignant melanoma. Methods: Two patients enrolled in the Argentine phase I/II BNCT clinical trial for cutaneous malignant melanoma were studied with DIRI. An uncooled infrared camera, providing a video output signal, was employed to register the temperature evolution of the normal skin and tumor regions in patients subjected to a mild local cooling (cold stimulus). In order to study the spatial correlation between dose and acute skin reactions, three-dimensional representations of the superficial dose delivered to skin were constructed and cameralike projections of the dose distribution were coregistered with visible and infrared images. Results: The main erythematous reaction was observed clinically between the second and fifth week post-BNCT. Concurrently, with its clinical onset, a reactive increase above the basal skin temperature was observed with DIRI in the third week post-BNCT within regions that received therapeutic doses. Melanoma nodules appeared as highly localized hyperthermic regions. 2 min after stimulus, these regions reached a temperature plateau and increased in size. Temperature differences with respect to normal skin up to 10 deg. C were observed in the larger nodules. Conclusions: Preliminary results suggest that DIRI, enhanced by the application of cold stimuli, may provide useful functional information associated with the metabolism and vasculature of tumors and inflammatory processes related to radiation-induced changes in the skin as well. These capabilities are aimed at complementing the clinical observations and standard imaging techniques, such as CT and Doppler ultrasound.

  15. Low-Temperature Facile Synthesis of Sb-Doped p-Type ZnO Nanodisks and Its Application in Homojunction Light-Emitting Diode.

    Science.gov (United States)

    Baek, Sung-Doo; Biswas, Pranab; Kim, Jong-Woo; Kim, Yun Cheol; Lee, Tae Il; Myoung, Jae-Min

    2016-05-25

    This study explores low-temperature solution-process-based seed-layer-free ZnO p-n homojunction light-emitting diode (LED). In order to obtain p-type ZnO nanodisks (NDs), antimony (Sb) was doped into ZnO by using a facile chemical route at 120 °C. The X-ray photoelectron spectra indicated the presence of (SbZn-2VZn) acceptor complex in the Sb-doped ZnO NDs. Using these NDs as freestanding templates, undoped n-type ZnO nanorods (NRs) were epitaxially grown at 95 °C to form ZnO p-n homojunction. The homojunction with a turn-on voltage of 2.5 V was found to be significantly stable up to 100 s under a constant voltage stress of 5 V. A strong orange-red emission was observed by the naked eye under a forward bias of 5 V. The electroluminescence spectra revealed three major peaks at 400, 612, and 742 nm which were attributed to the transitions from Zni to VBM, from Zni to Oi, and from VO to VBM, respectively. The presence of these deep-level defects was confirmed by the photoluminescence of ZnO NRs. This study paves the way for future applications of ZnO homojunction LEDs using low-temperature and low-cost solution processes with the controlled use of native defects.

  16. Facile synthesis of a MoO2-Mo2C-C composite and its application as favorable anode material for lithium-ion batteries

    Science.gov (United States)

    Zhu, Yanping; Wang, Shaofeng; Zhong, Yijun; Cai, Rui; Li, Li; Shao, Zongping

    2016-03-01

    A composite of MoO2-Mo2C-C is fabricated through a facile ion-exchange route for the first time as an alternative anode material for lithium-ion batteries (LIBs). A macroporous cinnamic anion-exchange resin interacts with ammonium molybdate tetrahydrate in aqueous solution, and the product is then calcined under an inert gas atmosphere. The interaction between the resin and ammonium molybdate tetrahydrate results in an atomic level dispersion of the molybdenum over the organic carbon precursor (resin), while the calcination process allows the formation of MoO2 and Mo2C as well as the pyrolysis of resin to solid carbon. According to field-emission scanning electron microscopy (SEM) and transmission electron microscopy (TEM) measurements, ultrafine MoO2 and Mo2C nanoparticles are uniformly dispersed but firmly attached within an amorphous carbon framework. When evaluated as an anode material, the as-synthesized sample exhibits superior electrochemical performance. The specific discharge capacity is as high as 1491 mA h g-1 in the first cycle and 724 mA h g-1 over 50 cycles at a current density of 0.2 A g-1. This simple, environmentally friendly, low-cost and easily scaled up method, has significant potential for mass industrial production of MoO2-based material as next-generation anode material of LIBs with wide application capability.

  17. A facile and green strategy for preparing newly-designed 3D graphene/gold film and its application in highly efficient electrochemical mercury assay.

    Science.gov (United States)

    Shi, Lei; Wang, Yan; Ding, Shiming; Chu, Zhenyu; Yin, Yu; Jiang, Danfeng; Luo, Jingyi; Jin, Wanqin

    2017-03-15

    In this work, we report a facile and green strategy for in situ and one step preparation of a novel 3D graphene/gold (G/Au) film. Triggering with unique driving force from hydrothermal growth, a 3D interlaced graphene framework with hierarchically porous structures was directly attached on a gold substrate pretreated with a self-assembled monolayer. Simultaneously, highly dispersive Au nanoparticles with tunable morphologies were anchored on the framework utilizing generated graphene as an endogenous reductant. Newly-designed 3D G/Au film possessed excellent properties of significantly large specific area, good electrical conductivity, high structure stability and substrate binding strength, etc. As a paradigm, an electrochemical Hg(2+) biosensor was constructed on 3D G/Au film, in which an exonuclease III-assisted target recycling was introduced. Impressively, an ultralow detection limit of 50 aM (S/N=3), a wide linear range from 0.1 fM to 0.1μM, a high selectivity and a good reliability for Hg(2+) assay in real water and serum samples were realized using prepared biosensor. It is highly envisioned that this work opens the door towards simply fabricating varying types of 3D graphene based hybrid films, and such G/Au film will have widespread applications in electroanalysis and electrocatalysis.

  18. Facile method for synthesis of TiO{sub 2} film and its application in high efficiency dye sensitized-solar cell (DSSC)

    Energy Technology Data Exchange (ETDEWEB)

    Widiyandari, Hendri, E-mail: h.widiyandari@undip.ac.id; Gunawan, S. K.V.; Suseno, Jatmiko Endro [Department of Physics, Diponegoro University, Jl. Prof. H. Soedarto SH, Semarang, Central Java 50275 (Indonesia); Purwanto, Agus [Department of Chemical Engineering, Sebelas Maret University, Jl. Ir. Sutami No. 36 A, Surakarta (Indonesia); Diharjo, Kuncoro [Department of Mechanical Engineering, Sebelas Maret University, Jl. Ir. Sutami No. 36 A, Surakarta (Indonesia)

    2014-02-24

    Dye-sensitized solar cells (DSSC) is a device which converts a solar energy to electrical energy. Different with semiconductor thin film based solar cell, DSSC utilize the sensitized-dye to absorb the photon and semiconductor such as titanium dioxide (TiO{sub 2}) and zinc oxide (ZnO) as a working electrode photoanode. In this report, the preparation of TiO{sub 2} film using a facile method of spray deposition and its application in DSSC have been presented. TiO{sub 2} photoanode was synthesized by growing the droplet of titanium tetraisopropoxide diluted in acid solution on the substrate of conductive glass flourine-doped tin oxide (FTO) with variation of precursor volume. DSSC was assemblied by sandwiching both of photoanode electrode and platinum counter electrode subsequently filling the area between these electrodes with triodine/iodine electrolite solution as redox pairs. The characterization of the as prepared DSSC using solar simulator (AM 1.5G, 100 mW/cm{sup 2}) and I-V source meter Keithley 2400 showed that the performance of DSSC was affected by the precursor volume.. The overall conversion efficiency of DSSC using the optimum TiO{sub 2} film was about 1.97% with the open circuit voltage (V{sub oc}) of 0.73 V, short circuit current density (J{sub sc}) of 4.61 mA and fill factor (FF) of 0.58.

  19. The EarthScope Array Network Facility: application-driven low-latency web-based tools for accessing high-resolution multi-channel waveform data

    Science.gov (United States)

    Newman, R. L.; Lindquist, K. G.; Clemesha, A.; Vernon, F. L.

    2008-12-01

    Since April 2004 the EarthScope USArray seismic network has grown to over 400 broadband stations that stream multi-channel data in near real-time to the Array Network Facility in San Diego. Providing secure, yet open, access to real-time and archived data for a broad range of audiences is best served by a series of platform agnostic low-latency web-based applications. We present a framework of tools that interface between the world wide web and Boulder Real Time Technologies Antelope Environmental Monitoring System data acquisition and archival software. These tools provide audiences ranging from network operators and geoscience researchers, to funding agencies and the general public, with comprehensive information about the experiment. This ranges from network-wide to station-specific metadata, state-of-health metrics, event detection rates, archival data and dynamic report generation over a stations two year life span. Leveraging open source web-site development frameworks for both the server side (Perl, Python and PHP) and client-side (Flickr, Google Maps/Earth and jQuery) facilitates the development of a robust extensible architecture that can be tailored on a per-user basis, with rapid prototyping and development that adheres to web-standards.

  20. Facile Preparation of Poly(lactic acid)/Brushite Bilayer Coating on Biodegradable Magnesium Alloys with Multiple Functionalities for Orthopedic Application.

    Science.gov (United States)

    Zhang, Lei; Pei, Jia; Wang, Haodong; Shi, Yongjuan; Niu, Jialin; Yuan, Feng; Huang, Hua; Zhang, Hua; Yuan, Guangyin

    2017-03-22

    Recently magnesium and its alloys have been proposed as a promising next generation orthopedic implant material, whereas the poor corrosion behavior, potential cytotoxicity, and the lack of efficient drug delivery system have limited its further clinical application, especially for the local treatment of infections or musculoskeletal disorders and diseases. In this study, we designed and developed a multifunctional bilayer composite coating of poly(lactic acid)/brushite with high interfacial bonding strength on a Mg-Nd-Zn-Zr alloy, aiming to improve the biocorrosion resistance and biocompatibility of the magnesium-based substrate, as well as to further incorporate the biofunctionality of localized drug delivery. The composite coating consisted of an inner layer of poly(lactic acid) serving as a drug carrier and an outer layer composed of brushite generated through chemical solution deposition, where a facile pretreatment of UV irradiation was applied to the poly(lactic acid) coating to facilitate the heterogeneous nucleation of brushite. The in vitro degradation results of electrochemical measurements and immersion tests indicated a considerable reduction of magnesium degradation provided the composite coating. A systematic investigation of cellular response with cell viability, adhesion, and ALP assays confirmed the coated Mg alloy induced no toxicity to MC3T3-E1 osteoblastic cells but rather fostered cell attachment and proliferation and promoted osteogenic differentiation, revealing excellent biosafety and biocompatibility and enhanced osteoinductive potential. An in vitro drug release profile of paclitaxel from the composite coating was monitored with UV-vis spectroscopy, showing an alleviated initial burst release and a sustained and controlled release feature of the drug-loaded composite coating. These findings suggested that the bilayer poly(lactic acid)/brushite coating provided effective protection for Mg alloy, greatly enhanced cytocompatibility and

  1. What is the best proton energy for accelerator-based BNCT using the 7Li(p,n)7Be reaction?

    Science.gov (United States)

    Allen, D A; Beynon, T D

    2000-05-01

    With a growing interest in the use of accelerator-based epithermal neutron sources for BNCT programs, in particular those based upon the 7Li(p,n)7Be reaction, there is a need to address the question of "what is the best proton energy to use?" This paper considers this question by using radiation transport calculations to investigate a range of proton energies from 2.15 to 3.5 MeV and a range of moderator sizes. This study has moved away completely from the use of empty therapy beam parameters and instead defines the beam quality and optimizes the moderator design using widely accepted in-phantom treatment planning figures of merit. It is concluded that up to a proton energy of about 2.8 MeV there is no observed variation in the achievable therapy beam quality, but a price is paid in terms of treatment time for not choosing the upper limit of this range. For higher proton energies, the beam quality falls, but with no improvement in treatment time for optimum configurations.

  2. Design and optimization of a beam shaping assembly for BNCT based on D-T neutron generator and dose evaluation using a simulated head phantom.

    Science.gov (United States)

    Rasouli, Fatemeh S; Masoudi, S Farhad

    2012-12-01

    A feasibility study was conducted to design a beam shaping assembly for BNCT based on D-T neutron generator. The optimization of this configuration has been realized in different steps. This proposed system consists of metallic uranium as neutron multiplier, TiF(3) and Al(2)O(3) as moderators, Pb as reflector, Ni as shield and Li-Poly as collimator to guide neutrons toward the patient position. The in-air parameters recommended by IAEA were assessed for this proposed configuration without using any filters which enables us to have a high epithermal neutron flux at the beam port. Also a simulated Snyder head phantom was used to evaluate dose profiles due to the irradiation of designed beam. The dose evaluation results and depth-dose curves show that the neutron beam designed in this work is effective for deep-seated brain tumor treatments even with D-T neutron generator with a neutron yield of 2.4×10(12) n/s. The Monte Carlo Code MCNP-4C is used in order to perform these calculations.

  3. Compact D-D/D-T neutron generators and their applications

    Energy Technology Data Exchange (ETDEWEB)

    Lou, Tak Pui [Univ. of California, Berkeley, CA (United States)

    2003-01-01

    Neutron generators based on the 2H(d,n)3He and 3H(d,n)4He fusion reactions are the most commonly available neutron sources. The applications of current commercial neutron generators are often limited by their low neutron yield and their short operational lifetime. A new generation of D-D/D-T fusion-based neutron generators has been designed at Lawrence Berkeley National Laboratory (LBNL) by using high current ion beams hitting on a self-loading target that has a large surface area to dissipate the heat load. This thesis describes the rationale behind the new designs and their potential applications. A survey of other neutron sources is presented to show their advantages and disadvantages compared to the fusion-based neutron generator. A prototype neutron facility was built at LBNL to test these neutron generators. High current ion beams were extracted from an RF-driven ion source to produce neutrons. With an average deuteron beam current of 24 mA and an energy of 100 keV, a neutron yield of >109 n/s has been obtained with a D-D coaxial neutron source. Several potential applications were investigated by using computer simulations. The computer code used for simulations and the variance reduction techniques employed were discussed. A study was carried out to determine the neutron flux and resolution of a D-T neutron source in thermal neutron scattering applications for condensed matter experiments. An error analysis was performed to validate the scheme used to predict the resolution. With a D-T neutron yield of 1014 n/s, the thermal neutron flux at the sample was predicted to be 7.3 x 105 n/cm2s. It was found that the resolution of cold neutrons was better than that of thermal neutrons when the duty factor is high. This neutron generator could be efficiently used for research and educational purposes at universities. Additional applications studied were positron production and

  4. Compact D-D/D-T neutron generators and their applications

    Energy Technology Data Exchange (ETDEWEB)

    Lou, Tak Pui

    2003-05-01

    Neutron generators based on the {sup 2}H(d,n){sup 3}He and {sup 3}H(d,n){sup 4}He fusion reactions are the most commonly available neutron sources. The applications of current commercial neutron generators are often limited by their low neutron yield and their short operational lifetime. A new generation of D-D/D-T fusion-based neutron generators has been designed at Lawrence Berkeley National Laboratory (LBNL) by using high current ion beams hitting on a self-loading target that has a large surface area to dissipate the heat load. This thesis describes the rationale behind the new designs and their potential applications. A survey of other neutron sources is presented to show their advantages and disadvantages compared to the fusion-based neutron generator. A prototype neutron facility was built at LBNL to test these neutron generators. High current ion beams were extracted from an RF-driven ion source to produce neutrons. With an average deuteron beam current of 24 mA and an energy of 100 keV, a neutron yield of >10{sup 9} n/s has been obtained with a D-D coaxial neutron source. Several potential applications were investigated by using computer simulations. The computer code used for simulations and the variance reduction techniques employed were discussed. A study was carried out to determine the neutron flux and resolution of a D-T neutron source in thermal neutron scattering applications for condensed matter experiments. An error analysis was performed to validate the scheme used to predict the resolution. With a D-T neutron yield of 10{sup 14} n/s, the thermal neutron flux at the sample was predicted to be 7.3 x 10{sup 5} n/cm{sup 2}s. It was found that the resolution of cold neutrons was better than that of thermal neutrons when the duty factor is high. This neutron generator could be efficiently used for research and educational purposes at universities. Additional applications studied were positron production and Boron Neutron Capture Therapy (BNCT). The

  5. A state-of-the-art epithermal neutron irradiation facility for neutron capture therapy

    Science.gov (United States)

    Riley, K. J.; Binns, P. J.; Harling, O. K.

    2004-08-01

    At the Massachusetts Institute of Technology (MIT) the first fission converter-based epithermal neutron beam (FCB) has proven suitable for use in clinical trials of boron neutron capture therapy (BNCT). The modern facility provides a high intensity beam together with low levels of contamination that is ideally suited for use with future, more selective boron delivery agents. Prescriptions for normal tissue tolerance doses consist of 2 or 3 fields lasting less than 10 min each with the currently available beam intensity, that are administered with an automated beam monitoring and control system to help ensure safety of the patient and staff alike. A quality assurance program ensures proper functioning of all instrumentation and safety interlocks as well as constancy of beam output relative to routine calibrations. Beam line shutters and the medical room walls provide sufficient shielding to enable access and use of the facility without affecting other experiments or normal operation of the multipurpose research reactor at MIT. Medical expertise and a large population in the greater Boston area are situated conveniently close to the university, which operates the research reactor 24 h a day for approximately 300 days per year. The operational characteristics of the facility closely match those established for conventional radiotherapy, which together with a near optimum beam performance ensure that the FCB is capable of determining whether the radiobiological promise of NCT can be realized in routine practice.

  6. Assessment of Physical, Chemical, and Hydrologic Factors Affecting the Infiltration of Treated Wastewater in theNew Jersey Coastal Plain, with Emphasis on theHammonton Land Application Facility

    Science.gov (United States)

    Reilly, Timothy J.; Romanok, Kristin M.; Tessler, Steven; Fischer, Jeffrey M.

    2010-01-01

    A hydrogeologic and water-quality investigation of the Hammonton Land Application Facility (Hammonton LAF) in Hammonton, New Jersey, was conducted to determine the factors that impede the infiltration of treated wastewater and to assess the potential for similar conditions to exist elsewhere in the Coastal Plain of New Jersey (particularly within the Pinelands National Reserve). Gamma logs, sediment cores, and hydraulic-profile testing indicate that extensive fine-grained strata and iron-cemented sands underlying the Hammonton LAF may impede infiltration and lead to the perching of diluted treated wastewater. Perched water was observed in augured holes adjacent to infiltration trenches, and analysis of wastewater loading and infiltration data indicates that infiltration trenches may receive lateral flow from multiple perched-water sources. Analysis of water-quality properties characteristic of treated wastewater show that although infiltrated wastewater is reaching the underlying aquifer, lengthy holding times and a long recharge pathway greatly reduce the concentrations of nitrate, boron, and many organic compounds typical of wastewater. Conditions at two currently operating facilities and one potential future facility in the New Jersey Coastal Plain were compared to those at the Hammonton Land Application Facility (LAF). Facilities operating as designed are not underlain by the restrictive strata that exist at the Hammonton LAF. Careful characterization of the geology and hydrology of the unsaturated zone underlying infiltration structures of future facilities in the New Jersey Coastal Plain and similar hydrogeologic settings will help to avoid constructing infiltration structures over or within low-hydraulic-conductivity strata that will decrease infiltration rates.

  7. 设备资产统一目录在设备全生命周期管理中的应用%Application of Facility Asset Unified Catalogues in Facility Life Cycle Management

    Institute of Scientific and Technical Information of China (English)

    李有铖; 黄邵远

    2016-01-01

    As asset intensive enterprises,power grid companies highly dependent on assets.Currently power grid companies manage assets according to the functions of departments.Due to the different focus and targets of different departments,and the lack of communications between different departments,it is hard to establish correspondences among the production facility ledgers,asset cards and actual equipment,making it hard achieve facility life cycle management dynamically and systematically. In this paper a new method is proposed to solve this problem.By building facility assert unified catalogues,the classifications of assets of different departments of China Southern Power Grid can be unified,which will lay a solid foundation for the facility life cycle management of power grid companies.%电力企业作为资产密集型企业,对资产的依赖程度较为突出.目前电力企业普遍采用基于职能的资产分段管理模式,各部门的关注重点与目标不同,欠缺协调沟通,导致设备的生产台账、资产卡片、现场实物无法对应,难以系统、动态地实现设备资产的全生命周期管理.为解决这一问题,提出了通过编制《设备资产统一目录》,以统一南方电网各管理部门对于设备资产的分类,为实现电网设备资产的全生命周期管理奠定坚实基础.

  8. Irradiation facility at the TRIGA Mainz for treatment of liver metastases.

    Science.gov (United States)

    Hampel, G; Wortmann, B; Blaickner, M; Knorr, J; Kratz, J V; Lizón Aguilar, A; Minouchehr, S; Nagels, S; Otto, G; Schmidberger, H; Schütz, C; Vogtländer, L

    2009-07-01

    The TRIGA Mark II reactor at the University of Mainz provides ideal conditions for duplicating BNCT treatment as performed in Pavia, Italy, in 2001 and 2003 [Pinelli, T., Zonta, A., Altieri, S., Barni, S., Braghieri, A., Pedroni, P., Bruschi, P., Chiari, P., Ferrari, C., Fossati, F., Nano, R., Ngnitejeu Tata, S., Prati, U., Ricevuti, G., Roveda, L., Zonta, C., 2002. TAOrMINA: from the first idea to the application to the human liver. In: Sauerwein et al. (Eds.), Research and Development in Neutron Capture Therapy. Proceedings of the 10th International Congress on Neutron Capture Therapy, Monduzzi editore, Bologna, pp. 1065-1072]. In order to determine the optimal parameters for the planned therapy and therefore for the design of the thermal column, calculations were conducted using the MCNP-code and the transport code ATTILA. The results of the parameter study as well as a possible configuration for the irradiation of the liver are presented.

  9. Irradiation facility at the TRIGA Mainz for treatment of liver metastases

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, G. [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz, Fritz-Strassmann-Weg 2, D-55128 Mainz (Germany)], E-mail: gabriele.hample@uni-mainz.de; Wortmann, B. [Evonik Energy Services GmbH Essen, Ruettenscheider Str. 1-3, D-45128 Essen (Germany); Blaickner, M. [Austrian Research Centers, 2444 Seibersdorf (Austria); Knorr, J. [TU Dresden, Institut fuer Energietechnik, D-01062 Dresden (Germany); Kratz, J.V. [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz, Fritz-Strassmann-Weg 2, D-55128 Mainz (Germany); Lizon Aguilar, A. [Evonik Energy Services GmbH Essen, Ruettenscheider Str. 1-3, D-45128 Essen (Germany); Minouchehr, S. [Transplantationschirurgie, Universitaetsklinikum Mainz, D-55131 Mainz (Germany); Nagels, S. [Forschungszentrum Karlsruhe GmbH, Institut fuer Strahlenforschung (ISF), Postfach 3640, D-76021 Karlsruhe (Germany); Otto, G. [Transplantationschirurgie, Universitaetsklinikum Mainz, D-55131 Mainz (Germany); Schmidberger, H. [Klinik und Poliklinik fuer Radioonkologie und Strahlentherapie, Universitaetsklinikum Mainz, D-55131 Mainz (Germany); Schuetz, C.; Vogtlaender, L. [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz, Fritz-Strassmann-Weg 2, D-55128 Mainz (Germany)

    2009-07-15

    The TRIGA Mark II reactor at University of Mainz provides ideal conditions for duplicating BNCT treatment as performed in Pavia, Italy, in 2001 and 2003 [Pinelli, T., Zonta, A., Altieri, S., Barni, S., Braghieri, A., Pedroni, P., Bruschi, P., Chiari, P., Ferrari, C., Fossati, F., Nano, R., Ngnitejeu Tata, S., Prati, U., Ricevuti, G., Roveda, L., Zonta, C., 2002. TAOrMINA: from the first idea to the application to the human liver. In: Sauerwein et al. (Eds.), Research and Development in Neutron Capture Therapy. Proceedings of the 10th International Congress on Neutron Capture Therapy, Monduzzi editore, Bologna, pp. 1065-1072]. In order to determine the optimal parameters for the planned therapy and therefore for the design of the thermal column, calculations were conducted using the MCNP-code and the transport code ATTILA. The results of the parameter study as well as a possible configuration for the irradiation of the liver are presented.

  10. 49 CFR 193.2019 - Mobile and temporary LNG facilities.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Mobile and temporary LNG facilities. 193.2019... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service...

  11. INDICTORS OF RESTORATION OF PROGRAM FACILITY OF MECHATRONICS SYSTEM

    OpenAIRE

    Frolov, V.

    2009-01-01

    The determination of reliability indictors of program facilities of mechatronic systems are offered. The defaillance modes of program facilities are represent. A short review of model reliability of program facility is presented. The indictors of restoration, their mathematical determinations and application for the characteristics of program facility restoration are offered.

  12. INDICTORS OF RESTORATION OF PROGRAM FACILITY OF MECHATRONICS SYSTEM

    Directory of Open Access Journals (Sweden)

    V. Frolov

    2009-01-01

    Full Text Available The determination of reliability indictors of program facilities of mechatronic systems are offered. The defaillance modes of program facilities are represent. A short review of model reliability of program facility is presented. The indictors of restoration, their mathematical determinations and application for the characteristics of program facility restoration are offered.

  13. Facility effluent monitoring plan for the plutonium uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiegand, D.L.

    1994-09-01

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

  14. Eficacia terapéutica y toxicidad de la terapia por captura neutrónica en boro (BNCT) en tejido con cancerización de campo: Estudio radiobiológico en un modelo experimental de cáncer bucal

    OpenAIRE

    Monti Hughes, Andrea

    2012-01-01

    BNCT se basa en la reacción de captura entre el boro depositado preferencialmente en tumor y los neutrones térmicos, generando partículas letales de corto alcance que dañan al tumor, preservando el tejido normal. Previamente, demostramos el éxito terapéutico del BNCT en tumores de la bolsa de la mejilla del hámster. El desafío pendiente era inhibir el desarrollo de segundos tumores primarios (STP) a partir de tejido con cancerización de campo, minimizando la mucositis limitante de dosis. Los ...

  15. Preliminary Design of LEU MNSR for BNCT with Excellent Epithermal Neutron Flux Treatment Beam%高额超热中子束流治疗孔道低浓化BNCT堆初步设计方案

    Institute of Scientific and Technical Information of China (English)

    于涛; 钱金栋; 谢金森

    2012-01-01

    Based on the Miniature Neutron Source Reactor (MNSR) with high enrichment uranium (HEU) fuel and accordance with the requirements of BNCT, the 19.5% of enriched fuel UO2 fuel core for BNCT with epithermal neutron treatment beam was primary designed, the reactor core parameters such as epithermal neutron flux density,epithermal neutron flux unit of fast neutron dose rate,epithermal neutron flux unit photon dose rate of γ,epithermal neutron flux ratio of thermal neutron flux, neutron spectrum were calculated and analyzed. The results show that the design program was an excellent epithermal neutron treatment beam.%根据硼中子俘获治疗( BNCT)中子源的要求,在高浓铀为燃料的微型反应堆(MNSR)的基础上,以富集度19.5%的UO2为燃料,将其堆芯低浓化并且添加水平超热中子束流治疗孔道,开展超热中子束流BNCT堆堆芯低浓化初步设计.计算BNCT堆的超热中子注量率、单位超热中子注量的快中子剂量率、单位超热中子注量的γ光子剂量率、超热中子注量与热中子的注量之比、中子束流能谱等关键参数.结果表明,该设计可以得到优良的超热中子束流.

  16. Computational assessment of deep-seated tumor treatment capability of the 9Be(d,n)10B reaction for accelerator-based boron neutron capture therapy (AB-BNCT).

    Science.gov (United States)

    Capoulat, M E; Minsky, D M; Kreiner, A J

    2014-03-01

    The 9Be(d,n)10B reaction was studied as an epithermal neutron source for brain tumor treatment through Boron Neutron Capture Therapy (BNCT). In BNCT, neutrons are classified according to their energies as thermal (epithermal (from 0.5 eV to 10 keV) or fast (>10 keV). For deep-seated tumors epithermal neutrons are needed. Since a fraction of the neutrons produced by this reaction are quite fast (up to 5-6 MeV, even for low-bombarding energies), an efficient beam shaping design is required. This task was carried out (1) by selecting the combinations of bombarding energy and target thickness that minimize the highest-energy neutron production; and (2) by the appropriate choice of the Beam Shaping Assembly (BSA) geometry, for each of the combinations found in (1). The BSA geometry was determined as the configuration that maximized the dose deliverable to the tumor in a 1 h treatment, within the constraints imposed by the healthy tissue dose adopted tolerance. Doses were calculated through the MCNP code. The highest dose deliverable to the tumor was found for an 8 μm target and a deuteron beam of 1.45 MeV. Tumor weighted doses ≥40 Gy can be delivered up to about 5 cm in depth, with a maximum value of 51 Gy at a depth of about 2 cm. This dose performance can be improved by relaxing the treatment time constraint and splitting the treatment into two 1-h sessions. These good treatment capabilities strengthen the prospects for a potential use of this reaction in BNCT.

  17. Applicability of the two-angle differential method to response measurement of neutron-sensitive devices at the RCNP high-energy neutron facility

    Science.gov (United States)

    Masuda, Akihiko; Matsumoto, Tetsuro; Iwamoto, Yosuke; Hagiwara, Masayuki; Satoh, Daiki; Sato, Tatsuhiko; Iwase, Hiroshi; Yashima, Hiroshi; Nakane, Yoshihiro; Nishiyama, Jun; Shima, Tatsushi; Tamii, Atsushi; Hatanaka, Kichiji; Harano, Hideki; Nakamura, Takashi

    2017-03-01

    Quasi-monoenergetic high-energy neutron fields induced by 7Li(p,n) reactions are used for the response evaluation of neutron-sensitive devices. The quasi-monoenergetic high-energy field consists of high-energy monoenergetic peak neutrons and unwanted continuum neutrons down to the low-energy region. A two-angle differential method has been developed to compensate for the effect of the continuum neutrons in the response measurements. In this study, the two-angle differential method was demonstrated for Bonner sphere detectors, which are typical examples of moderator-based neutron-sensitive detectors, to investigate the method's applicability and its dependence on detector characteristics. Experiments were performed under 96-387 MeV quasi-monoenergetic high-energy neutron fields at the Research Center for Nuclear Physics (RCNP), Osaka University. The measurement results for large high-density polyethylene (HDPE) sphere detectors agreed well with Monte Carlo calculations, which verified the adequacy of the two-angle differential method. By contrast, discrepancies were observed in the results for small HDPE sphere detectors and metal-induced sphere detectors. The former indicated that detectors that are particularly sensitive to low-energy neutrons may be affected by penetrating neutrons owing to the geometrical features of the RCNP facility. The latter discrepancy could be consistently explained by a problem in the evaluated cross-section data for the metals used in the calculation. Through those discussions, the adequacy of the two-angle differential method was experimentally verified, and practical suggestions were made pertaining to this method.

  18. Medical Image Analysis Facility

    Science.gov (United States)

    1978-01-01

    To improve the quality of photos sent to Earth by unmanned spacecraft. NASA's Jet Propulsion Laboratory (JPL) developed a computerized image enhancement process that brings out detail not visible in the basic photo. JPL is now applying this technology to biomedical research in its Medical lrnage Analysis Facility, which employs computer enhancement techniques to analyze x-ray films of internal organs, such as the heart and lung. A major objective is study of the effects of I stress on persons with heart disease. In animal tests, computerized image processing is being used to study coronary artery lesions and the degree to which they reduce arterial blood flow when stress is applied. The photos illustrate the enhancement process. The upper picture is an x-ray photo in which the artery (dotted line) is barely discernible; in the post-enhancement photo at right, the whole artery and the lesions along its wall are clearly visible. The Medical lrnage Analysis Facility offers a faster means of studying the effects of complex coronary lesions in humans, and the research now being conducted on animals is expected to have important application to diagnosis and treatment of human coronary disease. Other uses of the facility's image processing capability include analysis of muscle biopsy and pap smear specimens, and study of the microscopic structure of fibroprotein in the human lung. Working with JPL on experiments are NASA's Ames Research Center, the University of Southern California School of Medicine, and Rancho Los Amigos Hospital, Downey, California.

  19. 33 CFR 127.501 - Applicability.

    Science.gov (United States)

    2010-07-01

    ...) WATERFRONT FACILITIES WATERFRONT FACILITIES HANDLING LIQUEFIED NATURAL GAS AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Natural Gas Personnel Training § 127.501 Applicability. The...

  20. North Slope, Alaska ESI: FACILITY (Facility Points)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...