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Sample records for bnct program volume

  1. 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.

  2. 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.

  3. INEL BNCT Program

    International Nuclear Information System (INIS)

    Ackermann, A.L.; Dorn, R.V. III.

    1991-03-01

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

  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. INEL BNCT Research Program annual report 1994

    International Nuclear Information System (INIS)

    Venhuizen, J.R.

    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

  6. 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.

  7. 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.

  8. INEL BNCT Research Program annual report, 1992

    International Nuclear Information System (INIS)

    Venhuizen, J.R.

    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

  9. INEL BNCT research program: Annual report, 1995

    International Nuclear Information System (INIS)

    Venhuizen, J.R.

    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

  10. 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.

  11. 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.

  12. PBF/BNCT [power burst facility/boron neutron capture therapy] program for cancer treatment

    International Nuclear Information System (INIS)

    Dorn, R.V. III.

    1989-06-01

    Highlights of the PBF/BNCT Program during June include progress within the areas of gross boron analysis in tissue, blood, and urine; analytical methodologies development for BSH (sodium borocaptate) purity determination; boron microscopic (subcellular) analytical development; noninvasive boron quantification determination; dosimetry; and analytical radiation transport and interaction modeling for BNCT

  13. INEL BNCT research program publications, 1993

    International Nuclear Information System (INIS)

    1994-05-01

    This document is a collection of the published reports describing research supporting the Idaho National Engineering Laboratory Boron Neutron Capture Therapy Research Program for calendar year 1993. Contributions from the principal investigators are included, covering 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 (radiation dosimetry software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (tissue and efficacy studies of small and large animal models). These reports have previously appeared in the book: Advances in Neutron Capture Therapy, edited by A. H. Soloway, R. F. Barth, D. E. Carpenter, Plenum Press, 1993. Reports have also appeared in three journals: Angewandte Chemie, Strahlentherapie und Onkologie, and Nuclear Science and Engineering. This individual papers have been indexed separately elsewhere

  14. INEL BNCT Research Program Annual Report 1993

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R.

    1994-08-01

    This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory Boron Neutron Capture Therapy Research Program for calendar year 1993. Contributions from all the principal investigators are included, covering chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, boron drug analysis), physics (radiation dosimetry software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (tissue and efficacy studies of small and large animal models). Information on the potential toxicity of borocaptate sodium and boronophenylalanine is presented. Results of 21 spontaneous-tumor-bearing dogs that have been treated with boron neutron capture therapy at the Brookhaven National Laboratory are updated. Boron-containing drug purity verification is discussed in some detail. Advances in magnetic resonance imaging of boron in vivo are discussed. Several boron-carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Measurement of the epithermal-neutron flux of the Petten (The Netherlands) High Flux Reactor beam (HFB11B), and comparison to predictions are shown.

  15. 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.

  16. 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.

  17. 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.

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

    International Nuclear Information System (INIS)

    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

  19. 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.

  20. 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.

  1. INEL BNCT Research Program, January/February 1993

    International Nuclear Information System (INIS)

    Venhuizen, J.R.

    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

  2. INEL BNCT Research Program, May/June 1992

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    Venhuizen, J.R.

    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 10 B enriched decaborane

  4. The Idaho Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program overview

    International Nuclear Information System (INIS)

    Dorn, R.V. III; Griebenow, M.L.; Ackermann, A.L.; Miller, L.G.; Miller, D.L.; Wheeler, F.J.; Bradshaw, K.M.; Wessol, D.E.; Harker, Y.D.; Nigg, D.W.; Randolph, P.D.; Bauer, W.F.; Gavin, P.R.; Richards, T.L.

    1992-01-01

    The Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program has been funded since 1988 to evaluate brain tumor treatment using Na 2 B 12 H 11 SH (borocaptate sodium or BSH) and epithermal neutrons. The PBF/BNCT Program pursues this goal as a comprehensive, multidisciplinary, multiorganizational endeavor applying modern program management techniques. The initial focus was to: (1) establish a representative large animal model and (2) develop the generic analytical and measurement capabilities require to control treatment repeatability and determine critical treatment parameters independent of tumor type and body location. This paper will identify the PBF/BNCT Program elements and summarize the status of some of the developed capabilities

  5. INEL BNCT Research Program, March/April 1993

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, J.R. [ed.

    1993-06-01

    This report presents summaries for two months of current research of the Idaho National Engineering Laboratory Boron Neutron Capture Therapy 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 and boronophenylalanine are described. Treatment protocol development via the large animal (canine) modal 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.

  6. INEL BNCT Research Program, March/April 1993

    International Nuclear Information System (INIS)

    Venhuizen, J.R.

    1993-06-01

    This report presents summaries for two months of current research of the Idaho National Engineering Laboratory Boron Neutron Capture Therapy 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 and boronophenylalanine are described. Treatment protocol development via the large animal (canine) modal 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

  7. Microwave digestion techniques applied to determination of boron by ICP-AES in BNCT program

    International Nuclear Information System (INIS)

    Farias, Silvia S.; Di Santo, Norberto R.; Garavaglia, Ricardo N.; Pucci, Gladys N.; Batistoni, Daniel A.; Schwint, Amanda E.

    1999-01-01

    Recently, boron neutron capture therapy (BNCT) has merged as an interesting option for the treatment of some kind of tumors where established therapies show no success. A molecular boronated species, enriched in 10 B is administrated to the subject; it localizes in malignant tissues depending the kind of tumor and localization. Therefore, a very important fact in BNCT research is the detection of boron at trace or ultra trace levels precisely and accurately. This is extremely necessary as boronated species do localize in tumoral tissue and also localize in liver, kidney, spleen, skin, membranes. By this way, before testing a boronated species, it is mandatory to determine its biodistribution in a statistically meaning population, that is related with managing of a great number of samples. In the other hand, it is necessary to exactly predict when to begin the irradiation and to determine the magnitude of radiation to obtain the desired radiological dose for a specified mean boron concentration. This involves the determination of boron in whole blood, which is related with boron concentration in the tumor object of treatment. The methodology selected for the analysis of boron in whole blood and tissues must join certain characteristics: it must not be dependant of the chemical form of boron, it has to be fast and capable to determine boron accurately and precisely in a wide range of concentrations. The design and validation of experimental models involving animals in BNCT studies and the determination of boron in blood of animals and subjects upon treatment require reliable analytical procedures to determine boron quantitatively in those biologic materials. Inductively coupled plasma-atomic emission spectrometry (ICP-AES) using pneumatic nebulization is one of the most promising methods for boron analysis, but the sample must be liquid and have low solid concentration. In our case, biological tissues and blood, it is mandatory to mineralize and/or dilute samples

  8. Use of linear programming to obtain an optimum, multi-beam treatment plan in BNCT

    International Nuclear Information System (INIS)

    Nievaart, Sander; Moss, Ray; Sauerwein, Wolfgang; Wittig, Andrea

    2006-01-01

    For BNCT of melanoma metastases in the brain, it has been necessary to calculate the dose distributions in the patient for dozens of possible neutron beams and then to combine manually the different beams by individually weighting and adding them. This time consuming approach eventually gave the required treatment plan, which satisfied the prescription dose. However, by linear optimisation with the Simplex method, the optimum weights for a set of beams can be determined mathematically. The objective function to maximise is the minimum averaged physical boron dose in one certain lesion for every set of beams. The maximisation of this objective function is performed under the constraints of certain maximum and minimum dose limits in the organs at risk and lesions respectively and restricting the set of weighted beams to deliver an average total weighted dose of 7 Gy in the brain. After iteration, by using the constraint set for the minimum dose in the lesions as a variable and performed for all combinations of the neutron beams, the optimum beams and weights are found for each treatment. As a preliminary result, the total irradiation time decreased by more than 30%, which is advantageous regarding both the pharmacokinetics of the boron in the patient and patient comfort. (author)

  9. Present status of accelerator-based BNCT: Focus on developments in Argentina

    International Nuclear Information System (INIS)

    Cartelli, D.; Capoulat, M.E.; Bergueiro, J.; Gagetti, L.; Suárez Anzorena, M.; Grosso, M.F. del; Baldo, M.; Castell, W.; Padulo, J.; Suárez Sandín, J.C.; Igarzabal, M.; Erhardt, J.; Mercuri, D.

    2015-01-01

    In this work we provide some information on the present status of accelerator-based BNCT (AB-BNCT) worldwide and subsequently concentrate on the recent accelerator technology developments in Argentina. - Highlights: • The current status of projects and associated facilities for AB-BNCT worldwide is shown. • Only low (few MeV) energy accelerators are included. • The recent progress of the Argentine AB-BNCT program is described.

  10. Accelerator-based BNCT.

    Science.gov (United States)

    Kreiner, A J; Baldo, M; Bergueiro, J R; Cartelli, D; Castell, W; Thatar Vento, V; Gomez Asoia, J; Mercuri, D; Padulo, J; Suarez Sandin, J C; Erhardt, J; Kesque, J M; Valda, A A; Debray, M E; Somacal, H R; Igarzabal, M; Minsky, D M; Herrera, M S; Capoulat, M E; Gonzalez, S J; del Grosso, M F; Gagetti, L; Suarez Anzorena, M; Gun, M; Carranza, O

    2014-06-01

    The activity in accelerator development for accelerator-based BNCT (AB-BNCT) both worldwide and in Argentina is described. Projects in Russia, UK, Italy, Japan, Israel, and Argentina to develop AB-BNCT around different types of accelerators are briefly presented. In particular, the present status and recent progress of the Argentine project will be reviewed. The topics will cover: intense ion sources, accelerator tubes, transport of intense beams, beam diagnostics, the (9)Be(d,n) reaction as a possible neutron source, Beam Shaping Assemblies (BSA), a treatment room, and treatment planning in realistic cases. © 2013 Elsevier Ltd. All rights reserved.

  11. BNCT-RTPE: BNCT radiation treatment planning environment

    International Nuclear Information System (INIS)

    Wessol, D.E.; Wheeler, F.J.; Babcock, R.S.

    1995-01-01

    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

  12. Microwave digestion techniques applied to determination of boron by ICP-AES in BNCT program; Digestion de matrices biologicas asistida por microondas para el analisis espectrometrico de boro en BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Farias, Silvia S; Di Santo, Norberto R; Garavaglia, Ricardo N; Pucci, Gladys N; Batistoni, Daniel A [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Quimica; Schwint, Amanda E [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Radiobiologia

    1999-07-01

    Recently, boron neutron capture therapy (BNCT) has merged as an interesting option for the treatment of some kind of tumors where established therapies show no success. A molecular boronated species, enriched in {sup 10}B is administrated to the subject; it localizes in malignant tissues depending the kind of tumor and localization. Therefore, a very important fact in BNCT research is the detection of boron at trace or ultra trace levels precisely and accurately. This is extremely necessary as boronated species do localize in tumoral tissue and also localize in liver, kidney, spleen, skin, membranes. By this way, before testing a boronated species, it is mandatory to determine its biodistribution in a statistically meaning population, that is related with managing of a great number of samples. In the other hand, it is necessary to exactly predict when to begin the irradiation and to determine the magnitude of radiation to obtain the desired radiological dose for a specified mean boron concentration. This involves the determination of boron in whole blood, which is related with boron concentration in the tumor object of treatment. The methodology selected for the analysis of boron in whole blood and tissues must join certain characteristics: it must not be dependant of the chemical form of boron, it has to be fast and capable to determine boron accurately and precisely in a wide range of concentrations. The design and validation of experimental models involving animals in BNCT studies and the determination of boron in blood of animals and subjects upon treatment require reliable analytical procedures to determine boron quantitatively in those biologic materials. Inductively coupled plasma-atomic emission spectrometry (ICP-AES) using pneumatic nebulization is one of the most promising methods for boron analysis, but the sample must be liquid and have low solid concentration. In our case, biological tissues and blood, it is mandatory to mineralize and/or dilute

  13. Tandem electrostatic accelerators for BNCT

    International Nuclear Information System (INIS)

    Ma, J.C.

    1994-01-01

    The development of boron neutron capture therapy (BNCT) into a viable therapeutic modality will depend, in part, on the availability of suitable neutron sources compatible with installation in a hospital environment. Low-energy accelerator-based intense neutron sources, using electrostatic or radio frequency quadrupole proton accelerators have been suggested for this purpose and are underdevelopment at several laboratories. New advances in tandem electrostatic accelerator technology now allow acceleration of the multi-milliampere proton beams required to produce therapeutic neutron fluxes for BNCT. The relatively compact size, low weight and high power efficiency of these machines make them particularly attractive for installation in a clinical or research facility. The authors will describe the limitations on ion beam current and available neutron flux from tandem accelerators relative to the requirements for BNCT research and therapy. Preliminary designs and shielding requirements for a tandern accelerator-based BNCT research facility will also be presented

  14. Clinical practice in BNCT to the brain

    International Nuclear Information System (INIS)

    Nakagawa, Y.

    2001-01-01

    Our concept of Boron Neutron Capture Therapy (BNCT) is to selectively destroy tumour cells using the high LET particles yielded from the 10B(n,α)7Li reactions. The effort of clinical investigators has concentrated on how to escalate the radiation dose at the target point. BNCT in Japan combines thermal neutrons and BSH (Na 2 B 12 H 11 SH). The radiation dose is determined by the neutron fluence at the target point and the boron concentration in the tumour tissue. According to the recent analysis, the ratio of boron concentration (BSH) in tumour tissue and blood is nearly stable at around 1.2 to 1.69. Escalation of the radiation dose was carried out by means of improving the penetration of the thermal neutron beam. Since 1968, 175 patients with glioblastoma (n=83), anaplastic astrocytoma (n=44), low grade astrocytoma (n=16) or other types of tumour (n=32) were treated by BNCT at 5 reactors (HTR n=13, JRR-3 n=1, MulTR n=98, KUR n=30, JRR-2 n=33). The retrospective analysis revealed that the important factors related to the clinical results and QOL of the patients were minimum tumour volume radiation dose, more than 18Gy of physical dose and maximum vascular radiation dose (less than 15Gy) in the normal cortex. We have planned several trials to escalate the target radiation dose. One trial makes use of a cavity in the cortex following debulking surgery of the tumour tissue to improve neutron penetration. The other trial is introduction of epithermal neutron. KUR and JRR-4 were reconstructed and developed to be able to irradiate using epithermal neutrons. The new combination of surgical procedure and irradiation using epithermal neutrons should remarkably improve the target volume dose compared to the radiation dose treated by thermal neutrons. (author)

  15. Carborane-containing metalloporphyrins for BNCT

    International Nuclear Information System (INIS)

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

    1996-01-01

    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 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 μg 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

  16. 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.

  17. Long-survivors of glioblatoma treated with boron neutron capture therapy (BNCT)

    International Nuclear Information System (INIS)

    Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, H.

    2011-01-01

    The purpose of this study was to compare the radiation dose between long-survivors and non-long-survivors in patients with glioblatoma (GBM) treated with boron neutron capture therapy (BNCT). Among 23 GBM patients treated with BNCT, there were five patients who survived more than three years after diagnosis. The physical and weighted dose of the minimum gross tumor volume (GTV) of long-survivors was much higher than that of non-long survivors with significant statistical differences.

  18. BNCT of canine osteosarcoma

    International Nuclear Information System (INIS)

    Mitin, V.N.; Kulakov, V.N.; Khokhlov, V.F.

    2006-01-01

    A dog was diagnosed with osteosarcoma (8x6x5cm) in the right wing of ilium by radiography, radionuclide scintigraphy and histological study of biopsy material. The treatment plan was as follows: γ-therapy in combination with chemotherapy; prevention of hematogenous pulmonary metastases by the transfusion of 130 ml of allogenic marrow from a healthy donor; administration of 11.4g 10 B-boronphenylalanine into the right iliac artery; resection of the right iliac wing with the osteosarcoma lesion; neutron irradiation (MEPhI Reactor) of the bone fragment (dose on healthy osteocytes - 15±4 Gy (W), on tumor - 50±9 Gy (W); reimplantation and fixation of the fragment; three courses of adjuvant chemotherapy. The doses were determined in full-scale calculations of the reactor radiation fields with a model of the bone under the code RADUGA. The 10 B concentration (μg/g) in the bone was: normal tissue - 9±3, tumor - 28±5. In 24 hours post operation the dog was able to walk using the treated limb, and 6 months later it moved freely. The patient has been under observation for 30 months. The results of the research demonstrate complete cure. The use of similar treatment plans improves the therapeutic efficiency of BNCT. (author)

  19. Characterisation of the TAPIRO BNCT thermal facility

    Energy Technology Data Exchange (ETDEWEB)

    Rosi, G. [ENEA FIS-ION, CR Casaccia, Via Anguillarese 301, I-00060 Roma (Italy); Gambarini, G.; Colli, V.; Gay, S.; Scolari, L. [Dept. of Physics, Univ. of Milan, INFN, Via Celoria 16, I-20133 Milano (Italy); Fiorani, O.; Perrone, A. [ENEA FIS-ION, CR Casaccia, Via Anguillarese 301, I-00060 Roma (Italy); Nava, E. [ENEA FIS-NUC, Via Martiri di Monte Sole 4, I-40129 Bologna (Italy); Fasolo, F.; Visca, L.; Zanini, A. [INFN, Via Pietro Giuria 1, I-10125 Torino (Italy)

    2004-07-01

    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 cm{sup 3}). 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. (authors)

  20. Abscopal effect of boron neutron capture therapy (BNCT). Proof of principle in an experimental model of colon cancer

    Energy Technology Data Exchange (ETDEWEB)

    Trivillin, Veronica A.; Monti Hughes, Andrea; Schwint, Amanda E. [Comision Nacional de Energia Atomica (CNEA), Department of Radiobiology, B1650KNA San Martin, Provincia Buenos Aires (Argentina); Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET), Ciudad Autonoma de Buenos Aires (Argentina); Pozzi, Emiliano C.C.; Curotto, Paula [Centro Atomico Ezeiza, Comision Nacional de Energia Atomica (CNEA), Department of Research and Production Reactors, Provincia Buenos Aires (Argentina); Colombo, Lucas L. [Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET), Ciudad Autonoma de Buenos Aires (Argentina); Instituto de Oncologia Angel H. Roffo, Ciudad Autonoma de Buenos Aires (Argentina); Thorp, Silvia I.; Farias, Ruben O. [Comision Nacional de Energia Atomica (CNEA), Department of Instrumentation and Control, Provincia Buenos Aires (Argentina); Garabalino, Marcela A. [Comision Nacional de Energia Atomica (CNEA), Department of Radiobiology, B1650KNA San Martin, Provincia Buenos Aires (Argentina); Gonzalez, Sara J. [Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET), Ciudad Autonoma de Buenos Aires (Argentina); Comision Nacional de Energia Atomica (CNEA), Department of Instrumentation and Control, Provincia Buenos Aires (Argentina); Santa Cruz, Gustavo A. [Comision Nacional de Energia Atomica (CNEA), Department of Boron Neutron Capture Therapy, Provincia Buenos Aires (Argentina); Carando, Daniel G. [Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET), Ciudad Autonoma de Buenos Aires (Argentina); Universidad de Buenos Aires, Faculty of Exact and Natural Sciences, Ciudad Autonoma de Buenos Aires (Argentina)

    2017-11-15

    The aim of the present study was to evaluate, for the first time, the abscopal effect of boron neutron capture therapy (BNCT). Twenty-six BDIX rats were inoculated subcutaneously with 1 x 10{sup 6} DHD/K12/TRb syngeneic colon cancer cells in the right hind flank. Three weeks post-inoculation, the right leg of 12 rats bearing the tumor nodule was treated with BPA-BNCT (BPA-Boronophenylalanine) at the RA-3 nuclear reactor located in Buenos Aires, Argentina, at an absorbed dose of 7.5 Gy to skin as the dose-limiting tissue. The remaining group of 14 tumor-bearing rats were left untreated and used as control. Two weeks post-BNCT, 1 x 10{sup 6} DHD/K12/TRb cells were injected subcutaneously in the contralateral left hind flank of each of the 26 BDIX rats. Tumor volume in both legs was measured weekly for 7 weeks to determine response to BNCT in the right leg and to assess a potential influence of BNCT in the right leg on tumor development in the left leg. Within the BNCT group, a statistically significant reduction was observed in contralateral left tumor volume in animals whose right leg tumor responded to BNCT (post-treatment/pre-treatment tumor volume <1) versus animals who failed to respond (post/pre ≥1), i.e., 13 ± 15 vs 271 ± 128 mm{sup 3}. In addition, a statistically significant reduction in contralateral left leg tumor volume was observed in BNCT-responsive animals (post/pre <1) vs untreated animals, i.e., 13 ± 15 vs 254 ± 251 mm{sup 3}. The present study performed in a simple animal model provides proof of principle that the positive response of a tumor to BNCT is capable of inducing an abscopal effect. (orig.)

  1. Abscopal effect of boron neutron capture therapy (BNCT). Proof of principle in an experimental model of colon cancer

    International Nuclear Information System (INIS)

    Trivillin, Veronica A.; Monti Hughes, Andrea; Schwint, Amanda E.; Pozzi, Emiliano C.C.; Curotto, Paula; Colombo, Lucas L.; Thorp, Silvia I.; Farias, Ruben O.; Garabalino, Marcela A.; Gonzalez, Sara J.; Santa Cruz, Gustavo A.; Carando, Daniel G.

    2017-01-01

    The aim of the present study was to evaluate, for the first time, the abscopal effect of boron neutron capture therapy (BNCT). Twenty-six BDIX rats were inoculated subcutaneously with 1 x 10 6 DHD/K12/TRb syngeneic colon cancer cells in the right hind flank. Three weeks post-inoculation, the right leg of 12 rats bearing the tumor nodule was treated with BPA-BNCT (BPA-Boronophenylalanine) at the RA-3 nuclear reactor located in Buenos Aires, Argentina, at an absorbed dose of 7.5 Gy to skin as the dose-limiting tissue. The remaining group of 14 tumor-bearing rats were left untreated and used as control. Two weeks post-BNCT, 1 x 10 6 DHD/K12/TRb cells were injected subcutaneously in the contralateral left hind flank of each of the 26 BDIX rats. Tumor volume in both legs was measured weekly for 7 weeks to determine response to BNCT in the right leg and to assess a potential influence of BNCT in the right leg on tumor development in the left leg. Within the BNCT group, a statistically significant reduction was observed in contralateral left tumor volume in animals whose right leg tumor responded to BNCT (post-treatment/pre-treatment tumor volume <1) versus animals who failed to respond (post/pre ≥1), i.e., 13 ± 15 vs 271 ± 128 mm 3 . In addition, a statistically significant reduction in contralateral left leg tumor volume was observed in BNCT-responsive animals (post/pre <1) vs untreated animals, i.e., 13 ± 15 vs 254 ± 251 mm 3 . The present study performed in a simple animal model provides proof of principle that the positive response of a tumor to BNCT is capable of inducing an abscopal effect. (orig.)

  2. Laser program annual report, 1977. Volume 2

    International Nuclear Information System (INIS)

    Bender, C.F.; Jarman, B.D.

    1978-07-01

    This volume contains detailed information on each of the following sections: (1) fusion target design, (2) target fabrication, (3) laser fusion experiments and analysis, (4) advanced lasers, (5) systems and applications studies, and (6) laser isotope separation program

  3. Laser program annual report, 1977. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Bender, C.F.; Jarman, B.D. (eds.)

    1978-07-01

    This volume contains detailed information on each of the following sections: (1) fusion target design, (2) target fabrication, (3) laser fusion experiments and analysis, (4) advanced lasers, (5) systems and applications studies, and (6) laser isotope separation program. (MOW)

  4. Optimization of the application of BNCT to undifferentiated thyroid cancer

    International Nuclear Information System (INIS)

    Dagrosa, M.A.; Thomasz, L.; Longhino, J.

    2006-01-01

    The possible increase in BNCT efficacy for undifferentiated thyroid carcinoma (UTC) using BPA plus BOPP and nicotinamide (NA) as a radiosensitizer on the BNCT reaction was analyzed. In these studies nude mice were transplanted with the ARO cells and after 14 days they were treated as follows: 1) Control; 2) NCT (neutrons alone); 3) NCT plus NA (100 mg/kg bw/day for 3 days); 4) BPA (350 mg/kg bw) + neutrons; 5) BPA+ NA+ neutrons; 6) BPA+BOPP (60 mg/kg bw) + neutrons. The flux of hyperthermal neutrons was 2.8 10 8 during 85 min. Neutrons alone or with NA caused some tumor growth delay, while in the BPA, BPA+NA and BPA+BOPP groups a 100% halt of tumor growth was observed. When the initial tumor volume was 50 mm 3 or less a complete cure was found in BPA+NA (2/2); BPA (1/4); BPA+BOPP (7/7). After 90 days of complete regression, recurrence of tumor was observed in 2/2 BPA/NA (2/2) and BPA+BOPP (1/7). Caspase 3 activity was increased in BPA+NA (p<0.05 vs controls). BPA plus NA increased tumor apoptosis but only the combination of BPA+BOPP increased significantly BNCT efficiency. (author)

  5. 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...

  6. BNCT with linac, feasibility study

    International Nuclear Information System (INIS)

    Alfuraih, A.; Ma, A.; Spyrou, N.M.; Awotwi-Pratt, Joseph

    2006-01-01

    High energy photon beams from Medical Linear Accelerators (linacs) which are used in radiotherapy produce undesirable neutrons, beside the clinically useful electron and photon beams. Neutrons are produced from the photonuclear reaction (γ,n) of high energy photons with high Z-materials which compose the accelerator head. In this paper the possible use of these undesirable neutrons for BNCT is investigated, making use of high energy linacs already installed in hospitals, primarily for high energy electron and photon therapy and applying them in the context of BNCT. The photoneutron components emitted by the accelerator is the source for Monte Carlo simulations of the interactions that take place within the head of a voxel-based phantom. The neutron flux across the phantom head is calculated using different moderator arrangements and different techniques in the aim of increasing the thermal neutron flux at the targeted site. Also, we shall test different configurations of the linac head to maximize the exposure of high-Z materials to the photon beam, including the removal of the flattening filter, so as to boost the photoneutron production in the linac head. Experimental work will be conducted in hospitals to validate the Monte Carlo simulations. To make use of linacs for BNCT will be advantageous in the sense that the setting in a hospital department is much more acceptable by the public than a reactor installation. This will mean less complications regarding patient positioning and movement with respect to the beams, additional patient transportation and management will be more cost effective. (author)

  7. Implementation of BNCT treatment planning procedures

    International Nuclear Information System (INIS)

    Capala, J.; Ma, R.; Diaz, A.Z.; Chanana, A.D.; Coderre, J.A.

    2001-01-01

    Estimation of radiation doses delivered during boron neutron capture therapy (BNCT) requires combining data on spatial distribution of both the thermal neutron fluence and the 10 B concentration, as well as the relative biological effectiveness of various radiation dose components in the tumor and normal tissues. Using the treatment planning system created at Idaho National Engineering and Environmental Laboratory and the procedures we had developed for clinical trials, we were able to optimize the treatment position, safely deliver the prescribed BNCT doses, and carry out retrospective analyses and reviews. In this paper we describe the BNCT treatment planning process and its implementation in the ongoing dose escalation trials at Brookhaven National Laboratory. (author)

  8. Quality control procedure of the BNCT patient dose determination

    International Nuclear Information System (INIS)

    Bjugg, H.; Kortesniemi, M.; Seppaelae, T.; Karila, J.; Perkioe, J.; Ryynaenen, P.; Savolainen, S.; Auterinen, I.; Kotiluoto, P.; Seren, T.

    2000-01-01

    The concepts used at the Finnish BNCT facility for the patient dose quality assurance are introduced here. Dose planning images are obtained using a MR scanner with MRI sensitive markers. The dose distribution is computed with BNCT Rtpe. The program and the beam (DORT) model used have been verified with measurements and validated with MCNP calculations in phantoms. Dosimetric intercomparison has been done between FiR 1 and BMRR BNCT beams. The FiR 1 beam has been characterised also by visiting teams. Before every patient irradiation the relationship between beam monitor pulse rate and neutron fluence rate in the beam is checked by activation measurements. Cross-hair lasers used in the patient positioning are checked for spatial drift prior to each treatment. Kinetic models used to estimate the time-behaviour of blood boron concentration have been verified using independent patient sample data to assess and verify the performance of the applications. Quality control guides have been developed for each step in the patient irradiation. (author)

  9. Medical setup of intraoperative BNCT at JRR-4

    International Nuclear Information System (INIS)

    Akutsu, H.; Yamamoto, T.; Matsumura, A.

    2000-01-01

    Since October 1999, we have been performing clinical trials of intraoperative boron neutron capture therapy (IOBNCT) using a mixed thermal-epithermal beam at the Japan Research Reactor No. 4 (JRR-4). For immediate pre-BNCT care, including administration of a boron compound as well as post-BNCT care, a collaborating neurosurgical department of the University of Tsukuba was prepared in the vicinity of JRR-4. Following craniotomy in the treatment room, anesthetized patients were transported into the irradiation room for BNCT. The boron concentration in tissue was measured by the PGA and ICP-AES methods. The long-term follow-up was done at the University of Tsukuba Hospital. IOBNCT is a complex clinical procedure, which requires sophisticated operating team and co-medical staffs and also cooperation with physicist team. IOBNCT is a complex clinical procedure requiring a high level of cooperation among the operating team, co-medical staff, and physicists. For the safe and successful performance of IOBNCT, we have made the program including critical pathway and prepared various equipments for IOBNCT. To ensure the safe and successful performance of IOBNCT, we developed a critical pathway for use during the procedure, and prepared various apparatus for IOBNCT. (author)

  10. Accelerator based-boron neutron capture therapy (BNCT)-clinical QA and QC

    International Nuclear Information System (INIS)

    Suzuki, Minoru; Tanaka, Hiroki; Sakurai, Yoshinori; Yong, Liu; Kashino, Genro; Kinashi, Yuko; Masunaga, Shinichiro; Ono, Koji; Maruhashi, Akira

    2009-01-01

    Alpha-particle and recoil Li atom yielded by the reaction ( 10 B, n), due to their high LET properties, efficiently and specifically kill the cancer cell that has incorporated the boron. Efficacy of this boron neutron capture therapy (BNCT) has been demonstrated mainly in the treatment of recurrent head/neck and malignant brain cancers in Kyoto University Research Reactor Institute (KUR). As the clinical trial of BNCT is to start from 2009 based on an accelerator (not on the Reactor), this paper describes the tentative outline of the standard operation procedure of BNCT for its quality assurance (QA) and quality control (QC) along the flow of its clinical practice. Personnel concerned in the practice involve the attending physician, multiple physicians in charge of BNCT, medical physicists, nurses and reactor stuff. The flow order of the actual BNCT is as follows: Pre-therapeutic evaluation mainly including informed consent and confirmation of the prescription; Therapeutic planning including setting of therapy volume, and of irradiation axes followed by meeting for stuffs' agreement, decision of irradiating field in the irradiation room leading to final decision of the axis, CT for the planning, decision of the final therapeutic plan according to Japan Atomic Energy Agency-Computational Dosimetry System (JCDS) and meeting of all related personnel for the final confirmation of therapeutic plan; and BNCT including the transport of patient to KUR, dripping of boronophenylalanine, setting up of the patient on the machine, blood sampling for pharmacokinetics, boron level measurement for decision of irradiating time, switch on/off of the accelerator, confirmation of patient's movement in the irradiated field after the neutron irradiation, blood sampling for confirmation of the boron level, and patient's leave from the room. The QA/QC check is principally to be conducted with the two-person rule. The purpose of the clinical trial is to establish the usefulness of BNCT

  11. International Nuclear Model. Volume 3. Program description

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships

  12. Clinical results of BNCT for malignant meningiomas

    International Nuclear Information System (INIS)

    Miyatake, Shin-ichi; Tamura, Yoji; Kawabata, Shinji

    2006-01-01

    Malignant meningiomas is difficult pathology to be controlled as well as GBM. Since June of 2005, we applied BNCT for 7 cases of malignancy related meningiomas with 13 times neutron irradiation. Five were anaplastic, one was atypical meningiomas and one was sarcoma transformed from meningioma with cervical lymph node metastasis. All cases were introduced after repetitive surgeries and XRT or SRS. Follow-up images were available for 6 cases with observation duration between 2 to 9 months. We applied F-BPA-PET before BNCT in 6 out of 7 cases. One case was received methionine-PET. Five out of 6 cases who received BPA-PET study showed good BPA uptake more than 3 of T/N ratio. One atypical meningiomas cases showed 2.0 of T/N ratio. Original tumor sizes were between 9.2 to 92.7 ml. Two out of 5 anaplastic meningiomas showed CR and all six cases showed radiographic improvements. Clinical symptoms before BNCT such as hemiparesis and facial pain were improved after BNCT, except one case. An huge atypical meningiomas which arisen from tentorium and extended bilateral occipital lobes and brain stem, visual problems were worsened after repetitive BNCT with increase of peritumoral edema. Malignant meningiomas are seemed to be good candidate for BNCT. (author)

  13. Correction volumes and densities in Vitrea Program

    International Nuclear Information System (INIS)

    Abrantes, Marcos E.S.; Oliveira, A.H. de

    2014-01-01

    Introduction: with the increased use of 3D reconstruction techniques to assist in diagnosis, Vitrea® program is widely used. To use this program you need to know the correction values to generate the volumes and number of real CT human tissues. Objective: provide correction values for volumes and number of CT, read the Vitrea program, of the tissues generated by DICOM images from CT. Methodology: this study used a PMMA chest phantom to generate the DICOM images on a scanner. To check the calibration of the scanner was used Catphan phantom and compared the manufacturer of the values associated with its straight linearity. Results: the volume of PMMA phantom was of 11166.58 cm³ and CT number (123.5 ± 33.4) UH. For the volume found in Vitrea program, according to the structures of interest, were 11897.29 cm 3 , 10901.65 cm³, 16906.49 cm 3 and 11848.34 cm³ and corrections values are -6.14%, + 2.43% -6.94% -5.75% respectively for the tissues: lung, bone, soft and full. For the CT numbers found in this program were (97.60 ± 58.9) UH, (72.00 ± 176.00) UH, (143.20 ± 19.50) UH and (31.90 ± 239,10) UH and corrections of + 26.54%, + 71.53%, -13.64% and 387.15% respectively for tissues: lung, bone, soft and full. Conclusion: the procedure performed can be used in other 3D reconstruction programs and where there are tools to reading CT number, observing the necessary corrections

  14. Radiation protection in BNCT patients

    International Nuclear Information System (INIS)

    Blaumann, Hernan R.; Scharnichia, E.; Levanon, I.; Fernandez, C.; Facchini, Guillermo; Longhino, J.; Calzetta, Osvaldo; Pereira, M.

    2008-01-01

    Full text: Boron Neutron Capture Therapy (BNCT) is a technique that selectively targets cancer cells while sparing normal tissues by virtue of the differential uptake of a 10 B carrier compound in tumor. The National Atomic Energy Commission (CNEA) and the Oncology Institute 'Angel H. Roffo' (IOAR) began a BNCT programme in 2003 for treating cutaneous skin melanomas in extremities. The neutron beam used is the hyperthermal one developed at the RA-6 Reactor of the Bariloche Atomic Centre (CAB). The prescribed dose is delivered in one fraction and therefore patient positioning and knowledge of the dose received by normal tissue are crucial. 10 irradiations have been done since 2003, all of them in legs and feet and the dose prescription was determined by the maximum tolerable skin dose. Due to the characteristics of this treatment the patient body might be exposed not only to the primary beam but also to the secondary photon beam produced by neutron capture at the target itself. Thus a patient radiation-monitoring plan was implemented in order to evaluate the gamma dose delivered to sensible organs of each patient. An acrylic water-filled whole body phantom was used for preliminary gamma dose and thermal neutron flux measurements at positions related to patient's body sensible organs considering tentative patient positions. The beam port shielding was, in this way, optimized. TLD-700 and Manganese foils were used for gamma and thermal neutron detection. The TLD-700 thermal neutron response was previously evaluated by using the in-phantom beam dosimetry characterization. In-vivo dosimetry with TLD is routinely implemented in order to evaluate gamma dose to sensible organs of each patient. These organs are chosen depending on its distance from the zone to be irradiated and its radio-sensibility. All TLDs have been positioned well outside the irradiation field. Maximum gamma dose received outside the radiation field in healthy tissues was well below tolerance dose for

  15. 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.

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

    International Nuclear Information System (INIS)

    Subhash, Chandra

    2008-01-01

    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.

  17. International Photovoltaic Program Plan. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

    1979-12-01

    This second volume of a two-part report on the International Photovoltaic Program Plan contains appendices summarizing the results of analyses conducted in preparation of the plan. These analyses include compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about how US government actions could affect this market; international financing issues; and information on issues affecting foreign policy and developing countries.

  18. A new method to evaluate neutron spectra for bnct

    International Nuclear Information System (INIS)

    Martin Hernandez, Guido

    2001-01-01

    This paper deals with the development of a method to evaluate neutron spectra for BNCT. Physical dose deposition calculations for different neutron energies, ranging from thermal to fast, were performed. A matrix, containing dose for each energy and position in the beam center line was obtained. MCNP 4B and Snyder's head model were used. A simple computer code containing the matrix calculates the dose for each point in the beam center line depending on the input energy spectrum to be evaluated. The output of this program is the dose distribution in the brain and the dose gain, that is the ratio between dose to tumor and maximum dose to healthy tissue maximum

  19. Quality management in BNCT at a nuclear research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sauerwein, Wolfgang, E-mail: w.sauerwein@uni-due.de [NCTeam, Department of Radiation Oncology, University Hospital Essen, University Duisburg-Essen, Hufelandstrasse 55, 45122 Essen (Germany); Moss, Raymond [ESE Unit, Institute for Energy, Joint Research Centre, European Commission, Westerduinweg 3, P.O. Box 2 NL-1755ZG Petten (Netherlands); Stecher-Rasmussen, Finn [NCT Physics, Nassaulaan 12, 1815GK Alkmaar (Netherlands); Rassow, Juergen [NCTeam, Department of Radiation Oncology, University Hospital Essen, University Duisburg-Essen, Hufelandstrasse 55, 45122 Essen (Germany); Wittig, Andrea [Department of Radiotherapy and Radiation Oncology, University Hospital Marburg, Philipps-University Marburg, Baldingerstrasse, 35043 Marburg (Germany)

    2011-12-15

    Each medical intervention must be performed respecting Health Protection directives, with special attention to Quality Assurance (QA) and Quality Control (QC). This is the basis of safe and reliable treatments. BNCT must apply QA programs as required for performance and safety in (conventional) radiotherapy facilities, including regular testing of performance characteristics (QC). Furthermore, the well-established Quality Management (QM) system of the nuclear reactor used has to be followed. Organization of these complex QM procedures is offered by the international standard ISO 9001:2008.

  20. 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.

  1. BNCT Technology Development on HANARO Reactor

    International Nuclear Information System (INIS)

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

    2007-06-01

    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

  2. BNCT for malignant brain tumors in children

    International Nuclear Information System (INIS)

    Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, Hiroaki

    2006-01-01

    BSH-based intra-operative BNCT as an initial treatment underwent in 4 children with malignant brain tumors since 1998. There were 2 glioblastomas, one primitive neuroectodermal tumor (PNET) and one anaplastic ependymoma patient. They included two children under 3-year-old. All GBM patients were died of CSF dissemination without tumor regrowth in the primary site. Another PNET and anaplastic ependymoma patients are still alive without tumor recurrence. We can consider BNCT is optimal treatment modality for malignant brain tumor in children. (author)

  3. New EORTC clinical trials for BNCT

    International Nuclear Information System (INIS)

    Hideghety, K.; Moss, R.; Vries, M. de

    2000-01-01

    Due to ethical reasons, a separated optimization of the two components of BNCT in the frame of clinical investigations can only be performed applying the whole binary system. The ongoing trial at HFR (High Flux Reactor Petten) has proven the feasibility of BNCT under defined conditions. On that basis the European Commission supported a comprehensive research project on boron imaging including three further clinical studies. In the first trial the boron uptake related to the blood boron concentration and surrounding normal tissue in various solid tumours will be examined using BSH (Sodiumborocaptate), BPA (Boronophenylalanine) or both in order to explore tumour entities, which may gain benefit from BNCT. The major objectives of the second trial are to define the maximum tolerated single and cumulative dose, and the dose limiting toxicity of BSH. The third clinical trial, a phase II study is designed to evaluate the anti-tumour effect of fractionated BNCT at the Petten treatment facility against cerebral metastasis of malignant melanoma using BPA. (author)

  4. Introducing BNCT treatment in new treatment facilities

    International Nuclear Information System (INIS)

    Gabel, D.

    2001-01-01

    The physical and radiobiological studies that should be performed before the initiation of BNCT are discussed. The need for dose-escalation versus response studies in large animal models is questioned. These studies are time consuming, expensive and legally difficult in some countries and may be dispensable. (author)

  5. Clinical results of boron neutron capture therapy (BNCT) for glioblastoma

    International Nuclear Information System (INIS)

    Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, H.

    2011-01-01

    The purpose of this study was to evaluate the clinical outcome of BSH-based intra-operative BNCT (IO-BNCT) and BSH and BPA-based non-operative BNCT (NO-BNCT). We have treated 23 glioblastoma patients with BNCT without any additional chemotherapy since 1998. The median survival time (MST) of BNCT was 19.5 months, and 2-year, 3-year and 5-year survival rates were 26.1%, 17.4% and 5.8%, respectively. This clinical result of BNCT in patients with GBM is superior to that of single treatment of conventional radiotherapy compared with historical data of conventional treatment. - Highlights: ► In this study, we evaluate the clinical outcome of boron neutron capture therapy (BNCT) for malignant brain tumors. ► We have treated 23 glioblastoma (GBM) patients with BNCT without any additional chemotherapy. ► Clinical results of BNCT in patients with GBM are superior to that of single treatment of conventional radiotherapy compared with historical data of conventional treatment.

  6. Research program plan: piping. Volume 3

    International Nuclear Information System (INIS)

    Vagins, M.; Strosnider, J.

    1985-07-01

    Regulatory issues related to piping can be divided into the three areas of pipe cracking, postulated design basis pipe breaks, and design of piping for seismic and other dynamic loads. The first two of these issues are in the domain of the Materials Engineering Branch (MEBR), while the last of the three issues is the responsibility of the Mechanical/Structural Engineering Branch. This volume of the MEBR Research Plan defines the critical aspects of the pipe cracking and postulated design basis pipe break issues and identifies those research efforts and results necessary for their resolution. In general, the objectives of the MERB Piping Research Program are to provide experimentally validated analytic techniques and appropriate material properties characterization methods and data to support regulatory activities related to evaluating and ensuring piping integrity

  7. Design of a BNCT facility at HANARO

    International Nuclear Information System (INIS)

    Jun, Byung Jin; Lee, Byung Chul

    1998-01-01

    Based on the feasibility study of the BNCT at HANARO, it was confirmed that only thermal BNCT is possible at the IR beam tube if appropriate filtering system be installed. Medical doctors in Korea Cancer Center Hospital agreed that the thermal BNCT facility would be worthwhile for the BNCT technology development in Korea as well as superficial cancer treatment. For the thermal BNCT to be effective, the thermal neutron flux should be high enough for patient treatment during relatively short time and also the fast neutron and gamma-ray fluxes should be as low as possible. In this point of view, the following design requirements are set up: 1) thermal neutron flux at the irradiation position should be higher than 3x10 9 n/cm 2 -sec, 2) ratio of the fast neutrons and gamma-rays to the thermal neutrons should be minimized, and 3) patient treatment should be possible without interrupt to the reactor operation. To minimize the fast neutrons and gamma-rays with the required thermal neutrons at the irradiation position, a radiation filter consisting of single crystals of silicon and bismuth at liquid nitrogen temperature is designed. For the shielding purpose around the irradiation position, polyethylene, lead, LiF, etc., are appropriately arranged around the radiation filter. A water shutter in front of the radiation filter is adopted so as to avoid interrupt to the reactor operation. At present, detail design of the radiation filter is ongoing. Cooling capabilities of the filter will be tested through a mockup experiment. Dose rate distributions around the radiation filter and a prompt gamma-ray activation analysis system for the analyses of boron content in the biological samples are under design. The construction of this facility will be started from next year if it is permitted from the regulatory body this year. Some other future works exist and are described in the paper. (author)

  8. Early phase II study on BNCT in metastatic malignant melanoma using the boron carrier BPA (EORTC protocol 11011)

    International Nuclear Information System (INIS)

    Wittig, Andrea; Sauerwein, Wolfgang; Moss, Raymond

    2006-01-01

    The aim of the trial is to examine the clinical response of metastatic melanoma following BNCT with BPA. The trial contains an optional biodistribution sub-study, which is done if operable metastases are removed prior BNCT. BNCT is applied in 2 fractions at the HFR in Petten. In cases of diffuse brain metastases the whole brain is irradiated homogeneously using 5 irradiation beams from different directions. Up to now 4 patients suffering from multiple brain metastases (more than 20) have been included. In all cases we observed a partial response or no change in the irradiated volume. However, none of the patients survived more than 3 months. The pharmacokinetic of the BPA can be predicted very precisely using a two-compartment model. The treatment can be performed safety. (author)

  9. 'Sequential' Boron Neutron Capture Therapy (BNCT): A Novel Approach to BNCT for the Treatment of Oral Cancer in the Hamster Cheek Pouch Model

    International Nuclear Information System (INIS)

    Molinari, Ana J.; Pozzi, Emiliano C.C.; Hughes, Andrea Monti; Heber, Elisa M.; Garabalino, Marcela A.; Thorp, Silvia I.; Miller, Marcelo; Itoiz, Maria E.; Aromando, Romina F.; Nigg, David W.; Quintana, Jorge; Santa Cruz, Gustavo A.; Trivillin, Veronica A.; Schwint, Amanda E.

    2011-01-01

    In the present study we evaluated the therapeutic effect and/or potential radiotoxicity of the novel 'Tandem' Boron Neutron Capture Therapy (T-BNCT) for the treatment of oral cancer in the hamster cheek pouch model at RA-3 Nuclear Reactor. Two groups of animals were treated with 'Tandem BNCT', i.e. BNCT mediated by boronophenylalanine (BPA) followed by BNCT mediated by sodium decahydrodecaborate (GB-10) either 24 h (T-24h-BNCT) or 48 h (T-48h-BNCT) later. A total tumor dose-matched single application of BNCT mediated by BPA and GB-10 administered jointly ((BPA + GB-10)-BNCT) was administered to an additional group of animals. At 28 days post-treatment, T-24h-BNCT and T-48h-BNCT induced, respectively, overall tumor control (OTC) of 95% and 91%, with no statistically significant differences between protocols. Tumor response for the single application of (BPA + GB-10)-BNCT was 75%, significantly lower than for T-BNCT. The T-BNCT protocols and (BPA + GB-10)-BNCT induced reversible mucositis in dose-limiting precancerous tissue around treated tumors, reaching Grade 3/4 mucositis in 47% and 60% of the animals respectively. No normal tissue radiotoxicity was associated to tumor control for any of the protocols. 'Tandem' BNCT enhances tumor control in oral cancer and reduces or, at worst, does not increase, mucositis in dose-limiting precancerous tissue.

  10. An Accelerator Neutron Source for BNCT

    International Nuclear Information System (INIS)

    Blue, Thomas E.

    2006-01-01

    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 technologically 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

  11. 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.

  12. Characterisation of the TAPIRO BNCT epithermal facility

    Energy Technology Data Exchange (ETDEWEB)

    Burn, K. W. [FIS-NUC, ENEA, Via Martiri di Montesole 4, Bologna (Italy); Colli, V. [Dept. of Physics of Univ., INFN, Via Celoria 16, I-20133 Milano (Italy); Curzio, G.; D' Errico, F. [DIMNP, Univ. of Pisa, Via Diotisalvi 2, I-56126 Pisa (Italy); Gambarini, G. [Dept. of Physics of Univ., INFN, Via Celoria 16, I-20133 Milano (Italy); Rosi, G. [FIS-ION, ENEA, Casaccia, Via Anguillarese 301, I-00060 Santa Maria di Galeria, Roma (Italy); Scolari, L. [Dept. of Physics of Univ., INFN, Via Celoria 16, I-20133 Milano (Italy)

    2004-07-01

    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. (authors)

  13. Present status of Accelerator-Based BNCT.

    Science.gov (United States)

    Kreiner, Andres Juan; Bergueiro, Javier; Cartelli, Daniel; Baldo, Matias; Castell, Walter; Asoia, Javier Gomez; Padulo, Javier; Suárez Sandín, Juan Carlos; Igarzabal, Marcelo; Erhardt, Julian; Mercuri, Daniel; Valda, Alejandro A; Minsky, Daniel M; Debray, Mario E; Somacal, Hector R; Capoulat, María Eugenia; Herrera, María S; Del Grosso, Mariela F; Gagetti, Leonardo; Anzorena, Manuel Suarez; Canepa, Nicolas; Real, Nicolas; Gun, Marcelo; Tacca, Hernán

    2016-01-01

    This work aims at giving an updated report of the worldwide status of Accelerator-Based BNCT (AB-BNCT). There is a generalized perception that the availability of accelerators installed in hospitals, as neutron sources, may be crucial for the advancement of BNCT. Accordingly, in recent years a significant effort has started to develop such machines. A variety of possible charged-particle induced nuclear reactions and the characteristics of the resulting neutron spectra are discussed along with the worldwide activity in suitable accelerator development. Endothermic (7)Li(p,n)(7)Be and (9)Be(p,n)(9)B and exothermic (9)Be(d,n)(10)B are compared. In addition to having much better thermo-mechanical properties than Li, Be as a target leads to stable products. This is a significant advantage for a hospital-based facility. (9)Be(p,n)(9)B needs at least 4-5 MeV bombarding energy to have a sufficient yield, while (9)Be(d,n)(10)B can be utilized at about 1.4 MeV, implying the smallest possible accelerator. This reaction operating with a thin target can produce a sufficiently soft spectrum to be viable for AB-BNCT. The machines considered are electrostatic single ended or tandem accelerators or radiofrequency quadrupoles plus drift tube Linacs. (7)Li(p,n)(7)Be provides one of the best solutions for the production of epithermal neutron beams for deep-seated tumors. However, a Li-based target poses significant technological challenges. Hence, Be has been considered as an alternative target, both in combination with (p,n) and (d,n) reactions. (9)Be(d,n)(10)B at 1.4 MeV, with a thin target has been shown to be a realistic option for the treatment of deep-seated lesions.

  14. Retrospective review of the clinical BNCT trial at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Diaz, A.Z.; Chanana, A.D.; Coderre, J.A.; Ma, R.

    2000-01-01

    The primary objective of the phase I/II dose escalation studies was to evaluate the safety of the boronophenylalanine-fructose (BPA-F) mediated boron neutron capture therapy (BNCT) in subjects with glioblastoma multiforme (GBM). A secondary objective was to retrospectively assess the palliation of GBM by BNCT. Fifty-three subjects with GBM were treated under multiple dose escalation protocols at the Brookhaven Medical Research Reactor (BMRR). Twenty-six subjects were treated using one field, 17 subjects were treated using 2 fields and 10 subjects were treated using 3 fields. BPA-F related toxicity was not observed. The maximum radiation dose to a volume of approximately 1 cc of the normal brain varied from 8.9 to 15.9 gray-equivalent (Gy-Eq). The volume-weighted average radiation dose to normal brain varied from 1.9 to 9.5 Gy-Eq. Six RTOG (Radiation Therapy Oncology Group) grade 3 or 4 toxicities were attributed to BNCT. Four of the 53 subjects are still alive with 3 of them free of recurrent disease with over two years follow-up. The median times to progression and median survival time from diagnosis were 28.4 weeks and 12.8 months respectively. (author)

  15. OPTIMIZATION OF A NEUTRON BEAM SHAPING ASSEMBLY DESIGN FOR BNCT AND ITS DOSIMETRY SIMULATION BASED ON MCNPX

    Directory of Open Access Journals (Sweden)

    I Made Ardana

    2017-10-01

    OPTIMASI DESAIN KOLIMATOR NEUTRON UNTUK SISTEM BNCT DAN UJI DOSIMETRINYA MENGGUNAKAN PROGRAM MCNPX. Telah dilakukan penelitian tentang sistem BNCT yang meliputi dua tahapan simulasi dengan menggunakan program MCNPX yaitu uji simulasi untuk optimasi desain kolimator neutron untuk sistem BNCT berbasis Siklotron 30 MeV dan uji simulasi untuk menghitung fluks neutron dan dosimetri radiasi pada kanker sarkoma jaringan lunak pada leher dan kepala. Tujuan simulasi untuk mendapatkan desain kolimator yang paling optimal dalam memoderasi fluks neutron cepat yang dihasilkan dari sistem target berilium sehingga dapat dihasilkan fluks neutron yang sesuai untuk sistem BNCT. Uji optimasi dilakukan dengan cara memvariasikan bahan dan ketebalan masing-masing komponen dalam kolimator seperi reflektor, moderator, filter neutron cepat, filter neutron thermal, filter radiasi gamma dan lubang keluaran. Desain kolimator yang diperoleh dari hasil optimasi tersusun atas moderator berbahan Al dengan ketebalan 39 cm, filter neutron cepat berbahan LiF2 setebal 8,2 cm, dan filter neutron thermal berbahan B4C setebal 0,5 cm. Untuk reflektor, filter radiasi gamma dan lubang keluaran masing-masing menggunakan bahan PbF2, Pb dan Bi. Fluks neutron epithermal yang dihasilkan dari kolimator yang didesain adalah sebesar 2,83 x 109 n/s cm-2 dan telah memenuhi seluruh parameter fluks neutron yang sesuai untuk sistem BNCT. Selanjutnya uji simulasi dosimetri pada kanker sarkoma jaringan lunak pada leher dan kepala dilakukan dengan cara memvariasikan konsentrasi senyawa boron pada model phantom leher manusia (ORNL. Selanjutnya model phantom tersebut diiradiasi dengan fluks neutron yang berasal dari kolimator yang telah didesain sebelumnya. Hasilnya, fluks neutron thermal mencapai nilai tertinggi pada kedalaman 4,8 cm di dalam model phantom leher ORNL dengan laju dosis tertinggi terletak pada area jaringan kanker. Untuk masing-masing variasi konsentrasi senyawa boron pada model phantom leher ORNL supaya

  16. Highway Safety Program Manual: Volume 3: Motorcycle Safety.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…

  17. Synthesis and in-vivo detection of boronated compounds for use in BNCT

    International Nuclear Information System (INIS)

    Kabalka, G.W.

    1990-04-01

    The primary objective of the DOE Program at the University of Tennessee Biomedical Imaging Center is the development of new technology to detect boron compounds in-vivo. The research focuses on the development of multinuclear magnetic resonance imaging (MRI) and spectroscopy (MRS) techniques for verifying and measuring BNCT agents in-vivo. A small but significant portion of the effort is directed toward the design of boron-containing neutron-capture-therapy agents. The UT -- DOE program is unique in that it has access to two state-of-the-art multinuclear magnetic resonance imaging units housed in the Biomedical Imaging Center at the University of Tennessee Medical Center at Knoxville. Included in this report are two sections describing research accomplishments in multinuclear magnetic resonance imaging and synthesis of potential BNCT agents

  18. CIRMIS Data system. Volume 2. Program listings

    International Nuclear Information System (INIS)

    Friedrichs, D.R.

    1980-01-01

    The Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program is developing and applying the methodology for assessing the far-field, long-term post-closure safety of deep geologic nuclear waste repositories. AEGIS is being performed by Pacific Northwest Laboratory (PNL) under contract with the Office of Nuclear Waste Isolation (OWNI) for the Department of Energy (DOE). One task within AEGIS is the development of methodology for analysis of the consequences (water pathway) from loss of repository containment as defined by various release scenarios. Analysis of the long-term, far-field consequences of release scenarios requires the application of numerical codes which simulate the hydrologic systems, model the transport of released radionuclides through the hydrologic systems, model the transport of released radionuclides through the hydrologic systems to the biosphere, and, where applicable, assess the radiological dose to humans. The various input parameters required in the analysis are compiled in data systems. The data are organized and prepared by various input subroutines for utilization by the hydraulic and transport codes. The hydrologic models simulate the groundwater flow systems and provide water flow directions, rates, and velocities as inputs to the transport models. Outputs from the transport models are basically graphs of radionuclide concentration in the groundwater plotted against time. After dilution in the receiving surface-water body (e.g., lake, river, bay), these data are the input source terms for the dose models, if dose assessments are required.The dose models calculate radiation dose to individuals and populations. CIRMIS (Comprehensive Information Retrieval and Model Input Sequence) Data System is a storage and retrieval system for model input and output data, including graphical interpretation and display. This is the second of four volumes of the description of the CIRMIS Data System

  19. “Sequential” Boron Neutron Capture Therapy (BNCT): A Novel Approach to BNCT for the Treatment of Oral Cancer in the Hamster Cheek Pouch Model

    Energy Technology Data Exchange (ETDEWEB)

    Ana J. Molinari; Emiliano C. C. Pozzi; Andrea Monti Hughes; Elisa M. Heber; Marcela A. Garabalino; Silvia I. Thorp; Marcelo Miller; Maria E. Itoiz; Romina F. Aromando; David W. Nigg; Jorge Quintana; Gustavo A. Santa Cruz; Veronica A. Trivillin; Amanda E. Schwint

    2011-04-01

    In the present study we evaluated the therapeutic effect and/or potential radiotoxicity of the novel “Tandem” Boron Neutron Capture Therapy (T-BNCT) for the treatment of oral cancer in the hamster cheek pouch model at RA-3 Nuclear Reactor. Two groups of animals were treated with “Tandem BNCT”, i.e. BNCT mediated by boronophenylalanine (BPA) followed by BNCT mediated by sodium decahydrodecaborate (GB-10) either 24 h (T-24h-BNCT) or 48 h (T-48h-BNCT) later. A total tumor dose-matched single application of BNCT mediated by BPA and GB-10 administered jointly [(BPA + GB-10)-BNCT] was administered to an additional group of animals. At 28 days post-treatment, T-24h-BNCT and T-48h-BNCT induced, respectively, overall tumor control (OTC) of 95% and 91%, with no statistically significant differences between protocols. Tumor response for the single application of (BPA + GB-10)-BNCT was 75%, significantly lower than for T-BNCT. The T-BNCT protocols and (BPA + GB-10)-BNCT induced reversible mucositis in dose-limiting precancerous tissue around treated tumors, reaching Grade 3/4 mucositis in 47% and 60% of the animals respectively. No normal tissue radiotoxicity was associated to tumor control for any of the protocols. “Tandem” BNCT enhances tumor control in oral cancer and reduces or, at worst, does not increase, mucositis in dose-limiting precancerous tissue.

  20. Radiation transport calculation methods in BNCT

    International Nuclear Information System (INIS)

    Koivunoro, H.; Seppaelae, T.; Savolainen, S.

    2000-01-01

    Boron neutron capture therapy (BNCT) is used as a radiotherapy for malignant brain tumours. Radiation dose distribution is necessary to determine individually for each patient. Radiation transport and dose distribution calculations in BNCT are more complicated than in conventional radiotherapy. Total dose in BNCT consists of several different dose components. The most important dose component for tumour control is therapeutic boron dose D B . The other dose components are gamma dose D g , incident fast neutron dose D f ast n and nitrogen dose D N . Total dose is a weighted sum of the dose components. Calculation of neutron and photon flux is a complex problem and requires numerical methods, i.e. deterministic or stochastic simulation methods. Deterministic methods are based on the numerical solution of Boltzmann transport equation. Such are discrete ordinates (SN) and spherical harmonics (PN) methods. The stochastic simulation method for calculation of radiation transport is known as Monte Carlo method. In the deterministic methods the spatial geometry is partitioned into mesh elements. In SN method angular integrals of the transport equation are replaced with weighted sums over a set of discrete angular directions. Flux is calculated iteratively for all these mesh elements and for each discrete direction. Discrete ordinates transport codes used in the dosimetric calculations are ANISN, DORT and TORT. In PN method a Legendre expansion for angular flux is used instead of discrete direction fluxes, land the angular dependency comes a property of vector function space itself. Thus, only spatial iterations are required for resulting equations. A novel radiation transport code based on PN method and tree-multigrid technique (TMG) has been developed at VTT (Technical Research Centre of Finland). Monte Carlo method solves the radiation transport by randomly selecting neutrons and photons from a prespecified boundary source and following the histories of selected particles

  1. The studsvik BNCT project: structure and the proposed protocols

    International Nuclear Information System (INIS)

    Capala, J.; Stenstam, B.H.; Skoeld, K.; Henriksson, R.; Salford, L.; Carlsson, J.

    2000-01-01

    The BNCT facility at Studsvik is now ready for clinical trials. Scientific operations of the Studsvik BNCT project are overseen by the Scientific Advisory Board comprised of representatives of all major universities in Sweden. Furthermore, special task groups for clinical and preclinical studies have been formed to facilitate collaboration with academia and to assure the quality of the research. Proposed clinical Phase II trials for glioblastoma are sponsored by the Swedish National Neuro-Oncology Group and, initially, will involve two protocols: Protocol no.1. BNCT for glioblastoma patients who have not received any therapy other than surgery (including stereotactic biopsy only). Protocol no.2. BNCT as a palliative treatment for patients with recurrent glioblastoma following conventional therapies or BNCT. In both protocols, BPA, administered by a 6 hour i.v. infusion, will be used as the boron delivery agent. (author)

  2. SAFE users manual. Volume 4. Computer programs

    International Nuclear Information System (INIS)

    Grady, L.M.

    1983-06-01

    Documentation for the Safeguards Automated Facility Evaluation (SAFE) computer programs is presented. The documentation is in the form of subprogram trees, program abstracts, flowcharts, and listings. Listings are provided on microfiche

  3. Laser program annual report, 1977. Volume 1

    International Nuclear Information System (INIS)

    Bender, C.F.; Jarman, B.D.

    1978-07-01

    An overview is given of the laser fusion program. The solid-state program covers the Shiva and Nova projects. Laser components, control systems, alignment systems, laser beam diagnostics, power conditioning, and optical components are described. The fusion experimental program concerns the diagnostics and data acquisition associated with Argus and Shiva

  4. Laser program annual report, 1977. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Bender, C.F.; Jarman, B.D. (eds.)

    1978-07-01

    An overview is given of the laser fusion program. The solid-state program covers the Shiva and Nova projects. Laser components, control systems, alignment systems, laser beam diagnostics, power conditioning, and optical components are described. The fusion experimental program concerns the diagnostics and data acquisition associated with Argus and Shiva. (MOW)

  5. Implementing US Department of Energy lessons learned programs. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    The DOE Lessons Learned Handbook is a two-volume publication developed to supplement the DOE Lessons Learned Standard (DOE-STD-7501-95) with information that will organizations in developing or improving their lessons learned programs. Volume 1 includes greater detail than the Standard in areas such as identification and documentation of lessons learned; it also contains sections on specific processes such as training and performance measurement. Volume 2 (this document) contains examples of program documents developed by existing lessons learned programs as well as communications material, functional categories, transmittal documents, sources of professional and industry lessons learned, and frequently asked questions about the Lessons Learned List Service.

  6. Construction of voxel head phantom and application to BNCT dose calculation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Choon Sik; Lee, Choon Ik; Lee, Jai Ki [Hanyang Univ., Seoul (Korea, Republic of)

    2001-06-15

    Voxel head phantom for overcoming the limitation of mathematical phantom in depicting anatomical details was constructed and example dose calculation for BNCT was performed. The repeated structure algorithm of the general purpose Monte Carlo code, MCNP4B was applied for voxel Monte Carlo calculation. Simple binary voxel phantom and combinatorial geometry phantom composed of two materials were constructed for validating the voxel Monte Carlo calculation system. The tomographic images of VHP man provided by NLM(National Library of Medicine) were segmented and indexed to construct voxel head phantom. Comparison od doses for broad parallel gamma and neutron beams in AP and PA directions showed decrease of brain dose due to the attenuation of neutron in eye balls in case of voxel head phantom. The spherical tumor volume with diameter, 5cm was defined in the center of brain for BNCT dose calculation in which accurate 3 dimensional dose calculation is essential. As a result of BNCT dose calculation for downward neutron beam of 10keV and 40keV, the tumor dose is about doubled when boron concentration ratio between the tumor to the normal tissue is 30{mu}g/g to 3 {mu}g/g. This study established the voxel Monte Carlo calculation system and suggested the feasibility of precise dose calculation in therapeutic radiology.

  7. Some recent developments in treatment planning software and methodology for BNCT

    International Nuclear Information System (INIS)

    Nigg, D.W.; Wheeler, F.J.; Wessol, D.E.; Wemple, C.A.; Babcock, R.; Capala, J.

    1996-01-01

    Over the past several years/the Idaho National Engineering Laboratory (INEL) has led the development of a unique, internationally-recognized set of software modules (BNCT rtpe) for computational dosimetry and treatment planning for Boron Neutron Capture Therapy (BNCT). The computational capability represented by this software is essential to the proper administration of all forms of radiotherapy for cancer. Such software addresses the need to perform pretreatment computation and optimization of the radiation dose distribution in the target volume. This permits the achievement of the optimal therapeutic ratio (tumor dose relative to critical normal tissue dose) for each individual patient via a systematic procedure for specifying the appropriate irradiation parameters to be employed for a given treatment. These parameters include angle of therapy beam incidence, beam aperture and shape,and beam intensity as a function of position across the beam front. The INEL software is used for treatment planning in the current series of human glioma trials at Brookhaven National Laboratory (BNL) and has also been licensed for research and developmental purposes to several other BNCT research centers in the US and in Europe

  8. Some recent developments in treatment planning software and methodology for BNCT

    International Nuclear Information System (INIS)

    Nigg, D.W.; Wheeler, F.J.; Wessol, D.E.

    1996-01-01

    Over the past several years the Idaho National Engineering Laboratory (INEL) has led the development of a unique, internationally-recognized set of software modules (BNCT-rtpe) for computational dosimetry and treatment planning for Boron Neutron Capture Therapy (BNCT). The computational capability represented by this software is essential to the proper administration of all forms of radiotherapy for cancer. Such software addresses the need to perform pretreatment computation and optimization of the radiation dose distribution in the target volume. This permits the achievement of the optimal therapeutic ratio (tumor dose relative to critical normal tissue dose) for each individual patient via a systematic procedure for specifying the appropriate irradiation parameters to be employed for a given treatment. These parameters include angle of therapy beam incidence, beam aperture and shape, and beam intensity as a function of position across the beam front. The INEL software is used for treatment planning in the current series of human glioma trials at Brookhaven National Laboratory (BNL) and has also been licensed for research and developmental purposes to several other BNCT research centers in the US and in Europe

  9. Dose estimation of the THOR BNCT treatment room

    International Nuclear Information System (INIS)

    Hsu, F.Y.; Liu, H.M.; Yu, C.C.; Huang, Y.H.; Tsai, H.N.

    2006-01-01

    BNCT beam of Tsing Hua Open-pool Reactor (THOR) was designed and constructed since 1998. A treatment room for the newly modified THOR BNCT beam was constructed for the next clinical-stage trials in 2004. Dose distribution in a patient (or a phantom) is important as irradiated with the BNCT beam. The dose distributions for different type of radiations such as neutron and photons in the treatment room are strongly becoming the index or reference of success for a BNCT facility. An ART head phantom was placed in front of the THOR BNCT beam port and was irradiated. In each section of the head phantom, numbers of small holes are inside and separated uniformly. Dual detector: TLD-600 and TLD-700 chips were placed inside these holes within the phantom to distinct doses of neutron and photon. Besides, Dual-TLD chips were latticed placed in the horizontal plane of beam central axis, in the treatment room to estimate the spatial dose distribution of neutron and photon. Gold foils were assisted in TLD dose calibrations. Neutron and photon dose distributions in phantom and spatial dose distributions in the THOR BNCT treatment room were both estimated in this work. Testing and improvement in THOR BNCT beam were continuative during these years. Results of this work could be the reference and be helpful for the further clinical trials in nearly future. (author)

  10. Energy-efficient buildings program evaluations. Volume 2: Evaluation summaries

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A.D.; Mayi, D.; Edgemon, S.D.

    1997-04-01

    This document presents summaries of code and utility building program evaluations reviewed as the basis for the information presented in Energy-Efficient Buildings Program Evaluations, Volume 1: Findings and Recommendations, DOE/EE/OBT-11569, Vol. 1. The main purpose of this volume is to summarize information from prior evaluations of similar programs that may be useful background for designing and conducting an evaluation of the BSGP. Another purpose is to summarize an extensive set of relevant evaluations and provide a resource for program designers, mangers, and evaluators.

  11. American brain tumor patients treated with BNCT in Japan

    International Nuclear Information System (INIS)

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

    1995-01-01

    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

  12. AUA Program Master Plan. Volume 1: Overview

    Science.gov (United States)

    1997-03-01

    The Office of Air Traffic Systems Development (AUA) Program Master Plan : summarizes the management, development approach, and status of products and : services provided by the AUA organization to fulfill its role in supporting : National Airspace Sy...

  13. The BNCT project in the Czech Republic

    International Nuclear Information System (INIS)

    Burian, J.; Marek, M.; Rataj, J.; Honova, H.; Petruzelka, L.; Prokes, K.; Tovarys, F.; Dbaly, V.; Honzatko, J.; Tomandl, I.

    2000-01-01

    The start of clinical trials is expected before NCT Osaka 2000. The experiences from different part of project are presented. The BNCT facility at LVR-15 reactor of NRI consists of epithermal neutron beam with improved construction (6.98 x 10 8 /cm 2 s with acceptable background of fast neutrons and gammas) and irradiation and control rooms equipped by appropriate devices. Internationally-recognized software MacNCTPLAN is utilized for computational dosimetry and treatment planning. In the part of protocol the following parameters have been assessed: patient selection, BSH dosage, fractionation, starting dose, dose escalation steps. At the LVR-15, at horizontal channel, a prompt gamma ray analysis (PGRA) system has been developed and is operated for BNCT purposes. Some human blood samples were analyzed and compared with classical ICP method. During the process of licensing the experience was obtained, some notes are discussed in the paper. The first results were received for the study of biological effect of the LVR source for small animal model. (author)

  14. Maryland controlled fusion research program. Volume I

    International Nuclear Information System (INIS)

    1985-01-01

    This renewal proposal describes the University of Maryland research program on Magnetic Fusion Energy for a three-year period beginning January 1, 1986. This program consists of five tasks: (I) Plasma Theory; (II) Electron Cyclotron Emission Diagnostics for Mirror Machines; (III) Electron Cyclotron Emission Diagnostics on TFTR; (IV) Atomic Physics; and (V) Magnetic Field Measurement by Ion Beams. The four separate tasks of continuing research (Tasks I to IV) and the new experimental task (Task V) are described in detail. The task descriptions contain estimated budgets for CY 86, 87, and 88

  15. The therapeutic ratio in BNCT: Assessment using the Rat 9L gliosarcoma brain tumor and spinal cord models

    International Nuclear Information System (INIS)

    Coderre, J.A.; Micca, P.L.; Nawrocky, M.M.; Fisher, C.D.; Bywaters, A.; Morris, G.M.; Hopewell, J.W.

    1996-01-01

    During any radiation therapy, the therapeutic tumor dose is limited by the tolerance of the surrounding normal tissue within the treatment volume. The short ranges of the products of the 10 B(n,α) 7 Li reaction produced during boron neutron capture therapy (BNCT) present an opportunity to increase the therapeutic ratio (tumor dose/normal tissue dose) to levels unprecedented in photon radiotherapy. The mixed radiation field produced during BNCT comprises radiations with different linear energy transfer (LET) and different relative biological effectiveness (RBE). The short ranges of the two high-LET products of the 'B(n,a)'Li reaction make the microdistribution of the boron relative to target cell nuclei of particular importance. Due to the tissue specific distribution of different boron compounds, the term RBE is inappropriate in defining the biological effectiveness of the 10 B(n,α) 7 Li reaction. To distinguish these differences from true RBEs we have used the term open-quotes compound biological effectivenessclose quotes (CBE) factor. The latter can be defined as the product of the true, geometry-independent, RBE for these particles times a open-quotes boron localization factorclose quotes, which will most likely be different for each particular boron compound. To express the total BNCT dose in a common unit, and to compare BNCT doses with the effects of conventional photon irradiation, multiplicative factors (RBEs and CBEs) are applied to the physical absorbed radiation doses from each high-LET component. The total effective BNCT dose is then expressed as the sum of RBE-corrected physical absorbed doses with the unit Gray-equivalent (Gy-Eq)

  16. OCCUPATIONAL EDUCATION--PLANNING AND PROGRAMMING. VOLUME TWO.

    Science.gov (United States)

    KOTZ, ARNOLD

    ADDITIONAL POSITION PAPERS BASED ON INFORMATION GATHERED IN THE RECONNAISSANCE SURVEYS OF PLANNING AND PROGRAMING IN OCCUPATIONAL EDUCATION, REPORTED IN VOLUME ONE (VT 005 041), ARE PRESENTED. PART IV, CONCERNED WITH PROGRAM STRUCTURE AND BUDGETING AND THEIR RELATION TO THE PLANNING PROCESS, INCLUDES THE PAPERS--(1) "CURRENT POLICIES AND…

  17. Optimization of beam shaping assembly based on D-T neutron generator and dose evaluation for BNCT

    Science.gov (United States)

    Naeem, Hamza; Chen, Chaobin; Zheng, Huaqing; Song, Jing

    2017-04-01

    The feasibility of developing an epithermal neutron beam for a boron neutron capture therapy (BNCT) facility based on a high intensity D-T fusion neutron generator (HINEG) and using the Monte Carlo code SuperMC (Super Monte Carlo simulation program for nuclear and radiation process) is proposed in this study. The Monte Carlo code SuperMC is used to determine and optimize the final configuration of the beam shaping assembly (BSA). The optimal BSA design in a cylindrical geometry which consists of a natural uranium sphere (14 cm) as a neutron multiplier, AlF3 and TiF3 as moderators (20 cm each), Cd (1 mm) as a thermal neutron filter, Bi (5 cm) as a gamma shield, and Pb as a reflector and collimator to guide neutrons towards the exit window. The epithermal neutron beam flux of the proposed model is 5.73 × 109 n/cm2s, and other dosimetric parameters for the BNCT reported by IAEA-TECDOC-1223 have been verified. The phantom dose analysis shows that the designed BSA is accurate, efficient and suitable for BNCT applications. Thus, the Monte Carlo code SuperMC is concluded to be capable of simulating the BSA and the dose calculation for BNCT, and high epithermal flux can be achieved using proposed BSA.

  18. Clean Coal Technology Programs: Program Update 2003 (Volume 1)

    Energy Technology Data Exchange (ETDEWEB)

    Assistant Secretary for Fossil Energy

    2003-12-01

    Annual report on the Clean Coal Technology Demonstration Program (CCTDP), Power Plant Improvement Initiative (PPII), and Clean Coal Power Initiative (CCPI). The report addresses the roles of the programs, implementation, funding and costs, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

  19. Subseabed Disposal Program plan. Volume I. Overview

    International Nuclear Information System (INIS)

    1980-01-01

    Some of the most stable geologic formations are underneath the deep oceans. Purpose of this program is to assess the technical, environmental, and engineering feasibility of disposing of packaged high-level waste and/or repackaged spent reactor fuel in these formations

  20. Subseabed Disposal Program Plan. Volume I. Overview

    International Nuclear Information System (INIS)

    1981-07-01

    The primary objective of the Subseabed Disposal Program (SDP) is to assess the scientific, environmental, and engineering feasibility of disposing of processed and packaged high-level nuclear waste in geologic formations beneath the world's oceans. High-level waste (HLW) is considered the most difficult of radioactive wastes to dispose of in oceanic geologic formations because of its heat and radiation output. From a scientific standpoint, the understanding developed for the disposal of such HLW can be used for other nuclear wastes (e.g., transuranic - TRU - or low-level) and materials from decommissioned facilities, since any set of barriers competent to contain the heat and radiation outputs of high-level waste will also contain such outputs from low-level waste. If subseabed disposal is found to be feasible for HLW, then other factors such as cost will become more important in considering subseabed emplacement for other nuclear wastes. A secondary objective of the SDP is to develop and maintain a capability to assess and cooperate with the seabed nuclear waste disposal programs of other nations. There are, of course, a number of nations with nuclear programs, and not all of these nations have convenient access to land-based repositories for nuclear waste. Many are attempting to develop legislative and scientific programs that will avoid potential hazards to man, threats to other ocean uses, and marine pollution, and they work together to such purpose in meetings of the international NEA/Seabed Working Group. The US SDP, as the first and most highly developed R and D program in the area, strongly influences the development of subseabed-disposal-related policy in such nations

  1. Research program plan: reactor vessels. Volume 1

    International Nuclear Information System (INIS)

    Vagins, M.; Taboada, A.

    1985-07-01

    The ability of the licensing staff of the NRC to make decisions concerning the present and continuing safety of nuclear reactor pressure vessels under both normal and abnormal operating conditions is dependent upon the existence of verified analysis methods and a solid background of applicable experimental data. It is the role of this program to provide both the analytical methods and the experimental data needed. Specifically, this program develops fracture mechanics analysis methods and design criteria for predicting the stress levels and flaw sizes required for crack initiation, propagation, and arrest in LWR pressure vessels under all known and postulated operations conditions. To do this, not only must the methods be developed but they must be experimentally validated. Further, the materials data necessary for input to these analytical methods must be developed. Thus, in addition to methods development and large scale experimental verification this program also develops data to show that slow-load fracture toughness, rapid-load fracture toughness, and crack arrest toughness obtained from small laboratory specimens are truly representative of the toughness characteristics of the material behavior in pressure vessels in both the unirradiated and the irradiated conditions

  2. A case of astrocytoma, 19 year history after BNCT

    International Nuclear Information System (INIS)

    Kamano, Shuji

    2006-01-01

    A 39-year-old man had received Boron Neutron Capture Therapy (BNCT) in 1987 for a Grade II Astrocytoma. He gradually exacerbated and received a second operation in 1994. The mass taken in the second operation is almost competent with radiation necrosis. Following that, he shows no signs of recurrence. Currently, he has returned to full time employment in physical labor. This case suggests effectiveness of BNCT for rather low-grade astrocytomas. (author)

  3. International photovoltaic program. Volume 2: Appendices

    Science.gov (United States)

    Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

    1979-01-01

    The results of analyses conducted in preparation of an international photovoltaic marketing plan are summarized. Included are compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about the how US government actions could affect this market;international financing issues; and information on issues affecting foreign policy and developing countries.

  4. PROGRAM HTVOL: The Determination of Tree Crown Volume by Layers

    Science.gov (United States)

    Joseph C. Mawson; Jack Ward Thomas; Richard M. DeGraaf

    1976-01-01

    A FORTRAN IV computer program calculates, from a few field measurements, the volume of tree crowns. This volume is in layers of a specified thickness of trees or large shrubs. Each tree is assigned one of 15 solid forms, formed by using one of five side shapes (a circle, an ellipse, a neiloid, a triangle, or a parabolalike shape), and one of three bottom shapes (a...

  5. Clinical requirements and accelerator concepts for BNCT

    International Nuclear Information System (INIS)

    Ludewigt, B.A.; Bleuel, D.L.; Chu, W.T.; Donahue, R.J.; Kwan, J.; Leung, K.N.; Reginato, L.L.; Wells, R.P.

    1997-05-01

    Accelerator-based neutron sources are an attractive alternative to nuclear reactors for providing epithermal neutron beams for Boron Neutron Capture Therapy. Based on clinical requirements and neutronics modeling the use of proton and deuteron induced reactions in 7 Li and 9 Be targets has been compared. Excellent epithermal neutron beams can be produced via the 7 Li(p,n) 7 Be reaction at proton energies of ∼2.5 MeV. An electrostatic quadrupole accelerator and a lithium target, which can deliver and handle 2.5 MeV protons at beam currents up to 50 mA, are under development for an accelerator-based BNCT facility at the Lawrence Berkeley National Laboratory

  6. Development of a Tandem-ElectroStatic-Quadrupole accelerator facility for Boron Neutron Capture Therapy (BNCT)

    International Nuclear Information System (INIS)

    Kreiner, A.J.; Thatar Vento, V.; Levinas, P.; Bergueiro, J.; Burlon, A.A.; Di Paolo, H.; 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.; Repetto, M.; Obligado, M.; Nery, J.P.; Huck, H.; Igarzabal, M.; Fernandez Salares, A.

    2008-01-01

    There is a generalized perception that the availability of suitable particle accelerators installed in hospitals, as neutron sources, may be crucial for the advancement of Boron Neutron Capture Therapy (BNCT). An ongoing project to develop a Tandem-ElectroStatic-Quadrupole (TESQ) accelerator facility for Accelerator-Based (AB)-BNCT is described here. The project goal is a machine capable of delivering 30 mA of 2.4-2.5 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. A folded tandem, with 1.20-1.25 MV terminal voltage, combined with an ESQ chain is being designed and constructed. This machine is conceptually shown to be capable of accelerating a 30 mA proton beam to 2.5 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. This electrostatic machine is one of the technologically simplest and cheapest solutions for optimized AB-BNCT. At present there is no BNCT facility in the world with the characteristics presented in this work. For the accelerator, results on its design, construction and beam transport calculations are discussed. Taking into account the peculiarities of the expected irradiation field, the project also considers a specific study of the treatment room. This study aims at the design of the treatment room emphasizing aspects related to patient, personnel and public radiation protection; dose monitoring; patient positioning and room construction. The design considers both thermal (for the treatment of shallow tumors) and epithermal (for deep-seated tumors) neutron beams entering the room through a port connected to the accelerator via a moderation and neutron beam shaping assembly. Preliminary results of dose calculations for the treatment room design, using the MCNP program, are presented

  7. Highly Insulating Windows Volume Purchase Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-04-01

    This report documents the development, execution outcomes and lessons learned of the Highly Insulating Windows Volume Purchase (WVP) Program carried out over a three-year period from 2009 through 2012. The primary goals of the program were met: 1) reduce the incremental cost of highly insulating windows compared to ENERGY STAR windows; and 2) raise the public and potential buyers’ awareness of highly insulating windows and their benefits. A key outcome of the program is that the 2013 ENERGY STAR Most Efficient criteria for primary residential windows were adopted from the technical specifications set forth in the WVP program.

  8. Synfuel program analysis. Volume 2: VENVAL users manual

    Science.gov (United States)

    Muddiman, J. B.; Whelan, J. W.

    1980-07-01

    This volume is intended for program analysts and is a users manual for the VENVAL model. It contains specific explanations as to input data requirements and programming procedures for the use of this model. VENVAL is a generalized computer program to aid in evaluation of prospective private sector production ventures. The program can project interrelated values of installed capacity, production, sales revenue, operating costs, depreciation, investment, dent, earnings, taxes, return on investment, depletion, and cash flow measures. It can also compute related public sector and other external costs and revenues if unit costs are furnished.

  9. Intrasystem Electromagnetic Compatibility Analysis Program. Volume III. Computer Program Documentation

    Science.gov (United States)

    1974-12-01

    Cor intied) PROGRAM NAME SIMBOL DEFINITION FQEPDB fep IN dB FQEPL LOWER INTERVAL BOUNDARY FREQ OF fep FQEPU UPPER INTERVAL BOUNDARY FREQ OF f .4, fep...I• TOR. VARIABLES L __G~~ NM SIMBOL DEFINITION BWFE 1 BANDWIDTH FACTOR OF EM’TR BANDWIDTH FACTOR OF RCPT EINTB INTEGRATBD MARGIN BROAD BAND COMPON

  10. Small Business Management Volume III: Curriculum. An Adult Education Program.

    Science.gov (United States)

    Persons, Edgar A.; Swanson, Gordon I.

    The small business management adult education program outlined in this curriculum guide is designed to help small business entrepreneurs solve their business management problems and attain the goals they have established for their businesses and their families. (An instructor's manual and practice problems are in separate volumes.) The 3-year…

  11. Programmable calculator programs to solve softwood volume and value equations.

    Science.gov (United States)

    Janet K. Ayer. Sachet

    1982-01-01

    This paper presents product value and product volume equations as programs for handheld calculators. These tree equations are for inland Douglas-fir, young-growth Douglas-fir, western white pine, ponderosa pine, and western larch. Operating instructions and an example are included.

  12. Comparison and analysis of BNCT radiation dose between gold wire and JCDS measurement

    International Nuclear Information System (INIS)

    Kageji, T.; Mizobuchi, Y.; Nagahiro, S.; Nakagawa, Y.; Kumada, Hiroaki

    2006-01-01

    We compared and evaluated boron neutron capture therapy (BNCT) radiation dose between gold wire measurement and JAERI Computational Dosimetry System (JCDS). Gold wire analysis demonstrates the actual BNCT dose though it dose not reflect the real the maximum and minimum dose in tumor tissue. We can conclude that JCDS is precise and high-reliable dose planning system for BNCT. (author)

  13. NWTS waste package program plan. Volume II. Program logic networks

    International Nuclear Information System (INIS)

    1981-10-01

    This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced

  14. Boron neutron capture therapy (BNCT) inhibits tumor development from precancerous tissue: An experimental study that supports a potential new application of BNCT

    International Nuclear Information System (INIS)

    Monti Hughes, A.; Heber, E.M.; Pozzi, E.; Nigg, D.W.; Calzetta, O.; Blaumann, H.; Longhino, J.; Nievas, S.I.; Aromando, R.F.; Itoiz, M.E.; Trivillin, V.A.; Schwint, A.E.

    2009-01-01

    We previously demonstrated the efficacy of boron neutron capture therapy (BNCT) mediated by boronophenylalanine (BPA), GB-10 (Na 2 10 B 10 H 10 ) and (GB-10+BPA) to control tumors, with no normal tissue radiotoxicity, in the hamster cheek pouch oral cancer model. Herein we developed a novel experimental model of field-cancerization and precancerous lesions (globally termed herein precancerous tissue) in the hamster cheek pouch to explore the long-term potential inhibitory effect of the same BNCT protocols on the development of second primary tumors from precancerous tissue. Clinically, second primary tumor recurrences occur in field-cancerized tissue, causing therapeutic failure. We performed boron biodistribution studies followed by in vivo BNCT studies, with 8 months follow-up. All 3 BNCT protocols induced a statistically significant reduction in tumor development from precancerous tissue, reaching a maximum inhibition of 77-100%. The inhibitory effect of BPA-BNCT and (GB-10+BPA)-BNCT persisted at 51% at the end of follow-up (8 months), whereas for GB-10-BNCT it faded after 2 months. Likewise, beam-only elicited a significant but transient reduction in tumor development. No normal tissue radiotoxicity was observed. At 8 months post-treatment with BPA-BNCT or (GB-10+BPA)-BNCT, the precancerous pouches that did not develop tumors had regained the macroscopic and histological appearance of normal (non-cancerized) pouches. A potential new clinical application of BNCT would lie in its capacity to inhibit local regional recurrences.

  15. Constellation Program: Lessons Learned. Volume 1; Executive Summary

    Science.gov (United States)

    Rhatigan, Jennifer L. (Editor)

    2011-01-01

    This document (Volume I) provides an executive summary of the lessons learned from the Constellation Program. A companion Volume II provides more detailed analyses for those seeking further insight and information. In this volume, Section 1.0 introduces the approach in preparing and organizing the content to enable rapid assimilation of the lessons. Section 2.0 describes the contextual framework in which the Constellation Program was formulated and functioned that is necessary to understand most of the lessons. Context of a former program may seem irrelevant in the heady days of new program formulation. However, readers should take some time to understand the context. Many of the lessons would be different in a different context, so the reader should reflect on the similarities and differences in his or her current circumstances. Section 3.0 summarizes key findings developed from the significant lessons learned at the program level that appear in Section 4.0. Readers can use the key findings in Section 3.0 to peruse for particular topics, and will find more supporting detail and analyses in Section 4.0 in a topical format. Appendix A contains a white paper describing the Constellation Program formulation that may be of use to readers wanting more context or background information. The reader will no doubt recognize some very similar themes from previous lessons learned, blue-ribbon committee reviews, National Academy reviews, and advisory panel reviews for this and other large-scale human spaceflight programs; including Apollo, Space Shuttle, Shuttle/Mir, and the ISS. This could represent an inability to learn lessons from previous generations; however, it is more likely that similar challenges persist in the Agency structure and approach to program formulation, budget advocacy, and management. Perhaps the greatest value of these Constellation lessons learned can be found in viewing them in context with these previous efforts to guide and advise the Agency and its

  16. Diversion Path Analysis handbook. Volume 4 (of 4 volumes). Computer Program 2

    International Nuclear Information System (INIS)

    Schleter, J.C.

    1978-11-01

    The FORTRAN IV computer program, DPA Computer Program 2 (DPACP-2) is used to produce tables and statistics on modifications identified when performing a Diversion Path Analysis (DPA) in accord with the methodology given in Volume 1. The program requires 259088 bytes exclusive of the operating system. The data assembled and tabulated by DPACP-2 assist the DPA team in analyzing and evaluating modifications to the plant's safeguards system that would eliminate, or reduce the severity of, vulnerabilities identified by means of the DPA. These vulnerabilities relate to the capability of the plant's material control and material accounting subsystems to indicate diversion of special nuclear material (SNM) by a knowledgeable insider

  17. TRU Waste Sampling Program: Volume I. Waste characterization

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Kudera, D.E.

    1985-09-01

    Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies

  18. Proceedings of neutron irradiation technical meeting on BNCT

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    The 'Neutron Irradiation Technical Meeting for Boron Neutron Capture Therapy (BNCT)' was held on March 13, 2000 at Tokai Research Establishment. The Meeting is aimed to introduce the neutron beam facility for medical irradiation at JRR-4 to Japanese researchers widely, as well as providing an opportunity for young researchers, engineers, medical representatives such surgeons and doctors of pharmacology to present their research activities and to exchange valuable information. JAERI researcher presented the performance and the irradiation technology in the JRR-4 neutron beam facility, while external researchers made various and beneficial presentations containing such accelerator-based BNCT, spectrum-shifter, biological effect, pharmacological development and so on. In this meeting, a special lecture titled 'The Dawn of BNCT and Its Development.' was given by MD, Prof. Takashi Minobe, an executive director of Japan Foundation for Emergency Medicine. The 11 of the presented papers are indexed individually. (J.P.N.)

  19. Proceedings of neutron irradiation technical meeting on BNCT

    International Nuclear Information System (INIS)

    2000-10-01

    The 'Neutron Irradiation Technical Meeting for Boron Neutron Capture Therapy (BNCT)' was held on March 13, 2000 at Tokai Research Establishment. The Meeting is aimed to introduce the neutron beam facility for medical irradiation at JRR-4 to Japanese researchers widely, as well as providing an opportunity for young researchers, engineers, medical representatives such surgeons and doctors of pharmacology to present their research activities and to exchange valuable information. JAERI researcher presented the performance and the irradiation technology in the JRR-4 neutron beam facility, while external researchers made various and beneficial presentations containing such accelerator-based BNCT, spectrum-shifter, biological effect, pharmacological development and so on. In this meeting, a special lecture titled 'The Dawn of BNCT and Its Development.' was given by MD, Prof. Takashi Minobe, an executive director of Japan Foundation for Emergency Medicine. The 11 of the presented papers are indexed individually. (J.P.N.)

  20. 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.

  1. 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.

  2. BNCT Project at the J. Stefan TRIGA Reactor

    International Nuclear Information System (INIS)

    Glumac, B.; Maucec, M.; Jeraj, R.; Kodeli, I.

    1994-01-01

    Contribution presents condensed description of the BNCT method, as one of the most promising methods of cancer radio therapy in the future. Certain planned research activities considering realization of BNCT project in Slovenia are also shown. Modelling of irradiation facility as well as mathematical simulation of neutron and photon transport are completely performed by Monte Carlo computer simulation, and for that reason some basic characteristics and capabilities of MCNP4A computer code are also presented. Finally, some results obtained up to this time are presented. (author)

  3. Dosimetric analysis of BNCT - Boron Neutron Capture Therapy - coupled to 252Cf brachytherapy

    International Nuclear Information System (INIS)

    Brandao, Samia F.; Campos, Tarcisio P.R.

    2009-01-01

    The incidence of brain tumors is increasing in world population; however, the treatments employed in this type of tumor have a high rate of failure and in some cases have been considered palliative, depending on histology and staging of tumor. Its necessary to achieve the control tumor dose without the spread irradiation cause damage in the brain, affecting patient neurological function. Stereotactic radiosurgery is a technique that achieves this; nevertheless, other techniques that can be used on the brain tumor control must be developed, in order to guarantee lower dose on health surroundings tissues other techniques must be developing. The 252 Cf brachytherapy applied to brain tumors has already been suggested, showing promising results in comparison to photon source, since the active source is placed into the tumor, providing greater dose deposition, while more distant regions are spared. BNCT - Boron Neutron Capture Therapy - is another technique that is in developing to brain tumors control, showing theoretical superiority on the rules of conventional treatments, due to a selective irradiation of neoplasics cells, after the patient receives a borate compound infusion and be subjected to a epithermal neutrons beam. This work presents dosimetric studies of the coupling techniques: BNCT with 252 Cf brachytherapy, conducted through computer simulation in MCNP5 code, using a precise and well discretized voxel model of human head, which was incorporated a representative Glioblastoma Multiform tumor. The dosimetric results from MCNP5 code were exported to SISCODES program, which generated isodose curves representing absorbed dose rate in the brain. Isodose curves, neutron fluency, and dose components from BNCT and 252 Cf brachytherapy are presented in this paper. (author)

  4. Constellation Program Lessons Learned. Volume 2; Detailed Lessons Learned

    Science.gov (United States)

    Rhatigan, Jennifer; Neubek, Deborah J.; Thomas, L. Dale

    2011-01-01

    These lessons learned are part of a suite of hardware, software, test results, designs, knowledge base, and documentation that comprises the legacy of the Constellation Program. The context, summary information, and lessons learned are presented in a factual format, as known and described at the time. While our opinions might be discernable in the context, we have avoided all but factually sustainable statements. Statements should not be viewed as being either positive or negative; their value lies in what we did and what we learned that is worthy of passing on. The lessons include both "dos" and "don ts." In many cases, one person s "do" can be viewed as another person s "don t"; therefore, we have attempted to capture both perspectives when applicable and useful. While Volume I summarizes the views of those who managed the program, this Volume II encompasses the views at the working level, describing how the program challenges manifested in day-to-day activities. Here we see themes that were perhaps hinted at, but not completely addressed, in Volume I: unintended consequences of policies that worked well at higher levels but lacked proper implementation at the working level; long-term effects of the "generation gap" in human space flight development, the need to demonstrate early successes at the expense of thorough planning, and the consequences of problems and challenges not yet addressed because other problems and challenges were more immediate or manifest. Not all lessons learned have the benefit of being operationally vetted, since the program was cancelled shortly after Preliminary Design Review. We avoid making statements about operational consequences (with the exception of testing and test flights that did occur), but we do attempt to provide insight into how operational thinking influenced design and testing. The lessons have been formatted with a description, along with supporting information, a succinct statement of the lesson learned, and

  5. Frequency Domain Computer Programs for Prediction and Analysis of Rail Vehicle Dynamics : Volume 1. Technical Report

    Science.gov (United States)

    1975-12-01

    Frequency domain computer programs developed or acquired by TSC for the analysis of rail vehicle dynamics are described in two volumes. Volume I defines the general analytical capabilities required for computer programs applicable to single rail vehi...

  6. Savannah River Site Environmental Implementation Plan. Volume 2, Protection programs

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    Formal sitewide environmental planning at the . Savannah River Site (SRS) began in 1986 with the development and adoption of the Strategic Environmental Plan. The Strategic Environmental Plan describes the philosophy, policy, and overall program direction of environmental programs for the operation of the SRS. The Strategic Environmental Plan (Volume 2) provided the basis for development of the Environmental Implementation Plan (EIP). The EIP is the detailed, comprehensive environmental master plan for operating contractor organizations at the SRS. The EIP provides a process to ensure that all environmental requirements and obligations are being met by setting specific measurable goals and objectives and strategies for implementation. The plan is the basis for justification of site manpower and funding requests for environmental projects and programs over a five-year planning period.

  7. Boron Neutron Capture Therapty (BNCT) in an Oral Precancer Model: Therapeutic Benefits and Potential Toxicity of a Double Application of BNCT with a Six-Week Interval

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Monti Hughes; Emiliano C.C. Pozzi; Elisa M. Heber; Silvia Thorp; Marcelo Miller; Maria E. Itoiz; Romina F. Aromando; Ana J. Molinari; Marcela A. Garabalino; David W. Nigg; Veronica A. Trivillin; Amanda E. Schwint

    2011-11-01

    Given the clinical relevance of locoregional recurrences in head and neck cancer, we developed a novel experimental model of premalignant tissue in the hamster cheek pouch for long-term studies and demonstrated the partial inhibitory effect of a single application of Boron Neutron Capture Therapy (BNCT) on tumor development from premalignant tissue. The aim of the present study was to evaluate the effect of a double application of BNCT with a 6 week interval in terms of inhibitory effect on tumor development, toxicity and DNA synthesis. We performed a double application, 6 weeks apart, of (1) BNCT mediated by boronophenylalanine (BPA-BNCT); (2) BNCT mediated by the combined application of decahydrodecaborate (GB-10) and BPA [(GB-10 + BPA)-BNCT] or (3) beam-only, at RA-3 nuclear reactor and followed the animals for 8 months. The control group was cancerized and sham-irradiated. BPA-BNCT, (GB- 10 + BPA)-BNCT and beam-only induced a reduction in tumor development from premalignant tissue that persisted until 8, 3, and 2 months respectively. An early maximum inhibition of 100% was observed for all 3 protocols. No normal tissue radiotoxicity was detected. Reversible mucositis was observed in premalignant tissue, peaking at 1 week and resolving by the third week after each irradiation. Mucositis after the second application was not exacerbated by the first application. DNA synthesis was significantly reduced in premalignant tissue 8 months post-BNCT. A double application of BPA-BNCT and (GB-10 + BPA)-BNCT, 6 weeks apart, could be used therapeutically at no additional cost in terms of radiotoxicity in normal and dose-limiting tissues.

  8. Boron neutron capture therapy (BNCT) for glioblastoma multiforme (GBM), using the epithermal neutron beam at the Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Chadha, Manjeet; Capala, Jacek; Coderre, Jeffrey A.; Elowitz, Eric H.; Joel, Darrel D.; Hungyuan, B. Liu; Slatkin, Daniel N.; Chanana, Arjun D.

    1996-01-01

    , respectively. The 10 B concentration in the normal brain was ≤ that in the blood. Radiation Dosimetry: The estimated radiation doses were recorded using a normal brain endothelium to blood 10 B concentration ratio of 1:1 and a tumor to blood 10 B concentration ratio of 3.5:1. The average 10 B blood concentration during irradiation was 13.0 ± 1.5μg 10 B/g (range: 11.2-15.4). The maximum tumor dose ranged from 47.6-64.4 Gy-Eq (mean 52.8±4.2 Gy-Eq). The minimum target volume dose ranged from 7.8-16.2 Gy-Eq (mean 12.3±1.8 Gy-Eq). Dose to scalp ranged from 10-15 Gy-Eq. The critical brain structures in all cases received less than 6.5 Gy-Eq. Clinical Outcome: Following BNCT all patients experienced in-field alopecia, and grade 1 erythema was noted in 2 patients. Transient drop in lymphocyte counts was noted in 6 patients that returned to normal range in 2 weeks. No CNS toxicity attributed to BNCT was observed. At a median follow up of 9.5 mo (range 3-15 mo), 1 patient is dead from disseminated craniospinal disease and 6 from local recurrence. In the remaining 3 patients, all but 1 patient has shown evidence of disease progression at the primary site. Conclusion: It is feasible to deliver a single-fraction of BPA-based BNCT. At the dose prescribed, the patients did not experience any adverse morbidity. To further evaluate the therapeutic efficacy of BNCT, a dose escalation study delivering a minimum target volume dose of 17 Gy-Eq is in progress

  9. Diversion Path Analysis handbook. Volume 3 (of 4 volumes). Computer Program 1

    International Nuclear Information System (INIS)

    Schleter, J.C.

    1978-11-01

    The FORTRAN IV computer program, DPA Computer Program 1 (DPACP-1), is used to assemble and tabulate the data for Specific Diversion Paths (SDPs) identified when performing a Diversion Path Analysis (DPA) in accord with the methodology given in Volume 1. The program requires 255498 bytes exclusive of the operating system. The data assembled and tabulated by DPACP-1 are used by the DPA team to assist in analyzing vulnerabilities, in a plant's material control and material accounting subsystems, to diversion of special nuclear material (SNM) by a knowledgable insider. Based on this analysis, the DPA team can identify, and propose to plant management, modifications to the plant's safeguards system that would eliminate, or reduce the severity of, the identified vulnerabilities. The data are also used by plant supervision when investigating a potential diversion

  10. In vivo BNCT in experimental and spontaneous tumors at RA-1 reactor

    International Nuclear Information System (INIS)

    Trivillin, Veronica A.; Heber, Elisa M.; Itoiz, Maria E.; Schwint, Amanda E.; Nigg, David W.

    2003-01-01

    Within the search for new applications of Boron Neutron Capture Therapy (BNCT) and the basic research oriented towards the study of BNCT radiobiology to optimize its therapeutic gain, we previously proposed and validated the hamster cheek pouch oral cancer model and showed, for the first time, the success of BNCT to treat oral cancer in an experimental model. The staff of the Ra-1 Reactor (Constituyentes Atomic Center) adapted the thermal beam and physical set-up to perform in vivo BNCT of superficial tumors in small animals. We preformed a preliminary characterization of the thermal beam, performed beam only irradiation of normal and tumor bearing hamsters and in vivo BNCT of experimental oral squamous cell carcinomas in hamsters mediated by boron phenylalanine (BPA) and GB-10 (Na 2 10 B 10 H 10 ). Having demonstrated the absence of radio toxic effects in healthy tissue and a therapeutic effect of in vivo BNCT in hamster cheek pouch tumors employing the Ra-1 thermal beam, we performed a feasibility study of the treatment by BNCT of 3 terminal cases of spontaneous head and neck squamous cell carcinoma in cats following the corresponding biodistribution studies. This was the first treatment of spontaneous tumors by BNCT in our country and the first treatment by BNCT in cats worldwide. This preclinical study in terminal cases showed significant tumor control by BNCT with no damage to normal tissue. (author)

  11. An update on the clinical trial of BNCT at the BMRR

    International Nuclear Information System (INIS)

    Ma, R.; Capala, J.; Chanana, A.D.; Coderre, J.A.; Diaz, A.Z.

    1999-01-01

    Boron neutron capture therapy (BNCT) was proposed more than six decades ago. It is a binary treatment modality that requires selective delivery of a 10 B-labeled compound to a tumor and slow neutron irradiation of the tumor-bearing tissues. In order to improve the penetration of the neutron beam, an epithermal neutron beam was developed at the Brookhaven Medical Research Reactor (BMRR). This epithermal neutron beam can deliver relatively high thermal neutron fluence at depth without severe skin damage. Boronophenylalanine-fructose (BPA-F), a nontoxic boron carrier, was found to preferentially accumulate in tumor cells following intravenous infusion in patients with GBM. In preclinical BNCT studies in rats bearing 9L gliosarcoma, BPA-mediated BNCT was shown to be more efficacious than photon irradiation. In 1994, improvements in the neutron beam and in the understanding of the radiobiology of BPA-mediated BNCT led to the initiation of BNCT trials for human GBM at BMRR using BPA-F and epithermal neutrons. The primary objective of the phase I/II clinical trial of BPA-mediated BNCT at BMRR is to evaluate the safety of the BPA-F-mediated BNCT using epithermal neutrons in patients with GBM at a series of escalating BNCT doses. An incidental objective is to evaluate the therapeutic effectiveness of BNCT at each dose level. For each dose escalation group, the average brain dose (ABD) is escalated, as well as the minimum tumor dose. In summary, the BNCT procedure employed in the phase I/II clinical trial of BPA-F-mediated BNCT for GBM at BNL was found to be safe in all patients. The palliation afforded by a single session of BNCT compares favorably with palliation provided by fractionated photon therapy and adjuvant chemotherapy. If no evidence of radiation-induced brain toxicity is found in the current protocol, BNCT radiation dose will be further escalated

  12. The durban beach monitoring program: simple surveys speak volumes

    CSIR Research Space (South Africa)

    de Wet, p

    2010-10-01

    Full Text Available program: simple surveys speak volumes Pierre de Wet, Andrew Mather, Andr? Theron SAEON summit, 6 October 2010 ? CSIR 2010 Slide 1www.csir.co.za Outline ? Background / History ? Monitoring area circle6 Examples of survey data & trends circle6...) and near-shore deposition cf. classical understanding / scheme ? CSIR 2010 Slide 6 ? id. areas vulnerable to erosion ? effect of replenishment rates / locations visible Beach survey data s h o r e l i n e p o s i t i o n [ m...

  13. User's operating procedures. Volume 3: Projects directorate information programs

    Science.gov (United States)

    Haris, C. G.; Harris, D. K.

    1985-01-01

    A review of the user's operating procedures for the scout project automatic data system, called SPADS is presented. SPADS is the results of the past seven years of software development on a prime mini-computer. SPADS was developed as a single entry, multiple cross-reference data management and information retrieval system for the automation of Project office tasks, including engineering, financial, managerial, and clerical support. This volume, three of three, provides the instructions to operate the projects directorate information programs in data retrieval and file maintenance via the user friendly menu drivers.

  14. User's operating procedures. Volume 2: Scout project financial analysis program

    Science.gov (United States)

    Harris, C. G.; Haris, D. K.

    1985-01-01

    A review is presented of the user's operating procedures for the Scout Project Automatic Data system, called SPADS. SPADS is the result of the past seven years of software development on a Prime mini-computer located at the Scout Project Office, NASA Langley Research Center, Hampton, Virginia. SPADS was developed as a single entry, multiple cross-reference data management and information retrieval system for the automation of Project office tasks, including engineering, financial, managerial, and clerical support. This volume, two (2) of three (3), provides the instructions to operate the Scout Project Financial Analysis program in data retrieval and file maintenance via the user friendly menu drivers.

  15. Requirements for BNCT at a nuclear research reactor. Results from a BNCT workshop organized by the European Commission in Prague, November 2005

    International Nuclear Information System (INIS)

    Moss, Ray; Sauerwein, Wolfgang; Wittig, Andrea; Burian, Jiri

    2006-01-01

    As part of the European Commission's Enlargement and Integration Action (E and IA), which is intended to improve exchange and relationship within the extended European Union (EU), a Workshop was organized in Prague in November 2005. The purpose of the workshop was to present and discuss technical and organisational requirements in setting up a BNCT facility at a research reactor. Topics included: treatment of a patient by BNCT; organisational aspects and regulatory affairs; BNCT from the nuclear perspective and BNCT from the clinician's perspective. Presentations were given by BNCT experts in their particular field, whilst eleven different national nuclear research centres from the New Member States and Accession Countries, interested in developing a BNCT programme, presented the status of their preparations. The conclusions of the Workshop were that an early and close collaboration between nuclear and medical groups is the basis for BNCT, that a local effort to build a BNCT facility should be supported by a national research programme including basic and clinical science and that the JRC and its partners are ready to support national initiatives within the EU and candidate countries. (author)

  16. Boron neutron capture therapy (BNCT) inhibits tumor development from precancerous tissue: An experimental study that supports a potential new application of BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Monti Hughes, A.; Heber, E.M. [Department of Radiobiology, National Atomic Energy Commission (CNEA), Buenos Aires (Argentina); Pozzi, E. [Department of Radiobiology, National Atomic Energy Commission (CNEA), Buenos Aires (Argentina); Department of Research and Production Reactors, Ezeiza Atomic Center, CNEA, Buenos Aires (Argentina); Nigg, D.W. [Idaho National Laboratory, Idaho Falls, Idaho (United States); Calzetta, O.; Blaumann, H.; Longhino, J. [Department of Nuclear Engineering, Bariloche Atomic Center, CNEA, Rio Negro (Argentina); Nievas, S.I. [Department of Chemistry, CNEA, Buenos Aires (Argentina); Aromando, R.F. [Department of Oral Pathology, Faculty of Dentistry, University of Buenos Aires, Buenos Aires (Argentina); Itoiz, M.E. [Department of Radiobiology, National Atomic Energy Commission (CNEA), Buenos Aires (Argentina); Department of Oral Pathology, Faculty of Dentistry, University of Buenos Aires, Buenos Aires (Argentina); Trivillin, V.A. [Department of Radiobiology, National Atomic Energy Commission (CNEA), Buenos Aires (Argentina); Schwint, A.E. [Department of Radiobiology, National Atomic Energy Commission (CNEA), Buenos Aires (Argentina)], E-mail: schwint@cnea.gov.ar

    2009-07-15

    We previously demonstrated the efficacy of boron neutron capture therapy (BNCT) mediated by boronophenylalanine (BPA), GB-10 (Na{sub 2}{sup 10}B{sub 10}H{sub 10}) and (GB-10+BPA) to control tumors, with no normal tissue radiotoxicity, in the hamster cheek pouch oral cancer model. Herein we developed a novel experimental model of field-cancerization and precancerous lesions (globally termed herein precancerous tissue) in the hamster cheek pouch to explore the long-term potential inhibitory effect of the same BNCT protocols on the development of second primary tumors from precancerous tissue. Clinically, second primary tumor recurrences occur in field-cancerized tissue, causing therapeutic failure. We performed boron biodistribution studies followed by in vivo BNCT studies, with 8 months follow-up. All 3 BNCT protocols induced a statistically significant reduction in tumor development from precancerous tissue, reaching a maximum inhibition of 77-100%. The inhibitory effect of BPA-BNCT and (GB-10+BPA)-BNCT persisted at 51% at the end of follow-up (8 months), whereas for GB-10-BNCT it faded after 2 months. Likewise, beam-only elicited a significant but transient reduction in tumor development. No normal tissue radiotoxicity was observed. At 8 months post-treatment with BPA-BNCT or (GB-10+BPA)-BNCT, the precancerous pouches that did not develop tumors had regained the macroscopic and histological appearance of normal (non-cancerized) pouches. A potential new clinical application of BNCT would lie in its capacity to inhibit local regional recurrences.

  17. SERA -- An advanced treatment planning system for neutron therapy and BNCT

    International Nuclear Information System (INIS)

    Nigg, D.W.; Wemple, C.A.; Wessol, D.E.; Wheeler, F.J.; Albright, C.; Cohen, M.; Frandsen, M.; Harkin, G.; Rossmeier, M.

    1999-01-01

    Detailed treatment planning calculations on a patient-specific basis are required for boron neutron capture therapy (BNCT). Two integrated treatment planning systems developed specifically for BNCT have been in clinical use in the United States over the past few years. The MacNCTPLAN BNCT treatment planning system is used in the clinical BNCT trials that are underway at the Massachusetts Institute of Technology. A second system, BNCT rtpe (BNCT radiation therapy planning environment), developed independently by the Idaho national Engineering and Environmental Laboratory (INEEL) in collaboration with Montana State University (MSU), is used for treatment planning in the current series of BNCT clinical trials for glioblastoma at Brookhaven National Laboratory (BNL). This latter system is also licensed for use at several other BNCT research facilities worldwide. Although the currently available BNCT planning systems have served their purpose well, they suffer from somewhat long computation times (2 to 3 CPU-hours or more per field) relative to standard photon therapy planning software. This is largely due to the need for explicit three-dimensional solutions to the relevant transport equations. The simplifying approximations that work well for photon transport computations are not generally applicable to neutron transport computations. Greater computational speeds for BNCT treatment planning must therefore generally be achieved through the application of improved numerical techniques rather than by simplification of the governing equations. Recent efforts at INEEL and MSU have been directed toward this goal. This has resulted in a new paradigm for this type of calculation and the subsequent creation of the new simulation environment for radiotherapy applications (SERA) treatment planning system for BNCT. SERA is currently in initial clinical testing in connection with the trials at BNL, and it is expected to replace the present BNCT rtpe system upon general release

  18. Monte Carlo dose calculations for BNCT treatment of diffuse human lung tumours

    International Nuclear Information System (INIS)

    Altieri, S.; Bortolussi, S.; Bruschi, P.

    2006-01-01

    In order to test the possibility to apply BNCT in the core of diffuse lung tumours, dose distribution calculations were made. The simulations were performed with the Monte Carlo code MCNP.4c2, using the male computational phantom Adam, version 07/94. Volumes of interest were voxelized for the tally requests, and results were obtained for tissues with and without Boron. Different collimated neutron sources were tested in order to establish the proper energies, as well as single and multiple beams to maximize neutron flux uniformity inside the target organs. Flux and dose distributions are reported. The use of two opposite epithermal neutron collimated beams insures good levels of dose homogeneity inside the lungs, with a substantially lower radiation dose delivered to surrounding structures. (author)

  19. Nuclear engineering aspects of glioma BNCT research in Italy

    International Nuclear Information System (INIS)

    Curzio, G.; Mazzini, M.

    1998-01-01

    A research project on Boron Neutron Capture Therapy (BNCZ) of gliomas has been set up in Italy, with the participation of Departments of Oncology and Mechanical and Nuclear Construction (DCMN) of the University of Pisa, as well as the Neuroscience and Physics Departments of the Universities of Roma. The specific objective of DCMN Research Unit is the study of the physical-engineering aspects related to BNCT. The paper outlines the research lines in progress at DCMN: Monte Carlo calculations of neutron dose distribution for BNCT treatment planning; measurements of neutron fluxes, spectra and doses by neutron detectors specifically set up; design of modifications to the nuclear reactors of ENEA Casaccia Center. In particular, the paper emphasizes the most original contributions on dosimetric aspects, both from informatic and experimental points of view.(author)

  20. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP.

  1. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

    International Nuclear Information System (INIS)

    1979-12-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

  2. Improvement of neutron irradiation field of research reactors for BNCT

    International Nuclear Information System (INIS)

    Aizawa, Otohiko

    1992-01-01

    The modification of research reactors for an improvement of the irradiation field for BNCT has been investigated in comparison with the field characteristics of the 'old' configuration at the Musashi reactor. The new point of this study is that the evaluation has been done by using an arrangement including both the facility structure and a whole-body phantom, and also by considering the whole-body absorbed dose. (author)

  3. 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.

  4. Synthesis and evaluation of boronated folates for BNCT

    International Nuclear Information System (INIS)

    Shukla, S.; Sekido, M.; Guo, W.; Mueller, R.; Sudimack, J.; Lee, R.J.; Tjarks, W.; Adams, D.M.; Barth, R.F.

    2000-01-01

    To study the possible utilization of folic acid as the 10 B carrier for BNCT, folic acid conjugated boron containing liposomes and starburst dendrimers were prepared. In both systems folic acid was used as the recognition part and polyethylene glycol (PEG) as the spacer. In vitro studies were carried out using folate receptor overexpressing 24JK-FBP and KB cells. The results indicated that these boronated folic acid conjugates were incorporated into the tumor cells via receptor-mediated endocytosis. (author)

  5. 2.5 MeV CW 4-vane RFQ accelerator design for BNCT applications

    Science.gov (United States)

    Zhu, Xiaowen; Wang, Hu; Lu, Yuanrong; Wang, Zhi; Zhu, Kun; Zou, Yubin; Guo, Zhiyu

    2018-03-01

    Boron Neutron Capture Therapy (BNCT) promises a bright future in cancer therapy for its highly selective destruction of cancer cells, using the 10B +n→7Li +4 He reaction. It offers a more satisfactory therapeutic effect than traditional methods for the treatment of malignant brain tumors, head and neck cancer, melanoma, liver cancer and so on. A CW 4-vane RFQ, operating at 162.5 MHz, provides acceleration of a 20 mA proton beam to 2.5 MeV, bombarding a liquid lithium target for neutron production with a soft neutron energy spectrum. The fast neutron yield is about 1.73×1013 n/s. We preliminarily develop and optimize a beam shaping assembly design for the 7Li(p, n)7Be reaction with a 2.5 MeV proton beam. The epithermal neutron flux simulated at the beam port will reach up to 1 . 575 ×109 n/s/cm2. The beam dynamics design, simulation and benchmark for 2.5 MeV BNCT RFQ have been performed with both ParmteqM (V3.05) and Toutatis, with a transmission efficiency higher than 99.6% at 20 mA. To ease the thermal management in the CW RFQ operation, we adopt a modest inter-vane voltage design (U = 65 kV), though this does increase the accelerator length (reaching 5.2 m). Using the well-developed 3D electromagnetic codes, CST MWS and ANSYS HFSS, we are able to deal with the complexity of the BNCT RFQ, taking the contribution of each component in the RF volume into consideration. This allows us to optimize the longitudinal field distribution in a full-length model. Also, the parametric modeling technique is of great benefit to extensive modifications and simulations. In addition, the resonant frequency tuning of this RFQ is studied, giving the tuning sensitivities of vane channel and wall channel as -16.3 kHz/°C and 12.4 kHz/°C, respectively. Finally, both the multipacting level of this RFQ and multipacting suppressing in the coaxial coupler are investigated.

  6. A Tandem-electrostatic-quadrupole for accelerator-based BNCT

    International Nuclear Information System (INIS)

    Kreiner, A.J.; Kwan, J.W.; Burlon, A.A.; Di Paolo, H.; Henestroza, E.; Minsky, D.M.; Valda, A.A.; Debray, M.E.; Somacal, H.

    2007-01-01

    A project to develop a Tandem-electrostatic-quadrupole (TESQ) accelerator for accelerator-based boron neutron capture therapy (AB-BNCT) is described. A folded Tandem, with 1.25 MV terminal voltage, combined with an electrostatic quadrupole (ESQ) chain is being proposed. The project goal is a machine capable of delivering 30 mA of 2.5 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. This machine is conceptually shown to be capable of accelerating a 30 mA proton beam to 2.5 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. This electrostatic machine is the technologically simplest and cheapest solution for optimized AB-BNCT

  7. In vitro biological models in order to study BNCT

    International Nuclear Information System (INIS)

    Dagrosa, Maria A.; Kreimann, Erica L.; Schwint, Amanda E.; Juvenal, Guillermo J.; Pisarev, Mario A.; Farias, Silvia S.; Garavaglia, Ricardo N.; Batistoni, Daniel A.

    1999-01-01

    Undifferentiated thyroid carcinoma (UTC) lacks an effective treatment. Boron neutron capture therapy (BNCT) is based on the selective uptake of 10 B-boronated compounds by some tumours, followed by irradiation with an appropriate neutron beam. The radioactive boron originated ( 11 B) decays releasing 7 Li, gamma rays and alpha particles, and these latter will destroy the tumour. In order to explore the possibility of applying BNCT to UTC we have studied the biodistribution of BPA. In vitro studies: the uptake of p- 10 borophenylalanine (BPA) by the UTC cell line ARO, primary cultures of normal bovine thyroid cells (BT) and human follicular adenoma (FA) thyroid was studied. No difference in BPA uptake was observed between proliferating and quiescent ARO cells. The uptake by quiescent ARO, BT and FA showed that the ARO/BT and ARO/FA ratios were 4 and 5, respectively (p< 0.001). The present experimental results open the possibility of applying BNCT for the treatment of UTC. (author)

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

    International Nuclear Information System (INIS)

    Nakagawa, Yoshinobu; Kageji, Teruyoshi; Mizobuchi, Yoshifumi; Kumada, Hiroaki; Nakagawa, Yoshiaki

    2009-01-01

    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.

  9. Tandem-ESQ for accelerator-based BNCT

    International Nuclear Information System (INIS)

    Kreiner, A.J.; Burlon, A.A.; Di Paolo, H.; Minsky, D.M.; Valda, A.A.; Debray, M.E.; Somacal, H.R.; Kwan, J.W.; Henestroza, E.

    2006-01-01

    A project to develop a Tandem-ElectroStatic-Quadrupole (TESQ) accelerator for Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT) is described. A folded tandem, with 1.25 MV terminal voltage, combined with an ElectroStatic Quadrupole (ESQ) chain is being proposed. The project goal is a machine capable of delivering 30 mA of 2.5 MeV protons to be used in conjunction with a neutron production target based on the 7 Li(p,n) 7 Be reaction beyond its resonance at 2.25 MeV. This machine is conceptually shown to be capable of accelerating a 30 mA proton beam to 2.5 MeV. These are the specifications needed to produce sufficiently intense and clean epithermal neutron beams, based on the '7Li(p,n) 7 Be reaction, to perform BNCT treatment for deep-seated tumors in less than an hour. This electrostatic machine is the technologically simplest and cheapest solution for optimized AB-BNCT. (author)

  10. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume I. Program summary

    International Nuclear Information System (INIS)

    1980-06-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. The introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings, and recommendations. Each of Volumes II-VII reports on an individual assessment (Volumn II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

  11. Demonstration of the importance of a dedicated neutron beam monitoring system for BNCT facility

    International Nuclear Information System (INIS)

    Chao, Der-Sheng; Liu, Yuan-Hao; Jiang, Shiang-Huei

    2016-01-01

    The neutron beam monitoring system is indispensable to BNCT facility in order to achieve an accurate patient dose delivery. The neutron beam monitoring of a reactor-based BNCT (RB-BNCT) facility can be implemented through the instrumentation and control system of a reactor provided that the reactor power level remains constant during reactor operation. However, since the neutron flux in reactor core is highly correlative to complicated reactor kinetics resulting from such as fuel depletion, poison production, and control blade movement, some extent of variation may occur in the spatial distribution of neutron flux in reactor core. Therefore, a dedicated neutron beam monitoring system is needed to be installed in the vicinity of the beam path close to the beam exit of the RB-BNCT facility, where it can measure the BNCT beam intensity as closely as possible and be free from the influence of the objects present around the beam exit. In this study, in order to demonstrate the importance of a dedicated BNCT neutron beam monitoring system, the signals originating from the two in-core neutron detectors installed at THOR were extracted and compared with the three dedicated neutron beam monitors of the THOR BNCT facility. The correlation of the readings between the in-core neutron detectors and the BNCT neutron beam monitors was established to evaluate the improvable quality of the beam intensity measurement inferred by the in-core neutron detectors. In 29 sampled intervals within 16 days of measurement, the fluctuations in the mean value of the normalized ratios between readings of the three BNCT neutron beam monitors lay within 0.2%. However, the normalized ratios of readings of the two in-core neutron detectors to one of the BNCT neutron beam monitors show great fluctuations of 5.9% and 17.5%, respectively. - Highlights: • Two in-core neutron detectors and three BNCT neutron beam monitors were compared. • BNCT neutron beam monitors improve the stability in neutron

  12. Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

  13. 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.

  14. Fatal carotid blowout syndrome after BNCT for head and neck cancers

    International Nuclear Information System (INIS)

    Aihara, T.; Hiratsuka, J.; Ishikawa, H.; Kumada, H.; Ohnishi, K.; Kamitani, N.; Suzuki, M.; Sakurai, H.; Harada, T.

    2015-01-01

    Boron neutron capture therapy (BNCT) is high linear energy transfer (LET) radiation and tumor-selective radiation that does not cause serious damage to the surrounding normal tissues. BNCT might be effective and safe in patients with inoperable, locally advanced head and neck cancers, even those that recur at previously irradiated sites. However, carotid blowout syndrome (CBS) is a lethal complication resulting from malignant invasion of the carotid artery (CA); thus, the risk of CBS should be carefully assessed in patients with risk factors for CBS after BNCT. Thirty-three patients in our institution who underwent BNCT were analyzed. Two patients developed CBS and experienced widespread skin invasion and recurrence close to the carotid artery after irradiation. Careful attention should be paid to the occurrence of CBS if the tumor is located adjacent to the carotid artery. The presence of skin invasion from recurrent lesions after irradiation is an ominous sign of CBS onset and lethal consequences. - Highlights: • This study is fatal carotid blowout syndrome after BNCT for head and neck cancers. • Thirty-three patients in our institution who underwent BNCT were analyzed. • Two patients (2/33) developed CBS. • The presence of skin invasion from recurrent lesions after irradiation is an ominous sign of CBS. • We must be aware of these signs to perform BNCT safely.

  15. 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.

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

    International Nuclear Information System (INIS)

    Chadha, M.

    1996-01-01

    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

  17. Summaries on various researches aiming at the closed head BNCT

    International Nuclear Information System (INIS)

    Ono, Koji

    2000-01-01

    As in the boron neutron capture therapy (BNCT) flight of alpha particle formed by reaction of neutron and boron is nearly equal to diameter of cancer cell, when a boron compound accumulates selectively to a cancer cell to be radiated onto the cell by enough amount of neutron beam the alpha particles are irradiated onto the cancer cells nearly selectively. Like this, this is a curing means capable of overcoming a problem undecidable by a paradigm of radiation remedy in the 20th Century, a micro dose amount effect supposing to be a paradigm in the 21st Century, the very (biological) dose concentration into cancer cell is a curing method matching to upgrading on rate of cancer control and improvement on post-cure of the patients without increase of subreaction in every tumors. Here were summarized on characteristic comparison of thermal outer-neutron beams in KUR, JRR-4 and the Peten HFR reactors, development of new boron compounds, effect of BNCT on re-oxygenation of the cancer, and induction of mutation by neutron beam. (G.K.)

  18. Boron dose determination for BNCT using Fricke and EPR dosimetry

    International Nuclear Information System (INIS)

    Wielopolski, L.; Ciesielski, B.

    1995-01-01

    In Boron Neutron Capture Therapy (BNCT) the dominant dose delivered to the tumor is due to α and 7 Li charged particles resulting from a neutron capture by 10 B and is referred to herein as the boron dose. Boron dose is directly attributable to the following two independent factors, one boron concentration and the neutron capture energy dependent cross section of boron, and two the energy spectrum of the neutrons that interact with boron. The neutron energy distribution at a given point is dictated by the incident neutron energy distribution, the depth in tissue, geometrical factors such as beam size and patient's dimensions. To account for these factors can be accommodated by using Monte Carlo theoretical simulations. However, in conventional experimental BNCT dosimetry, e.g., using TLDs or ionization chambers, it is only possible to estimate the boron dose. To overcome some of the limitations in the conventional dosimetry, modifications in ferrous sulfate dosimetry (Fricke) and Electron Paramagnetic Resonance (EPR) dosimetry in alanine, enable to measure specifically boron dose in a mixed gamma neutron radiation fields. The boron dose, in either of the dosimeters, is obtained as a difference between measurements with boronated and unboronated dosimeters. Since boron participates directly in the measurements, the boron dosimetry reflects the true contribution, integral of the neutron energy spectrum with boron cross section, of the boron dose to the total dose. Both methods are well established and used extensively in dosimetry, they are presented briefly here

  19. Simulation model for wind energy storage systems. Volume III. Program descriptions. [SIMWEST CODE

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume III, the SIMWEST program description contains program descriptions, flow charts and program listings for the SIMWEST Model Generation Program, the Simulation program, the File Maintenance program and the Printer Plotter program. Volume III generally would not be required by SIMWEST user.

  20. After-School Academic Enrichment Programs. Information Capsule. Volume 1509

    Science.gov (United States)

    Blazer, Christie

    2016-01-01

    The number of U.S. children attending after-school programs has been steadily increasing. In 2014, the most recent year for which data were available, approximately 10.2 million students, representing about 23 percent of U.S. families, were enrolled in an after-school program. Of the students attending after-school programs, the majority do so at…

  1. Clean Coal Technology Programs: Completed Projects (Volume 2)

    Energy Technology Data Exchange (ETDEWEB)

    Assistant Secretary for Fossil Energy

    2003-12-01

    Annual report on the Clean Coal Technology Demonstration Program (CCTDP), Power Plant Improvement Initiative (PPII), and Clean Coal Power Initiative (CCPI). The report addresses the roles of the programs, implementation, funding and costs, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

  2. Gene transfer-applied BNCT (g-BNCT) for amelanotic melanoma in brain. Further upregulation of 10B uptake by cell modulation

    International Nuclear Information System (INIS)

    Iwakura, M.; Tamaki, N.; Hiratsuka, J.

    2000-01-01

    Our success in eradicating melanoma by single BNCT with BPA led to the next urgent theme, i.e. application of such BNCT for currently uncurable melanoma metastasis in brain. In order to establish 10 B-BPA-BNCT for melanoma in brain, we have investigated the pharmacokinetics of BPA which is most critical factor for successful BNCT, in melanotic and amelanotic and further tyrosinase gene-transfected amelanotic melanoma proliferating in brain having blood-brain-barrier, as compared to melanoma proliferating in skin. We have established three implanted models for melanoma in brain: 1) A1059 cells, amelanotic melanoma, 2) B16B15b cells, melanotic melanoma cells, highly metastatic to brain, and 3) TA1059 cells, with active melanogenesis induced by tyrosinase gene transfection. We would like to report the results of comparative analysis of the BPA uptake ability in these melanoma cells in both brain and skin. Based on these findings, we are further investigating to enhance 10 B-BPA uptake by not only g-BNCT but also by additional melanogenesis upregulating cell modulation. (author)

  3. Feasibility study to develop BNCT facility at the Indonesian research reactor

    International Nuclear Information System (INIS)

    Hastowo, H.

    2001-01-01

    A survey on the Indonesian research reactors and its supporting facilities has been done in order to check the possibility to install BNCT facility. Oncologists from several hospitals have been informing about the BNCT treatment for tumours and they give a positive response to support utilisation of the BNCT facility. Several aspects required to support the BNCT treatment have also been identified and related activities on that matter soon will be initiated. The interim result in our survey indicated that utilisation of the 30 MW Multipurpose reactor would not be possible from the technical point of view. Further study will be concentrated on the TRIGA reactor and an epithermal neutron beam facility at the thermal column of this reactor will be designed for further work. (author)

  4. Successful BNCT for patients with cutaneous and mucosal melanomas. Report of 4 cases

    International Nuclear Information System (INIS)

    Morita, Norimasa; Hiratsuka, Junichi; Kuwabara, Chiaki; Aihara, Teruhito; Harada, Tamotsu; Imajo, Yoshinari; Ono, Koji; Fukuda, Hiroshi; Kumada, Hiroaki

    2006-01-01

    Since 2003 we have conducted BNCT clinical trials on melanomas at the Kyoto University Research Reactor (KUR) and Japan Research Reactor No.4 (JRR-4). We report 4 patients given BNCT for malignant melanomas: 2 with superficial spreading types on the heel, 1 with mucosal melanoma in the nasal cavity, and 1 with a melanoma on the vulva and in the vagina. The two cutaneous melanomas and the nasal cavity mucosal melanoma showed a complete response (CR) by 6 months after BNCT. The residual melanoma showed a partial response (PR) by 3 months after treatment and no regrowth since then. Although two patients experienced normal-tissue damage that exceeded the tolerance level, all the participants were cured within a few months of treatment. BNCT was shown to be a promising treatment for mucosal, as well as for cutaneous, melanomas. (author)

  5. Development of breast cancer irradiation technique for BNCT at JRR-4

    International Nuclear Information System (INIS)

    Nakamura, Takemi; Horiguchi, Hironori; Arai, Masaji; Yanagie, Hironobu

    2014-06-01

    In the Department of Research Reactor and Tandem Accelerator, developments of irradiation technique with application enlargement for breast cancer on BNCT have been performed in the second medium term plans. We compiled this report about the technological development to solve several problems with the irradiation of breast cancer in the medical irradiation facility of JRR-4. In the present study, design fabrication of a collimator for breast cancer, dose evaluation analysis by clinical model, investigation of dose enhancement at deeper region and investigation of fixing method for breast cancer irradiation were studied. By these evaluation results, we verified that the developed breast cancer irradiation technique can be applied to BNCT medical irradiation of JRR-4. These results are expected to be able to contribute to breast cancer irradiation techniques of other reactor-based BNCT and future accelerator-based BNCT. (author)

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

    International Nuclear Information System (INIS)

    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. Alpha-amino alcohol of para-boronophenylalanine, BPAol, as a potential boron carrier for BNCT

    International Nuclear Information System (INIS)

    Takagaki, M.; Ono, K.; Masunaga, S.; Kinashi, Y.

    2000-01-01

    α amino alcohol of boronophenylalanine BPAol in which -COOH group is replaced with hydrophilic group of -OH of p-boronophenylalanine (BPA) has been synthesized and its BNCT effect on experimental tumor models have been investigated. Tumor cell killing effect of BPAol on C6 gliosarcoma cells was very high 4.4 times as that of BPA, since it was actively accumulated into tumor cells in 4-5 times as that of BPA. Carboxylic group of BPA might not play as an essential role in uptake of BPA into tumor cells. BPAol-based BNCT strongly inhibited the tumor growth of Green's melanotic melanoma hamsters even under therapeutic dose of BPA-based BNCT. These preliminary findings strongly warrant further extensive pre-clinical study for BPAol as a boron carrier for BNCT. (author)

  8. Fusion Engineering Device. Volume 1. Mission and program summary

    International Nuclear Information System (INIS)

    1981-10-01

    This volume presents, in summary form, a recommended approach to implementing the Magnetic Fusion Energy Engineering Act of 1980. These recommendations constitute the findings of the FED Technical Management Board (TMB). The TMB and the affiliated technical managers gave particular scrutiny to elucidating the role of FED in fusion development and to defining the device mission

  9. SU-E-J-100: Reconstruction of Prompt Gamma Ray Three Dimensional SPECT Image From Boron Neutron Capture Therapy(BNCT)

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, D; Jung, J; Suh, T [The Catholic University of Korea, College of medicine, Department of biomedical engineering (Korea, Republic of)

    2014-06-01

    Purpose: Purpose of paper is to confirm the feasibility of acquisition of three dimensional single photon emission computed tomography (SPECT) image from boron neutron capture therapy (BNCT) using Monte Carlo simulation. Methods: In case of simulation, the pixelated SPECT detector, collimator and phantom were simulated using Monte Carlo n particle extended (MCNPX) simulation tool. A thermal neutron source (<1 eV) was used to react with the boron uptake region (BUR) in the phantom. Each geometry had a spherical pattern, and three different BURs (A, B and C region, density: 2.08 g/cm3) were located in the middle of the brain phantom. The data from 128 projections for each sorting process were used to achieve image reconstruction. The ordered subset expectation maximization (OSEM) reconstruction algorithm was used to obtain a tomographic image with eight subsets and five iterations. The receiver operating characteristic (ROC) curve analysis was used to evaluate the geometric accuracy of reconstructed image. Results: The OSEM image was compared with the original phantom pattern image. The area under the curve (AUC) was calculated as the gross area under each ROC curve. The three calculated AUC values were 0.738 (A region), 0.623 (B region), and 0.817 (C region). The differences between length of centers of two boron regions and distance of maximum count points were 0.3 cm, 1.6 cm and 1.4 cm. Conclusion: The possibility of extracting a 3D BNCT SPECT image was confirmed using the Monte Carlo simulation and OSEM algorithm. The prospects for obtaining an actual BNCT SPECT image were estimated from the quality of the simulated image and the simulation conditions. When multiple tumor region should be treated using the BNCT, a reasonable model to determine how many useful images can be obtained from the SPECT could be provided to the BNCT facilities. This research was supported by the Leading Foreign Research Institute Recruitment Program through the National Research

  10. Physics of epi-thermal boron neutron capture therapy (epi-thermal BNCT).

    Science.gov (United States)

    Seki, Ryoichi; Wakisaka, Yushi; Morimoto, Nami; Takashina, Masaaki; Koizumi, Masahiko; Toki, Hiroshi; Fukuda, Mitsuhiro

    2017-12-01

    The physics of epi-thermal neutrons in the human body is discussed in the effort to clarify the nature of the unique radiologic properties of boron neutron capture therapy (BNCT). This discussion leads to the computational method of Monte Carlo simulation in BNCT. The method is discussed through two examples based on model phantoms. The physics is kept at an introductory level in the discussion in this tutorial review.

  11. A survey of electric and hybrid vehicles simulation programs. Volume 2: Questionnaire responses

    Science.gov (United States)

    Bevan, J.; Heimburger, D. A.; Metcalfe, M. A.

    1978-01-01

    The data received in a survey conducted within the United States to determine the extent of development and capabilities of automotive performance simulation programs suitable for electric and hybrid vehicle studies are presented. The survey was conducted for the Department of Energy by NASA's Jet Propulsion Laboratory. Volume 1 of this report summarizes and discusses the results contained in Volume 2.

  12. Proceedings of the 1995 U.S. DOE hydrogen program review, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This document containes reports from the proceedings of the 1995 U.S. DOE hydrogen program review. Reports are organized under the topics of systems analysis, utilization, storage, and production. This volume, Volume I, contains the reports concerned with systems analysis and utilization. Individual reports were processed separately for the DOE data bases.

  13. Summer Food Service Program. Nourishing News. Volume 3, Issue 8

    Science.gov (United States)

    Idaho State Department of Education, 2009

    2009-01-01

    The primary goal of the Summer Food Service Program (SFSP) is to provide nutritious meals to children in low-income areas when school is not in session. This issue of "Nourishing News" focuses on SFSPs. The articles contained in this issue are: (1) Is Your Summer Food Program Financially Fit? (Jean Zaske); (2) Keeping the…

  14. Perspectives in Peer Programs. Volume 28, Number 1, Winter 2018

    Science.gov (United States)

    Tindall, Judith, Ed.; Black, David R., Ed.; Routson, Sue, Ed.

    2018-01-01

    This issue of "Perspectives in Peer Programs," the official journal of the National Association of Peer Program Professionals (NAPP), includes: (1) Introduction to this Issue on NAPPP Programmatic Standards Checklist, Programmatic Standards, Ethics, and Rubric; (2) NAPPP Programmatic Standards Checklist; (3) NAPPP Programmatic Standards;…

  15. Super Efficient Refrigerator Program (SERP) evaluation. Volume 1: Process evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Sandahl, L.J.; Ledbetter, M.R.; Chin, R.I.; Lewis, K.S.; Norling, J.M.

    1996-01-01

    The Pacific Northwest National Laboratory (PNNL) conducted this study for the US Department of Energy (DOE) as part of the Super Efficient Refrigerator Program (SERP) Evaluation. This report documents the SERP formation and implementation process, and identifies preliminary program administration and implementation issues. The findings are based primarily on interviews with those familiar with the program, such as utilities, appliance manufacturers, and SERP administrators. These interviews occurred primarily between March and April 1995, when SERP was in the early stages of program implementation. A forthcoming report will estimate the preliminary impacts of SERP within the industry and marketplace. Both studies were funded by DOE at the request of SERP Inc., which sought a third-party evaluation of its program.

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

    International Nuclear Information System (INIS)

    Capala, J.; Diaz, A.Z.; Chadha, M.

    1997-01-01

    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

  17. 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.

  18. Resource Programs : Draft Environmental Impact Statement, Volume 2, Appendices.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-03-01

    Every two years, Bonneville Power Administration (BPA) prepares a Resource Program which identifies the resource actions BPA will take to meet its obligation to serve the forecasted power requirements of its customers. The Resource Program`s Environmental Impact Statement (RPEIS) is a programmatic environmental document which will support decisions made in several future Resource Programs. Environmental documents tiered to the EIS may be prepared on a site-specific basis. The RPEIS includes a description of the environmental effects and mitigation for the various resource types available in order to evaluate the trade-offs among them. It also assesses the environmental impacts of adding thirteen alternative combinations of resources to the existing power system. This report contains the appendices to the RPEIS.

  19. Aquatic Plant Control Research Program. Volume A-00-1

    National Research Council Canada - National Science Library

    Kirk, James

    2000-01-01

    ... at the Waterways Experiment Station. It is principally intended to be a forum whereby information pertaining to and resulting from the Corps of Engineers' nationwide Aquatic Plant Control Research Program (APCRP...

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

    International Nuclear Information System (INIS)

    Mancuso, C.A.

    1995-01-01

    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

  1. Workshop on the Suborbital Science Sounding Rocket Program, Volume 1

    Science.gov (United States)

    1991-01-01

    The unique characteristics of the sounding rocket program is described, with its importance to space science stressed, especially in providing UARS correlative measurements. The program provided opportunities to do innovative scientific studies in regions not other wise accessible; it was a testbed for developing new technologies; and its key attributes were flexibility, reliability, and economy. The proceedings of the workshop are presented in viewgraph form, including the objectives of the workshop and the workshop agenda.

  2. SOLTECH 92 proceedings: Solar Process Heat Program. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1992-03-01

    This document is a limited Proceedings, documenting the presentations given at the symposia conducted by the US Department of Energy`s (DOE) Solar Industrial Program and Solar Thermal Electrical Program at SOLTECH92. The SOLTECH92 national solar energy conference was held in Albuquerque, New Mexico during the period February 17--20, 1992. The National Renewable Energy Laboratory manages the Solar Industrial Program; Sandia National Laboratories (Albuquerque) manages the Solar Thermal Electric Program. The symposia sessions were as follows: (1) Solar Industrial Program and Solar Thermal Electric Program Overviews, (2) Solar Process Heat Applications, (3) Solar Decontamination of Water and Soil; (4) Solar Building Technologies, (5) Solar Thermal Electric Systems, (6) PV Applications and Technologies. For each presentation given in these symposia, these Proceedings provide a one- to two-page abstract and copies of the viewgraphs and/or 35mm slides utilized by the speaker. Some speakers provided additional materials in the interest of completeness. The materials presented in this document were not subjected to a peer review process.

  3. Load monitoring program: Status and results report. Volume 1: Summary

    International Nuclear Information System (INIS)

    1994-06-01

    British Columbia Hydro conducts a monitoring program to provide information on customer needs and values for planning; to measure customer response, energy savings impacts, and load shape impacts due to changes in rate level, rate restructuring, and Power Smart programs; to estimate end-use consumption and load shapes by customer class; and to provide load information for distribution and system load studies. To achieve these objectives, the monitoring program tracks the characteristics and energy use patterns of a sample of BC Hydro residential, commercial, and industrial customers over a period of several years. The entire sample will be surveyed periodically to obtain information on changes in building characteristics, equipment stocks, and energy-use behavior and attitudes. A report is provided on the status of monitoring program activities and some results obtained in 1993/94. For the residential sector, the results include typical load profiles, end-user demographics, and extent of electric space heating and water heating. In the commercial sector, customers were divided into two main groups. The large-building group was relatively well organized in terms of energy needs and participated in Power Smart programs. The small-building group was relatively energy-inefficient and relatively unaware of Power Smart programs. 43 figs., 15 tabs

  4. SOLTECH 1992 proceedings: Solar Process Heat Program, volume 1

    Science.gov (United States)

    1992-03-01

    This document is a limited Proceedings, documenting the presentations given at the symposia conducted by the U.S. Department of Energy's (DOE) Solar Industrial Program and Solar Thermal Electrical Program at SOLTECH92. The SOLTECH92 national solar energy conference was held in Albuquerque, New Mexico during the period February 17-20, 1992. The National Renewable Energy Laboratory manages the Solar Industrial Program; Sandia National Laboratories (Albuquerque) manages the Solar Thermal Electric Program. The symposia sessions were as follows: (1) Solar Industrial Program and Solar Thermal Electric Program Overviews, (2) Solar Process Heat Applications, (3) Solar Decontamination of Water and Soil, (4) Solar Building Technologies, (5) Solar Thermal Electric Systems, and (6) Photovoltaic (PV) Applications and Technologies. For each presentation given in these symposia, these Proceedings provide a one- to two-page abstract and copies of the viewgraphs and/or 35 mm slides utilized by the speaker. Some speakers provided additional materials in the interest of completeness. The materials presented in this document were not subjected to a peer review process.

  5. MOD-5A wind turbine generator program design report: Volume 1: Executive Summary

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator covering work performed between July 1980 and June 1984 is discussed. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 1, the Executive Summary, summarizes all phases of the MOD-5A program. The performance and cost of energy generated by the MOD-5A are presented. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation, power generation, and control and instrumentation subsystems - is described briefly. The early phases of the MOD-5A program, during which the design was analyzed and optimized, and new technologies and materials were developed, are discussed. Manufacturing, quality assurance, and safety plans are presented. The volume concludes with an index of volumes 2 and 3.

  6. Hydride heat pump. Volume I. Users manual for HYCSOS system design program. [HYCSOS code

    Energy Technology Data Exchange (ETDEWEB)

    Gorman, R.; Moritz, P.

    1978-05-01

    A method for the design and costing of a metal hydride heat pump for residential use and a computer program, HYCSOS, which automates that method are described. The system analyzed is one in which a metal hydride heat pump can provide space heating and space cooling powered by energy from solar collectors and electric power generated from solar energy. The principles and basic design of the system are presented, and the computer program is described giving detailed design and performance equations used in the program. The operation of the program is explained, and a sample run is presented. This computer program is part of an effort to design, cost, and evaluate a hydride heat pump for residential use. The computer program is written in standard Fortran IV and was run on a CDC Cyber 74 and Cyber 174 computer. A listing of the program is included as an appendix. This report is Volume 1 of a two-volume document.

  7. ALBEMO, a program for the calculation of the radiation transport in void volumes with reflecting walls

    International Nuclear Information System (INIS)

    Mueller, K.; Vossebrecker, H.

    The Monte Carlo Program ALBEMO calculates the distribution of neutrons and gamma rays in void volumes which are bounded by reflecting walls with x, y, z coordinates. The program is based on the albedo method. The effect of significant simplifying assumptions is investigated. Comparisons with experiments show satisfying agreement

  8. A logical approach to determine a waste segregation/volume reduction program

    International Nuclear Information System (INIS)

    Shriner, G.D.; Carmel, P.G.; Shimmura, H.

    1986-01-01

    This paper discusses advantages and disadvantages of hand sorting versus use of automated radioactive waste segregation monitors and makes an analysis of costs/versus benefits based on volume with time. Many programs to be employed to prevent unnecessary waste generation with little or no additional cost to the power plant. Parameters needed to perform a cost analysis and methods used to obtain them are discussed. Recommendations on use of vendor-supplied services for segregation, volume reduction, and decontamination are given. The data provided will enable the selection of a program(s) to benefit the individual user's requirements

  9. Boron Neutron Capture Therapy (BNCT) in an experimental model of lung metastases in BDIX rats

    International Nuclear Information System (INIS)

    Trivillin, V.A.; Garabalino, M.A.; Colombo, L.L.

    2013-01-01

    Boron Neutron Capture Therapy (BNCT) in an experimental model of lung metastases in BDIX rats Introduction: Boron Neutron Capture Therapy (BNCT) is based on selective tumor uptake of boron compounds, followed by neutron irradiation. BNCT was proposed for the treatment of unresectable, diffuse lung metastases. The aim of the present study was to perform BNCT studies in an experimental model of lung metastases. Materials and Methods: 3 x 106/0.5 ml colon carcinoma cells (DHD/K12/TRb) were injected iv in syngeneic BDIX rats. Three weeks post-inoculation, rats with diffuse lung metastases were used for in vivo BNCT studies in the RA-3 Nuclear Reactor. Based on previous biodistribution studies and computational dosimetry with Monte Carlo simulation, 2 doses were prescribed, i.e. 4 Gy and 8 Gy minimum absorbed dose to tumor. The animals were assigned to 5 experimental groups (n= 4 to 8) at each dose level: T0 (euthanized pre-treatment), BPA-BNCT, Comb-BNCT (BPA+GB-10), Beam only (background dose) and Sham (same manipulation, no treatment). Boron concentration was measured in a blood sample taken pre-irradiation to verify that the value was in the range established in previous biodistribution studies. The animals were followed clinically for 2 weeks after neutron irradiation and then euthanized to assess the response of tumor and normal lung, macroscopically and histologically. To date we have evaluated the end-point weight of lung (normal lung + metastases) and % lung weight/body weight as an indicator of tumor growth. Results: The statistical analysis (ANOVA) of % lung weight/body weight showed statistically significant differences (p<0.05) between groups T0 (0.79 ± 0.38) and Sham (1.87 ± 0.91). No statistically significant differences were observed between the Beam only groups (at both dose levels) and Sham. Similar and statistically significant tumor control was induced in the groups BPA-BNCT Low dose (LD) (0.56 ± 0.11), BPA-BNCT High dose (HD) (0.80 ± 0.16), Comb-BNCT

  10. First clinical results on the finnish study on BPA-mediated BNCT in glioblastoma

    International Nuclear Information System (INIS)

    Kankaanranta, L.; Seppaelae, T.; Kallio, M.

    2000-01-01

    An open phase I dose-escalation boron neutron capture therapy (BNCT) study on glioblastoma multiforme (GBM) was initiated at the BNCT facility FiR 1, Espoo, Finland, in May 1999. The aim of the study is to investigate the safety of boronophenylalanine (BPA)-mediated BNCT. Ten GBM patients were treated with a 2-field treatment plan using one fraction. BPA-F was used as the 10 B carrier infused as a fructose solution 290 mg BPA/kg over 2-hours prior to irradiation with epithermal neutrons. Average doses to the normal brain, contrast enhancing tumour, and the target ranged from 3.0 to 5.6 Gy (W), from 35.1 to 66.7 Gy (W), and from 29.6 to 53.6 Gy (W), respectively. BNCT was associated with acceptable toxicity. The median follow-up is 9 months (range, 3 to 16 months) post diagnosis in July 2000. Seven of the 10 patients have recurrent or persistent GBM, and the median time to progression is 8 months. Only one patient has died, and the estimated 1-year overall survival is 86%. Five of the recurrent tumours were treated with external beam photon radiation therapy to the total dose of 30-40 Gy with few acute side-effects. These preliminary findings suggest that acute toxicity of BPA-mediated BNCT is acceptable when average brain doses of 5.6 Gy (W) or less are used. The followup time is too short to evaluate survival, but the estimated 1-year survival of 86% achieved with BNCT followed by conventional photon irradiation at the time of tumour progression is encouraging and emphasises the need of further investigation of BPA-mediated BNCT. (author)

  11. URSULA2 computer program. Volume 3. User's manual. Final report

    International Nuclear Information System (INIS)

    Singhal, A.K.

    1980-01-01

    This report is intended to provide documentation for the users of the URSULA2 code so that they can appreciate its important features such as: code structure, flow chart, grid notations, coding style, usage of secondary storage and its interconnection with the input preparation program (Reference H3201/4). Subroutines and subprograms have been divided into four functional groups. The functions of all subroutines have been explained with particular emphasis on the control subroutine (MAIN) and the data input subroutine (BLOCK DATA). Computations for the flow situations similar to the reference case can be performed simply by making alterations in BLOCK DATA. Separate guides for the preparation of input data and for the interpretation of program output have been provided. Furthermore, two appendices; one for the URSULA2 listing and the second for the glossary of FORTRAN variables, are included to make this report self-sufficient

  12. USAF/SCEEE Summer Faculty Research Program (1979). Volume 2

    Science.gov (United States)

    1979-12-01

    K. Schwarzschild , Math. Phys, Kiasse, Grottingen Nachrichten, p. 41 (1906). . 28-21 I -. 4; 1979 USAF - SCEEE SUMMER FACULTY RESEARCH PROGRAM...Wollam, 1968, p. 57. 22. Richard H. Hall, Organizations Structure and Process (New Jersey: Prentice-Hall, Inc., 2nd ed., 1978). 23. Karl E. Weick, The...The Analysis of the U.S. Army Aircraft Maintenance System, Battelle Memorial Institute, 1970. (AD703839) Weick, Karl E. The Social Psychology of

  13. Liquid Metal Fast Breeder Reactor program. Volume IV. Environmental statement

    International Nuclear Information System (INIS)

    1974-12-01

    A broad overview is presented of the many implications of LMFBR program implementation, up to and encompassing a fully developed LMFBR power plant economy, including the secondary impacts, the unavoidable adverse environmental impacts, cumulative environmental impacts, and cost-benefit analyses, and alternative energy strategies. Under the heading of secondary impacts, the national implications of the availability of electricity from LMFBRs, and the specific economic impacts of the LMFBR program are examined. The currently feasible alternatives and potential future alternatives for mitigating adverse environmental impacts of the LMFBR fuel cycle are described. The problems of safeguarding special nuclear material from potential diversion to unauthorized purposes are analyzed. The cumulative environmental effects of LMFBR operation to the Year 2020, the decommissioning of LMFBRs and fuel cycle facilities upon the completion of their useful life, the irreversible and irretrievable commitments of resources that will accompany implementation of an LMFBR economy, and an analysis of the costs and benefits of implementing the LMFBR Program are included. (U.S.)

  14. Dosimetric study of varying aperture-surface distance at the Finnish BNCT facility

    International Nuclear Information System (INIS)

    Uusi-Simola, Jouni; Seppaelae, Tiina; Nieminen, Katja; Kotiluoto, Petri; Seren, Tom; Auterinen, Iiro; Kortesniemi, Mika; Savolainen, Sauli

    2006-01-01

    Comparison of experimental and calculated dosimetric values in a water phantom was performed at the Finnish BNCT facility at the FiR 1 research reactor. The purpose was to study the effect of changing aperture to surface distance (ASD) to radiation dose and to verify the accuracy of the treatment planning and to provide data for comparison of the methods. A magnesium ionisation chamber flushed with argon gas was used to measure absorbed photon dose rate. Diluted manganese (Mn) and gold (Au) foils and Mn wires were used to determine Mn and Au activation reaction rates. Computer simulations with both SERA and MCNP programs were used to independently calculate the corresponding values. Photon dose and activation reaction rate depth profiles at beam central axis an axial profiles at 2.5 and 6 cm depths were measured and calculated for 11 and 14 and 17 cm diameter apertures. Depth profiles for activation reaction rates were determined for the clinically used 11 and 14 cm diameter apertures for 0, 5, and 10 cm ASD. In addition, the optional 17 cm beam was characterised at 0 and 5 cm ASD. The beam intensity decreases by approximately 20% and 40% when ASD is increased to 5 cm or 10 cm, respectively. The shape of the 55 Mn activation reaction rate depth profile and photon depth radial profile did not vary more than 5% for the 14 cm beam when the ASD was increased from 0 cm to 10 cm. (author)

  15. Aircraft Configuration Noise Reduction. Volume 3. Computer Program Source Listing

    Science.gov (United States)

    1976-06-01

    BANOS.ABU( . C BCF = THE ARRAY OF BAND CEN\\TER FRECUENCIES. AbSOKP I b C T =AMBIENT TEMPERATURE IN’ DEGREES FARENHEIT ABSUtRP 17 C AdSOt(P 18 C OUTPUT...C 1) ARGUMENT (XI REMAINS IUCHANGEC LFI .7 C 2) NO CTHER SUbPROGRAMS REQLIRED C ER STANDARC FORTRAN IV LIbkARY. CFI 28 c 3) ABSOLUTE ERROR IS LESS...MINOR AND MAJOR INDEX CCLtNTERS CORSP. 76 14 NRN = 1 CfjRSPL 7S ICI = 1B129NCOF) CORSPL 8C IF (IGO .GT. 1) GO TO 105 CORSPL 81 C CORSPL 82 C ZERO CUT

  16. User's operating procedures. Volume 1: Scout project information programs

    Science.gov (United States)

    Harris, C. G.; Harris, D. K.

    1985-01-01

    A review of the user's operating procedures for the Scout Project Automatic Data System, called SPADS is given. SPADS is the result of the past seven years of software development on a Prime minicomputer located at the Scout Project Office. SPADS was developed as a single entry, multiple cross reference data management and information retrieval system for the automation of Project office tasks, including engineering, financial, managerial, and clerical support. The instructions to operate the Scout Project Information programs in data retrieval and file maintenance via the user friendly menu drivers is presented.

  17. Energy extension service pilot program evaluation report: the first year. Volume II: pilot state reports

    Energy Technology Data Exchange (ETDEWEB)

    1979-09-01

    Volume II of the Energy Extension Service Evaluation presents a discussion of the operations of the ten EES pilot-state programs during the period from October 1, 1977 through September 30, 1978. Each of the ten pilot states - Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming - received a grant of approximately $1.1 million to develop and implement a 19-month program beginning on October 1, 1977. Volume II provides a case-study description of the operations of the pilot program in each state, with special attention given to the two programs selected in each state for more detailed study and survey research. Some survey data and analysis are presented for the emphasis programs.

  18. Stirling Space Engine Program. Volume 1; Final Report

    Science.gov (United States)

    Dhar, Manmohan

    1999-01-01

    The objective of this program was to develop the technology necessary for operating Stirling power converters in a space environment and to demonstrate this technology in full-scale engine tests. Hardware development focused on the Component Test Power Converter (CTPC), a single cylinder, 12.5-kWe engine. Design parameters for the CTPC were 150 bar operating pressure, 70 Hz frequency, and hot-and cold-end temperatures of 1050 K and 525 K, respectively. The CTPC was also designed for integration with an annular sodium heat pipe at the hot end, which incorporated a unique "Starfish" heater head that eliminated highly stressed brazed or weld joints exposed to liquid metal and used a shaped-tubed electrochemical milling process to achieve precise positional tolerances. Selection of materials that could withstand high operating temperatures with long life were another focus. Significant progress was made in the heater head (Udimet 700 and Inconel 718 and a sodium-filled heat pipe); the alternator (polyimide-coated wire with polyimide adhesive between turns and a polyimide-impregnated fiberglass overwrap and samarium cobalt magnets); and the hydrostatic gas bearings (carbon graphite and aluminum oxide for wear couple surfaces). Tests on the CTPC were performed in three phases: cold end testing (525 K), engine testing with slot radiant heaters, and integrated heat pipe engine system testing. Each test phase was successful, with the integrated engine system demonstrating a power level of 12.5 kWe and an overall efficiency of 22 percent in its maiden test. A 1500-hour endurance test was then successfully completed. These results indicate the significant achievements made by this program that demonstrate the viability of Stirling engine technology for space applications.

  19. Geothermal energy program summary: Volume 1: Overview Fiscal Year 1988

    Science.gov (United States)

    1989-02-01

    Geothermal energy is a here-and-now technology for use with dry steam resources and high-quality hydrothermal liquids. These resources are supplying about 6 percent of all electricity used in California. However, the competitiveness of power generation using lower quality hydrothermal fluids, geopressured brines, hot dry rock, and magma still depends on the technology improvements sought by the DOE Geothermal Energy R and D Program. The successful outcome of the R and D initiatives will serve to benefit the U.S. public in a number of ways. First, if a substantial portion of our geothermal resources can be used economically, they will add a very large source of secure, indigenous energy to the nation's energy supply. In addition, geothermal plants can be brought on line quickly in case of a national energy emergency. Geothermal energy is also a highly reliable resource, with very high plant availability. For example, new dry steam plants at The Geysers are operable over 99 percent of the time, and the small flash plant in Hawaii, only the second in the United States, has an availability factor of 98 percent. Geothermal plants also offer a viable baseload alternative to fossil and nuclear plants -- they are on line 24 hours a day, unaffected by diurnal or seasonal variations. The hydrothermal power plants with modern emission control technology have proved to have minimal environmental impact. The results to date with geopressured and hot dry rock resources suggest that they, too, can be operated so as to reduce environmental effects to well within the limits of acceptability. Preliminary studies on magma are also encouraging. In summary, the character and potential of geothermal energy, together with the accomplishments of DOE's Geothermal R and D Program, ensure that this huge energy resource will play a major role in future U.S. energy markets.

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

    International Nuclear Information System (INIS)

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

    2003-01-01

    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 10 B(n,α) 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

  1. Fission reactor based epithermal neutron irradiation facilities for routine clinical application in BNCT-Hatanaka memorial lecture

    International Nuclear Information System (INIS)

    Harling, Otto K.

    2009-01-01

    Based on experience gained in the recent clinical studies at MIT/Harvard, the desirable characteristics of epithermal neutron irradiation facilities for eventual routine clinical BNCT are suggested. A discussion of two approaches to using fission reactors for epithermal neutron BNCT is provided. This is followed by specific suggestions for the performance and features needed for high throughput clinical BNCT. An example of a current state-of-the-art, reactor based facility, suited for routine clinical use is discussed. Some comments are provided on the current status of reactor versus accelerator based epithermal neutron sources for BNCT. This paper concludes with a summary and a few personal observations on BNCT by the author.

  2. Subseabed Disposal Program Plan. Volume II. FY80 budget and subtask work plans

    International Nuclear Information System (INIS)

    1980-01-01

    This volume of the Subseabed Disposal Program Plan presents a breakdown of the master program structure by major activity. Each activity is described and accompanied by a specific cost plan schedule and a milestone plan. The costs have been compiled in the Cost Plan Schedules attached to each Subtask Work Plan. The FY 1980 budget for the Subseabed Disposal Program is summarized at the second level of the Work Breakdown Structure. The milestone plans for FY 80 are presented. The milestones can be changed only with the concurrence of the Sandia Subseabed Program Manager

  3. Effect of different BNCT protocols on DNA synthesis in precancerous and normal tissues in an experimental model of oral cancer

    International Nuclear Information System (INIS)

    Heber, Elisa M.; Aromando, Romina; Trivillin, Veronica A.; Itoiz, Maria E.; Kreimann, Erica L.; Schwint, Amanda E.; Nigg, David W.

    2006-01-01

    We previously reported the therapeutic success of different BNCT protocols in the treatment of oral cancer, employing the hamster cheek pouch model. The aim of the present study was to evaluate the effect of these BNCT protocols on DNA synthesis in precancerous and normal tissue in this model and assess the potential lag in the development of second primary tumors in precancerous tissue. The data are relevant to potential control of field cancerized tissue and tolerance of normal tissue. We evaluated DNA synthesis in precancerous and normal pouch tissue 1-30 days post-BNCT mediated by BPA, GB-10 or BPA + GB-10 employing incorporation of bromo-deoxyuridine as an end-point. The BNCT-induced potential lag in the development of second primary tumors in precancerous tissue was monitored. A drastic, statistically significant reduction in DNA synthesis occurred in pacancerous tissue as early as 1 day post-BNCT and was sustained at virtually all time points until 30 days post-BNCT for all protocols. The histological categories evaluated individually within precancerous tissue (dysplasia, hyperplasia and NUMF [no unusual microscopic features]) responded similarly. DNA synthesis in normal tissue treated with BNCT oscillated around the very low pre-treatment values. A BNCT-induced lag in the development of second primary tumors was observed. BNCT induced a drastic fall in DNA synthesis in precancerous tissue that would be associated to the observed lag in the development of second primary tumors. The minimum variations in DNA synthesis in BNCT-treated normal tissue would correlate with the absence of normal tissue radiotoxicity. The present data would contribute to optimize therapeutic efficacy in the treatment of field-cancerized areas. (author)

  4. 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)

  5. Radiation shielding design of BNCT treatment room for D-T neutron source.

    Science.gov (United States)

    Pouryavi, Mehdi; Farhad Masoudi, S; Rahmani, Faezeh

    2015-05-01

    Recent studies have shown that D-T neutron generator can be used as a proper neutron source for Boron Neutron Capture Therapy (BNCT) of deep-seated brain tumors. In this paper, radiation shielding calculations have been conducted based on the computational method for designing a BNCT treatment room for a recent proposed D-T neutron source. By using the MCNP-4C code, the geometry of the treatment room has been designed and optimized in such a way that the equivalent dose rate out of the treatment room to be less than 0.5μSv/h for uncontrolled areas. The treatment room contains walls, monitoring window, maze and entrance door. According to the radiation protection viewpoint, dose rate results of out of the proposed room showed that using D-T neutron source for BNCT is safe. Copyright © 2015 Elsevier Ltd. All rights reserved.

  6. 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 ...

  7. 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.

  8. Liquid Li based neutron source for BNCT and science application.

    Science.gov (United States)

    Horiike, H; Murata, I; Iida, T; Yoshihashi, S; Hoashi, E; Kato, I; Hashimoto, N; Kuri, S; Oshiro, S

    2015-12-01

    Liquid lithium (Li) is a candidate material for a target of intense neutron source, heat transfer medium in space engines and charges stripper. For a medical application of BNCT, epithermal neutrons with least energetic neutrons and γ-ray are required so as to avoid unnecessary doses to a patient. This is enabled by lithium target irradiated by protons at 2.5 MeV range, with utilizing the threshold reaction of (7)Li(p,n)(7)Be at 1.88 MeV. In the system, protons at 2.5 MeV penetrate into Li layer by 0.25 mm with dissipating heat load near the surface. To handle it, thin film flow of high velocity is important for stable operation. For the proton accelerator, electrostatic type of the Schnkel or the tandem is planned to be employed. Neutrons generated at 0.6 MeV are gently moderated to epithermal energy while suppressing accompanying γ-ray minimum by the dedicated moderator assembly. Copyright © 2015 Elsevier Ltd. All rights reserved.

  9. BNCT clinical trials of skin melanoma patients in Argentina

    International Nuclear Information System (INIS)

    Roth, Berta M.; Bonomi, Marcelo R.; Gonzalez, Sara J.

    2006-01-01

    The clinical outcome of six skin melanoma BNCT irradiations is presented. Three patients (A, B and C), with multiple subcutaneous skin metastases progressed to chemotherapy were infused with ∼14 g/m 2 of boronophenylalanine ( 10 BPA)-fructose and irradiated in the hyperthermal neutron beam of the RA-6 reactor. Patient A received two one fraction irradiations in different areas of the leg, B received one fraction and C was irradiated in three consecutive fields at the calf, heel and foot sole. The maximum prescribed dose to normal skin ranged from 16.5 to 24 Gy-Eq. With a minimum follow-up of 10 months there was a G1 acute epithelitis in A and B and a G3 in C. No late toxicity was observed. Due to the in-field tumor-growth-delay and the absence of severe acute and/or late toxicity observed during the follow-up period, a dose-escalation trial is ongoing. (author)

  10. 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

  11. Conceptual design of 30 MeV magnet system used for BNCT epithermal neutron source

    International Nuclear Information System (INIS)

    Slamet Santosa; Taufik

    2015-01-01

    Conceptual design of 30 MeV Magnet System Used for BNCT Epithermal Neutron Source has been done based on methods of empirical model of basic equation, experiences of 13 MeV cyclotron magnet design and personal communications. In the field of health, cyclotron can be used as an epithermal neutron source for Boron Neutron Capture Therapy (BNCT). The development of cyclotron producing epithermal neutrons for BNCT has been performed at Kyoto University, of which it produces a proton beam current of 1.1 mA with energy of 30 MeV. With some experiences on 13 MeV cyclotron magnet design, to support BNCT research and development we performed the design studies of 30 MeV cyclotron magnet system, which is one of the main components of the cyclotron for deflecting proton beam into circular trajectory and serves as beam focusing. Results of this study are expected to define the parameters of particular cyclotron magnet. The scope of this study includes the study of the parameters component of the 30 MeV cyclotron and magnet initial parameters. The empirical method of basic equation model is then corroborated by a simulation using Superfish software. Based on the results, a 30 MeV cyclotron magnet for BNCT neutron source enables to be realized with the parameters of B 0 = 1.06 T, frequency RF = 64.733938 ≈ 65 MHz, the external radius of 0.73 m, the radius of the polar = 0.85 m, BH = 1.95 T and a gap hill of 4 cm. Because proton beam current that be needed for BNCT application is very large, then in the calculation it is chosen a great focusing axial νz = 0.630361 which can generate B V = 0.44 T. (author)

  12. Might iodomethyl-α-tyrosine be a surrogate for BPA in BNCT?

    International Nuclear Information System (INIS)

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

    1996-01-01

    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 10 B nuclei in the targeted tumor. For BNCT of brain tumors, it is crucial that 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 18 F-fluoroboronophenylaianine [FBPA] as a positron 18 F (T 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 123 I alpha methyltyrosine as a surrogate for BPA in BNCT

  13. 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.

  14. National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

    International Nuclear Information System (INIS)

    Adams, J.P.; Carboneau, M.L.

    1999-01-01

    This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body

  15. Superconductivity Program for electric power systems: 1994 annual PEER review. Volume 1, Meeting proceedings

    International Nuclear Information System (INIS)

    1994-01-01

    This is Volume I of information presented at the Annual Peer Review of the Superconductivity Program For Electric Power Systems. Topics include: Wire development; powder synthesis; characterization of superconducting materials; electric power applications; magnetic refrigerators; and motor cooling issues. Individual reports were processed separately for the database

  16. National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

    Energy Technology Data Exchange (ETDEWEB)

    J. P. Adams; M. L. Carboneau

    1999-03-01

    This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body.

  17. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    International Nuclear Information System (INIS)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ( 242 Cm). This report also includes discussions about waste types and forms in which 242 Cm can be found and 242 Cm behavior in the environment and in the human body

  18. National low-level waste management program radionuclide report series, Volume 14: Americium-241

    International Nuclear Information System (INIS)

    Winberg, M.R.; Garcia, R.S.

    1995-09-01

    This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 ( 241 Am). This report also includes discussions about waste types and forms in which 241 Am can be found and 241 Am behavior in the environment and in the human body

  19. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    Energy Technology Data Exchange (ETDEWEB)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

  20. Proceedings of the 1995 U.S. DOE hydrogen program review. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The 1995 US DOE Hydrogen Program Review was held April 18-21, 1995 in Coral Gables, FL. Volume II of the Proceedings contains 8 papers presented under the subject of hydrogen storage and 17 papers presented on hydrogen production. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  1. A treatment planning comparison of BPA- or BSH-based BNCT of malignant gliomas

    International Nuclear Information System (INIS)

    Capala, J.; Coderre, J.A.; Chanana, A.D.

    1996-01-01

    Accurate delivery of the prescribed dose during clinical BNCT requires knowledge (or reasonably valid assumptions) about the boron concentrations in tumor and normal tissues. For conversion of physical dose (Gy) into photon-equivalent dose (Gy-Eq), relative biological effectiveness (RBE) and/or compound-adjusted biological effectiveness (CBE) factors are required for each tissue. The BNCT treatment planning software requires input of the following values: the boron concentration in blood and tumor, RBEs in brain, tumor and skin for the high-LET beam components, the CBE factors for brain, tumor, and skin, and the RBE for the gamma component

  2. A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 2

    International Nuclear Information System (INIS)

    Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

    1993-01-01

    This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified, of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the second

  3. A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 1

    International Nuclear Information System (INIS)

    Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

    1993-01-01

    This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the first

  4. Studies for the application of Boron neutron capture therapy (BNCT) to the treatment of differentiated thyroid cancer (CDT)

    International Nuclear Information System (INIS)

    Carpano, Marina; Thomasz, Lisa; Perona, Marina; Juvenal, Guillermo J.; Pisarev, Mario; Dagrosa, Maria A.; Nievas, Susana I.; Pozzi, Emiliano; Thorp, Silvia

    2009-01-01

    Boron neutron capture therapy (BNCT) is a high linear energy transfer (LET) radiotherapy for cancer, which it is based on the nuclear reaction that occurs when boron-10 that it is a non radioactive isotope of the natural elemental boron, is irradiated with low energy thermal neutrons to produce an alpha particle and a nucleus of lithium-7. Both particles have a range smaller than the diameter of a cell causing cell tumor death without significant damage to the surrounding normal tissues. In previous studies we have shown that BNCT can be a possibility for the treatment of undifferentiated thyroid cancer (UTC). However, more than 80 % of patients with thyroid neoplasm present differentiated carcinoma (CDT). These carcinomas are treated by surgery followed by therapy with 131 I and mostly these forms are well controlled. But in some patients recurrence of the tumor is observed. BNCT can be an alternative for these patients in who the tumor lost the capacity to concentrate iodide. The aim of these studies was to evaluate the possibility of treating differentiated thyroid cancer by BNCT. Materials and Methods: The human cell lines of follicular (WRO) and papillary carcinomas (TPC-1) were grown in RPMI and modified DMEM medium respectively. Both supplemented with 10 % of SFB. The cell line of thyroid rat, FRTL-5, used as control normal, was cultured in DMEM/F12. The uptakes of 125 I and p-borophenylalanine BPA (6.93mM) were studied. The intracellular boron concentration was measured by inductively coupled plasma optical emission spectroscopy (ICP-OES) at 2 hr post incubation. The NIH strain of male nude mice, aged 6 to 8 weeks and weighing 20 to 25 g were implanted (s.c) in the back right flank with different concentrations of tumor cells. The size of the tumors was measured with a caliper twice or three times a week and the volume was calculated according the following formulae: A 2 x B/2 (were A is the width and B is the length). To evaluate the BPA uptake, animals

  5. Towards a new therapy protocol for liver metastases. Effect of boron compounds and BNCT on normal liver regeneration

    International Nuclear Information System (INIS)

    Cardoso, Jorge E.; Heber, Elisa M.; Trivillin, Veronica A.

    2006-01-01

    The Taormina project developed a new method for BNCT treatment of multifocal unresectable liver metastases based on whole liver autograft. The Roffo Institute liver surgeons propose a new technique based on partial liver autograft that would pose less risk to the patient but would require significant healthy liver regeneration following BNCT. The aim of the present study was to assess the effect of BPA, GB-10 (Na 2 10 B 10 H 10 ) and (GB-10 + BPA) and of BNCT mediated by these boron compounds on normal liver regeneration in the Wistar rat. Normal liver regeneration, body weight, hemogram, liver and kidney function were assessed following partial hepatectomy post administration of BPA, GB-10 or (GB-10 + BPA) and post in vivo BNCT at the RA-6 Reactor. These end-points were evaluated 9 days following partial hepatectomy, the time at which complete liver regeneration occurs in untreated controls. The corresponding biodistribution studies were conducted to perform dosimetric calculations. BPA, GB-10 and (GB-10 + PBA) and in vivo BNCT mediated by these boron compounds in dose ranges compatible with therapy did not cause alterations in the outcome of normal liver regeneration, and did not induce alterations in body weight, hemogram, liver or kidney function. The experimental data available to date support the development of a new BNCT protocol for the treatment of liver metastases that requires the regeneration of normal liver past-BNCT. (author)

  6. Liquid Li based neutron source for BNCT and science application

    International Nuclear Information System (INIS)

    Horiike, H.; Murata, I.; Iida, T.; Yoshihashi, S.; Hoashi, E.; Kato, I.; Hashimoto, N.; Kuri, S.; Oshiro, S.

    2015-01-01

    Liquid lithium (Li) is a candidate material for a target of intense neutron source, heat transfer medium in space engines and charges stripper. For a medical application of BNCT, epithermal neutrons with least energetic neutrons and γ-ray are required so as to avoid unnecessary doses to a patient. This is enabled by lithium target irradiated by protons at 2.5 MeV range, with utilizing the threshold reaction of "7Li(p,n)"7Be at 1.88 MeV. In the system, protons at 2.5 MeV penetrate into Li layer by 0.25 mm with dissipating heat load near the surface. To handle it, thin film flow of high velocity is important for stable operation. For the proton accelerator, electrostatic type of the Schnkel or the tandem is planned to be employed. Neutrons generated at 0.6 MeV are gently moderated to epithermal energy while suppressing accompanying γ-ray minimum by the dedicated moderator assembly. - Highlights: • Liquid lithium (Li) is a candidate material for a target of intense neutron source. • An accelerator based neutron source with p-liquid Li target for boron neutron capture therapy is under development in Osaka University, Japan. • In our system, the harmful radiation dose due to rays and fast neutrons will be suppressed very low. • The system performance are very promising as a state of art cancer treatment system. • The project is planned as a joint undertaking between industries and Osaka University.

  7. Radiation Transport Simulation for Boron Neutron Capture Therapy (BNCT)

    Energy Technology Data Exchange (ETDEWEB)

    Ziegner, M.; Blaickner, M. [AIT Austrian Institute of Technology GmbH, Health and Environment Department, Molecular Medicine, Muthgasse 11, 1190 Wien (Austria); Ziegner, M.; Khan, R.; Boeck, H. [Vienna University of Technology, Institute of Atomic and Subatomic Physics, Stadionallee 2, 1020 Wien (Austria); Bortolussi, S.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, National Institute of Nuclear Physics (INFN) Pavia Section, Pavia (Italy); Schmitz, T.; Hampel, G. [Nuclear Chemistry, University of Mainz, Fritz Strassmann Weg 2, 55099 Mainz (Germany)

    2011-07-01

    This work is part of a larger project initiated by the University of Mainz and aiming to use the university's TRIGA reactor to develop a treatment for liver metastases based on Boron Neutron Capture Therapy (BNCT). Diffuse distribution of cancerous cells within the organ makes complete resection difficult and the vicinity to radiosensitive organs impedes external irradiation. Therefore the method of 'autotransplantation', first established at the University of Pavia, is used. The liver is taken out of the body, irradiated in the thermal column of the reactor, therewith purged of metastases and then reimplanted. A highly precise dosimetry system is to be developed by means of measurements at the University of Mainz and computational calculations at the AIT. The stochastic MCNP-5 Monte Carlo-Code, developed by Los Alamos Laboratories, is applied. To verify the calculations of the flux and the absorbed dose in matter a number of measurements are performed irradiating different phantoms and liver sections in a 20cm x 20cm beam tube, which was created by removing graphite blocks from the thermal column of the reactor. The detector material consists of L- {alpha} -alanine pellets which are thought to be the most suitable because of their good tissue equivalence, small size and their wide response range. Another experiment focuses on the determination of the relative biological effectiveness (RBE-factor) of the neutron and photon dose for liver cells. Therefore cell culture plates with the cell medium enriched with {sup 157}Gd and {sup 10}B at different concentrations are irradiated. With regard to the alanine pellets MCNP-5 calculations give stable results. Nevertheless the absorbed dose is underestimated compared to the measurements, a phenomenon already observed in previous works. The cell culture calculations showed the enormous impact of the added isotopes with high thermal neutron cross sections, especially {sup 157}Gd, on the absorbed dose

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

    Energy Technology Data Exchange (ETDEWEB)

    D.W. Nigg; William Bauer; Various Others

    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 (70–85 ppm). 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.

  9. Tumor blood vessel "normalization" improves the therapeutic efficacy of boron neutron capture therapy (BNCT) in experimental oral cancer

    Energy Technology Data Exchange (ETDEWEB)

    D. W. Nigg

    2012-01-01

    We previously demonstrated the efficacy of BNCT mediated by boronophenylalanine (BPA) to treat tumors in a hamster cheek pouch model of oral cancer with no normal tissue radiotoxicity and moderate, albeit reversible, mucositis in precancerous tissue around treated tumors. It is known that boron targeting of the largest possible proportion of tumor cells contributes to the success of BNCT and that tumor blood vessel normalization improves drug delivery to the tumor. Within this context, the aim of the present study was to evaluate the effect of blood vessel normalization on the therapeutic efficacy and potential radiotoxicity of BNCT in the hamster cheek pouch model of oral cancer.

  10. 2-O-α-glucopytanosyl L-ascorbic acid reduced mutagenicity at HPRT locus of mouse splenocytes following BNCT

    International Nuclear Information System (INIS)

    Kinashi, Yuko; Masunaga, Shin-ichiro; Suzuki, Minoru; Nagata, Kanji; Ono, Koji

    2006-01-01

    In boron neutron capture therapy (BNCT), normal tissue surrounding the tumor cells sometimes take up boron compounds resulting in radiation-induced damage to normal tissue. We have previously reported the evidence for increased the mutagenicity of thermal neutron in the presence of boron. In addition, we described the biological radio-protective effects of the ascorbic acid for mutation induction following BNCT in vitro. Here, we investigated these radio-protective effects of ascorbic acid for mutation induction in mouse splenocytes on HPRT locus following a BNCT study in vivo. (author)

  11. Tumor blood vessel 'normalization' improves the therapeutic efficacy of boron neutron capture therapy (BNCT) in experimental oral cancer

    International Nuclear Information System (INIS)

    Nigg, D.W.

    2012-01-01

    We previously demonstrated the efficacy of BNCT mediated by boronophenylalanine (BPA) to treat tumors in a hamster cheek pouch model of oral cancer with no normal tissue radiotoxicity and moderate, albeit reversible, mucositis in precancerous tissue around treated tumors. It is known that boron targeting of the largest possible proportion of tumor cells contributes to the success of BNCT and that tumor blood vessel normalization improves drug delivery to the tumor. Within this context, the aim of the present study was to evaluate the effect of blood vessel normalization on the therapeutic efficacy and potential radiotoxicity of BNCT in the hamster cheek pouch model of oral cancer.

  12. "Sequential” Boron Neutron Capture Therapy (BNCT): A Novel Approach to BNCT for the Treatment of Oral Cancer in the Hamster Cheek Pouch Model

    Energy Technology Data Exchange (ETDEWEB)

    Ana J. Molinari; Andrea Monti Hughes; Elisa M. Heber; Marcela A. Garabalino; Veronica A. Trivillin; Amanda E. Schwint; Emiliano C. C. Pozzi; Maria E. Itoiz; Silvia I. Thorp; Romina F. Aromando; David W. Nigg; Jorge Quintana; Gustavo A. Santa Cruz

    2011-04-01

    Boron Neutron Capture Therapy (BNCT) is a binary treatment modality that involves the selective accumulation of 10B carriers in tumors followed by irradiation with a thermal or epithermal neutron beam. The minor abundance stable isotope of boron, 10B, interacts with low energy (thermal) neutrons to produce high linear energy transfer (LET) a-particles and 7Li ions. These disintegration products are known to have a high relative biological effectiveness (RBE). Their short range (<10 {micro}m) would limit the damage to cells containing 10B (1,2). Thus, BNCT would target tumor tissue selectively, sparing normal tissue. Clinical trials of BNCT for the treatment of glioblastoma multiforme and/or melanoma and, more recently, head and neck tumors and liver metastases, using boronophenylalanine (BPA) or sodium mercaptoundecahydrododecaborane (BSH) as the 10B carriers, have been performed or are underway in Argentina, Japan, the US and Europe (e.g. 3-8). To date, the clinical results have shown a potential, albeit inconclusive, therapeutic advantage for this technique. Contributory translational studies have been carried out employing a variety of experimental models based on the implantation of tumor cells in normal tissue (e.g. 5).

  13. Program evaluation: Weatherization Residential Assistance Partnership (WRAP) Program. Volume 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    The Connecticut low income weatherization program was developed in response to a 1987 rate docket order from the Connecticut Department of Public Utility Control (DPUC) to Connecticut Light & Power Co., an operating subsidiary of Northeast Utilities (NU). (Throughout this report, NU is referred to as the operator of the program.) This program, known as the Weatherization Residential Assistance Partnership, or WRAP, was configured utilizing input from a collaborative group of interested parties to the docket. It was agreed that this program would be put forth by the electric utility, but would not ignore oil and gas savings (thus, it was to be ``fuel- blind``). The allocated cost of conservation services for each fuel source, however, should be cost effective. It was to be offered to those utility customers at or below 200 percent of the federal poverty levels, and provide a wide array of energy saving measures directed toward heating, water heating and lighting. It was felt by the collaborative group that this program would raise the level of expenditures per participant for weatherization services provided by the state, and by linking to and revising the auditing process for weatherization, would lower the audit unit cost. The program plans ranged from the offering of low-cost heating, water heating and infiltration measures, increased insulation levels, carpentry and plumbing services, to furnace or burner replacement. The program was configured to allow for very comprehensive weatherization and heating system servicing.

  14. Clinical results of BNCT for malignant gliomas using BSH and BPA simultaneously

    International Nuclear Information System (INIS)

    Miyatake, Shin-ichi; Kawabata, Shinji; Kajimoto, Yoshinaga

    2006-01-01

    Since 2002 to 2006, we applied BNCT for 41 cases of malignant gliomas. We used 3 different protocols. In each protocol, we used BSH and BPA simultaneously. In protocol 1, BSH 5g/body and BPA 250 mg/kg were used for consecutive 13 cases. Median survival time (MST) of newly diagnosed 4 cases of GB was 23 months after diagnosis. 2 cases were still alive. All cases including recurrent ones showed radiographic improvement. Eight out of 12 cases showed more than 50% mass reduction on images. Major cause of death was CSF dissemination. In protocol 2, BNCT were applied for 4 patients, two times with one to 2 week-interval. MST after BNCT was 13.3 months. In protocol 3, BPA 700 mg/kg were used with 20 to 30 Gy XRT after BNCT. XRT boost was applied especially for deeper part of the tumor. In protocol 3, 6 newly diagnosed GB patients were observed more than 16 months. 3 were dead and 3 were still alive on the preparation of this abstract. MST of these 6 patients was 17.3 months after diagnosis. In each protocol, radiation necrosis was the problem for recurrent cases, while removal of the necrosis prolonged the survival and recovered the neurological deficits. (author)

  15. Radiobiology studies for the evaluation of epithermal neutron beams used for BNCT

    International Nuclear Information System (INIS)

    Green, S.; Jones, B.; Mill, A.J.

    2006-01-01

    This paper outlines our plans for a study to establish the radiobiological effectiveness of the various mixes of radiation components present in an epithermal neutron beam designed for BNCT and to incorporate these data into clinical protocols for the treatment of malignant glioma. This is a description of work which is funded and just now beginning in Birmingham so no results can be presented. Our project will involve a combination of experimental measurements carried out in Birmingham and in Boston and mathematical modelling carried out in Birmingham. Despite all the extant in-vitro and in-vivo work, there is no widely accepted method to determine biological effect by accounting for variations in beam component mix, dose rate and treatment fractionation for disparate from the various BNCT centres. The objectives of this study are: To develop a cell-based radiobiology protocol to provide essential data on safety and efficacy of beams for Boron Neutron Capture Therapy (BNCT) in advance of clinical trials. To exploit the facilities at Massachusetts Institute of Technology for variable dose-rate epithermal irradiations to validate the above protocol. To develop mathematical models of this radiobiological system that can be used to inform decisions on dose selection, fractionation schedules, BNCT use as supplementary boosts or for re-treatment of recurrent cancers. To provide fundamental data relevant to the understanding of the radiobiology of simultaneous mixed high-and low-LET radiations over a clinically relevant dose-range. (author)

  16. Radiobiology of BNCT mediated by GB-10 and GB-10+BPA in experimental oral cancer

    Energy Technology Data Exchange (ETDEWEB)

    Trivillin, Veronica A.; Heber, Elisa M.; Itoiz, Maria E.; Nigg, David; Calzetta, Osvaldo; Blaumann, Herman; Longhino, Juan; Schwint, Amanda E. E-mail: schwint@cnea.gov.ar

    2004-11-01

    We previously reported biodistribution and pharmacokinetic data for GB-10 (Na{sub 2}{sup 10}B{sub 10}H{sub 10}) and the combined administration of GB-10 and boronophenylalanine (BPA) as boron delivery agents for boron neutron capture therapy (BNCT) in the hamster cheek pouch oral cancer model. The aim of the present study was to assess, for the first time, the response of hamster cheek pouch tumors, precancerous tissue and normal tissue to BNCT mediated by GB-10 and BNCT mediated by GB-10 and BPA administered jointly using the thermalized epithermal beam of the RA-6 Reactor at the Bariloche Atomic Center. GB-10 exerted 75.5% tumor control (partial+complete remission) with no damage to precancerous tissue around tumor or to normal tissue. Thus, GB-10 proved to be a therapeutically efficient boron agent in this model despite the fact that it is not taken up selectively by oral tumor tissue. GB-10 exerted a selective effect on tumor blood vessels leading to significant tumor control with a sparing effect on normal tissue. BNCT mediated by the combined administration of GB-10 and BPA resulted in a reduction in the dose to normal tissue and would thus allow for significant escalation of dose to tumor without exceeding normal tissue tolerance.

  17. Radiobiology of BNCT mediated by GB-10 and GB-10+BPA in experimental oral cancer

    International Nuclear Information System (INIS)

    Trivillin, Veronica A.; Heber, Elisa M.; Itoiz, Maria E.; Nigg, David; Calzetta, Osvaldo; Blaumann, Herman; Longhino, Juan; Schwint, Amanda E.

    2004-01-01

    We previously reported biodistribution and pharmacokinetic data for GB-10 (Na 2 10 B 10 H 10 ) and the combined administration of GB-10 and boronophenylalanine (BPA) as boron delivery agents for boron neutron capture therapy (BNCT) in the hamster cheek pouch oral cancer model. The aim of the present study was to assess, for the first time, the response of hamster cheek pouch tumors, precancerous tissue and normal tissue to BNCT mediated by GB-10 and BNCT mediated by GB-10 and BPA administered jointly using the thermalized epithermal beam of the RA-6 Reactor at the Bariloche Atomic Center. GB-10 exerted 75.5% tumor control (partial+complete remission) with no damage to precancerous tissue around tumor or to normal tissue. Thus, GB-10 proved to be a therapeutically efficient boron agent in this model despite the fact that it is not taken up selectively by oral tumor tissue. GB-10 exerted a selective effect on tumor blood vessels leading to significant tumor control with a sparing effect on normal tissue. BNCT mediated by the combined administration of GB-10 and BPA resulted in a reduction in the dose to normal tissue and would thus allow for significant escalation of dose to tumor without exceeding normal tissue tolerance

  18. 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 ...

  19. Time factor of BSH from intravenous infusion to neutron irradiation for BNCT in patients with glioblastoma

    International Nuclear Information System (INIS)

    Kageji, T.; Nagahiro, S.; Kitamura, K.; Nakagawa, Y.; Hatanaka, H.; Haritz, D.; Grochulla, F.; Haselsberger, K.; Gabel, D.

    2000-01-01

    The present report evaluates the time factor of BSH from infusion to irradiation in patients with glioblastoma as a cooperative study in Europe and Japan. For BNCT with BSH after intravenous infusion, this work confirms that the planned neutron irradiation after intravenous BSH infusion appears to be optimal around 12-19 hours after the infusion. (author)

  20. Azaboranes with hydroxypropyl residues as possible new compounds for use in BNCT

    International Nuclear Information System (INIS)

    Bauer, C.; Gabel, D.; Doefler, U.

    2000-01-01

    The azaboranes of the type RNH 2 B 8 H 11 NHR where R contains a hydroxyl group are possible new compounds for BNCT, because they are water stable and more or less water soluble for physiological transport. These compounds also fulfil the condition of not being toxic. (author)

  1. Summer Research Program - 1996 High School Apprenticeship Program Volume 15A Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1996-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  2. Summer Research Program - 1996 High School Apprenticeship Program. Volume 12B, Armstrong Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1996-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  3. Summer Research Program - 1998 High School Apprenticeship Program Final Reports. Volume 12, Armstrong Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1998-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  4. USAF Summer Research Program - 1995 High School Apprenticeship Program Final Reports, Volume 14, Rome Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1995-01-01

    The United States Air Force High School Apprenticeship Program's (USAF HSAP) purpose is to place outstanding high school students whose interests are in the areas of mathematics, engineering, and science to work in a laboratory environment...

  5. Summer Research Program - 1996 High School Apprenticeship Program. Volume 16, Arnold Engineering Development Center

    National Research Council Canada - National Science Library

    Moore, Gary

    1996-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  6. Summer Research Program - 1997. High School Apprenticeship Program. Final Reports, Volume 12A, Armstrong Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  7. Summer Research Program - 1998 High School Apprenticeship Program. Volume 14. Phillips Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1998-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  8. Summer Research Program - 1997. High School Apprenticeship Program. Final Reports Volume 15B, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  9. Summer Research Program - 1996. High School Apprenticeship Program Final Reports. Volume 15B, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1996-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  10. Summer Research Program - 1998 High School Apprenticeship Program Volume 15C Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1998-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  11. Summer Research Program - 1998 High School Apprenticeship Program Volume 13 Rome Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1998-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  12. 1997 Summer Research Program (SRP), High School Apprenticeship Program (HSAP), Final Reports, Volume 13, Phillips Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  13. Summer Research Program - 1997 High School Apprenticeship Program. Volume 14, Rome Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  14. Summer Research Program - 1997. High School Apprenticeship Program Final Reports. Volume 15A, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  15. Summer Research Program - 1998 High School Apprenticeship Program Volume 15B Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1998-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  16. Summer Research Program - 1997 High School Appenticeship Program Volume 16 Arnold Engineering Development Center

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  17. Summer Research Program - 1997. High School Apprenticeship Program. Final Reports. Volume 15C, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  18. Summer Research Program - 1996 High School Apprenticeship Program Volume 13 Phillips Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1996-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  19. Summer Research Program (1992). Summer Faculty Research Program (SFRP) Reports. Volume 2. Armstrong Laboratory

    Science.gov (United States)

    1992-12-01

    Comparison of Alternative Multiship Aircraft Simulation Dr. William C. Moor Systems Utilizing Benefit Estimation 27 Vocalizations of Naturally Ranging Groups...binocular display devices, like miost of thie llead-Mounited Displays.we can presetnt different visual stimulus to two hiuman eye channels. In p~ articular ...Menus -requires more complex -should minimise user programming programming -should be straightforward -shouldn’t distract driver -workload shouldn’t be

  20. United States Air Force High School Apprenticeship Program: 1989 Program Management Report. Volume 2

    Science.gov (United States)

    1989-12-01

    error determination of a root, and the Gaussian probability function. I found this 47-7 flowcharting exposure to be an asset while writing more...writing simple programs based upon flowcharts . This skill was further enhanced when my mentor taught me how to take a flowchart (or program) written in...software that teaches Ada to beginners . Though the first part of Ada-Tutr was review, the package proved to be very helpful in assisting me to write more

  1. Isotope Brayton ground demonstration testing and flight qualification. Volume 1. Technical program

    Energy Technology Data Exchange (ETDEWEB)

    1974-12-09

    A program is proposed for the ground demonstration, development, and flight qualification of a radioisotope nuclear heated dynamic power system for use on space missions beginning in the 1980's. This type of electrical power system is based upon and combines two aerospace technologies currently under intense development; namely, the MHW isotope heat source and the closed Brayton cycle gas turbine. This power system represents the next generation of reliable, efficient economic electrical power equipment for space, and will be capable of providing 0.5 to 2.0 kW of electric power to a wide variety of spacecraft for earth orbital and interplanetary missions. The immediate design will be based upon the requirements for the Air Force SURVSATCOM mission. The proposal is presented in three volumes plus an Executive Summary. This volume describes the tasks in the technical program.

  2. Advanced Transportation System Studies. Technical Area 3: Alternate Propulsion Subsystems Concepts. Volume 3; Program Cost Estimates

    Science.gov (United States)

    Levack, Daniel J. H.

    2000-01-01

    The objective of this contract was to provide definition of alternate propulsion systems for both earth-to-orbit (ETO) and in-space vehicles (upper stages and space transfer vehicles). For such propulsion systems, technical data to describe performance, weight, dimensions, etc. was provided along with programmatic information such as cost, schedule, needed facilities, etc. Advanced technology and advanced development needs were determined and provided. This volume separately presents the various program cost estimates that were generated under three tasks: the F- IA Restart Task, the J-2S Restart Task, and the SSME Upper Stage Use Task. The conclusions, technical results , and the program cost estimates are described in more detail in Volume I - Executive Summary and in individual Final Task Reports.

  3. Alternative fuels for vehicles fleet demonstration program. Final report, volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The Alternative Fuels for Vehicles Fleet Demonstration Program (AFV-FDP) was a multiyear effort to collect technical data for use in determining the costs and benefits of alternative-fuel vehicles (AFVs) in typical applications in New York State. This report, Volume 2, includes 13 appendices to Volume 1 that expand upon issues raised therein. Volume 1 provides: (1) Information about the purpose and scope of the AFV-FDP; (2) A summary of AFV-FDP findings organized on the basis of vehicle type and fuel type; (3) A short review of the status of AFV technology development, including examples of companies in the State that are active in developing AFVs and AFV components; and (4) A brief overview of the status of AFV deployment in the State. Volume 3 provides expanded reporting of AFV-FDP technical details, including the complete texts of the brochure Garage Guidelines for Alternative Fuels and the technical report Fleet Experience Survey Report, plus an extensive glossary of AFV terminology. The appendices cover a wide range of issues including: emissions regulations in New York State; production and health effects of ozone; vehicle emissions and control systems; emissions from heavy-duty engines; reformulated gasoline; greenhouse gases; production and characteristics of alternative fuels; the Energy Policy Act of 1992; the Clean Fuel Fleet Program; garage design guidelines for alternative fuels; surveys of fleet managers using alternative fuels; taxes on conventional and alternative fuels; and zero-emission vehicle technology.

  4. Logic Estimation of the Optimum Source Neutron Energy for BNCT of Brain Tumors

    International Nuclear Information System (INIS)

    Dorrah, M.A.; Gaber, F.A.; Abd Elwahab, M.A.; Kotb, M.A.; Mohammed, M.M.

    2012-01-01

    BNCT is very complicated technique; primarily due to the complexity of element composition of the brain. Moreover; numerous components contributes to the over all radiation dose both to normal brain and to tumor. Simple algebraic summation cannot be applied to these dose components, since each component should at first be weighed by its relative biological effectiveness (RBE) value. Unfortunately, there is no worldwide agreement on these RBE values. For that reason, the parameters required for accurate planning of BNCT of brain tumors located at different depths in brain remained obscure. The most important of these parameters is; the source neutron energy. Thermal neutrons were formerly employed for BNCT, but they failed to prove therapeutic efficacy. Later on; epithermal neutrons were suggested proposing that they would be enough thermalized while transporting in the brain tissues. However; debate aroused regarding the source neutrons energy appropriate for treating brain tumors located at different depths in brain. Again, the insufficient knowledge regarding the RBE values of the different dose components was a major obstacle. A new concept was adopted for estimating the optimum source neutrons energy appropriate for different circumstances of BNCT. Four postulations on the optimum source neutrons energy were worked out, almost entirely independent of the RBE values of the different dose components. Four corresponding condition on the optimum source neutrons energy were deduced. An energy escalation study was carried out investigating 65 different source neutron energies, between 0.01 eV and 13.2 MeV. MCNP4B Monte C arlo neutron transport code was utilized to study the behavior of neutrons in the brain. The deduced four conditions were applied to the results of the 65 steps of the neutron energy escalation study. A source neutron energy range of few electron volts (eV) to about 30 keV was estimated to be the most appropriate for BNCT of brain tumors located at

  5. Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

  6. Proceedings of the Advanced Turbine Systems Annual Program Review meeting. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    Goal of the 8-year program are to develop cleaner, more efficient, and less expensive gas turbine systems for utility and industrial electric power generation, cogeneration, and mechanical drive units. The conference is held annually for energy executives, engineers, scientists, and other interested parties in industry, academia, and Government. This volume contains 28 poster presentations and appendices; the poster papers are processed separately for the data base.

  7. Proceedings of the Advanced Turbine Systems Annual Program Review meeting. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    Goal of the 8-year program is to develop cleaner, more efficient, and less expensive gas turbine systems for utility and industrial electric power generation, cogeneration, and mechanical drive units. The conference is held annually for energy executives, engineers, scientists, and other interested parties industry, academia, and Government. Advanced turbine systems topics discussed during five technical sessions included policy and strategic issues, program element overviews and technical reviews, related activities, university/industry consortium interactions, and supportive projects. Twenty-one papers presented during the technical sessions are contained in this volume; they are processed separately for the data base.

  8. National low-level waste management program radionuclide report series, Volume 15: Uranium-238

    International Nuclear Information System (INIS)

    Adams, J.P.

    1995-09-01

    This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ( 238 U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which 238 U can be found, and 238 U behavior in the environment and in the human body

  9. Kilowatt isotope power system. Phase II plan. Volume I. Phase II program plan

    International Nuclear Information System (INIS)

    1978-01-01

    The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Phase II of the overall 3-phase KIPS program is described. This volume presents a program plan for qualifying the organic Rankine power system for flight test in 1982. The program plan calls for the design and fabrication of the proposed flight power system; conducting a development and a qualification program including both environmental and endurance testing, using an electrical and a radioisotope heat source; planning for flight test and spacecraft integration; and continuing ground demonstration system testing to act as a flight system breadboard and to accumulate life data

  10. Energy Extension Service Pilot Program: evaluation report after two years. Volume II. State reports

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-04-01

    This report, Vol. II, presents a discussion of the operations of the ten EES pilot state programs during the period from October 1, 1977 through September 30, 1979. Each of the ten pilot states - Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming - received a grant of approximately $1.1 million to develop and implement an 18-month program beginning on October 1, 1977. In September 1978, each State received an additional $370,000 for service-delivery programs for the extension of the pilot program, April 1979 through September 1979. A case-study description of the operations of the pilot program in each State is provided here, with special attention given to the two programs selected in each State for more-detailed study and survey research. Although the thrust of this volume is descriptive, some survey data and analyses are presented for the emphasis programs. Two telephone surveys of clients and a non-client sample were conducted, one at the end of the first year of the pilot program (October 1977 - September 1978) and one at the end of the second year (October 1978 - September 1979).

  11. 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.

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

    International Nuclear Information System (INIS)

    Aiyama, H.; Nakai, K.; Yamamoto, T.; Nariai, T.; Kumada, H.; Ishikawa, E.; Isobe, T.; Endo, K.; Takada, T.; Yoshida, F.; Shibata, Y.; Matsumura, A.

    2011-01-01

    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: ► Boron neutron capture therapy (BNCT) for recurrent glioma and malignant brain tumor. ► Two cases with recurrent glioblastoma and anaplastic meningioma. ► No severe adverse events have been observed using BNCT. ► BNCT has a possibility of a safe palliative therapy for malignant brain tumors.

  13. United States Air Force High School Apprenticeship Program: 1989 Program Management Report. Volume 1

    Science.gov (United States)

    1988-12-01

    summer and I had to reconfigure the program to work on our other machines. GKS for each machine is slightly different, which required reprogramming for...a water range. Each sortie involved a specific set of flight maneuvers with the PVHD mode changing once per mission to establish subconscious

  14. Balanced program plan. Volume 10. Fusion: analysis for biomedical and environmental research

    International Nuclear Information System (INIS)

    Hungate, F.P.

    1976-06-01

    Development of the Balanced Program Plan for analysis for biomedical and environmental research was initiated in the spring of 1975. The goal was a redefinition of research efforts and priorities to meet ERDA's requirements for a program of health and environmental research to support the development and commercialization of energy technologies. As part of the Balanced Program planning effort the major ERDA-supported multidisciplinary laboratories were assigned responsibility for analyzing the research needs of each of nine energy technologies and describing a research program to meet these needs. The staff of the Division of Biomedical and Environmental Research was assigned the task of defining a research program addressed to each of five biomedical and environmental research categories (characterization, measurement and monitoring; physical and chemical processes and effects; health effects; ecological effects; and integrated assessment and socioeconomic processes and effects) applicable to all energy technologies. The first drafts of these documents were available for a work-shop in June 1975 at which the DBER staff and scientists from the laboratories developed a comprehensive set of program recommendations. Pacific Northwest Laboratory was assigned responsibility for defining research needs and a recommended research program for fusion and fission technologies. This report, Volume 10, presents the input for fusion

  15. Fusion power research and development program. Volume IV. 5-year program, budget and milestone summaries

    International Nuclear Information System (INIS)

    1976-07-01

    Budget data are given for each of the tokamak systems, mirror systems, and high density plasma systems for the years 1976 through 1982. All major facilities currently under ERDA contract are included. In addition, budget data are given for the development and technology program consisting of the following; (1) magnetic systems, (2) plasma engineering, (3) fusion reactor materials, (4) fusion systems engineering, (5) environment and safety, and (6) applied plasma physics

  16. NWTS waste package program plan. Volume I. Program strategy, description, and schedule

    International Nuclear Information System (INIS)

    1981-10-01

    This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced

  17. Boron neutron capture therapy (BNCT) for high-grade gliomas of the brain: a cautionary note

    International Nuclear Information System (INIS)

    Laramore, George E.; Spence, Alexander M.

    1996-01-01

    Purpose/Objective: Boron neutron capture therapy (BNCT) is a method of treating high-grade gliomas of the brain that involves incorporating 10 B into the tumor using appropriate pharmacological agents and then irradiating the tumor with thermal or epithermal neutron beams. To date, over 120 patients have been treated in this manner by Japanese investigators using a thermal neutron beam from a nuclear reactor. Favorable reports on outcome have motivated considerable current research in BNCT. The purpose of this study is to provide an independent analysis of the Japanese data by identifying the subset of patients from the United States who received this treatment in Japan and comparing their outcomes relative to a matched cohort who received conventional therapy in various Radiation Therapy Oncology Group (RTOG) studies. Methods and Materials: The principal referral sources of patients to Japan for BNCT were identified and the names of patients sent for treatment obtained. The treating physicians in Japan were also contacted to see if additional patients from the United States had been treated. Either the patients or their next of kin were contacted, and permission was obtained to retrieve medical records including tumor pathology for central review. Prognostic variables according to an analysis of the RTOG brain tumor database by Curran et al. were determined from these records and used to construct a matched cohort of patients treated conventionally. Results: A total of 14 patients were identified who had traveled to Japan for BNCT treatment between July, 1987 and June, 1994. In the case of one patient (deceased), it was not possible to contact the next of kin. Material was obtained on the other 13 patients and review of the pathology indicated that 1 patient had a central nervous system lymphoma rather than a high-grade glioma. Survival data was analyzed for the other 12 patients on an actuarial basis, and this showed no difference compared to survival data for a

  18. TFTR lithium blanket module program. Final design report. Volume VII. LBM instrumentation and Program of Experiments and Analysis

    International Nuclear Information System (INIS)

    Harker, Y.D.; Tsang, F.Y.; Jassby, D.L.

    1983-07-01

    The Program of Experiments and Analysis comprises 3 spheres of activity: (1) measurements of neutron fluence and flux spectra inside and around the LBM, and of tritium production in the LBM central zone; (2) neutronic-code modeling and analysis of the TFTR/LBM system to predict the quantities measured in (1); (3) comparisons of the predicted and measured quantities, and improvements of the code modeling and analysis and the experimental techniques, in order to resolve any discrepancy between prediction and measurement. The measurement techniques are discussed. Section 5 of this volume discusses the strategy for carrying out the measurement program, for making comparisons with the neutronics code predictions, and for resolving discrepancies

  19. Therapeutic efficacy and toxicity of a single and double application of boron neutron capture therapy (BNCT) in a hamster cheek pouch oral precancer model

    International Nuclear Information System (INIS)

    Monti Hughes, A; Pozzi, E C C; Thorp, S; Garabalino, M A; Farias, R O; Gonzalez, S J; Heber, E M; Itoiz, M E; Aromando, R F; Molinari, A J; Miller, M; Nigg, D W; Curotto, P; Trivillin, V A; Schwint, A E

    2012-01-01

    Tumor development from tissue with potentially malignant disorders (PMD) gives rise to second primary tumors. We previously demonstrated the partial inhibitory effect on tumor development of Boron Neutron Capture Therapy (BNCT) mediated by the boron compounds BPA (boronophenylalanine) and decahydrodecaborate (GB-10) in a hamster pouch oral precancer model. Seeking to optimize BNCT, the aim of the present study was to contribute to the knowledge of BNCT radiobiology for oral precancer and assess new BNCT protocols in terms of inhibition of tumor development and radiotoxicity. Groups of cancerized hamsters were locally exposed to single or double applications (2 weeks apart) of BPA-BNCT or (GB-10 + BPA)-BNCT at a total dose of 8Gy to tissue with PMD; to a single application of BPA-BNCT at 6Gy and to a double application (4 weeks apart) of BPA-BNCT or (BPA + GB-10)-BNCT at a total dose of 10Gy. Cancerized, sham-irradiated hamsters served as controls. Clinical status, tumor development from tissue with PMD and mucositis were followed for 8 months. The marked therapeutic efficacy of single applications of BNCT at 6 and 8Gy were associated to severe radiotoxicity. Dose fractionation into 2 applications reduced mucositis but also reduced therapeutic efficacy, depending on dose and interval between applications. A double application (4 weeks apart) of (GB-10 + BPA)-BNCT at a total dose of 10Gy rendered the best therapeutic advantage, i.e. 63% - 100% inhibition of tumor development with only slight mucositis in 67% of cases. The data reported herein show that issues such as dose levels and dose fractionation, interval between applications, and choice of boron compounds are pivotal to therapeutic advantage and must be tailored for a particular pathology and anatomic site. The present study determined treatment conditions that would contribute to optimize BNCT for precancer and that would warrant cautious assessment in a clinical scenario (author)

  20. Proceedings of the 1998 U.S. DOE Hydrogen Program Review: Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    This document contains technical progress reports on 42 research projects funded by the DOE Hydrogen Program in Fiscal Year 1998, in support of its mission to make hydrogen a cost-effective energy carrier for utility, building, and transportation applications. Each year, the Program conducts a rigorous review of its portfolio of projects, utilizing teams of experts to provide vital feedback on the progress of research. These proceedings serve as an important technology reference for the DOE Hydrogen Program. The papers in Volume 2 are arranged under the following topical sections: Storage and separation systems; Thermal systems; and Transportation systems. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  1. United States Air Force Summer Faculty Research Program. Program Technical Report. 1990. Volume 3

    Science.gov (United States)

    1991-06-05

    flowchart of the progran "NCHIPSIM" is shown o. the following two pages. 95-7 SSTAR ’ ’.Choose-Chip type; Microprocessor or Gate,-Array Choose...oeet ~alulaew ntegrionRsut YEYES FLOW CHART FOR NCHIPSIM" 95-9 IV. THE PROGRAM "NCHIPSIM": Using the flowchart and the steps outlined in the above...would make the technique more versatile in flaw detection in metallic materials. 113-16 REFERENCES 1. RUDLIN, J.R., "A Beginners Guide to-Eddy Current

  2. An optimum source neutron spectrum and holder shape for extra-corporal treatment of liver cancer by BNCT

    International Nuclear Information System (INIS)

    Nievaart, Sander; Moss, Ray; Sauerwein, Wolfgang; Malago, Massimo; Kloosterman, Jan Leen; Hagen, Tim van der; Dam, Hugo van

    2006-01-01

    In extra-corporal treatment of liver cancer by BNCT, it is desired to have an as homogeneous as possible thermal neutron field throughout the organ. Previous work has shown that when using an epithermal neutron beam, the shape of the holder in which the liver is placed is the critical factor. This study develops the notion further as to what is the optimum neutron spectrum to perform such treatments. In the design calculations, when using Monte Carlo techniques, it is shown that when the expected contributions of the source neutrons in every part of the liver is calculated, a linear optimization scheme such as the Simplex method results in a mix of thermal and epithermal source neutrons to get the highest homogeneity for the thermal neutron field. This optimisation method is demonstrated in 3 holder shapes: cuboid, cylindrical and spherical with each 3 volumes of 2, 4 and 6 litres. A 10 cm thick cuboid model, irradiated from both sides gives the highest homogeneity. The spherical (rotating) holder has the lowest homogeneity but the highest contribution of every source neutron to the thermal neutrons in the liver. This can be advantageous when using a relatively small sized neutron beam with a low strength. (author)

  3. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 1 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared of each Appendix for inclusion in the Energy Data Base

  4. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Hinga, K.R. (ed.)

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base.

  5. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    International Nuclear Information System (INIS)

    Hinga, K.R.

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  6. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 2 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume II, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  7. Office of Technology Development's Research, Development, Demonstration, Testing and Evaluation Mid-Year Program Review. Volume 2

    International Nuclear Information System (INIS)

    1994-01-01

    This document, Volume 2, presents brief summaries of programs being investigated at USDOE sites for waste processing, remedial action, underground storage tank remediation, and robotic applications in waste management

  8. Experimental Engineering Section semiannual progress report, March 1-August 31, 1976. Volume 2. Biotechnology and environmental programs

    Energy Technology Data Exchange (ETDEWEB)

    Pitt, Jr., W. W.; Mrochek, J. E. [comps.

    1978-03-01

    This volume contains the progress report of the biotechnology and environmental programs in the Experimental Engineering Section of the Chemical Technology Division. Research efforts in these programs during this report period have been in five areas: (1) environmental research; (2) centrifugal analyzer development; (3) advanced analytical systems development; (4) bioengineering research; and (5) bioengineering development. Summaries of these programmatic areas are contained in Volume I.

  9. Regulatory Oversight Program, July 1, 1993 - March 3, 1997. Volume 2: Appendices

    International Nuclear Information System (INIS)

    1997-01-01

    On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 2 contains copies of the documents which established the relationship between NRC, DOE, USEC, and DOL (Dept of Labor) required to facilitate regulatory oversight transition

  10. Regulatory Oversight Program, July 1, 1993--March 3, 1997. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 2 contains copies of the documents which established the relationship between NRC, DOE, USEC, and DOL (Dept of Labor) required to facilitate regulatory oversight transition.

  11. Monte Carlo simulations of the cellular S-value, lineal energy and RBE for BNCT

    International Nuclear Information System (INIS)

    Liu Chingsheng; Tung Chuanjong

    2006-01-01

    Due to the non-uniform uptake of boron-containing pharmaceuticals in cells and the short-ranged alpha and lithium particles, microdosimetry provides useful information on the cellular dose and response of boron neutron capture therapy (BNCT). Radiation dose and quality in BNCT may be expressed in terms of the cellular S-value and the lineal energy spectrum. In the present work, Monte Carlo simulations were performed to calculate these microdosimetric parameters for different source-target configurations and sizes in cells. The effective relative biological effectiveness (RBE) of the Tsing Hua Open-pool Reactor (THOR) epithermal neutron beam was evaluated using biological weighting functions that depended on the lineal energy. RBE changes with source-target configurations and sizes were analyzed. (author)

  12. The Phase I/II BNCT Trials at the Brookhaven medical research reactor: Critical considerations

    International Nuclear Information System (INIS)

    Diaz, A.Z.

    2001-01-01

    A phase I/II clinical trial of boronophenylalanine-fructose (BPA-F) mediated boron neutron capture therapy (BNCT) for Glioblastoma Multiforme (GBM) was initiated at Brookhaven National Laboratory (BNL) in 1994. Many critical issues were considered during the design of the first of many sequential dose escalation protocols. These critical issues included patient selection criteria, boron delivery agent, dose limits to the normal brain, dose escalation schemes for both neutron exposure and boron dose, and fractionation. As the clinical protocols progressed and evaluation of the tolerance of the central nervous system (CNS) to BPA-mediated BNCT at the BMRR continued new specifications were adopted. Clinical data reflecting the progression of the protocols will be presented to illustrate the steps taken and the reasons behind their adoption. (author)

  13. Radioprotective agents to reduce BNCT (Boron Neutron Capture Therapy) induced mucositis in the hamster cheek pouch

    International Nuclear Information System (INIS)

    Monti Hughes, A.; Pozzi, E.C.C.; Thorp, S.

    2013-01-01

    Introduction: BNCT is based on the capture reaction between boron, selectively targeted to tumor tissue, and thermal neutrons which gives rise to lethal, short-range high linear energy transfer particles that selectively damage tumor tissue, sparing normal tissue. We previously evidenced a remarkable therapeutic success of BNCT mediated by boronophenylalanine (BPA) in the hamster cheek pouch oral cancer and pre cancer model. Despite therapeutic efficacy, mucositis induced in premalignant tissue was dose limiting and favored, in some cases, tumor development. In a clinical scenario, oral mucositis limits the dose administered to head and neck tumors. Aim: Our aim was to evaluate the effect of the administration of different radioprotective agents, seeking to reduce BNCT-induced mucositis to acceptable levels in dose-limiting premalignant tissue; without compromising therapeutic effect evaluated as inhibition on tumor development in premalignant tissue; without systemic or local side effects; and without negative effects on the biodistribution of the boron compound used for treatment. Materials and methods: Cancerized hamsters with DMBA (dimethylbenzanthracene) were treated with BPA-BNCT 5 Gy total absorbed dose to premalignant tissue, at the RA-3 Nuclear Reactor, divided into different groups: 1-treated with FLUNIXIN; 2- ATORVASTATIN; 3-THALIDOMIDE; 4-HISTAMINE (two concentrations: Low -1 mg/ml- and High -5 mg/ml-); 5-JNJ7777120; 6-JNJ10191584; 7-SALINE (vehicle). Cancerized animals without any treatment (neither BNCT nor radioprotective therapy) were also analyzed. We followed the animals during one month and evaluated the percentage of animals with unacceptable/severe mucositis, clinical status and percentage of animals with new tumors post treatment. We also performed a preliminary biodistribution study of BPA + Histamine “low” concentration to evaluate the potential effect of the radioprotector on BPA biodistribution. Results: Histamine

  14. On line local measurement of thermal neutron flux on BNCT patient using SPND

    International Nuclear Information System (INIS)

    Miller, M.E.; Sztejnberg Goncalves-Carralves, M.L.; Gonzalez, S.J.

    2006-01-01

    The first on-line neutron flux measurement on a patient using a self-powered neutron detector (SPND) was assessed during the fourth clinical trial of the Boron Neutron Capture Therapy (BNCT) Project carried out at the National Atomic Energy Commission of Argentina (CNEA) and the medical center Angel H. Roffo. The SPND was specially developed and assembled for BNCT by CNEA. Its small size, 1 cm sensible length and 1.9 mm diameter, allowed performing a localized measurement. Since the treated tumors were cutaneous melanomas of nodular type, the SPND was located on the patient's skin. The patient was exposed to three different and consecutive fields and in each of them the SPND was used to measure local thermal neutron fluxes at selected dosimetric reference points. The values of the measured fluxes agreed with the ones estimated by calculation. This trial also demonstrated the usefulness of the SPND for assessing flux on-line. (author)

  15. 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.

  16. MCNP study for epithermal neutron irradiation of an isolated liver at the Finnish BNCT facility.

    Science.gov (United States)

    Kotiluoto, P; Auterinen, I

    2004-11-01

    A successful boron neutron capture treatment (BNCT) of a patient with multiple liver metastases has been first given in Italy, by placing the removed organ into the thermal neutron column of the Triga research reactor of the University of Pavia. In Finland, FiR 1 Triga reactor with an epithermal neutron beam well suited for BNCT has been extensively used to irradiate patients with brain tumors such as glioblastoma and recently also head and neck tumors. In this work we have studied by MCNP Monte Carlo simulations, whether it would be beneficial to treat an isolated liver with epithermal neutrons instead of thermal ones. The results show, that the epithermal field penetrates deeper into the liver and creates a build-up distribution of the boron dose. Our results strongly encourage further studying of irradiation arrangement of an isolated liver with epithermal neutron fields.

  17. Design and simulation of an optimized e-linac based neutron source for BNCT research

    International Nuclear Information System (INIS)

    Durisi, E.; Alikaniotis, K.; Borla, O.; Bragato, F.; Costa, M.; Giannini, G.; Monti, V.; Visca, L.; Vivaldo, G.; Zanini, A.

    2015-01-01

    The paper is focused on the study of a novel photo-neutron source for BNCT preclinical research based on medical electron Linacs. Previous studies by the authors already demonstrated the possibility to obtain a mixed thermal and epithermal neutron flux of the order of 10"7 cm"−"2 s"−"1. This paper investigates possible Linac’s modifications and a new photo-converter design to rise the neutron flux above 5 10"7 cm"−"2 s"−"1, also reducing the gamma contamination. - Highlights: • Proposal of a mixed thermal and epithermal (named hyperthermal) neutron source based on medical high energy electron Linac. • Photo-neutron production via Giant Dipole Resonance on high Z materials. • MCNP4B-GN simulations to design the photo-converter geometry maximizing the hyperthermal neutron flux and minimizing the fast neutron and gamma contaminations. Hyperthermal neutron field suitable for BNCT preclinical research.

  18. Four cases of facial melanoma treated by BNCT with 10B-p-boronophenylalanine

    International Nuclear Information System (INIS)

    Fukuda, H.; Mishima, Y.; Hiratsuka, J.; Kobayashi, T.; Karashima, H.; Yoshino, K.; Tsuru, K.; Araki, K.; Ichihashi, M.

    2000-01-01

    We treated four cases of facial melanoma by BNCT with 10 B-paraboronophenylalanine · fructose complex (BPA). The patients received 180 to 200 mg BPA/kg-BW intravenously for 3 to 5 hours. One to two hours after the end of BPA administration, they were irradiated with a thermal neutron beam at the Kyoto University Reactor (KUR). The local control of the tumors was good and complete regression was achieved in all cases. The acute and subacute skin reactions ranged from dry desquamation to erosion and were within tolerable limits. After 2 to 3 months, the skin recovered from damage with slight pigmentation or depigmentation and without serious functional or cosmetic problems. Our results indicate BNCT of facial melanoma is promising not only for tumor cure but also for good QOL of the patients, although surgery is the standard and first choice for the treatment of malignant melanoma. (author)

  19. Treatment optimization of a brain tumor in BNCT by Monte Carlo method

    International Nuclear Information System (INIS)

    Nejat, S.; Binesh, A.; Karimian, A.

    2012-01-01

    Brain cancers are one of the most important diseases. BNCT (Boron Neutron Capture Therapy) is used to brain tumor treatment. In this method the 1 0B (n,α) 7 Li reaction is used. The purpose of this study is absorbed dose evaluation of tumoral and healthy parts of brain. To achieve this aim the brain was simulated by a cylindrical phantom with the dimensions of 20 cm in diameter and height. In BNCT treatment the BSH (Na 2 B 12 H 11 SH) is injected to the human body and absorbed in the healthy and tumoral parts by the ratios of 18 and 65 ppm respectively. So in this research the absorption of BSH in tumoral and healthy parts of brain was considered as the mentioned ratio. Then the neutron with the energy range of 50 eV - 10 keV was exposed to the brain and maximum absorbed dose in healthy and tumoral parts of brain were calculated for a cylindrical tumor with the thickness of about 1 cm which was considered in 5.5 cm depth of brain. This research showed the suitable energy to treat this tumor by BNCT is interval 4 keV- 6keV. The average of dose which is met with healthy and tumor tissue was gained for 6 keV energy of brain 1.18x10 -12 cGy/n and 5.98x10 -12 cGy/n respectively. Maximum of dose which is met with healthy tissue was 4.3 Gy which is much less than standard amount 12.6 Gy. Therefore BNCT method is known as an effective way in the therapy of this kind of tumor. (authors)

  20. Feasibility study on BNCT-SPECT using a CdTe detector

    International Nuclear Information System (INIS)

    Murata, Isao; Mukai, Taiki; Ito, Masao; Miyamaru, Hiroyuki; Yoshida, Shigeo

    2011-01-01

    There is no doubt that boron neutron capture therapy (BNCT) is a promising cancer therapy in the near future. At present, one of the severest problems to solve is monitoring of the treatment effect during neutron irradiation. It is known to be difficult in real time. So far, activation foils, small detectors and so on were used to measure the thermal neutron fluence in a certain place of the tumor. The dose distribution is thus estimated from the measured result and prediction with a transport code. In the present study, 478 keV gamma-rays emitted from the excited state of 7 Li produced by 10 B(n,α) 7 Li reaction are directly measured to realize real time monitoring of the treatment effect of BNCT. In this paper, the result of the feasibility study carried out using a Monte Carlo transport code is summarized. We used CdTe detectors with a quite narrow collimator to obtain a BNCT image keeping good spatial resolution. The intensity of capture gamma-rays of 2223 keV produced by 1 H(n,γ) 2 H reaction is very much higher than that of 478 keV. We thus adjusted the detector efficiency by selecting an appropriate thickness so as to optimize the efficiency ratio between 478 and 2223 keV. From the result of the detector response calculation, in case of 20 mm thick CdTe detector with the collimator of 2 mm in diameter, sufficient net count of ∼1000 for 478 keV in 30 min. was realized. It means an efficient and high-resolution BNCT-SPECT image could be obtained. (author)

  1. A colorimetric determination of boron in biological sample for boron neutron capture therapy (BNCT)

    International Nuclear Information System (INIS)

    Camillo, M.A.P.; Tomac Junior, U.

    1990-01-01

    The boron neutron capture therapy (BNCT) has shown better prognosis in the treatment of glyemas and gluoblastomas grade III and IV than other therapies. During the treatment the levels of Na 2 10 B 12 H 11 SH must be known in several compartiments of the organism and with this purpose the method of colorimetric determination of boron using curcumine was established. This method is simple, reprodutible and adequate sensitivity for this control. (author) [pt

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

    Science.gov (United States)

    Herrera, M S; González, S J; Burlon, A A; Minsky, D M; Kreiner, A J

    2011-12-01

    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. Copyright © 2011 Elsevier Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

    Herrera, M.S.; González, S.J.; Burlon, A.A.; Minsky, D.M.; Kreiner, A.J.

    2011-01-01

    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.

  4. Stirling Space Engine Program. Volume 2; Appendixes A, B, C and D

    Science.gov (United States)

    Dhar, Manmohan

    1999-01-01

    The objective of this program was to develop the technology necessary for operating Stirling power converters in a space environment and to demonstrate this technology in full-scale engine tests. Volume 2 of the report includes the following appendices: Appendix A: Heater Head Development (Starfish Heater Head Program, 1/10th Segment and Full-Scale Heat Pipes, and Sodium Filling and Processing); Appendix B: Component Test Power Converter (CTPC) Component Development (High-temperature Organic Materials, Heat Exchanger Fabrication, Beryllium Issues, Sodium Issues, Wear Couple Tests, Pressure Boundary Penetrations, Heating System Heaters, and Cooler Flow Test); Appendix C: Udimet Testing (Selection of the Reference Material for the Space Stirling Engine Heater Head, Udimet 720LI Creep Test Result Update, Final Summary of Space Stirling Endurance Engine Udimet 720L1 Fatigue Testing Results, Udimet 720l1 Weld Development Summary, and Udimet 720L1 Creep Test Final Results Summary), and Appendix D: CTPC Component Development Photos.

  5. Rotorcraft Flight Simulation Computer Program C81 with Datamap Interface, Volume 2. Programmer’s Manual

    Science.gov (United States)

    1981-10-01

    overview of the computer program capabilities and the principal mathematical models incorporated in the program are given in Volume I of the documentation...blank card must still be placed in the appropriate place in the Model Data Set. For example, the mathematical model of a UH-lH would not need a wing...SIN %4114 LV OADs CC £6 $ 2. 27 4L 4+ 4 l’l <m L & % CC O 04i18K5 twsSTVEL 13L4.S2 ASK 2? b 41.815 . 8 ’ILbLS a CL 7 8 £0 1 £0 £0 12 £6 1 M90 A/ MUfI H

  6. Medical set-up of boron neutron capture therapy (BNCT) for malignant glioma at the Japan research reactor (JRR)-4

    International Nuclear Information System (INIS)

    Yamamoto, T.; Matsumura, A.; Nose, T.; Shibata, Y.; Nakai, K.; Sakurai, F.; Kishi, T.; Kumada, H.; Yamamoto, K.; Torii, Y.

    2001-01-01

    The University of Tsukuba project for boron neutron capture therapy (BNCT) was initiated at the Japan Atomic Energy Research Institute (JAERI) in 1992. The clinical study for BNCT began at the Japan Research Reactor (JRR)-2 of the JAERI in November 1995. By the end of 1998, a new medical irradiation facility had been installed in JRR-4 of that included a new medical treatment room and patient-monitoring area adjacent to the irradiation room. The medical treatment room was built to reflect a hospital-type operation room that includes an operating table with a carbon head frame, anesthesia apparatus with several cardiopulmonary monitors, etc. Following craniotomy in the treatment room, a patient under anesthesia is transported into the irradiation room for BNCT. The boron concentration in tissue is measured with prompt gamma ray analysis (PGA) and simultaneously by inductively coupled plasma atomic emission spectroscopy (ICP-AES) methods. For the immediate pre- and post-BNCT care, a collaborating neurosurgical department of the University of Tsukuba was prepared in the vicinity of the JAERI. The long term follow-up is done at the University of Tsukuba Hospital. Epithermal neutron beam also became available at the new JRR-4. By changing the thickness and/or the configuration of heavy water, a cadmium plate, and a graphite reflector, the JRR-4 provides a variety of neutron beams, including three typical beams (Epithermal mode and Thermal modes I and II). Intraoperative BNCT using the thermal beam is planned to study at the beginning of the clinical trial. The ongoing development of the JAERI Computational Dosimetry System (JCDS) and radiobiological studies have focused in the application of the epithermal beam for BNCT. After obtaining these basic data, we are planning to use the epithermal beam for intraoperative BNCT. (author)

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

    International Nuclear Information System (INIS)

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

    2015-01-01

    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. - Highlights: • Hyaluronic acid (HA) is a nonimmunogenic, biocompatible polymer. • Boron–HA (BHA) acid can contain a large number of boron atoms for BNCT. • Active targeting can be realized with CD44 and other HA receptors on tumor cells. • BHA showed a certain degree of toxicity against C6 tumor cells and V79 fibroblasts. • BHA was injected into rats via the tail vein, boron was detected in tumors in vivo.

  8. Optimization of the irradiation beam in the BNCT research facility at IEA-R1 reactor

    International Nuclear Information System (INIS)

    Castro, Vinicius Alexandre de

    2014-01-01

    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)

  9. Quality assurance for BNCT at nuclear facilities. A necessary burden or the unavoidable seal of approval

    International Nuclear Information System (INIS)

    Moss, R.; Morrissey, J.; Sauerwein, W.; Hideghety, K.; Rassow, J.; Stecher-Rasmussen, F.

    2000-01-01

    The BNCT clinical trial at the HFR Petten is performed on a completely multi-national basis. The irradiation facility is located in one country (The Netherlands), is operated by an international team of experts under the leadership of a radiotherapist from another country (Germany) and treats patients coming from different European countries. In gaining the necessary approval, it became apparent, especially in the many discussions with the (Dutch) Health authorities that Quality Assurance (QA) would be and is a critical aspect. This is even more so, in the case of BNCT, where it was not only a (relatively) new experimental treatment (in 1996/97) about to be performed for the first time in Europe, but it was to be performed in a non-hospital environment and furthermore in a nuclear research reactor. It was necessary therefore to comply, as closely as possible, with similarly accepted practices in conventional radiotherapy. Despite QA being a sometimes burdensome task, this paper nevertheless raises the issue as to whether it is necessary or whether it is the seal of approval for BNCT as an acceptable mode of treatment in mainstream radiotherapy. (author)

  10. In vivo tyrosinase mini-gene transfer enhances killing effect of BNCT on amelanotic melanoma

    International Nuclear Information System (INIS)

    Kondoh, H.; Mishima, Y.; Hiratsuka, J.; Iwakura, M.

    2000-01-01

    Using accentuated melanogenesis principally occurring within melanoma cells, we have successfully treated human malignant melanoma (Mm) with 10 B-BPA BNCT. Despite this success, there are still remaining issues for poorly melanogenic Mm and further non-pigment cell tumors. We found the selective accumulation of 10 B-BPA to Mm is primarily due to the complex formation of BPA and melanin-monomers activity synthesized within Mm cells. Then, we succeeded in transferring the tyrosinase gene into amelanotic to substantially produce melanin monomers. These cells has demonstrated increased boron accumulation and enhanced killing effect of BNCT. Further, transfection of TRP-2 (DOPAchrome tautomerase) gene into poorly eumelanotic and slightly phenomelanotic Mm cells in culture cell systems also led to increased BPA accumulation. Thereafter, we studied in vivo gene transfer. We transferred the tyrosinase mini-gene by intra-tumor injection into poorly melanotic Mm proliferating subcutaneously in hamster skin, and performed BNCT. Compared to control tumors, gene-transferred tumors showed increased BPA accumulation leading to enhanced killing effect. (author)

  11. FiR 1 reactor in service for boron neutron capture therapy (BNCT) and isotope production

    International Nuclear Information System (INIS)

    Auterinen, I.; Salmenhaara, S.E.J. . Author

    2004-01-01

    The FiR 1 reactor, a 250 kW Triga reactor, has been in operation since 1962. The main purpose for the existence of the reactor is now the Boron Neutron Capture Therapy (BNCT), but FiR 1 has also an important national role in providing local enterprises and research institutions in the fields of industrial measurements, pharmaceuticals, electronics etc. with isotope production and activation analysis services. In the 1990's a BNCT treatment facility was built at the FiR 1 reactor located at Technical Research Centre of Finland. A special new neutron moderator material Fluental TM (Al+AlF3+Li) developed at VTT ensures the superior quality of the neutron beam. Also the treatment environment is of world top quality after a major renovation of the whole reactor building in 1997. Recently the lithiated polyethylene neutron shielding of the beam aperture was modified to ease the positioning of the patient close to the beam aperture. Increasing the reactor power to 500 kW would allow positioning of the patient further away from the beam aperture. Possibilities to accomplish a safety analysis for this is currently under considerations. Over thirty patients have been treated at FiR 1 since May 1999, when the license for patient treatment was granted to the responsible BNCT treatment organization, Boneca Corporation. Currently three clinical trial protocols for tumours in the brain as well as in the head and neck region are recruiting patients. (author)

  12. Radiation field characterization of a BNCT research facility using Monte Carlo Method - Code MCNP-4B

    International Nuclear Information System (INIS)

    Hernandes, Antonio Carlos

    2002-01-01

    Boron Neutron Capture Therapy - BNCT- is a selective cancer treatment and arises as an alternative therapy to treat cancer when usual techniques - surgery, chemotherapy or radiotherapy - show no satisfactory results. The main proposal of this work is to project a facility to BNCT studies. This facility relies on the use of an AmBe neutron source and on a set of moderators, filters and shielding which will provide the best neutron/gamma beam characteristic for these BNCT studies, i.e., high intensity thermal and/or epithermal neutron fluxes and with the minimum feasible gamma rays and fast neutrons contaminants. A computational model of the experiment was used to obtain the radiation field in the sample irradiation position. The calculations have been performed with the MCNP 4B Monte Carlo Code and the results obtained can be regarded as satisfactory, i.e., a thermal neutron fluency Ν Τ = 1,35x10 8 n/cm 2 , a fast neutron dose of 5,86x -1 0 Gy/Ν Τ and a gamma ray dose of 8,30x -14 Gy/Ν Τ . (author)

  13. In vivo tyrosinase mini-gene transfer enhances killing effect of BNCT on amelanotic melanoma

    Energy Technology Data Exchange (ETDEWEB)

    Kondoh, H.; Mishima, Y. [Mishima Institute for Dermatological Research, Kobe, Hyogo (Japan); Hiratsuka, J. [Kawasaki Medical School, Dept. of Radiation Oncology, Kurashiki, Okayama (Japan); Iwakura, M. [Kobe Univ. (Japan). School of Medicine

    2000-10-01

    Using accentuated melanogenesis principally occurring within melanoma cells, we have successfully treated human malignant melanoma (Mm) with {sup 10}B-BPA BNCT. Despite this success, there are still remaining issues for poorly melanogenic Mm and further non-pigment cell tumors. We found the selective accumulation of {sup 10}B-BPA to Mm is primarily due to the complex formation of BPA and melanin-monomers activity synthesized within Mm cells. Then, we succeeded in transferring the tyrosinase gene into amelanotic to substantially produce melanin monomers. These cells has demonstrated increased boron accumulation and enhanced killing effect of BNCT. Further, transfection of TRP-2 (DOPAchrome tautomerase) gene into poorly eumelanotic and slightly phenomelanotic Mm cells in culture cell systems also led to increased BPA accumulation. Thereafter, we studied in vivo gene transfer. We transferred the tyrosinase mini-gene by intra-tumor injection into poorly melanotic Mm proliferating subcutaneously in hamster skin, and performed BNCT. Compared to control tumors, gene-transferred tumors showed increased BPA accumulation leading to enhanced killing effect. (author)

  14. An accelerator neutron source for BNCT. Technical progress report, 1 June 1993--31 May 1994

    International Nuclear Information System (INIS)

    Blue, T.E.; Vafai, K.

    1994-02-01

    This is the progress report for the project entitled, ''An Accelerator Neutron Source for BNCT.'' The progress report is for the period from July 1, 1993 to date. The overall objective of our research project is to develop an Accelerator Epithermal Neutron Irradiation Facility (AENIF) for Boron Neutron Capture Therapy (BNCT). The AENIF consists of a 2.5 MeV high current proton accelerator, a lithium target to produce source neutrons, and a moderator/reflector assembly to obtain from the energetic source neutrons an epithermal neutron field suitable for BNCT treatments. Our project goals are to develop the non-accelerator components of the AENIF, and to specifically include in our development: (1) design, numerical simulation, and experimental verification of a target assembly which is capable of removing 75 kW of beam power; (2) re-optimization of the moderator assembly design based on in-phantom dose assessments using neutron spectra calculated in phantom and an energy-dependent neutron Relative Biological Effectiveness (RBE); (3) construction of a prototype moderator assembly and confirmation of its design by measurements; (4) design of the shielding of the accelerator and treatment rooms for an AENIF; and (5) design of a high energy beam transport system which is compatible with the shielding design and the thermal-hydraulic design

  15. 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.

  16. An epithermal neutron source for BNCT based on an ESQ-accelerator

    International Nuclear Information System (INIS)

    Ludewigt, B.A.; Chu, W.T.; Donahue, R.J.; Kwan, J.; Phillips, T.L.; Reginato, L.L.; Wells, R.P.

    1997-07-01

    An accelerator-based BNCT facility is under development at the Lawrence Berkeley National Laboratory. Neutrons will be produced via the 7 Li(p,n) reaction at proton energies of about 2.5 MeV with subsequent moderation and filtering for shaping epithermal neutron beams for BNCT. Moderator, filter, and shielding assemblies have been modeled using MCNP. Head-phantom dose distributions have been calculated using the treatment planning software BNCT RTPE. The simulation studies have shown that a proton beam current of ∼ 20 mA is required to deliver high quality brain treatments in about 40 minutes. The results also indicate that significantly higher doses can be delivered to deep-seated tumors in comparison to the Brookhaven Medical Research Reactor beam. An electrostatic quadrupole (ESQ) accelerator is ideally suited to provide the high beam currents desired. A novel power supply utilizing the air-coupled transformer concept is under development. It will enable the ESQ-accelerator to deliver proton beam currents exceeding 50 mA. A lithium target has been designed which consists of a thin layer of lithium on an aluminum backing. Closely spaced, narrow coolant passages cut into the aluminum allow the removal of a 50kW heat-load by convective water cooling. The system under development is suitable for hospital installation and has the potential for providing neutron beams superior to reactor sources

  17. Monitoring total boron in blood for BNCT by a novel atomic emission method

    International Nuclear Information System (INIS)

    Laakso, J.; Kulvik, M.; Ruokonen, I.; Vaehaetalo, J.; Faerkkilae, M.; Kallio, M.; Zilliacus, R.

    2000-01-01

    In BNCT the duration and timing of the is adjusted by 10 B concentrations in whole blood. Time-frame for determinations is less than 20 minutes. Therefore fast and accurate boron determinations are a prerequisite for BNCT. We present a method based on ICP-AES instrument for whole blood and plasma boron determinations with protein precipitation with trichloroacetic acid as sample pre-treatment and beryllium as an internal standard. The method was compared to established but tedious ICP-mass spectrometric method with wet ashing as a sample pre-treatment. The ICP-AES method is in good agreement (correlation coefficient 0.99) the ICP-MS. Within-day and between-day imprecisions were less than 3,5% CV for whole blood samples. Samples taken during and after BPA-F infusion (290 mg/kg) revealed an uneven distribution between plasma and erythrocytes. The present method is feasible and one of the fastest currently available for BNCT. Our results indicate that BPA-F or its metabolites do not seem to be tightly bound to plasma proteins. It also seems that determination of boron in plasma sample may be preferable than measuring boron in whole blood. (author)

  18. Considerations in reviewing the waste volume reduction program in a large utility

    International Nuclear Information System (INIS)

    Kohout, R.; Calzolari, L.M.

    1987-01-01

    A program is underway at Ontario Hydro to establish a desirable future scheme for central processing/volume reduction of solid radioactive Low-Level Wastes (LLW) prior to their placement into the centralized storage, and in the future into a disposal facility. The approach being investigated is to furnish the current Waste Volume Reduction Facility (WVRF) with state-of-art processes, reclassify the waste categories and segregate the wastes such that each volume reduction (VR) process is then applied where it would be most effective. The ''optimized'' approach is then compared with other, specific schemes, which basically differ in that each scheme omits one of the major VR processes, thus allowing the next most effective process to take over its role. Each scheme is assessed quantitatively from the viewpoint of cost and VR effectiveness, and qualitatively from the viewpoint of resultant waste form. The economic assessments take into consideration the long term (20 year) impact of selected VR schemes on the overall waste management cost, including construction and operation of the storage facility. This paper highlights the overall study, includes the major results, and identifies aspects that need to be addressed in the selection of a desirable combination of VR processes in absence of knowledge of future waste disposal costs

  19. EPRI tailored collaboration 3 Calvert Cliffs cost and volume reduction program

    International Nuclear Information System (INIS)

    Rigsby, M.D.; Watson, B.A.

    1995-01-01

    Baltimore Gas ampersand Electric's (BGE) Calvert Cliffs Nuclear Power Plant (CCNPP) is a two unit PWR located approximately 60 miles south of Baltimore, Maryland on the Chesapeake Bay. Both units are of Combustion Engineering design, Unit 1 began commercial operation is 1975 and Unit 2 in 1978. BGE contracted with EPRI to participate in the industry initiative to reduce low-level waste volumes with the expectation to: (1) Reduce O ampersand M costs through LLRW reduction by lowering the volume requiring processing, transportation, and storage/disposal. (2) Manage responsibility available resources; i.e., material, equipment, personnel, etc., through segregation. decontamination, recycling and worker awareness. (3) Improve Calvert Cliff's positive image in the community by minimizing the impact on the environment through generating less LLRW. Baltimore Gas ampersand Electric is committed to effective management of low-level radioactive waste (LLRW) at the Calvert Cliffs Nuclear Power Plant. Established Nuclear Program Policies and Procedures support CCNPP's commitment to minimizing generation of low-level radioactive waste (LLRW). Since the mid 1980's, CCNPP has made progress in reducing the volume of LLRW generated and disposed. EPRI's onsite assessment and subsequent assistance pointed out several areas for improvement

  20. Quality assurance program manual for nuclear power plants. Volume I. Policies

    International Nuclear Information System (INIS)

    1976-01-01

    The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

  1. Energy Extension Service Pilot Program: evaluation report after two years. Volume I. Evaluation summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-04-01

    The EES pilot program was initiated in August 1977, when 10 states were selected on a competitive basis for participation. The pilot states (Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming) devoted the first 6 months to start-up activities. This document is a follow-up report to the three volume Evaluation Summary of the first year of the pilot EES program published in September 1979. The purpose of this report is to provide an overview of the impacts and costs of the two years of the pilot program, and to check the consistency of findings over the two year period. The analysis addresses the following: (1) were the impact findings of Year I and Year II consistent, or did Year I and Year II attitudes and behavior vary. If variation existed, could it be attributed to program changes as the EES progressed from a start-up phase (Year I) to more normal service delivery (Year II); and (2) did costs of service delivery change (again reflecting start-up and normal service delivery costs). Did cost changes affect conclusions about the relative cost effectiveness of delivering services to different target audiences.

  2. Mod-5A wind turbine generator program design report. Volume 3: Final design and system description, book 2

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3MW MOD-5A wind turbine generator is documented. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 3, book 2 describes the performance and characteristics of the MOD-5A wind turbine generator in its final configuration. The subsystem for power generation, control, and instrumentation subsystems is described in detail. The manufacturing and construction plans, and the preparation of a potential site on Oahu, Hawaii, are documented. The quality assurance and safety plan, and analyses of failure modes and effects, and reliability, availability and maintainability are presented.

  3. Microcomputer based program for predicting heat transfer under reactor accident conditions. Volume I

    International Nuclear Information System (INIS)

    Cheng, S.C.; Groeneveld, D.C.; Leung, L.K.H.; Wong, Y.L.; Nguyen, C.

    1987-07-01

    A microcomputer based program called Heat Transfer Prediction Software (HTPS) has been developed. It calculates the heat transfer for the tube and bundle geometries for steady state and transient conditions. This program is capable of providing the best estimated of the hot pin temperatures during slow transients for 37- and 28-element CANDU type fuel bundles. The program is designed for an IBM-PC AT/XT (or IBM-PC compatible computer) equipped with a Math Co-processor. The following input parameters are required: pressure, mass flux, hydraulic diameter, and quality. For the steady state case, the critical heat flux (CHF), the critical heat flux temperature, the minimum film boiling temperature, and the minimum film boiling heat flux are the primary outputs. With either the surface heat flux or wall temperature specified, the program determines the heat transfer regime and calculates the surface heat flux, wall temperatures and heat transfer coefficient. For the slow transient case, the pressure, mass flux, quality, and volumetric heat generation rate are the time dependent input parameters required to calculate the hot pin sheath temperatures and surface heat fluxes. A simple routine for generating properties has been developed for light water to support the above program. It contains correlations that have been verified for pressures ranging from 0.6kPa to 30 MPa, and temperatures up to 1100 degrees Celcius. The thermodynamic and transport properties that can be generated from this routine are: density, specific volume, enthalpy, specific heat capacity, conductivity, viscosity, surface tension and Prandtl number for saturated liquid, saturated vapour, subcooled liquid for superheated vapour. A software for predicting flow regime has also been developed. It determines the flow pattern at specific flow conditions, and provides a correction factor for calculating the CHF during partially stratified horizontal flow. The technical bases for the program and its

  4. Microcomputer based program for predicting heat transfer under reactor accident conditions. Volume II

    International Nuclear Information System (INIS)

    Cheng, S.C.; Groeneveld, D.C.; Leung, L.K.H.; Wong, Y.L.; Nguyen, C.

    1987-07-01

    A microcomputer based program called Heat Transfer Prediction Software (HTPS) has been developed. It calculates the heat transfer for tube and bundle geometries for steady state and transient conditions. This program is capable of providing the best estimated of the hot pin temperatures during slow transients for 37- and 28-element CANDU type fuel bundles. The program is designed for an IBM-PC AT/XT (or IBM-PC compatible computer) equipped with a Math Co-processor. The following input parameters are required: pressure, mass flux, hydraulic diameter, and quality. For the steady state case, the critical heat flux (CHF), the critical heat flux temperature, the minimum film boiling temperature, and the minimum film boiling heat flux are the primary outputs. With either the surface heat flux or wall temperature specified, the program determines the heat transfer regime and calculates the surface heat flux, wall temperature and heat transfer coefficient. For the slow transient case, the pressure, mass flux, quality, and volumetric heat generation rate are the time dependent input parameters are required to calculate the hot pin sheath temperatures and surface heat fluxes. A simple routine for generating properties has been developed for light water to support the above program. It contains correlations that have been verified for pressures ranging from 0.6kPa to 30 MPa, and temperatures up to 1100 degrees Celcius. The thermodynamic and transport properties that can be generated from this routine are: density, specific volume, enthalpy, specific heat capacity, conductivity, viscosity, surface tension and Prandtle number for saturated liquid, saturated vapour, subcooled liquid of superheated vapour. A software for predicting flow regime has also been developed. It determines the flow pattern at specific flow conditions, and provides a correction factor for calculating the CHF during partially stratified horizontal flow. The technical bases for the program and its structure

  5. SMACS - a system of computer programs for probabilistic seismic analysis of structures and subsystems. Volume II. Example problem

    International Nuclear Information System (INIS)

    Maslenikov, O.R.; Johnson, J.J.; Tiong, L.W.; Mraz, M.J.; Bumpus, S.; Gerhard, M.A.

    1985-03-01

    In this volume of the SMACS User's Manual an example problem is presented to demonstrate the type of problem that SMACS is capable of solving and to familiarize the user with format of the various data files involved. This volume is organized into thirteen appendices which follow a short description of the problem. Each appendix contains listings of the input and output files associated with each computer run that was necessary to solve the problem. In cases where one SMACS program uses data generated by another SMACS program, the data file is shown in the appendix for the programs which generated it

  6. Effects of a Modified German Volume Training Program on Muscular Hypertrophy and Strength.

    Science.gov (United States)

    Amirthalingam, Theban; Mavros, Yorgi; Wilson, Guy C; Clarke, Jillian L; Mitchell, Lachlan; Hackett, Daniel A

    2017-11-01

    Amirthalingam, T, Mavros, Y, Wilson, GC, Clarke, JL, Mitchell, L, and Hackett, DA. Effects of a modified German volume training program on muscular hypertrophy and strength. J Strength Cond Res 31(11): 3109-3119, 2017-German Volume Training (GVT), or the 10 sets method, has been used for decades by weightlifters to increase muscle mass. To date, no study has directly examined the training adaptations after GVT. The purpose of this study was to investigate the effect of a modified GVT intervention on muscular hypertrophy and strength. Nineteen healthy men were randomly assign to 6 weeks of 10 or 5 sets of 10 repetitions for specific compound resistance exercises included in a split routine performed 3 times per week. Total and regional lean body mass, muscle thickness, and muscle strength were measured before and after the training program. Across groups, there were significant increases in lean body mass measures, however, greater increases in trunk (p = 0.043; effect size [ES] = -0.21) and arm (p = 0.083; ES = -0.25) lean body mass favored the 5-SET group. No significant increases were found for leg lean body mass or measures of muscle thickness across groups. Significant increases were found across groups for muscular strength, with greater increases in the 5-SET group for bench press (p = 0.014; ES = -0.43) and lat pull-down (p = 0.003; ES = -0.54). It seems that the modified GVT program is no more effective than performing 5 sets per exercise for increasing muscle hypertrophy and strength. To maximize hypertrophic training effects, it is recommended that 4-6 sets per exercise be performed, as it seems gains will plateau beyond this set range and may even regress due to overtraining.

  7. Development, Verification and Validation of Parallel, Scalable Volume of Fluid CFD Program for Propulsion Applications

    Science.gov (United States)

    West, Jeff; Yang, H. Q.

    2014-01-01

    There are many instances involving liquid/gas interfaces and their dynamics in the design of liquid engine powered rockets such as the Space Launch System (SLS). Some examples of these applications are: Propellant tank draining and slosh, subcritical condition injector analysis for gas generators, preburners and thrust chambers, water deluge mitigation for launch induced environments and even solid rocket motor liquid slag dynamics. Commercially available CFD programs simulating gas/liquid interfaces using the Volume of Fluid approach are currently limited in their parallel scalability. In 2010 for instance, an internal NASA/MSFC review of three commercial tools revealed that parallel scalability was seriously compromised at 8 cpus and no additional speedup was possible after 32 cpus. Other non-interface CFD applications at the time were demonstrating useful parallel scalability up to 4,096 processors or more. Based on this review, NASA/MSFC initiated an effort to implement a Volume of Fluid implementation within the unstructured mesh, pressure-based algorithm CFD program, Loci-STREAM. After verification was achieved by comparing results to the commercial CFD program CFD-Ace+, and validation by direct comparison with data, Loci-STREAM-VoF is now the production CFD tool for propellant slosh force and slosh damping rate simulations at NASA/MSFC. On these applications, good parallel scalability has been demonstrated for problems sizes of tens of millions of cells and thousands of cpu cores. Ongoing efforts are focused on the application of Loci-STREAM-VoF to predict the transient flow patterns of water on the SLS Mobile Launch Platform in order to support the phasing of water for launch environment mitigation so that vehicle determinantal effects are not realized.

  8. A preclinical study of boron neutron capture therapy (BNCT) of spontaneous tumors in cats at RA-6 in Argentina

    International Nuclear Information System (INIS)

    Trivillin, Veronica A.; Heber, Elisa M.; Itoiz, Maria E.; Schwint, Amanda E.; Calzetta, Osvaldo A.; Blaumann, Hernan R.; Longhino, J.; Rao, Monica; Cantarelli, Maria de los A.

    2005-01-01

    BNCT is a binary treatment modality that combines irradiation with a thermal or epithermal neutron beam with tumor-seeking, boron containing drugs to produce selective irradiation of tumor tissue. Having demonstrated that BNCT mediated by boronophenylalanine (BPA) 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 RA-1. Having demonstrated partial tumor control with no radio toxic effects, the aim of the present study was to evaluate the effect of BPA-BNCT on tumor and normal tissue in 3 cases of spontaneous SCC in feline patients employing a higher neutron fluence than in the previous study. The present study was performed at RA-6 with the thermalized epithermal neutron beam. All three irradiations were successful. Except for an initial, moderate and reversible mucositis, no significant radio toxic effects were observed in terms of clinical follow-up, histological examination, biochemical analysis and assessment of autopsy material. Partial tumor control was evidenced in terms of growth inhibition and partial necrosis and improvement in the quality of life during the survival period. Optimization of the therapeutic efficacy of BNCT would require improvement in boron tumor targeting and strategies to increase in-depth dose in large tumors. (author)

  9. Reprint of Application of BNCT to the treatment of HER2+ breast cancer recurrences: Research and developments in Argentina

    International Nuclear Information System (INIS)

    Gadan, M.A.; González, S.J.; Batalla, M.; Olivera, M.S.; Policastro, L.; Sztejnberg, M.L.

    2015-01-01

    In the frame of the Argentine BNCT Project a new research line has been started to study the application of BNCT to the treatment of locoregional recurrences of HER2+ breast cancer subtype. Based on former studies, the strategy considers the use of immunoliposomes as boron carriers nanovehicles to target HER2 overexpressing cells. The essential concerns of the current stage of this proposal are the development of carriers that can improve the efficiency of delivery of boron compounds and the dosimetric assessment of treatment feasibility. For this purpose, an specific pool of clinical cases that can benefit from this application was determined. In this work, we present the proposal and the advances related to the different stages of current research. - Highlights: • A new proposal of BNCT for HER2+ breast cancer treatment is introduced. • The proposal considers development of immunoliposomes as boron carrier nanovehicles. • Locoregional recurrences after treatment were identified as candidates for initial BNCT studies. • First analysis show acceptable neutron flux distributions provided by RA-6 BNCT facility.

  10. Recovery Act: Finite Volume Based Computer Program for Ground Source Heat Pump Systems

    Energy Technology Data Exchange (ETDEWEB)

    James A Menart, Professor

    2013-02-22

    This report is a compilation of the work that has been done on the grant DE-EE0002805 entitled Finite Volume Based Computer Program for Ground Source Heat Pump Systems. The goal of this project was to develop a detailed computer simulation tool for GSHP (ground source heat pump) heating and cooling systems. Two such tools were developed as part of this DOE (Department of Energy) grant; the first is a two-dimensional computer program called GEO2D and the second is a three-dimensional computer program called GEO3D. Both of these simulation tools provide an extensive array of results to the user. A unique aspect of both these simulation tools is the complete temperature profile information calculated and presented. Complete temperature profiles throughout the ground, casing, tube wall, and fluid are provided as a function of time. The fluid temperatures from and to the heat pump, as a function of time, are also provided. In addition to temperature information, detailed heat rate information at several locations as a function of time is determined. Heat rates between the heat pump and the building indoor environment, between the working fluid and the heat pump, and between the working fluid and the ground are computed. The heat rates between the ground and the working fluid are calculated as a function time and position along the ground loop. The heating and cooling loads of the building being fitted with a GSHP are determined with the computer program developed by DOE called ENERGYPLUS. Lastly COP (coefficient of performance) results as a function of time are provided. Both the two-dimensional and three-dimensional computer programs developed as part of this work are based upon a detailed finite volume solution of the energy equation for the ground and ground loop. Real heat pump characteristics are entered into the program and used to model the heat pump performance. Thus these computer tools simulate the coupled performance of the ground loop and the heat pump. The

  11. Finite Volume Based Computer Program for Ground Source Heat Pump System

    Energy Technology Data Exchange (ETDEWEB)

    Menart, James A. [Wright State University

    2013-02-22

    This report is a compilation of the work that has been done on the grant DE-EE0002805 entitled ?Finite Volume Based Computer Program for Ground Source Heat Pump Systems.? The goal of this project was to develop a detailed computer simulation tool for GSHP (ground source heat pump) heating and cooling systems. Two such tools were developed as part of this DOE (Department of Energy) grant; the first is a two-dimensional computer program called GEO2D and the second is a three-dimensional computer program called GEO3D. Both of these simulation tools provide an extensive array of results to the user. A unique aspect of both these simulation tools is the complete temperature profile information calculated and presented. Complete temperature profiles throughout the ground, casing, tube wall, and fluid are provided as a function of time. The fluid temperatures from and to the heat pump, as a function of time, are also provided. In addition to temperature information, detailed heat rate information at several locations as a function of time is determined. Heat rates between the heat pump and the building indoor environment, between the working fluid and the heat pump, and between the working fluid and the ground are computed. The heat rates between the ground and the working fluid are calculated as a function time and position along the ground loop. The heating and cooling loads of the building being fitted with a GSHP are determined with the computer program developed by DOE called ENERGYPLUS. Lastly COP (coefficient of performance) results as a function of time are provided. Both the two-dimensional and three-dimensional computer programs developed as part of this work are based upon a detailed finite volume solution of the energy equation for the ground and ground loop. Real heat pump characteristics are entered into the program and used to model the heat pump performance. Thus these computer tools simulate the coupled performance of the ground loop and the heat pump

  12. Regulatory Oversight Program, July 1, 1993--March 3, 1997. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations (ORO) to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 3 contains copies of two reports that document the DOE/ORO regulatory oversight inspection and enforcement history for each gaseous diffusion plant site. Each report provides a formal mechanism by which DOE/ORO could communicate the inspection and enforcement history to NRC. The reports encompass the inspection activities that occurred during July 1, 1993 through March 2, 1997.

  13. National Low-Level Waste Management Program radionuclide report series. Volume 2, Niobium-94

    International Nuclear Information System (INIS)

    Adams, J.P.; Carboneau, M.L.

    1995-04-01

    The Purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to, state representatives and developers of low-level radioactive waste disposal facilities about the radiological chemical, and physical characteristics of selected radionuclides and their behavior in the low-level radioactive waste disposal facility environment. Extensive surveys of available literature provided information used to produce this series of reports and an introductory report. This report is Volume 11 of the series. It outlines the basic radiological, chemical, and physical characteristics of niobium-94, waste types and forms that contain it, and its behavior in environmental media such as soils, plants, groundwater, air, animals and the human body

  14. Environmental Hazards Assessment Program. Volume 4: Annual report, July 1, 1993--June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The Medical University of South Carolina's (MUSC) vision is to become the premier national resource for medical information and for environmental/health risk assessment. A key component to the success of the many missions of the Environmental Hazards Assessment Program (EHAP) is timely access to large volumes of data. The significant growth in the number of environmental/health information systems that has occurred over the past few years has made data access challenging. This study documents the results of the needs assessment effort conducted to determine the information access and processing requirements of EHAP. The following topics are addressed in this report: immunological consequences of beryllium exposure; assessment of genetic risks to environmental diseases; low dose-rate radiation health effects; environmental risk perception in defined populations; information support and access systems; and environmental medicine and risk communication: curriculum and a professional support network-Department of Family Medicine

  15. 2004 Power marketing program final EIS - final environmental impact statement. Volume 2 - appendices

    International Nuclear Information System (INIS)

    1997-02-01

    This volume contains appendices to the Final Environmental Impact Statement (FEIS) for the Power Marketing Program proposal of the Western Area Power Administration. The FEIS identified peaking power scheduling as the environmentally preferred alternative, and presented the analysis of alternatives and environmental impacts. Sixteen appendices to the FEIS are included in this document. The appendices are: Statutory and Legal Framework; Sierra Nevada Region Customer Groups and Economic Regions; Renewable Technology Cost Information Matrix; Hydrological Assumptions; Recreation Resources; Archaeological and Historical Resources; Incremental Power Resources; Air Quality Regulatory Structure; Energy Generation; Stage Contents Relationships for Regulating Reservoirs; Power Costs; Socioeconomic Impacts; Projected Air Resource Impacts; Land use, Water Quality, and Solid Waste Impact Factors; Draft Environmental Impact Statement Comments and Responses, and Contractor Disclosure Statements. 21 figs., 24 tabs

  16. Environmental Hazards Assessment Program. Volume 4: Annual report, July 1, 1993--June 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Medical University of South Carolina`s (MUSC) vision is to become the premier national resource for medical information and for environmental/health risk assessment. A key component to the success of the many missions of the Environmental Hazards Assessment Program (EHAP) is timely access to large volumes of data. The significant growth in the number of environmental/health information systems that has occurred over the past few years has made data access challenging. This study documents the results of the needs assessment effort conducted to determine the information access and processing requirements of EHAP. The following topics are addressed in this report: immunological consequences of beryllium exposure; assessment of genetic risks to environmental diseases; low dose-rate radiation health effects; environmental risk perception in defined populations; information support and access systems; and environmental medicine and risk communication: curriculum and a professional support network-Department of Family Medicine.

  17. International Nuclear Model. Volume 3. Program description. Appendix A-H (Part 1)

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decisions based on an input set of technical, economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. This volume contains appendices A through H including a description of subroutines and the Fortran listing of the program

  18. Development of computer program for the economic evaluation of the volume reduction system for the low-level radwaste

    International Nuclear Information System (INIS)

    Yang, Jin Yeong

    1994-02-01

    This study provides the basis for investigating the benefits of purchasing volume reduction equipment and includes the establishment of a volume reduction data base, the creation of the volume reduction cost analysis computer program PEEVR (Program of Economic Evaluation for the Volume Reduction), and a generic analysis designed to identify the major costs influencing the economics of the various equipment options. In treating the plant types and the wastes, this study considers that condensate polishing system is included or not in PWR and precoat condensate polishing system, deep bed condensate polishing system in BWR and the 5 waste streams, i.e., compatible trash (COTRASH), ion exchange resin (IXRESIN), concentrate liquid (CONCLIQ), filter sludge (FSLUDGE), non compatible trash (COTRASH). This study uses the PVRR and LRR methods to create cost analysis and performs sensitivity analysis for the each cost variable and shows that future burial costs increases are the major factors in the economic evaluation

  19. Development of computer program for the economic evaluation of the volume reduction system for the low-level radioactive waste

    International Nuclear Information System (INIS)

    Yang, Jin Yeong; Lee, Kun Jai

    1994-01-01

    This study provides the basis for investigating the benefits of purchasing volume reduction equipment and includes the establishment of a volume reduction data base, the creation of the volume reduction cost analysis computer program PEEVR (Program of Economic Evaluation for the Volume Reduction), and a generic analysis designed to identify the major costs influencing the economics of the various equipment options. In treating the plant types and the wastes, this study considers that condensate polishing system is included or not in PWR and precoatcondensate polishing system, deep bed condensate polishing system in BWR and the 5 waste streams, i. e., compactibIe trash (COTRASH), ion exchange resin (IXRESIN), concentrate liquid (CONCLIQ), filter sludge (FSLUDGE), non compactible trash (COTRASH). This study uses the PVRR and LRR methods to create cost analysis and performs sensitivity analysis for the each cost variables and shows that future burial costs increases are the major factors in the economic evaluation

  20. Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

    International Nuclear Information System (INIS)

    Christensen, E.J.; Gordon, D.E.

    1983-12-01

    The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

  1. The use of positron emission tomography in BNCT treatment planning for metastatic malignant melanoma and glioblastoma multiforme

    International Nuclear Information System (INIS)

    Kabalka, G.; Nichols, T.; Smith, G.; Miller, L.; Kahn, M.

    2000-01-01

    Positron emission tomography (PET) evaluations of six glioblastoma multiforme (GBM) and one metastatic melanoma (MM) patient have been carried out utilizing fluorine-18 labeled p-boronophenylalanine. Four of the GBM patients were imaged both prior to and post BNCT. In one GBM patient, biopsy derived boron distribution data compared favorably to the PET derived data. The PET data have been used as input to dosimetry calculations and the results vary from those obtained using current protocols. In addition, PET images of the thorax would indicate that the utility of PET for staging tumors for BNCT may extend beyond the brain. However, higher than anticipated levels of activity in the lungs (as also seen in salivary glands) indicate the more effective BNCT agents will be required. (author)

  2. Boron neutron capture therapy combined with fractionated photon irradiation for glioblastoma: A recursive partitioning analysis of BNCT patients

    International Nuclear Information System (INIS)

    Nakai, K.; Yamamoto, T.; Aiyama, H.; Takada, T.; Yoshida, F.; Kageji, T.; Kumada, H.; Isobe, T.; Endo, K.; Matsuda, M.; Tsurubuchi, T.; Shibata, Y.; Takano, S.; Mizumoto, M.; Tsuboi, K.; Matsumura, A.

    2011-01-01

    Eight patients to received Boron Neutron Capture Therapy (BNCT) were selected from 33 newly diagnosed glioblastoma patients (NCT(+) group). Serial 42 glioblastoma patients (NCT(−) group) were treated without BNCT. The median OS of the NCT(+) group and NCT (−) group were 24.4 months and 14.9 months. In the high risk patients (RPA class V), the median OS of the NCT(+) group tended to be better than that of NCT(−) group. 50% of BNCT patients were RPA class V. - Highlights: ► We treated 8 patients with boron neutron capture therapy (NCT) for glioblastoma. ► We compare the overall survival between NCT including series and without NCT series. ► The median overall survival of the NCT including series was 24.4 months. ► In the high risk patients, the median OS of NCT including series tended to be better.

  3. The hamster cheek pouch (HCP) as an experimental model of oral cancer for BNCT: biodistribution and pharmacokinetics of BPA

    International Nuclear Information System (INIS)

    Kreimann, E.; Itoiz, M.E.; Dagrosa, A.; Garavaglia, R.; Farias, S.; Batistoni, D.; Schwint, A.E.

    2000-01-01

    We propose and validate the HCP model of oral cancer for BNCT studies. This model serves to explore new applications of the technique, study the biology of BNCT and assess Boron uptake in clinically relevant oral tissues. Tumors are induced by a process that mimics spontaneous malignant transformation instead of by the growth of implanted tumor cells. Syrian hamsters were submitted to tumor induction with a chemical carcinogenesis protocol and then used for biodistribution and pharmacokinetic studies of BPA. The data reveal selective uptake by tumor and, to a lesser degree, by precancerous tissue. Boron concentration in oral tissues and skin was higher than in blood, an issue of clinical relevance given that these tissues may be dose-limiting. Absolute and relative values of Boron concentration would be potentially therapeutic. Boron concentration exhibited a linear relationship with percentage of viable tissue in HCP tumors. The HCP model would provide a novel, contributory approach to BNCT research. (author)

  4. Boron neutron capture therapy: Brain Tumor Treatment Evaluation Program

    International Nuclear Information System (INIS)

    Griebenow, M.L.; Dorn, R.V. III; Gavin, P.R.; Spickard, J.H.

    1988-01-01

    The United States (US) Department of Energy (DOE) recently initiated a focused, multidisciplined program to evaluate Boron Neutron Capture Therapy (BNCT) for the treatment of brain tumors. The program, centered at the DOE/endash/Idaho National Engineering Laboratory (INEL), will develop the analytical, diagnostic and treatment tools, and the database required for BNCT technical assessment. The integrated technology will be evaluated in a spontaneously-occurring canine brain-tumor model. Successful animal studies are expected to lead to human clinical trials within four to five years. 2 refs., 3 figs

  5. 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

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

    International Nuclear Information System (INIS)

    Fujii, Hitoshi; Tabata, Yasuhiko; Kaneda, Yasufumi; Sawa, Yoshiki; Lee, Chun Man; Matsuyama, Akifumi; Komoda, Hiroshi; Sasai, Masao; Suzuki, Minoru; Asano, Tomoyuki; Doki, Yuichiro; Kirihata, Mitsunori; Ono, Koji

    2011-01-01

    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 10 B 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 10 B 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 10 B (sodium borocaptate: BSH) delivery using HVJ-E and cationized gelatin for treating multiple liver tumors with BNCT without severe adverse events. 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. CG-HVJ-E reduced hemagglutination activity by half and was significantly less toxic in mice than HVJ-E. Higher 10 B 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 < 0.05). In suppressing the spread of tumor cells in mice, BNCT treatment was as effective with CG-HVJ-E-BSH as with BSH

  7. Variable thickness transient ground-water flow model. Volume 3. Program listings

    International Nuclear Information System (INIS)

    Reisenauer, A.E.

    1979-12-01

    The Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program is developing and applying the methodology for assessing the far-field, long-term post-closure safety of deep geologic nuclear waste repositories. AEGIS is being performed by Pacific Northwest Laboratory (PNL) under contract with the Office of Nuclear Waste Isolation (OWNI) for the Department of Energy (DOE). One task within AEGIS is the development of methodology for analysis of the consequences (water pathway) from loss of repository containment as defined by various release scenarios. Analysis of the long-term, far-field consequences of release scenarios requires the application of numerical codes which simulate the hydrologic systems, model the transport of released radionuclides through the hydrologic systems to the biosphere, and, where applicable, assess the radiological dose to humans. Hydrologic and transport models are available at several levels of complexity or sophistication. Model selection and use are determined by the quantity and quality of input data. Model development under AEGIS and related programs provides three levels of hydrologic models, two levels of transport models, and one level of dose models (with several separate models). This is the third of 3 volumes of the description of the VTT (Variable Thickness Transient) Groundwater Hydrologic Model - second level (intermediate complexity) two-dimensional saturated groundwater flow

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

    International Nuclear Information System (INIS)

    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.

    2009-01-01

    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.

  9. High neutronic efficiency, low current targets for accelerator-based BNCT applications

    International Nuclear Information System (INIS)

    Powell, J.R.; Ludewig, H.; Todosow, M.

    1998-01-01

    The neutronic efficiency of target/filters for accelerator-based BNCT applications is measured by the proton current required to achieve a desirable neutron current at the treatment port (10 9 n/cm 2 /s). In this paper the authors describe two possible targeyt/filter concepts wihch minimize the required current. Both concepts are based on the Li-7 (p,n)Be-7 reaction. Targets that operate near the threshold energy generate neutrons that are close tothe desired energy for BNCT treatment. Thus, the filter can be extremely thin (∼ 5 cm iron). However, this approach has an extremely low neutron yield (n/p ∼ 1.0(-6)), thus requiring a high proton current. The proposed solutino is to design a target consisting of multiple extremely thin targets (proton energy loss per target ∼ 10 keV), and re-accelerate the protons between each target. Targets operating at ihgher proton energies (∼ 2.5 MeV) have a much higher yield (n/p ∼ 1.0(-4)). However, at these energies the maximum neutron energy is approximately 800 keV, and thus a neutron filter is required to degrade the average neutron energy to the range of interest for BNCT (10--20 keV). A neutron filter consisting of fluorine compounds and iron has been investigated for this case. Typically a proton current of approximately 5 mA is required to generate the desired neutron current at the treatment port. The efficiency of these filter designs can be further increased by incorporating neutron reflectors that are co-axial with the neutron source. These reflectors are made of materials which have high scattering cross sections in the range 0.1--1.0 MeV

  10. 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.

  11. Co-registration of the BNCT treatment planning images for clinical practice

    International Nuclear Information System (INIS)

    Salli, Eero; Seppaelae, Tiina; Kankaanranta, Leena; Asikainen, Sami; Savolainen, Sauli; Koivunoro, Hanna

    2006-01-01

    We have co-registered MRI, CT and FBPA-PET images for BNCT in clinical practice. Co-registration improves the spatial accuracy of the treatment planning by enabling use of information from all the co-registered modalities. The multimodal co-registration has been implemented as a service product provided by the Imaging Center of Helsinki University Central Hospital to other departments. To increase the accuracy of co-registration and patient positioning in the head area BNCT, a patient-specific fixation mask suitable for PET, MRI and CT was developed. The goal of the fixation mask is to normalize the orientation of the patient's head and neck. Co-registration is performed at the image processing unit by using a rigid body model, mutual-information based algorithms and partly in-house developed software tools. The accuracy of co-registration is verified by comparing the locations of the external skin markers and anatomical landmarks in different modalities. After co-registration, the images are transformed and covered into a format required by the BNCT dose-planning software and set to the dose-planning unit of the hospital. So far co-registration has been done for 22 patients. The co-registration protocol has proved to be reliable and efficient. Some registration errors are seen on some patients in the neck area because the rigid-body model used in co-registration is not fully valid for the brain-neck entity. The registration accuracy in this area could likely be improved by implementing a co-registration procedure utilizing a partly non-rigid body model. (author)

  12. Neutron field characterization in the installation for BNCT study in the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Carneiro Junior, Valdeci

    2008-01-01

    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 8 ± 0,12.10 8 n/cm 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)

  13. Application of HVJ envelope system to boron neutron capture therapy (BNCT)

    International Nuclear Information System (INIS)

    Nakai, Kei; Kurooka, Masaaki; Kaneda, Yasufumi; Yamamoto, Tetsuya; Matsumura, Akira; Asano, Tomoyuki

    2006-01-01

    Boron Neutron Capture Therapy (BNCT) has been used clinically for the treatment of malignant tumors. Two drugs, p-boronophenylalanine (BPA) and sulfhydral borane (BSH), have been used as boron delivery agents. These drugs seem to be taken up preferentially in solid tumors, but it is uncertain whether therapeutic quantities of boron atoms are taken up by micro-invasive or distant tumor cells. High accumulation and high selective delivery of boron into tumor tissues are the most important requirements to achieve efficient BNCT for malignant tumor. The HVJ envelope (HVJ-E) vector system is a novel fusion-mediated gene delivery system based on inactivated hemagglutinating virus of Japan (HVJ; Sendai virus). Although we developed this vector system for gene transfer, it can also deliver proteins, synthetic oligonucleotides, and drugs. HVJ-liposome, which is liposome fused with HVJ-E, has higher boron trapping efficiency than HVJ-E alone. We report the boron delivery into cultured cells with HVJ-liposome systems. The cellular 10 B concentration after 60 min incubation with HVJ-E containing BSH was 24.9 μg/g cell pellet for BHK-21 cells (baby hamster kidney cells) and 19.4 μg/g cell pellet for SCC VII cells (murine squamous cell carcinoma). These concentrations are higher than that of 60 min incubated cells with BSH containing (100μg 10 B/ml) medium. These results indicate the HVJ-E fused with tumor cell membrane and rapidly delivered boron agents, and that the HVJ-E-mediated delivery system could be applicable to BNCT. Plans are underway to begin neutron radiation experiments in vivo and in vitro. (author)

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

    International Nuclear Information System (INIS)

    Nigg, D.W.; Venhuizen, J.R.; Wheeler, F.J.; Wemple, C.A.; Tripard, G.E.; Gavin, P.R.

    2000-01-01

    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. Collimator and shielding design for boron neutron capture therapy (BNCT) facility at TRIGA MARK II reactor

    International Nuclear Information System (INIS)

    Mohd Rafi Mohd Solleh; Abdul Aziz Tajuddin; Abdul Aziz Mohamed; Eid Mahmoud Eid Abdel Munem; Mohamad Hairie Rabir; Julia Abdul Karim; Yoshiaki, Kiyanagi

    2011-01-01

    The geometry of reactor core, thermal column, collimator and shielding system for BNCT application of TRIGA MARK II Reactor were simulated with MCNP5 code. Neutron particle lethargy and dose were calculated with MCNPX code. Neutron flux in a sample located at the end of collimator after normalized to measured value (Eid Mahmoud Eid Abdel Munem, 2007) at 1 MW power was 1.06 x 10 8 n/ cm 2 / s. According to IAEA (2001) flux of 1.00 x 10 9 n/ cm 2 / s requires three hours of treatment. Few modifications were needed to get higher flux. (Author)

  16. Development of the patient setting system for BNCT at JRR-4

    International Nuclear Information System (INIS)

    Kumada, H.; Yamamoto, K.; Torii, Y.

    2000-01-01

    A new treatment planning software: Computational Dosimetry System (JCDS) is in progress its development for BNCT with epithermal neutron beam in JAERI. Irradiation conditions such as beam angle to a patient are calculated by JCDS. In order to implement these conditions, it is necessary to precisely set the patient to actual irradiation position simulated by JCDS beforehand. Therefore, the Patient Setting System, which accurately and quickly sets the patient to the irradiation position, is being developed with JCDS concurrently. In this report, the current status of the development of JCDS and the Patient Setting System in JAERI will be described. (author)

  17. Spectrum shaping assessment of accelerator-based fusion neutron sources to be used in BNCT treatment

    Science.gov (United States)

    Cerullo, N.; Esposito, J.; Daquino, G. G.

    2004-01-01

    Monte Carlo modelling of an irradiation facility, for boron neutron capture therapy (BNCT) application, using a set of advanced type, accelerator based, 3H(d,n) 4He (D-T) fusion neutron source device is presented. Some general issues concerning the design of a proper irradiation beam shaping assembly, based on very hard energy neutron source spectrum, are reviewed. The facility here proposed, which represents an interesting solution compared to the much more investigated Li or Be based accelerator driven neutron source could fulfil all the medical and safety requirements to be used by an hospital environment.

  18. Design of a beam shaping assembly for an accelerator-based BNCT system

    International Nuclear Information System (INIS)

    Stichelbaut, F.; Forton, E.; Jongen, Y.

    2006-01-01

    A complete BNCT system based on a high-intensity proton accelerator is developed by the IBA company. The neutron beam is produced via the 7 Li(p,n) 7 Be reaction using a solid lithium target. The neutron energy spectrum is tailored with a beam shaping assembly surrounding the target. This device is the object of an extensive R and D project and is fully designed with the Monte Carlo simulation code MCNPX. The emphasis is put on the treatment quality, notably the radiation dose at the skin level, and the achievable neutron flux. (author)

  19. Beam shaping assembly optimization for (7)Li(p,n)(7)Be accelerator based BNCT.

    Science.gov (United States)

    Minsky, D M; Kreiner, A J

    2014-06-01

    Within the framework of accelerator-based BNCT, a project to develop a folded Tandem-ElectroStatic-Quadrupole accelerator is under way at the Atomic Energy Commission of Argentina. The proposed accelerator is conceived to deliver a proton beam of 30mA at about 2.5MeV. In this work we explore a Beam Shaping Assembly (BSA) design based on the (7)Li(p,n)(7)Be neutron production reaction to obtain neutron beams to treat deep seated tumors. © 2013 Elsevier Ltd. All rights reserved.

  20. In vitro studies of the cellular response to boron neutron capture therapy (BNCT) in thyroid carcinoma

    International Nuclear Information System (INIS)

    Rodriguez, C; Carpano, M; Perona, M; Thorp, S; Curotto, P; Pozzi, E; Casal, M; Juvenal, G; Pisarev, M; Dagrosa, A

    2012-01-01

    Background: Previously, we have started to study the mechanisms of DNA damage and repair induced by BNCT in thyroid carcinoma some years ago. We have shown different genotoxic patterns for tumor cells irradiated with gamma rays, neutrons alone or neutrons plus different compounds, boronophenylalanine (BPA) or α, β - dihydroxyethyl)-deutero-porphyrin IX (BOPP). In the present study we analyzed the expression of Ku70, Rad51 and Rad54 components of non homologous end-joing (NHEJ) and homologous recombination repair (HRR) pathways, respectively, induced by BNCT in human cells of thyroid carcinoma. Methods: A human cell line of follicular thyroid carcinoma (WRO) in exponential growth phase was distributed into the following groups: 1) Gamma Radiation, 2) Radiation with neutrons beam (NCT), 3) Radiation with n th in presence of BPA (BNCT). A control group for each treatment was added. The cells were irradiated in the thermal column facility of the RA-3 reactor (flux= 1.10 10 n/cm 2 sec) or with a source of 60 Co. The irradiations were performed during different lapses in order to obtain a total physical dose of 3 Gy (±10%). The mRNA expressions of Ku70, Rad 51 and Rad 54 were analysed by reverse transcription-polymerase chain reaction (RT-PCR) at different times post irradiation (2, 4, 6, 24 and 48 h). DNA damage was evaluated by immunofluorescence using an antibody against the phosphorylation of histone H2AX, which indicates double strand breaks in the DNA. Results: The expression of Rad51 increased at 2 h post-irradiation and it lasted until 6 h only in the neutron and neutron + BPA groups (p<0.05). Rad54 showed an up-regulation from 2 to 24 h in both groups irradiated with the neutron beam (with and without BPA) (p<0.05). On the other hand, Ku70 mRNA did not show a modification of its expression in the irradiated groups respect to the control group. Conclusion: these results would indicate an activation of the HRR pathway in the thyroid carcinoma cells treated by

  1. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    International Nuclear Information System (INIS)

    1980-06-01

    The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear materials or facilities of such programs, whether in nuclear-weapons states (NWS's) or nonnuclear-weapons states (NNW's). Accordingly, this volume emphasizes one important factor in such decisions, the resistance of nuclear-power systems to the proliferation of nuclear-weapons capabilities

  2. National Aeronautics and Space Administration (NASA)/American Society for Engineering Education (ASEE) Summer Faculty Fellowship Program, 1998. Volume 1

    Science.gov (United States)

    Bannerot, Richard B. (Editor); Sickorez, Donn G. (Editor)

    1999-01-01

    JSC NASA/ASEE Summer Faculty Fellowship Program was conducted by the University of Houston and JSC, under ASEE. The objectives of the program are to further the professional knowledge of qualified engineering and science members; stimulate an exchange of ideas between participants and NASA; enrich and refresh the research and teaching activities of participants; and contribute to the research objectives of the NASA Centers. Each faculty fellow spent at least 10 weeks at JSC engaged in a research project commensurate with his/her interests and background and worked in collaboration with a NASA/JSC colleague. This document is a compilation of the final reports on the fellows' research projects performed during the summer of 1998. Volume 1, current volume, contains the first reports, and volume 2 contains the remaining reports.

  3. Mod-5A wind turbine generator program design report. Volume 4: Drawings and specifications, book 5

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. There are four volumes. This volume contains the drawings and specifications that were developed in preparation for building the MOD-5A wind turbine generator. Detail drawings of several assemblies and subassemblies are given. This is the fifth book of volume 4.

  4. Tumor control induced by Boron Neutron Capture Therapy (BNCT) as a function of dose in an experimental model of liver metastases at 5 weeks follow-up

    International Nuclear Information System (INIS)

    Pozzi, E C C; Trivillin, V A; Colombo, L L; Monti Hughes, A; Thorp, S; Cardoso, J E; Garabalino, M A; Molinari, A J; Heber, E M; Curotto, Paula; Miller, M; Itoiz, M E; Aromando, R F; Nigg, D W; Schwint, A E

    2012-01-01

    BNCT has been proposed for the treatment of multifocal, non-resectable, bilobar colorectal liver metastases that do not respond to chemotherapy. We recently reported that BNCT mediated by boronophenylalanine (BPA) induced significant remission of experimental colorectal tumor nodules in rat liver at 3 weeks follow-up with no contributory liver toxicity (Pozzi et al.,2012). The aim of the present study was to evaluate tumor control and potential liver toxicity of BPA-BNCT at 5 weeks follow-up. Prescribed dose was retrospectively evaluated based on blood boron values, allowing for assessment of response over a range of delivered dose values (author)

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

    Science.gov (United States)

    Fujimoto, T; Andoh, T; Sudo, T; Fujita, I; Imabori, M; Moritake, H; Sugimoto, T; Sakuma, Y; Takeuchi, T; Sonobe, H; Epstein, Alan L; Akisue, T; Kirihata, M; Kurosaka, M; Fukumori, Y; Ichikawa, H

    2011-12-01

    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. Copyright © 2011 Elsevier Ltd. All rights reserved.

  6. Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

    International Nuclear Information System (INIS)

    Stone, J.A.; Christensen, E.J.

    1983-12-01

    This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

  7. RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation

    International Nuclear Information System (INIS)

    1976-06-01

    A discussion is presented of the use of the RELAP4/MOD5 computer program in simulating the thermal-hydraulic behavior of light-water reactor systems when subjected to postulated transients such as a LOCA, pump failure, or nuclear excursion. The volume is divided into main sections which cover: (1) program description, (2) input data, (3) problem initialization, (4) user guidelines, (5) output discussion, (6) source program description, (7) implementation requirements, (8) data files, (9) description of PLOTR4M, (10) description of STH20, (11) summary flowchart, (12) sample problems, (13) problem definition, and (14) problem input

  8. 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.

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

    International Nuclear Information System (INIS)

    Bakeine, G.J.; Di Salvo, M.; Bortolussi, S.; Stella, S.; Bruschi, P.; Bertolotti, A.; Nano, R.; Clerici, A.; Ferrari, C.; Zonta, C.; Marchetti, A.; Altieri, S.

    2009-01-01

    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.

  10. Feasibility of the utilization of BNCT in the fast neutron therapy beam at Fermilab

    International Nuclear Information System (INIS)

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

    2000-01-01

    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

  11. {sup 124}Sb–Be photo-neutron source for BNCT: Is it possible?

    Energy Technology Data Exchange (ETDEWEB)

    Golshanian, Mohadeseh [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of); Department of Physics, Shahrood University, Shahrood (Iran, Islamic Republic of); Rajabi, Ali Akbar [Department of Physics, Shahrood University, Shahrood (Iran, Islamic Republic of); Kasesaz, Yaser, E-mail: ykasesaz@aeoi.org.ir [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of)

    2016-11-01

    In this research a computational feasibility study has been done on the use of {sup 124}SbBe 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 {sup 124}Sb, the epithermal neutron flux at the designed beam exit is 0.23×10{sup 9} (n/cm{sup 2} 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 {sup 124}Sb could be achieved using three 50 kCi rods of {sup 124}Sb 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.

  12. 9Be(d,n)10B-based neutron sources for BNCT

    International Nuclear Information System (INIS)

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

    2014-01-01

    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 ≥40 Gy-Eq, with a maximum value of 51 Gy-Eq at a depth of about 2.7 cm, in a 60 min 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. - Highlights: • Study of the 9 Be(d,n) 10 B reaction as a source of epithermal neutrons for BNCT. • Evaluation of the optimal configuration of target thickness, deuteron energy and BSA design. • Computational dose assessment for brain tumor treatments using the MCNP code. • Treatment planning assessment of a particular clinical Glioblastoma Multiforme case. • Dose performances were comparable to those obtained with an optimized 7 Li(p,n)-based source

  13. Radiation field characterization of a BNCT research facility using Monte Carlo method - code MCNP-4B

    International Nuclear Information System (INIS)

    Hernandez, Antonio Carlos

    2002-01-01

    Boron Neutron Capture Therapy - BNCT - is a selective cancer treatment and arises as an alternative therapy to treat cancer when usual techniques - surgery, chemotherapy or radiotherapy - show no satisfactory results. The main proposal of this work is to project a facility to BNCT studies. This facility relies on the use of an Am Be neutron source and on a set of moderators, filters and shielding which will provide the best neutron/gamma beam characteristic for these Becton studies, i.e., high intensity thermal and/or epithermal neutron fluxes and with the minimum feasible gamma rays and fast neutrons contaminants. A computational model of the experiment was used to obtain the radiation field in the sample irradiation position. The calculations have been performed with the MCNP 4B Monte Carlo Code and the results obtained can be regarded as satisfactory, i.e., a thermal neutron fluencyN T = 1,35x10 8 n/cm , a fast neutron dose of 5,86x10 -10 Gy/N T and a gamma ray dose of 8,30x10 -14 Gy/N T . (author)

  14. Calculation of fluence rate distributions in a pre design clinical facility for BNCT at the LFR

    International Nuclear Information System (INIS)

    Peeters, T.T.J.M.; Freudenreich, W.E.

    1995-12-01

    In a previous study [1], it was demonstrated that the creation of a thermal neutron facility for clinical BNCT in the LFR is feasible. Monte Carlo calculations had shown that the neutron fluence rates and gamma dose rates at the detector position of a model representing a first outline of a clinical facility met all requirements that are necessary for clinical BNCT. In order to gain more information about the neutron fluence rates at several positions, a second step is required. Calculations have been performed for the free beam and for a tumour bearing phantom at 5 cm and 10 cm distance from the irradiation window. Due to thermalization and back scattering, the thermal fluence rates in the tumour at 5 and 10 cm distance from the bismuth shield appeared to be approximately twice as high as the thermal fluence rates in the free beam at the corresponding positions of 5 to 6 cm and 10 to 11 cm from the irradiation window. (orig.)

  15. Design of thermal neutron beam based on an electron linear accelerator for BNCT.

    Science.gov (United States)

    Zolfaghari, Mona; Sedaghatizadeh, Mahmood

    2016-12-01

    An electron linear accelerator (Linac) can be used for boron neutron capture therapy (BNCT) by producing thermal neutron flux. In this study, we used a Varian 2300 C/D Linac and MCNPX.2.6.0 code to simulate an electron-photoneutron source for use in BNCT. In order to decelerate the produced fast neutrons from the photoneutron source, which optimize the thermal neutron flux, a beam-shaping assembly (BSA) was simulated. After simulations, a thermal neutron flux with sharp peak at the beam exit was obtained in the order of 3.09×10 8 n/cm 2 s and 6.19×10 8 n/cm 2 s for uranium and enriched uranium (10%) as electron-photoneutron sources respectively. Also, in-phantom dose analysis indicates that the simulated thermal neutron beam can be used for treatment of shallow skin melanoma in time of about 85.4 and 43.6min for uranium and enriched uranium (10%) respectively. Copyright © 2016. Published by Elsevier Ltd.

  16. A phase-I clinical trial for cranial BNCT at Harvard-MIT

    International Nuclear Information System (INIS)

    Busse, P.M.; Palmer, M.R.; Harling, O.K.

    2000-01-01

    Phase I trial designed to determine the maximum tolerable dose to normal tissue for cranial BNCT (Boron Neutron Capture Therapy) irradiations was recently completed at Harvard Medical School and MIT. Twenty-two subjects diagnosed with either glioblastoma multiforme or intracranial melanoma were treated between 1996 and 1999. Subjects received either one or two administrations of boronophenylalanine intravenously at doses between 250 and 350 mg/kg body weight, then exposed in one, two or three fields to epithermal neutrons at the MIT Research Reactor in one or two fractions. Over the course of the study, the maximum normal tissue dose target was increased from 8.8 to 14.2 RBE (Relative Biological Effectiveness) Gy in 10% increments. Subjects have been followed clinically and radiographically. Of those patients surviving beyond six months, no MRI (Magnetic Resonance Image) white-matter changes were observed and no long-term complications attributable to BNCT were evident. Tumor responses were observed, particularly with the melanoma subjects. With increasing doses, difficulties arose from long irradiation times (approximately 3 hours) and the emergence of acute reactions in the skin and mucosa. The trial was stopped in May 1999. Future trials will be initiated with the new high intensity, low background fission converter beam at MIT. (author)

  17. Biodistribution of Boron compounds in an experimental model of liver metastases for Boron Neutron Capture (BNCT) Studies

    International Nuclear Information System (INIS)

    Garabalino, Marcela A.; Monti Hughes, Andrea; Molinari, Ana J.; Heber, Elisa M.; Pozzi, Emiliano C.C.; Itoiz, Maria E.; Trivillin, Veronica A.; Schwint, Amanda E.; Nievas, Susana; Aromando, Romina F.

    2009-01-01

    Boron Neutron Capture Therapy (BNCT) is a binary treatment modality that involves the selective accumulation of 10 B carriers in tumors followed by irradiation with thermal or epithermal neutrons. The high linear energy transfer alpha particles and recoiling 7 Li nuclei emitted during the capture of a thermal neutron by a 10 B nucleus have a short range and a high biological effectiveness. Thus, BNCT would potentially target neoplastic tissue selectively. In previous studies we demonstrated the therapeutic efficacy of different BNCT protocols in an experimental model of oral cancer. More recently we performed experimental studies in normal rat liver that evidenced the feasibility of treating liver metastases employing a novel BNCT protocol proposed by JEC based on ex-situ treatment and partial liver auto-transplant. The aim of the present study was to perform biodistribution studies with different boron compounds and different administration protocols to determine the protocols that would be therapeutically useful in 'in vivo' BNCT studies at the RA-3 Nuclear Reactor in an experimental model of liver metastases in rats. Materials and Methods. A total of 70 BDIX rats (Charles River Lab., MA, USA) were inoculated in the liver with syngeneic colon cancer cells DH/DK12/TRb (ECACC, UK) to induce the development of subcapsular metastatic nodules. 15 days post-inoculation the animals were used for biodistribution studies. A total of 11 protocols were evaluated employing the boron compounds boronophenylalanine (BPA) and GB-10 (Na 2 10 B 1 -0H 10 ), alone or combined employing different doses and administration routes. Tumor, normal tissue and blood samples were processed for boron measurement by ICP-OES. Results. Several protocols proved potentially useful for BNCT studies in terms of absolute boron concentration in tumor and preferential uptake of boron by tumor tissue, i.e. BPA 15.5 mg 10 B/kg iv + GB-10 50 mg 10 B/kg iv; BPA 46.5 mg 10 B/kg ip; BPA 46.5 mg 10 B/kg ip

  18. Low Cost High Performance Generator Technology Program. Volume 4. Mission application study

    International Nuclear Information System (INIS)

    1975-07-01

    Results of initial efforts to investigate application of selenide thermoelectric RTG's to specific missions as well as an indication of development requirements to enable satisfaction of emerging RTG performance criteria are presented. Potential mission applications in DoD such as SURVSATCOM, Advance Defense Support Program, Laser Communication Satellite, Satellite Data System, Global Positioning Satellite, Deep Space Surveillance Satellite, and Unmanned Free Swimming Submersible illustrate power requirements in the range of 500 to 1000 W. In contrast, the NASA applications require lower power ranging from 50 W for outer planetary atmospheric probes to about 200 W for spacecraft flights to Jupiter and other outer planets. The launch dates for most of these prospective missions is circa 1980, a requirement roughly compatible with selenide thermoelectric and heat source technology development. A discussion of safety criteria is included to give emphasis to the requirements for heat source design. In addition, the observation is made that the potential accident environments of all launch vehicles are similar so that a reasonable composite set of design specifications may be derived to satisfy almost all applications. Details of the LCHPG application potential is afforded by three designs: an 80 W RTG using improved selenide thermoelectric material, a 55 to 65 W LCHPG using current and improved selenide materials, and the final 500 W LCHPG as reported in Volume 2. The final results of the LCHPG design study have shown that in general, all missions can expect an LCHPG design which yields 10 percent efficiency at 3 W/lb with the current standard selenide thermoelectric materials, with growth potential to 14 percent at greater than 4 W/lb in the mid 1980's time frame

  19. Impacts of Outer Continental Shelf (OCS) development on recreation and tourism. Volume 5. Program logic manual

    Energy Technology Data Exchange (ETDEWEB)

    1987-04-01

    The final report for the project is presented in five volumes. This volume is the Programmer's Manual. It covers: a system overview, attractiveness component of gravity model, trip-distribution component of gravity model, economic-effects model, and the consumer-surplus model. The project sought to determine the impact of Outer Continental Shelf development on recreation and tourism.

  20. Evaluation of spacecraft technology programs (effects on communication satellite business ventures), volume 2

    Science.gov (United States)

    Greenburg, J. S.; Kaplan, M.; Fishman, J.; Hopkins, C.

    1985-01-01

    The computational procedures used in the evaluation of spacecraft technology programs that impact upon commercial communication satellite operations are discussed. Computer programs and data bases are described.

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

    Energy Technology Data Exchange (ETDEWEB)

    Pozzi, E. [Research and Production Reactors, National Atomic Energy Commission, Ezeiza Atomic Center (Argentina); Department of Radiobiology, National Atomic Energy Commission, Constituyentes Atomic Center (Argentina)], E-mail: epozzi@cnea.gov.ar; Nigg, D.W. [Idaho National Laboratory, Idaho Falls (United States); Miller, M.; Thorp, S.I. [Instrumentation and Control Department, National Atomic Energy Commission, Ezeiza Atomic Center (Argentina); Heber, E.M. [Department of Radiobiology, National Atomic Energy Commission, Constituyentes Atomic Center (Argentina); Zarza, L.; Estryk, G. [Research and Production Reactors, National Atomic Energy Commission, Ezeiza Atomic Center (Argentina); Monti Hughes, A.; Molinari, A.J.; Garabalino, M. [Department of Radiobiology, National Atomic Energy Commission, Constituyentes Atomic Center (Argentina); Itoiz, M.E. [Department of Radiobiology, National Atomic Energy Commission, Constituyentes Atomic Center (Argentina); Department of Oral Pathology, Faculty of Dentistry, University of Buenos Aires (Argentina); Aromando, R.F. [Department of Oral Pathology, Faculty of Dentistry, University of Buenos Aires (Argentina); Quintana, J. [Research and Production Reactors, National Atomic Energy Commission, Ezeiza Atomic Center (Argentina); Trivillin, V.A.; Schwint, A.E. [Department of Radiobiology, National Atomic Energy Commission, Constituyentes Atomic Center (Argentina)

    2009-07-15

    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 7.1x10{sup 9} n cm{sup -2} s{sup -1} and the fast neutron flux was 2.5x10{sup 6} n cm{sup -2} s{sup -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 {sup 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. Dosimetry and radiobiology at the new RA-3 reactor boron neutron capture therapy (BNCT) facility: Application to the treatment of experimental oral cancer

    International Nuclear Information System (INIS)

    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.

    2009-01-01

    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 7.1x10 9 n cm -2 s -1 and the fast neutron flux was 2.5x10 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.

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

    International Nuclear Information System (INIS)

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

    1998-01-01

    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 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 experiments

  4. Comparison of the radiobiological effects of Boron neutron capture therapy (BNCT) and conventional Gamma Radiation

    International Nuclear Information System (INIS)

    Dagrosa, Maria A.; Carpano, Marina; Perona, Marina; Thomasz, Lisa; Juvenal, Guillermo J.; Pisarev, Mario; Pozzi, Emiliano; Thorp, Silvia

    2009-01-01

    BNCT is an experimental radiotherapeutic modality that uses the capacity of the isotope 10 B to capture thermal neutrons leading to the production of 4 He and 7 Li, particles with high linear energy transfer (LET). The aim was to evaluate and compare in vitro the mechanisms of response to the radiation arising of BNCT and conventional gamma therapy. We measured the survival cell fraction as a function of the total physical dose and analyzed the expression of p27/Kip1 and p53 by Western blotting in cells of colon cancer (ARO81-1). Exponentially growing cells were distributed into the following groups: 1) BPA (10 ppm 10 B) + neutrons; 2) BOPP (10 ppm 10 B) + neutrons; 3) neutrons alone; 4) gamma-rays. A control group without irradiation for each treatment was added. The cells were irradiated in the thermal neutron beam of the RA-3 (flux= 7.5 10 9 n/cm 2 sec) or with 60 Co (1Gy/min) during different times in order to obtain total physical dose between 1-5 Gy (±10 %). A decrease in the survival fraction as a function of the physical dose was observed for all the treatments. We also observed that neutrons and neutrons + BOPP did not differ significantly and that BPA was the more effective compound. Protein extracts of irradiated cells (3Gy) were isolated to 24 h and 48 h post radiation exposure. The irradiation with neutrons in presence of 10 BPA or 10 BOPP produced an increase of p53 at 24 h maintain until 48 h. On the contrary, in the groups irradiated with neutrons alone or gamma the peak was observed at 48 hr. The level of expression of p27/Kip1 showed a reduction of this protein in all the groups irradiated with neutrons (neutrons alone or neutrons plus boron compound), being more marked at 24 h. These preliminary results suggest different radiobiological response for high and low let radiation. Future studies will permit establish the role of cell cycle in the tumor radio sensibility to BNCT. (author)

  5. Comparison of the image-derived radioactivity and blood-sample radioactivity for estimating the clinical indicators of the efficacy of boron neutron capture therapy (BNCT): 4-borono-2-18F-fluoro-phenylalanine (FBPA) PET study.

    Science.gov (United States)

    Isohashi, Kayako; Shimosegawa, Eku; Naka, Sadahiro; Kanai, Yasukazu; Horitsugi, Genki; Mochida, Ikuko; Matsunaga, Keiko; Watabe, Tadashi; Kato, Hiroki; Tatsumi, Mitsuaki; Hatazawa, Jun

    2016-12-01

    In boron neutron capture therapy (BNCT), positron emission tomography (PET) with 4-borono-2- 18 F-fluoro-phenylalanine (FBPA) is the only method to estimate an accumulation of 10 B to target tumor and surrounding normal tissue after administering 10 B carrier of L-paraboronophenylalanine and to search the indication of BNCT for individual patient. Absolute concentration of 10 B in tumor has been estimated by multiplying 10 B concentration in blood during BNCT by tumor to blood radioactivity (T/B) ratio derived from FBPA PET. However, the method to measure blood radioactivity either by blood sampling or image data has not been standardized. We compared image-derived blood radioactivity of FBPA with blood sampling data and studied appropriate timing and location for measuring image-derived blood counts. We obtained 7 repeated whole-body PET scans in five healthy subjects. Arterialized venous blood samples were obtained from the antecubital vein, heated in a heating blanket. Time-activity curves (TACs) of image-derived blood radioactivity were obtained using volumes of interest (VOIs) over ascending aorta, aortic arch, pulmonary artery, left and right ventricles, inferior vena cava, and abdominal aorta. Image-derived blood radioactivity was compared with those measured by blood sampling data in each location. Both the TACs of blood sampling radioactivity in each subject, and the TACs of image-derived blood radioactivity showed a peak within 5 min after the tracer injection, and promptly decreased soon thereafter. Linear relationship was found between blood sampling radioactivity and image-derived blood radioactivity in all the VOIs at any timing of data sampling (p radioactivity measured in the left and right ventricles 30 min after injection showed high correlation with blood radioactivity. Image-derived blood radioactivity was lower than blood sampling radioactivity data by 20 %. Reduction of blood radioactivity of FBPA in left ventricle after 30 min of FBPA

  6. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    International Nuclear Information System (INIS)

    1979-12-01

    Volume IV provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest

  7. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest.

  8. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    International Nuclear Information System (INIS)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest

  9. National Aeronautics and Space Administration (NASA)/American Society for Engineering Education (ASEE) summer faculty fellowship program, 1986, Volume 1

    International Nuclear Information System (INIS)

    Mcinnis, B.; Goldstein, S.

    1987-06-01

    The Johnson Space Center (JSC) NASA/ASEE Summer Faculty Fellowship Program was conducted by the University of Houston. The basic objectives of the program are: (1) to further the professional knowledge of qualified engineering and science faculty members; (2) to stimulate an exchange of ideas between participants and NASA; (3) to enrich and refresh the research and teaching objectives of participants' institutions; and (4) to contribute to the research objectives of the NASA Centers. Each faculty fellow spent ten weeks at JSC engaged in a research project commensurate with his interests and background and worked in collaboration with a NASA/JSC colleague. Volume 1 contains sections 1 through 14

  10. Mod-5A wind turbine generator program design report. Volume 4: Drawings and specifications, book 4

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator are documented. There are four volumes. This volume contains the drawings and specifications that were developed in preparation for building the MOD-5A wind turbine generator. This volume contains 5 books of which this is the fourth, providing drawings 47A380128 through 47A387125. In addition to the parts listing and where-used list, the logic design of the controller software and the code listing of the controller software are provided. Also given are the aerodynamic profile coordinates.

  11. Mod-5A wind turbine generator program design report. Volume 4: Drawings and specifications, book 2

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. There are four volumes. This volume contains the drawings and specifications that were developed in preparation for building the MOD-5A wind turbine generator. This is the second book of volume four. Some of the items it contains are specs for the emergency shutdown panel, specs for the simulator software, simulator hardware specs, site operator terminal requirements, control data system requirements, software project management plan, elastomeric teeter bearing requirement specs, specs for the controls electronic cabinet, and specs for bolt pretensioning.

  12. Short-term moderate intensive high volume training program provides aerobic endurance benefit in wheelchair basketball players.

    Science.gov (United States)

    Skucas, Kestutis; Pokvytyte, Vaida

    2017-04-01

    The aim of this paper was to investigate the effect of short-term period, moderate intensity and high volume endurance training on physiological variables in elite wheelchair basketball players. Eight wheelchair basketball players were examined. The subjects participated in a two-week intervention program of mainly two training types: wheelchair basketball and wheelchair driving endurance training. The subjects performed the continuously increasing cycling exercise (CCE) at the constant 60 rpm arm cranking speed at the beginning of the program and after two weeks of the program. The initial workload was 20 W, then the workload was increased by 2 W every 5 seconds until fatigue. The post training of the wheelchair basketball group in the study showed a significant improvement in the peak oxygen uptake (VO2peak) and the peak power output (POpeak). VO2peak increased by 9% from 2.32±0.16 L/min to 2.53±0.2 L/min (Pbasketball squad had relatively high levels of aerobic fitness prior to participating in the endurance training program. Nevertheless, the high-volume, moderate-intensity, short-term training program, which evolved over the two-weeks period, resulted in the improvement of the athlete's aerobic endurance. The ventilatory threshold (VT) and the second ventilatory threshold (VT2) are good markers for aerobic capacity of wheelchair athletes.

  13. Comparison of three experimental protocols in pre clinical studies for thyroid cancer treatment using sodium butyrate in combination with boron neutron capture therapy (BNCT)

    International Nuclear Information System (INIS)

    Perona, M; Rodriguez, C; Carpano, M; Majdalani E; Nievas, S; Olivera, M; Pisarev, M; Cabrini, R; Juvenal, G; Dagrosa A

    2012-01-01

    for group 2 (NaB 3.4% plus BPA) and of 22.5 ± 0.9 ppm for the group which received BPA alone. The tumor/blood and tumor/surrounding skin ratios were 6.93 and 2.85 for group 1; 6.22 and 2.49 for group 2 and 4.25 and 2.12 for group 3. Conclusions: The chronic administration of sodium butyrate in the water ad libitum did not affect the body weight and decreased the tumor volume showing an antitumoral compound activity by itself. However the BPA uptake was lower in this group than in the BPA group alone, which could be due to a decrease of the proliferative rate. The group which received NaB 24 h before BPA administration showed an increase in the tumor boron uptake that could be attributed to an increase in the expression of the BPA transporter. The sodium butyrate could be combined to BNCT for optimization of the treatment of thyroid carcinoma (author)

  14. Tumor development in field-cancerized tissue is inhibited by a double application of Boron neutron capture therapy (BNCT) without exceeding radio-tolerance

    International Nuclear Information System (INIS)

    Monti Hughes, Andrea; Heber, Elisa M.; Itoiz, Maria E.; Molinari, Ana J.; Garabalino, Marcela A.; Trivillin, Veronica A.; Schwint, Amanda E.; Aromando, Romina F.

    2009-01-01

    Introduction: BNCT is based on the capture reaction between boron, selectively targeted to tumor tissue, and thermal neutrons which gives rise to lethal, short-range high linear energy transfer particles that selectively damage tumor tissue, sparing normal tissue. We previously evidenced a remarkable therapeutic success of a 'single' application of boron neutron capture therapy (BNCT) mediated by boronophenylalanine (BPA), GB-1(Na 2 10 B 10 H 10 ) or (GB-10+BPA) to treat hamster cheek pouch tumors with no normal tissue radiotoxicity. Based on these results, we developed a model of precancerous tissue in the hamster cheek pouch for long-term studies. Employing this model we evaluated the long-term potential inhibitory effect on the development of second primary tumors from precancerous tissue and eventual radiotoxicity of a single application of BNCT mediated by BPA, GB-10 or (GB-10+BPA), in the RA-6. The clinical rationale of this study was to search for a BNCT protocol that is therapeutic for tumor, not radio-toxic for the normal tissue that lies in the neutron beam path, and exerts the desired inhibitory effect on the development of second primary tumors, without exceeding the radio-tolerance of precancerous tissue, the dose limiting tissue in this case. Second primary tumors that arise in precancerous tissue (also called locoregional recurrences) are a frequent cause of therapeutic failure in head and neck tumors. Aim: Evaluate the radiotoxicity and inhibitory effect of a 'double' application of the same BNCT protocols that were proved therapeutically successful for tumor and precancerous tissue, with a long term follow up (8 months). A 'double' application of BNCT is a potentially useful strategy for the treatment of tumors, in particular the larger ones, but the cost in terms of side-effects in dose-limiting tissues might preclude its application and requires cautious evaluation. Materials and methods: We performed a double application of 1) BPA-BNCT; 2) (GB

  15. 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.

  16. Study on high speed lithium jet for neutron source of boron neutron capture therapy (BNCT)

    International Nuclear Information System (INIS)

    Takahashi, Minoru; Kobayashi, Tooru; Zhang, Mingguang; Mak, Michael; Stefanica, Jiri; Dostal, Vaclav; Zhao Wei

    2012-01-01

    The feasibility study of a liquid lithium type proton beam target was performed for the neutron source of the boron neutron capture therapy (BNCT). As the candidates of the liquid lithium target, a thin sheet jet and a thin film flow on a concave wall were chosen, and a lithium flow experiment was conducted to investigate the hydrodynamic stability of the targets. The surfaces of the jets and film flows with a thickness of 0.5 mm and a width of 50 mm were observed by means of photography. It has been found that a stable sheet jet and a stable film flow on a concave wall can be formed up to certain velocities by using a straight nozzle and a curved nozzle with the concave wall, respectively. (author)

  17. Measuring the stopping power of α particles in compact bone for BNCT

    Science.gov (United States)

    Provenzano, L.; Rodríguez, L. M.; Fregenal, D.; Bernardi, G.; Olivares, C.; Altieri, S.; Bortolussi, S.; González, S. J.

    2015-01-01

    The stopping power of α particles in thin films of decalcified sheep femur, in the range of 1.5 to 5.0 MeV incident energy, was measured by transmission of a backscattered beam from a heavy target. Additionally, the film elemental composition was determined by Rutherford Backscattering Spectrometry (RBS). These data will be used to measure boron concentration in thin films of bone using a spectrometry technique developed by the University of Pavia, since the concentration ratio between healthy tissue and tumor is of fundamental importance in Boron Neutron Capture Therapy (BNCT). The present experimental data are compared with numerical simulation results and with tabulated stopping power data of non-decalcified human bone.

  18. SPES-BNCT Project Beam Shaping Assembly. State of the Art

    International Nuclear Information System (INIS)

    Ceballos Sanchez, Cesar

    2007-01-01

    The SPES-BNCT project will exploit the intense proton beam provided by the RFQ (30mA, 5MeV), currently under construction at LNL, to yield a neutron source using the 9 Be(p,xn) nuclear reaction. The goal is to setup an accelerator-driven, thermal neutron beam facility, aimed at the Boron Neutron Capture experimental treatment of extended shallow skin melanoma. The neutron energy spectrum is shifted with a beam shaping assembly (BSA) surrounding the target. This device is fully designed with the Monte Carlo simulation code MCNPX, with the purpose of maximizing the thermal neutron component of the beam and focusing it on the irradiation area. (Author)

  19. A core laboratory offering full evaluation of new boron compounds. A service to the BNCT community

    International Nuclear Information System (INIS)

    Zamenhof, R.G.; Patel, H.; Palmer, M.R.; Lin, H.C.; Busse, P.M.; Harling, O.; Binns, P.J.; Riley, K.J.; Bernard, J.

    2000-01-01

    A joint project by the Beth Israel Deaconess Medical Center at Harvard Medical School and The Nuclear Reactor Laboratory of the Massachusetts Institute of Technology is proposed which would provide a core laboratory for the evaluation of new boron compounds. Federal agency funding has been applied for to support such a facility. The facility's evaluation of candidate boron compounds will include: quantitative cellular boron uptake; cell survival curve analysis (using a thermal neutron beam); small or large animal pharmacokinetic analysis; macro- and micro boron distribution analysis using high-resolution autoradiography, prompt gamma analysis and ICP-AES; small or large animal in vivo tumor control studies (using thermal or epithermal neutron beams); and pharmacological in vivo toxicity evaluation. The laboratory will include small and large animal surgical facilities and resources for additional boron compound chemistry as required by the evaluation procedure. This facility will be open to the BNCT research community. (author)

  20. Neutron therapy coupling brachytherapy and boron neutron capture therapy (BNCT) techniques

    International Nuclear Information System (INIS)

    Chaves, Iara Ferreira.

    1994-12-01

    In the present dissertation, neutron radiation techniques applied into organs of the human body are investigated as oncologic radiation therapy. The proposal treatment consists on connecting two distinct techniques: Boron Neutron Capture Therapy (BNCT) and irradiation by discrete sources of neutrons, through the brachytherapy conception. Biological and radio-dosimetrical aspects of the two techniques are considered. Nuclear aspects are discussed, presenting the nuclear reactions occurred in tumoral region, and describing the forms of evaluating the dose curves. Methods for estimating radiation transmission are reviewed through the solution of the neutron transport equation, Monte Carlo methodology, and simplified analytical calculation based on diffusion equation and numerical integration. The last is computational developed and presented as a quickly way to neutron transport evaluation in homogeneous medium. The computational evaluation of the doses for distinct hypothetical situations is presented, applying the coupled techniques BNTC and brachytherapy as an possible oncologic treatment. (author). 78 refs., 61 figs., 21 tabs

  1. Effects of secondary interactions on the dose calculation in treatments with Boron Neutron Capture Therapy (BNCT)

    International Nuclear Information System (INIS)

    Monteiro, E.

    2004-01-01

    The aimed of this work consists of evaluating the influence of the secondary contributions of dose (thermal neutrons dose, epithermal neutrons dose, fast neutrons dose and photon dose) in treatment planning with BNCT. MCNP4B Code was used to calculate RBE-Gy doses through the irradiation of the modified Snyder head head phantom.A reduction of the therapeutical gain of monoenergetic neutron beans was observed in non invasive treatments, provoked for the predominance of the fast neutron dose component in the skin, showing that the secondary contributions of dose can contribute more in the direction to raise the dose in the fabric healthy that in the tumor, thus reducing the treatment efficiency. (author)

  2. Effective dose evaluation for BNCT treatment in the epithermal neutron beam at THOR

    Energy Technology Data Exchange (ETDEWEB)

    Wang, J.N. [Department of Engineering and System Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan (China)] [Division of Health Physics, Institute of Nuclear Energy Research, No. 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Huang, C.K. [Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan (China); Tsai, W.C. [Department of Engineering and System Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan (China); Liu, Y.H. [Nuclear Science and Technol. Develop. Center, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan (China); Jiang, S.H., E-mail: shjiang@mx.nthu.edu.tw [Department of Engineering and System Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan (China)] [Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Rd., Hsinchu 30013, Taiwan (China)

    2011-12-15

    This paper aims to evaluate the effective dose as well as equivalent doses of several organs of an adult hermaphrodite mathematical phantom according to the definition of ICRP Publication 60 for BNCT treatments of brain tumors in the epithermal neutron beam at THOR. The MCNP5 Monte Carlo code was used for the calculation of the average absorbed dose of each organ. The effective doses for a typical brain tumor treatment with a tumor treatment dose of 20 Gy-eq were evaluated to be 0.59 and 0.35 Sv for the LLAT and TOP irradiation geometries, respectively. In addition to the stochastic effect, it was found that it is also likely to produce deterministic effects, such as cataracts and depression of haematopoiesis.

  3. Mod-5A wind turbine generator program design report. Volume 4: Drawings and specifications, book 3

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. This volume contains the drawings and specifications developed for the final design. This volume is divided into 5 books of which this is the third, containing drawings 47A380074 through 47A380126. A full breakdown parts listing is provided as well as a where used list.

  4. Improvements at the biological shielding of BNCT research facility in the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Souza, Gregorio Soares de

    2011-01-01

    The technique of neutron capture in boron is a promising technique in cancer treatment, it uses the high LET particles from the reaction 10 B (n, α) 7 Li to destroy cancer cells.The development of this technique began in the mid-'50s and even today it is the object of study and research in various centers around the world, Brazil has built a facility that aims to conduct research in BNCT, this facility is located next to irradiation channel number three at the research nuclear reactor IEA-R1 and has a biological shielding designed to meet the radiation protection standards. This biological shielding was developed to allow them to conduct experiments with the reactor at maximum power, so it is not necessary to turn on and off the reactor to irradiate samples. However, when the channel is opened for experiments the background radiation in the experiments salon increases and this background variation makes it impossible to perform measurements in a neutron diffraction research that utilizes the irradiation channel number six. This study aims to further improve the shielding in order to minimize the variation of background making it possible to perform the research facility in BNCT without interfering with the action of the research group of the irradiation channel number six. To reach this purpose, the code MCNP5, dosimeters and activation detectors were used to plan improvements in the biological shielding. It was calculated with the help of the code an improvement that can reduce the average heat flow in 71.2% ± 13 and verified experimentally a mean reduce of 70 ± 9% in dose due to thermal neutrons. (author)

  5. Cell death following BNCT: A theoretical approach based on Monte Carlo simulations

    Energy Technology Data Exchange (ETDEWEB)

    Ballarini, F., E-mail: francesca.ballarini@pv.infn.it [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, Pavia (Italy)] [INFN (National Institute of Nuclear Physics)-Sezione di Pavia, via Bassi 6, Pavia (Italy); Bakeine, J. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, Pavia (Italy); Bortolussi, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, Pavia (Italy)] [INFN (National Institute of Nuclear Physics)-Sezione di Pavia, via Bassi 6, Pavia (Italy); Bruschi, P. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, Pavia (Italy); Cansolino, L.; Clerici, A.M.; Ferrari, C. [University of Pavia, Department of Surgery, Experimental Surgery Laboratory, Pavia (Italy); Protti, N.; Stella, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, Pavia (Italy)] [INFN (National Institute of Nuclear Physics)-Sezione di Pavia, via Bassi 6, Pavia (Italy); Zonta, A.; Zonta, C. [University of Pavia, Department of Surgery, Experimental Surgery Laboratory, Pavia (Italy); Altieri, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, Pavia (Italy)] [INFN (National Institute of Nuclear Physics)-Sezione di Pavia, via Bassi 6, Pavia (Italy)

    2011-12-15

    In parallel to boron measurements and animal studies, investigations on radiation-induced cell death are also in progress in Pavia, with the aim of better characterisation of the effects of a BNCT treatment down to the cellular level. Such studies are being carried out not only experimentally but also theoretically, based on a mechanistic model and a Monte Carlo code. Such model assumes that: (1) only clustered DNA strand breaks can lead to chromosome aberrations; (2) only chromosome fragments within a certain threshold distance can undergo misrejoining; (3) the so-called 'lethal aberrations' (dicentrics, rings and large deletions) lead to cell death. After applying the model to normal cells exposed to monochromatic fields of different radiation types, the irradiation section of the code was purposely extended to mimic the cell exposure to a mixed radiation field produced by the {sup 10}B(n,{alpha}) {sup 7}Li reaction, which gives rise to alpha particles and Li ions of short range and high biological effectiveness, and by the {sup 14}N(n,p){sup 14}C reaction, which produces 0.58 MeV protons. Very good agreement between model predictions and literature data was found for human and animal cells exposed to X- or gamma-rays, protons and alpha particles, thus allowing to validate the model for cell death induced by monochromatic radiation fields. The model predictions showed good agreement also with experimental data obtained by our group exposing DHD cells to thermal neutrons in the TRIGA Mark II reactor of University of Pavia; this allowed to validate the model also for a BNCT exposure scenario, providing a useful predictive tool to bridge the gap between irradiation and cell death.

  6. Clinical lessons from the first applications of BNCT on unresectable liver metastases

    Energy Technology Data Exchange (ETDEWEB)

    Zonta, A; Prati, U; Roveda, L; Ferrari, C; Zonta, S; Clerici, Am; Zonta, C; Pinelli, T [Department of Nuclear and Theoretical Physics, University of Pavia and I.N.F.N., Pavia (Italy); Fossati, F [Department of Nuclear and Theoretical Physics, University of Pavia and I.N.F.N., Pavia (Italy); Altieri, S [Department of Nuclear and Theoretical Physics, University of Pavia and I.N.F.N., Pavia (Italy); Bortolussi, S [Department of Nuclear and Theoretical Physics, University of Pavia and I.N.F.N., Pavia (Italy); Bruschi, P [Department of Nuclear and Theoretical Physics, University of Pavia and I.N.F.N., Pavia (Italy); Nano, R [Department of Animal Biology, University of Pavia (Italy); Barni, S [Department of Animal Biology, University of Pavia (Italy); Chiari, P [Department of Animal Biology, University of Pavia (Italy); Mazzini, G [IGM CNR Histochemistry and Cytometry Section, University of Pavia (Italy)

    2006-05-15

    After a long series of studies on the effects of neutron irradiation of 10B loaded neoplastic cells both in culture and in animal experiments, we started the clinical application of BNCT on humans affected by liver metastases of a radically resected colon adenocarcinoma. The procedure we adopted includes a first surgical phase, with hepatectomy; a radiotherapeutic phase, in which the isolated liver, washed and chilled, is extracorporeally irradiated with thermal neutrons; and then a second surgical phase for the reconnection of the liver to the patient. Until now two patients have been subjected to the BNCT treatment. The first one survived 44 months with a good quality of life, and died because of diffuse recurrences of his intestinal tumour. The second patient had the same early perioperative course, but after 33 days a worsening of a dilatative cardiomyopaty, from which he was suffering, determined a cardiac failure and eventually death. This clinical experience, although limited, has shown that extracorporeal neutron irradiation of the liver is a feasible procedure, able to ensure the complete destruction of liver metastases and a possible long lasting survival. In our patients neutron irradiation caused massive cellular necrosis highly specific to tumour cells, whereas normal cells were mostly spared. Nevertheless, the impact of such a traumatic operation on the patient's organism must be taken into account. Finally, we have to be aware that the fight against tumour rarely leads to a complete victory. We now have an innovative weapon which is both powerful and partly unsettled: it must be refined and above all used.

  7. 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. Copyright © 2015 Elsevier Ltd. All rights reserved.

  8. Economic impacts from energy efficiency programs - Variations in multiplier effects by program type and region. Volume 1

    International Nuclear Information System (INIS)

    Gardner, John; Skumatz, Lisa

    2007-01-01

    Research indicates that the value of omitted program effects - specifically non-energy benefits (NEBs) - represent a significant share of overall program impacts. One of the largest components of societal benefits is the direct and indirect economic and job creation effects stimulated by the investment in conservation on behalf of the program. The literature has indicated that the valuations assigned to this category of these categories can be large, but much of the literature overstates the impact of economic NEBs. We conducted extensive research to develop reliable and defensible estimates of these benefits categories. This study used input-output analysis to update the economic multipliers for NEBs in several ways. Net: Developed 'net' estimates of the multipliers (rather than 'gross' factors)Variations by Region: Estimated multipliers for multiple states and for the entire US; Variations by Program Type: Developed estimates based on different types or categories of programs (e.g weatherization vs. new construction vs. appliance programs, etc.), Variations in Baseline Assumptions: Different assumptions about where the expenditures are transferred 'from' for the net analysis (e.g. from 'generation', from a mixed market basket, etc.); and Variations over Time: Used data from multiple time periods to examine changes in the size of multipliers over time. We examined the results by state, by program type, and over time and found dramatic differences in the economic impacts by program type and territory under consideration. The results provide estimates of the economic impacts derived from the program; however, for communities or utilities with economic development goals, the results can be used to help select between program alternatives. The results are new, and the revised figures have been used to compute more reliable and tailored estimates of economic non-energy benefits that can be applied in regulatory tests

  9. Balanced program plan. Volume XI. Fission analysis for biomedical and environmental research

    International Nuclear Information System (INIS)

    Foster, R.F.

    1976-06-01

    Factors involved in the formulation of an ERDA-sponsored program for health and environmental research in connection with the fission fuel cycle are discussed under the following section headings: major issues associated with the use of nuclear power; fission fuel cycle technology: milling, UF 6 production, uranium enrichment, plutonium fuel fabrication, power production (reactors), fuel reprocessing, waste management, fuel and waste transportation; problem definition: characterization, measurement and monitoring, transport processes, health effects, ecological processes and effects, and integrated assessment; budget; characterization, measuring and monitoring program units; transport processes program units; health effects program units; ecological processes and effects program units; and integrated assessment program units

  10. Army Enlisted Personnel Competency Assessment Program Phase 1. Volume 1: Needs Analysis

    National Research Council Canada - National Science Library

    Knapp, Deirdre

    2004-01-01

    .... The PerformM21 program has two mutually supporting tracks. The first is a needs analysis that will result in design recommendations and identification of issues related to implementation of a competency assessment program...

  11. The Savannah River Site`s Groundwater Monitoring Program: First quarter 1993, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1993-08-01

    This report summarizes the Savannah River Site (SRS) Groundwater Monitoring Program conducted by the Environmental Protection Department`s Environmental Monitoring Section (EPD/EMS) during the first quarter of 1993. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program`s activities; and serves as an official document of the analytical results.

  12. 1997 Summer Research Program (SRP), High School Apprenticeship Program (HSAP), Final Reports, Volume 12B, Armstrong Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  13. Artificial neural networks to evaluate the boron concentration decreasing profile in Blood-BPA samples of BNCT patients

    International Nuclear Information System (INIS)

    García-Reiriz, Alejandro; Magallanes, Jorge; Zupan, Jure; Líberman, Sara

    2011-01-01

    For the prediction of decay concentration profiles of the p-boronophenylalanine (BPA) in blood during BNCT treatment, a method is suggested based on Kohonen neural networks. The results of a model trained with the concentration profiles from the literature are described. The prediction of the model was validated by the leave-one-out method. Its robustness shows that it is mostly independent on small variations. The ability to fit retrospective experimental data shows an uncertainty lower than the two compartment model used previously. - Highlights: ► We predicted decaying concentration profiles of BPA in blood during BNCT therapy. ► Is suggested a method based on Kohonen neural networks. ► The results show that it is very robust and mostly independent of small variations. ► It has a better ability to fit retrospective experimental data. ► The model could be progressively improved by adding new data to the training matrix.

  14. Mock-up experiment at Birmingham University for BNCT project of Osaka University – Neutron flux measurement with gold foil

    International Nuclear Information System (INIS)

    Tamaki, S.; Sakai, M.; Yoshihashi, S.; Manabe, M.; Zushi, N.; Murata, I.; Hoashi, E.; Kato, I.; Kuri, S.; Oshiro, S.; Nagasaki, M.; Horiike, H.

    2015-01-01

    Mock-up experiment for development of accelerator based neutron source for Osaka University BNCT project was carried out at Birmingham University, UK. In this paper, spatial distribution of neutron flux intensity was evaluated by foil activation method. Validity of the design code system was confirmed by comparing measured gold foil activities with calculations. As a result, it was found that the epi-thermal neutron beam was well collimated by our neutron moderator assembly. Also, the design accuracy was evaluated to have less than 20% error. - Highlights: • Accelerator based neutron source for BNCT is being developed in Osaka University. • Mock-up experiment was carried out at Birmingham University, UK. • Neutronics performance of our assembly was evaluated from gold foil activation. • Gold foil activation was determined by using HPGe detectors. • Validity of the neutronics design code system was confirmed.

  15. 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. Copyright © 2014 Elsevier Ltd. All rights reserved.

  16. 1992-1993 Bonneville Appliance Efficiency Program: Showerhead evaluation. Volume I - report

    Energy Technology Data Exchange (ETDEWEB)

    Warwick, W.M.

    1995-01-01

    The Bonneville Power Administration (Bonneville) provides wholesale electric power to over 100 retail distribution utilities in the Pacific Northwest. Bonneville is faced with meeting growing loads from these utilities. It acquires conservation as one means of meeting this load growth. Bonneville has offered a variety of conservation programs since 1980. Efficient showerheads have been a feature in residential conservation programs ever since. Bonneville launched the Residential Appliance Efficiency Program to focus on water-heater energy conservation opportunities in 1992. The Residential Appliance Efficiency Program consists of two parts, a water-heater efficiency program, and a hot-water efficiency program. This report evaluates the savings and costs of the first two years of the showerhead portion of the Residential Appliance Efficiency Program (the showerhead program). Although it is not a formal evaluation of the program limited to implementation or a {open_quotes}process{close_quotes} evaluation, observations about program design and implementation are included as appropriate. Results of this evaluation are limited to program participants within the Bonneville service territory.

  17. Impact of intra-arterial administration of boron compounds on dose-volume histograms in boron neutron capture therapy for recurrent head-and-neck tumors

    International Nuclear Information System (INIS)

    Suzuki, Minoru; Sakurai, Yoshinori; Nagata, Kenji; Kinashi, Yuko; Masunaga, Shinichiro; Ono, Koji; Maruhashi, Akira; Kato, Ituro; Fuwa, Nobukazu; Hiratsuka, Junichi; Imahori, Yoshio

    2006-01-01

    Purpose: To analyze the dose-volume histogram (DVH) of head-and-neck tumors treated with boron neutron capture therapy (BNCT) and to determine the advantage of the intra-arterial (IA) route over the intravenous (IV) route as a drug delivery system for BNCT. Methods and Materials: Fifteen BNCTs for 12 patients with recurrent head-and-neck tumors were included in the present study. Eight irradiations were done after IV administration of boronophenylalanine and seven after IA administration. The maximal, mean, and minimal doses given to the gross tumor volume were assessed using a BNCT planning system. Results: The results are reported as median values with the interquartile range. In the IA group, the maximal, mean, and minimal dose given to the gross tumor volume was 68.7 Gy-Eq (range, 38.8-79.9), 45.0 Gy-Eq (range, 25.1-51.0), and 13.8 Gy-Eq (range, 4.8-25.3), respectively. In the IV group, the maximal, mean, and minimal dose given to the gross tumor volume was 24.2 Gy-Eq (range, 21.5-29.9), 16.4 Gy-Eq (range, 14.5-20.2), and 7.8 Gy-Eq (range, 6.8-9.5), respectively. Within 1-3 months after BNCT, the responses were assessed. Of the 6 patients in the IV group, 2 had a partial response, 3 no change, and 1 had progressive disease. Of 4 patients in the IA group, 1 achieved a complete response and 3 a partial response. Conclusion: Intra-arterial administration of boronophenylalanine is a promising drug delivery system for head-and-neck BNCT

  18. RETRAN-02: a program for transient thermal-hydraulic analysis of complex fluid-flow systems. Volume 4. Applications

    International Nuclear Information System (INIS)

    Peterson, C.E.; Gose, G.C.; McFadden, J.H.

    1983-01-01

    RETRAN-02 represents a significant achievement in the development of a versatile and reliable computer program for use in best estimate transient thermal-hydraulic analysis of light water reactor systems. The RETRAN-02 computer program is an extension of the RETRAN-01 program designed to provide analysis capabilities for 1) BWR and PWR transients, 2) small break loss of coolant accidents, 3) balance of plant modeling, and 4) anticipated transients without scram, while maintaining the analysis capabilities of the predecessor code. The RETRAN-02 computer code is constructed in a semimodular and dynamic dimensioned form where additions to the code can be easily carried out as new and improved models are developed. This report (the fourth of a five volume computer code manual) describes the verification and validation of RETRAN-02

  19. NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 1, Part 3

    Science.gov (United States)

    Jung, David S.; Lee, Leonine S.; Manzo, Michelle A.

    2010-01-01

    This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume I: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries of the program's operations.

  20. Mod-5A Wind Turbine Generator Program Design Report. Volume 4: Drawings and Specifications, Book 1

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. Volume 4 contains the drawings and specifications that were developed in preparation for building the MOD-5A wind turbine generator. This is the first of five books of volume four. It contains structural design criteria, generator step-up transformer specs, specs for design, fabrication and testing of the system, specs for the ground control enclosure, systems specs, slip ring specs, and control system specs.

  1. Discrimination of various contributions to the absorbed dose in BNCT: Fricke-gel imaging and intercomparison with other experimental results

    Energy Technology Data Exchange (ETDEWEB)

    Gambarini, G. E-mail: grazia.gambarini@mi.infn.it; Agosteo, S.; Marchesi, P.; Nava, E.; Palazzi, P.; Pecci, A.; Rosi, G.; Tinti, R

    2000-11-15

    A method is described for the 3D measurements of absorbed dose in a ferrous sulphate gel phantom, exposed in the thermal column of a nuclear reactor. The method, studied for Boron Neutron Capture Therapy (BNCT) purposes, allows absorbed dose imaging and profiling, with the separation of different contributions coming from different secondary radiations, generated from thermal neutrons. In fact, the biological effectiveness of the different radiations is different. Tests with conventional dosimeters were performed too.

  2. Labelled compounds of interest as antitumour agents. Pt. 4: Deuteration and tritiation of a nitroimidazole-carborane designed for BNCT

    International Nuclear Information System (INIS)

    Scobie, Martin; Bew, S.P.; Threadgill, M.D.

    1994-01-01

    Quenching the anion generated from a 2-(ω-carboranylalkyl)dithiane with 2 H 2 O at -78 o C and at 0 o C introduced deuterium exclusively at C-2 of the carborane. Extension of this model reaction to a bioreductively-targetted carborane allowed the synthesis of 2-[ 2 H]- and 2-[ 3 H]-isotopomers of a nitroimidazole-carborane which is of interest in boron neutron capture therapy (BNCT) of cancer. (author)

  3. Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-A: Resource description, program history, wells tested, university and company based research, site restoration

    Energy Technology Data Exchange (ETDEWEB)

    John, C.J.; Maciasz, G.; Harder, B.J.

    1998-06-01

    The US Department of Energy established a geopressured-geothermal energy program in the mid 1970`s as one response to America`s need to develop alternate energy resources in view of the increasing dependence on imported fossil fuel energy. This program continued for 17 years and approximately two hundred million dollars were expended for various types of research and well testing to thoroughly investigate this alternative energy source. This volume describes the following studies: Geopressured-geothermal resource description; Resource origin and sediment type; Gulf Coast resource extent; Resource estimates; Project history; Authorizing legislation; Program objectives; Perceived constraints; Program activities and structure; Well testing; Program management; Program cost summary; Funding history; Resource characterization; Wells of opportunity; Edna Delcambre No. 1 well; Edna Delcambre well recompletion; Fairfax Foster Sutter No. 2 well; Beulah Simon No. 2 well; P.E. Girouard No. 1 well; Prairie Canal No. 1 well; Crown Zellerbach No. 2 well; Alice C. Plantation No. 2 well; Tenneco Fee N No. 1 well; Pauline Kraft No. 1 well; Saldana well No. 2; G.M. Koelemay well No. 1; Willis Hulin No. 1 well; Investigations of other wells of opportunity; Clovis A. Kennedy No. 1 well; Watkins-Miller No. 1 well; Lucien J. Richard et al No. 1 well; and the C and K-Frank A. Godchaux, III, well No. 1.

  4. Boron neutron capture therapy (BNCT) translational studies in the hamster cheek pouch model of oral cancer at the new ''B2'' configuration of the RA-6 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Monti Hughes, Andrea; Trivillin, Veronica A.; Schwint, Amanda E. [Constituyentes Atomic Center, National Atomic Energy Commission (CNEA), Department of Radiobiology, San Martin, Province Buenos Aires (Argentina); National Research Council (CONICET), Ciudad Autonoma de Buenos Aires (Argentina); Longhino, Juan; Boggio, Esteban [Bariloche Atomic Center, CNEA, Department of Nuclear Engineering, San Carlos de Bariloche, Province Rio Negro (Argentina); Medina, Vanina A.; Martinel Lamas, Diego J. [National Research Council (CONICET), Ciudad Autonoma de Buenos Aires (Argentina); Pontifical Catholic University of Argentina (UCA), Laboratory of Tumoral Biology and Inflammation, School of Medical Sciences, Institute for Biomedical Research (BIOMED CONICET-UCA), Ciudad Autonoma de Buenos Aires (Argentina); Garabalino, Marcela A.; Heber, Elisa M.; Pozzi, Emiliano C.C. [Constituyentes Atomic Center, National Atomic Energy Commission (CNEA), Department of Radiobiology, San Martin, Province Buenos Aires (Argentina); Itoiz, Maria E. [Constituyentes Atomic Center, National Atomic Energy Commission (CNEA), Department of Radiobiology, San Martin, Province Buenos Aires (Argentina); UBA, Department of Oral Pathology, Faculty of Dentistry, Ciudad Autonoma de Buenos Aires (Argentina); Aromando, Romina F. [UBA, Department of Oral Pathology, Faculty of Dentistry, Ciudad Autonoma de Buenos Aires (Argentina); Nigg, David W. [Idaho National Laboratory, Idaho Falls (United States)

    2017-11-15

    Boron neutron capture therapy (BNCT) is based on selective accumulation of B-10 carriers in tumor followed by neutron irradiation. We demonstrated, in 2001, the therapeutic effect of BNCT mediated by BPA (boronophenylalanine) in the hamster cheek pouch model of oral cancer, at the RA-6 nuclear reactor. Between 2007 and 2011, the RA-6 was upgraded, leading to an improvement in the performance of the BNCT beam (B2 configuration). Our aim was to evaluate BPA-BNCT radiotoxicity and tumor control in the hamster cheek pouch model of oral cancer at the new ''B2'' configuration. We also evaluated, for the first time in the oral cancer model, the radioprotective effect of histamine against mucositis in precancerous tissue as the dose-limiting tissue. Cancerized pouches were exposed to: BPA-BNCT; BPA-BNCT + histamine; BO: Beam only; BO + histamine; CONTROL: cancerized, no-treatment. BNCT induced severe mucositis, with an incidence that was slightly higher than in ''B1'' experiments (86 vs 67%, respectively). BO induced low/moderate mucositis. Histamine slightly reduced the incidence of severe mucositis induced by BPA-BNCT (75 vs 86%) and prevented mucositis altogether in BO animals. Tumor overall response was significantly higher in BNCT (94-96%) than in control (16%) and BO groups (9-38%), and did not differ significantly from the ''B1'' results (91%). Histamine did not compromise BNCT therapeutic efficacy. BNCT radiotoxicity and therapeutic effect at the B1 and B2 configurations of RA-6 were consistent. Histamine slightly reduced mucositis in precancerous tissue even in this overly aggressive oral cancer model, without compromising tumor control. (orig.)

  5. Boron neutron capture therapy (BNCT) translational studies in the hamster cheek pouch model of oral cancer at the new ''B2'' configuration of the RA-6 nuclear reactor

    International Nuclear Information System (INIS)

    Monti Hughes, Andrea; Trivillin, Veronica A.; Schwint, Amanda E.; Longhino, Juan; Boggio, Esteban; Medina, Vanina A.; Martinel Lamas, Diego J.; Garabalino, Marcela A.; Heber, Elisa M.; Pozzi, Emiliano C.C.; Itoiz, Maria E.; Aromando, Romina F.; Nigg, David W.

    2017-01-01

    Boron neutron capture therapy (BNCT) is based on selective accumulation of B-10 carriers in tumor followed by neutron irradiation. We demonstrated, in 2001, the therapeutic effect of BNCT mediated by BPA (boronophenylalanine) in the hamster cheek pouch model of oral cancer, at the RA-6 nuclear reactor. Between 2007 and 2011, the RA-6 was upgraded, leading to an improvement in the performance of the BNCT beam (B2 configuration). Our aim was to evaluate BPA-BNCT radiotoxicity and tumor control in the hamster cheek pouch model of oral cancer at the new ''B2'' configuration. We also evaluated, for the first time in the oral cancer model, the radioprotective effect of histamine against mucositis in precancerous tissue as the dose-limiting tissue. Cancerized pouches were exposed to: BPA-BNCT; BPA-BNCT + histamine; BO: Beam only; BO + histamine; CONTROL: cancerized, no-treatment. BNCT induced severe mucositis, with an incidence that was slightly higher than in ''B1'' experiments (86 vs 67%, respectively). BO induced low/moderate mucositis. Histamine slightly reduced the incidence of severe mucositis induced by BPA-BNCT (75 vs 86%) and prevented mucositis altogether in BO animals. Tumor overall response was significantly higher in BNCT (94-96%) than in control (16%) and BO groups (9-38%), and did not differ significantly from the ''B1'' results (91%). Histamine did not compromise BNCT therapeutic efficacy. BNCT radiotoxicity and therapeutic effect at the B1 and B2 configurations of RA-6 were consistent. Histamine slightly reduced mucositis in precancerous tissue even in this overly aggressive oral cancer model, without compromising tumor control. (orig.)

  6. First clinical results from the EORTC phase I Trial ''postoperative treatment of glioblastoma with BNCT at the Petten irradiation facility''

    International Nuclear Information System (INIS)

    Sauerwein, W.; Hideghety, K.; Rassow, J.; Devries, M.J.; Goetz, C.; Paquis, P.; Grochulla, F.; Wolbers, J.G.; Haselsberger, K.; Turowski, B.; Moss, R.L.; Stecher-Rasmussen, F.; Touw, D.; Wiestler, O.D.; Frankhauser, H.; Gabel, D.

    2001-01-01

    Based on the pre-clinical work of the European Collaboration on Boron Neutron Capture Therapy a study protocol was prepared in 1995 to initiate Boron Neutron Capture Therapy (BNCT) in patients at the High Flux Reactor (HFR) in Petten. Bio-distribution and pharmacokinetics data of the boron drug Na 2 B 12 H 11 SH (BSH) as well as the radiobiological effects of BNCT with BSH in healthy brain tissue of dogs were considered in designing the strategy for this clinical Phase I trial. The primary goal of the radiation dose escalation study is the investigation of possible adverse events due to BNCT; i.e. to establish the dose limiting toxicity and the maximal tolerated dose. The treatment is delivered in 4 fractions at a defined average boron concentration in blood. Cohorts of 10 patients are treated per dose group. The starting dose was set at 80% of the dose at which neurological symptoms occurred in preclinical dog experiments following a single fraction. After an observation period of at least 6 months, the dose is increased by 10% for the next cohort if less then three severe side effects related to the treatment occurred. The results of the first cohort are presented here. The evaluated dose level can be considered safe. (author)

  7. Capability of NIPAM polymer gel in recording dose from the interaction of 10B and thermal neutron in BNCT

    International Nuclear Information System (INIS)

    Khajeali, Azim; Reza Farajollahi, Ali; Kasesaz, Yaser; Khodadadi, Roghayeh; Khalili, Assef; Naseri, Alireza

    2015-01-01

    The capability of N-isopropylacrylamide (NIPAM) polymer gel to record the dose resulting from boron neutron capture reaction in BNCT was determined. In this regard, three compositions of the gel with different concentrations of 10 B were prepared and exposed to gamma radiation and thermal neutrons. Unlike irradiation with gamma rays, the boron-loaded gels irradiated by neutron exhibited sensitivity enhancement compared with the gels without 10 B. It was also found that the neutron sensitivity of the gel increased by the increase of concentration of 10 B. It can be concluded that NIPAM gel might be suitable for the measurement of the absorbed dose enhancement due to 10 B and thermal neutron reaction in BNCT. - Highlights: • Three compositions of NIPAM gel with different concentration of 10 B have been exposed by gamma and thermal neutron. • The vials containing NIPAM gel have been irradiated by an automatic system capable of providing for dose uniformity. • Suitability of NIPAM polymer gel in measuring radiation doses in BNCT has been investigated.

  8. 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.

  9. First clinical results from the EORTC phase I Trial ''postoperative treatment of glioblastoma with BNCT at the Petten irradiation facility''

    Energy Technology Data Exchange (ETDEWEB)

    Sauerwein, W; Hideghety, K; Rassow, J [Department of Radiotherapy, University of Essen (Germany); Devries, M J [NDDO Oncology, Amsterdam (Netherlands); Goetz, C [Neurochirurgische Klinik, Klinikum Grosshadern Muenchen, Munich (Germany); Paquis, P [Dept. de Neurochirurgie, Hopital Pasteur, Nice (France); Grochulla, F [Klinik fuer Neurochirurgie, Zentralkrankenhaus Bremen (Germany); Wolbers, J G [Department of Neurosurgery, University Hospital ' ' Vrije Universiteit' ' , Amsterdam (Netherlands); Haselsberger, K [Klinik fuer Neurochirurgie, Karl-Franzens-Universitaet, Graz (Austria); Turowski, B [Institut fuer Neuroradiologie, Johann-Wolfgang-von-Goethe-Universitaet, Frankfurt (Germany); Moss, R L [HFR Unit, Joint Research Centre, European Commission, Petten (Netherlands); Stecher-Rasmussen, F [Nuclear Research and Consultancy Group NRG, Petten (Netherlands); Touw, D [Pharmacy, University/Academic Hospital ' ' Vrije Universiteit' ' , Amsterdam (Netherlands); Wiestler, O D [Department of Neuropathology, German Brain Tumour Reference Centre, Universitaetsklinikum Bonn (Germany); Frankhauser, H [Service de Neurochirurgie CHUV, Lausanne (Switzerland); Gabel, D [Chemistry Department, University of Bremen (Germany)

    2001-05-01

    Based on the pre-clinical work of the European Collaboration on Boron Neutron Capture Therapy a study protocol was prepared in 1995 to initiate Boron Neutron Capture Therapy (BNCT) in patients at the High Flux Reactor (HFR) in Petten. Bio-distribution and pharmacokinetics data of the boron drug Na{sub 2}B{sub 12}H{sub 11}SH (BSH) as well as the radiobiological effects of BNCT with BSH in healthy brain tissue of dogs were considered in designing the strategy for this clinical Phase I trial. The primary goal of the radiation dose escalation study is the investigation of possible adverse events due to BNCT; i.e. to establish the dose limiting toxicity and the maximal tolerated dose. The treatment is delivered in 4 fractions at a defined average boron concentration in blood. Cohorts of 10 patients are treated per dose group. The starting dose was set at 80% of the dose at which neurological symptoms occurred in preclinical dog experiments following a single fraction. After an observation period of at least 6 months, the dose is increased by 10% for the next cohort if less then three severe side effects related to the treatment occurred. The results of the first cohort are presented here. The evaluated dose level can be considered safe. (author)

  10. STICAP: A linear circuit analysis program with stiff systems capability. Volume 1: Theory manual. [network analysis

    Science.gov (United States)

    Cooke, C. H.

    1975-01-01

    STICAP (Stiff Circuit Analysis Program) is a FORTRAN 4 computer program written for the CDC-6400-6600 computer series and SCOPE 3.0 operating system. It provides the circuit analyst a tool for automatically computing the transient responses and frequency responses of large linear time invariant networks, both stiff and nonstiff (algorithms and numerical integration techniques are described). The circuit description and user's program input language is engineer-oriented, making simple the task of using the program. Engineering theories underlying STICAP are examined. A user's manual is included which explains user interaction with the program and gives results of typical circuit design applications. Also, the program structure from a systems programmer's viewpoint is depicted and flow charts and other software documentation are given.

  11. PLANS; a finite element program for nonlinear analysis of structures. Volume 2: User's manual

    Science.gov (United States)

    Pifko, A.; Armen, H., Jr.; Levy, A.; Levine, H.

    1977-01-01

    The PLANS system, rather than being one comprehensive computer program, is a collection of finite element programs used for the nonlinear analysis of structures. This collection of programs evolved and is based on the organizational philosophy in which classes of analyses are treated individually based on the physical problem class to be analyzed. Each of the independent finite element computer programs of PLANS, with an associated element library, can be individually loaded and used to solve the problem class of interest. A number of programs have been developed for material nonlinear behavior alone and for combined geometric and material nonlinear behavior. The usage, capabilities, and element libraries of the current programs include: (1) plastic analysis of built-up structures where bending and membrane effects are significant, (2) three dimensional elastic-plastic analysis, (3) plastic analysis of bodies of revolution, and (4) material and geometric nonlinear analysis of built-up structures.

  12. Redefining the Boundaries of Language Study. Issues in Language Program Direction: A Series of Annual Volumes.

    Science.gov (United States)

    Kramsch, Claire, Ed.

    The papers in this volume fall into five categories. After "Introduction: Making the Invisible Visible" (Claire Kramsch), Part 1, "Theoretical Boundaries," includes "The Metamorphosis of the Foreign Language Director, or: Waking Up to Theory" (Mark Webber) and "Subjects-in-Process: Revisioning TA Development…

  13. Operation of Wastewater Treatment Plants: A Field Study Training Program. Volume I. Second Edition.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    This manual was prepared by experienced wastewater collection system workers to provide a home study course to develop new qualified workers and expand the abilities of existing workers. This volume is directed primarily towards entry-level operators and the operators of ponds, package plants, or small treatment plants. Ten chapters examine the…

  14. Smolt Monitoring Program, Volume II, Migrational Characteristics of Columbia Basin Salmon and Steelhead Trout, 1986 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Fish Passage Center

    1987-02-01

    Smolt Monitoring Program Annual Report, 1986, Volume I, describes the results of travel time monitoring and other migrational characteristics of yearling and sub-yearling chinook salmon (Oncorhynchus tshawytscha), sockeye salmon (Oncorhynchus nerka), and steelhead trout (Salmo gairdneri). This volume presents the data from Fish Passage Center freeze brands used in the analysis of travel time for Lewiston, Lower Granite, Lower Monumental, Rock Island, McNary, and John Day dams. Summary of data collection procedures and explanation of data listings are presented in conjunction with the mark recapture data. Data for marked fish not presented in this report will be provided upon request. Daily catch statistics (by species), flow, and sample parameters for the smolt monitoring sites, Clearwater, Lewiston, Lower Granite, Lower Monumental, Rock Island, McNary, John Day, and Bonneville also will be provided upon request.

  15. Energy-efficient buildings program evaluations. Volume 1: Findings and recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A.D.; Mayi, D.; Edgemon, S.D.

    1997-04-01

    This study was conducted for the US Department of Energy (DOE) by Pacific Northwest National Laboratory (PNNL). DOE operates the Building Standards and Guidelines Program (BSGP) to increase the effectiveness of building energy codes, standards, and guidelines. The main purpose of this report is to lay the groundwork for conducting an overall evaluation of the program and its effectiveness. Another purpose of this report is to summarize an extensive set of relevant evaluations and provide a building efficiency and program evaluation information resource for program designers, managers, and evaluators. This study presents information from 119 evaluations that have been conducted of both utility and code programs related to energy efficiency in new residential and commercial buildings. The authors used the information in these evaluations to identify major themes and lessons learned from utility and code programs. They also used the information to gain insights into appropriate evaluation methodologies and establish guidelines for designing future evaluations and an evaluation of the BSGP. The report presents general lessons about evaluating programs that have implications for future evaluations included the following. The evaluations provided the basis for developing an effective evaluation approach for residential building energy-efficiency codes and other energy-efficiency programs and other insights for conducting commercial building program evaluations. The findings for conducting effective evaluations are categorized by steps in the evaluation process.

  16. Geothermal direct heat program: roundup technical conference proceedings. Volume II. Bibliography of publications. State-coupled geothermal resource assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Ruscetta, C.A. (ed.)

    1982-07-01

    Lists of publications are presented for the Geothermal Resource Assessment Program for the Utah Earth Science Laboratory and the following states: Alaska, Arizona, California, Colorado, Hawaii, Idaho, Kansas, Montana, Nebraska, Nevada, New Mexico, New York, North Dakota, Oregon, Texas, Utah, and Washington.

  17. The relation between media promotions and service volume for a statewide tobacco quitline and a web-based cessation program

    Directory of Open Access Journals (Sweden)

    Schillo Barbara A

    2011-12-01

    Full Text Available Abstract Background This observational study assessed the relation between mass media campaigns and service volume for a statewide tobacco cessation quitline and stand-alone web-based cessation program. Methods Multivariate regression analysis was used to identify how weekly calls to a cessation quitline and weekly registrations to a web-based cessation program are related to levels of broadcast media, media campaigns, and media types, controlling for the impact of external and earned media events. Results There was a positive relation between weekly broadcast targeted rating points and the number of weekly calls to a cessation quitline and the number of weekly registrations to a web-based cessation program. Additionally, print secondhand smoke ads and online cessation ads were positively related to weekly quitline calls. Television and radio cessation ads and radio smoke-free law ads were positively related to web program registration levels. There was a positive relation between the number of web registrations and the number of calls to the cessation quitline, with increases in registrations to the web in 1 week corresponding to increases in calls to the quitline in the subsequent week. Web program registration levels were more highly influenced by earned media and other external events than were quitline call volumes. Conclusion Overall, broadcast advertising had a greater impact on registrations for the web program than calls to the quitline. Furthermore, registrations for the web program influenced calls to the quitline. These two findings suggest the evolving roles of web-based cessation programs and Internet-use practices should be considered when creating cessation programs and media campaigns to promote them. Additionally, because different types of media and campaigns were positively associated with calls to the quitline and web registrations, developing mass media campaigns that offer a variety of messages and communicate through

  18. Defense Small Business Innovation Research Program (SBIR). Volume 1. Army Abstracts of Phase 1 Awards 1990

    Science.gov (United States)

    1990-01-01

    94025 Program Manager: WILSON SMART Contract #: Title: DIAMOND HEAT PUPES FOR EFFICIENT COOLING OF HIGH POWER DENSITY DEVICES Topic #: A90-034 Office...PARK, CA 94025 Program Manager: WILSON SMART Contract #: Title: DOPED DIAMOND QUANTUM WELLS FOR FIELD EFFECT TRANSISTORS Topic #: A90-111 Office: ETDL ID

  19. Defense Small Business Innovation Research Program (SBIR). Volume 3. Air Force Abstracts of Phase 1 Awards

    Science.gov (United States)

    1990-01-01

    APPLICATION. CRYSTALLUME 125 CONSTITUTION DR MENLO PARK, CA 94025 Program Manager: WILSON SMART Contract #: Title: DIAMOND WAVEGUIDES FOR THE LONG WAVELENGTH...MENLO PARK, CA 94025 Program Manager: WILSON SMART Contract #: Title: DIAMOND COATINGS FOR INFRARED MATERIAL Topic #: AF90-019 Office: MSD/PMR ID

  20. Evaluation of spacecraft technology programs (effects on communication satellite business ventures), volume 1

    Science.gov (United States)

    Greenburg, J. S.; Gaelick, C.; Kaplan, M.; Fishman, J.; Hopkins, C.

    1985-01-01

    Commercial organizations as well as government agencies invest in spacecraft (S/C) technology programs that are aimed at increasing the performance of communications satellites. The value of these programs must be measured in terms of their impacts on the financial performane of the business ventures that may ultimately utilize the communications satellites. An economic evaluation and planning capability was developed and used to assess the impact of NASA on-orbit propulsion and space power programs on typical fixed satellite service (FSS) and direct broadcast service (DBS) communications satellite business ventures. Typical FSS and DBS spin and three-axis stabilized spacecraft were configured in the absence of NASA technology programs. These spacecraft were reconfigured taking into account the anticipated results of NASA specified on-orbit propulsion and space power programs. In general, the NASA technology programs resulted in spacecraft with increased capability. The developed methodology for assessing the value of spacecraft technology programs in terms of their impact on the financial performance of communication satellite business ventures is described. Results of the assessment of NASA specified on-orbit propulsion and space power technology programs are presented for typical FSS and DBS business ventures.

  1. Viscous wing theory development. Volume 2: GRUMWING computer program user's manual

    Science.gov (United States)

    Chow, R. R.; Ogilvie, P. L.

    1986-01-01

    This report is a user's manual which describes the operation of the computer program, GRUMWING. The program computes the viscous transonic flow over three-dimensional wings using a boundary layer type viscid-inviscid interaction approach. The inviscid solution is obtained by an approximate factorization (AFZ)method for the full potential equation. The boundary layer solution is based on integral entrainment methods.

  2. Scheduling language and algorithm development study. Volume 2, phase 2: Introduction to plans programming. [user guide

    Science.gov (United States)

    Cochran, D. R.; Ishikawa, M. K.; Paulson, R. E.; Ramsey, H. R.

    1975-01-01

    A user guide for the Programming Language for Allocation and Network Scheduling (PLANS) is presented. Information is included for the construction of PLANS programs. The basic philosophy of PLANS is discussed, and access and update reference techniques are described along with the use of tree structures.

  3. Final environmental statement, Liquid Metal Fast Breeder Reactor Program. Volume 1

    International Nuclear Information System (INIS)

    1975-12-01

    Information is presented under the following section headings: LMFBR program options and their compatibility with the major issues affecting commercial development, Proposed Final Environmental Statement for the LMFBR program, December 1974, WASH-1535, supplemental material, and material relating to Proposed Final Environmental Statement review

  4. World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

    International Nuclear Information System (INIS)

    1979-06-01

    Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment

  5. Skylab experiments. Volume 6: Mechanics. [Skylab program accomplishments for high school level education

    Science.gov (United States)

    1973-01-01

    Skylab program activities are presented in a form adapted to instruction of high school students. The overall goals of the program are discussed. The specific accomplishments of the mechanics investigations are described. The subjects involved are as follows: (1) evaluation of mobility aids, (2) mass measurement devices, and (3) space guidance crew/vehicle disturbances.

  6. World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment. (JWR)

  7. The Development and Application of the RAND Program Classification Tool. The RAND Toolkit, Volume 1

    Science.gov (United States)

    2014-01-01

    service, reference DoD programs related to psycho - logical health and TBI, but the R-PCT can be applied to other content areas or organizations. Table...and provides a high-level description, comparison, or classification of programs. Furthermore, given its simple architecture , the R-PCT can be

  8. The application of SHIELD-HIT12A computer code to calculate of absorption dose for in vitro and in vivo test in BNCT

    International Nuclear Information System (INIS)

    Yohannes Sardjono; Hamidatul Faqqiyyah; Niels Bassler

    2014-01-01

    The projection of world population growth and increased longevity are leading to a rapid increase in the total number of middle-aged and older adults, with a corresponding increase in the number of deaths caused by non communicable diseases. It is projected that the annual number of deaths due to cardiovascular disease will increase from 17 million in 2008 to 25 million in 2030 with annual cancer deaths increasing from 7.6 million to 13 million. Boron Neutron Capture Therapy is a therapy that utilizes the absorption interaction of Boron-10 with thermal neutron and become He-4 particle and located in cell target and very short half life gamma emission. Studies were carried out to dose distribution in HER-2+ breast cancer therapy by Boron Neutron Capture Therapy (BNCT) using SHIELD Heavy Ion Therapy (HIT12A) T program. The Monte Carlo particle transport code SHIELD-HIT1 is designed to precisely simulate therapeutic beams of protons and ions in biological tissue relevant for ion beam cancer therapy. SHIELD-HIT (Heavy Ion Therapy) evolved from the common SHIELD code that models interactions of hadrons and atomic nuclei in complex extended targets in the energy range up to 1 TeV/nucleon. Through this computer code can be applied to calculate of absorption dose in cell target. (author)

  9. Super-Efficient Refrigerator Program (SERP) evaluation volume 2: Preliminary impact and market transformation assessment

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A.D.; Conger, R.L.

    1996-08-01

    The Super Efficient Refrigerator Program (SERP) is a collaborative utility program intended to transform the market for energy-efficient and environmentally friendly refrigerators. It is one of the first examples of a large-scale {open_quotes}market transformation{close_quotes} energy efficiency program. This report documents the preliminary impact and market transformation evaluation of SERP ({open_quotes}the Program{close_quotes}). Pacific Northwest National Laboratory (PNNL) conducted this evaluation for the U.S. Department of Energy. This study focuses on the preliminary impact evaluation and market transformation assessment, but also presents limited process evaluation information. It is based on interviews with refrigerator dealers and manufacturers, interviews with utility participants, industry data, and information from the Program administrators. Results from this study complement those from prior process evaluation also conducted by PNNL. 42 refs., 5 figs., 4 tabs.

  10. Balanced program plan: analysis for biomedical and environmental research. Volume 7. Conservation and energy efficiency

    International Nuclear Information System (INIS)

    1975-07-01

    Energy conservation technologies encompass the entire spectrum of human activities: electrical supply, industry, commercial and residential buildings, transportation and various overlapping combinations of these. This report is concerned with those conservation technologies that appear to be most important in the near and intermediate terms. Many of the specific R and D programs are contained in the preliminary ''Conservation Program Plan'' of the ERDA Assistant Administrator for Conservation. However, some projects are included that are supported by other Federal agencies and private industry. Section 1 contains a brief description of each conservation technology and an enumeration of health/safety/environmental impacts, both beneficial and adverse, that are expected to accrue from the new technology. Section 2 contains a brief discussion of problems, priorities and programs. Section 3 contains ''Problem Definitions'' and ''Program Units'' that are recommended to become a part of the ''BER Balanced Program Plan.''

  11. Medical University of South Carolina Environmental Hazards Assessment Program. Volume 6: Annual report, July 1, 1993--June 30, 1994 deliverables

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Medical University of South Carolina`s vision is to become the premier national resource for medical information and for environmental/health risk assessment. A key component to the success of the many missions of the Environmental Hazards Assessment Program (EHAP) is timely access to large volumes of data. This study documents the results of the needs assessment effort conducted to determine the information access and processing requirements of EHAP. This report addresses the Department of Environmental Health Science, education and training initiative.

  12. 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

  13. 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

  14. United States Air Force Summer Research Program -- 1993 Summer Research Program Final Reports. Volume 12. Armstrong Laboratory

    Science.gov (United States)

    1993-01-01

    driving force of this experiment was to observe the photoelectric effect in biological substances (amino acids, proteins , or spores), a conducting metal...exercise before a flight, and maintaining a high protein , low bulk diet. Some leave alcohol out of their daily routine to help in the process of...report is going to give you ideas about how the R-WISE program works and looks. R-WISE has eight tools: Freewriting ( Dinosaur Drag), Sticky Notes

  15. United States Air Force Summer Research Program -- 1991. High School Apprenticeship Program (HSAP) Reports, Volume 13: Wright Laboratory

    Science.gov (United States)

    1991-12-01

    subroutines will be implemented in the program to provide for enhanced flexibility and increased user-friendliness. The final product should allow ease...would convert Turbo Pascal into Quick C. The converter worked well, and I was able to finish most of the code conversion (minus the commenting) during the...benchmarking had two variables - the computer system the tests were to be performed on and the vendor marketing a VHDL implementation for that computer

  16. Outer Continental Shelf Environmental Assessment Program. Final reports of principal investigators. Volume 74

    International Nuclear Information System (INIS)

    1991-10-01

    The volume contains: synthesis of seismicity studies for western Alaska; bottom and near-bottom sediment dynamics in Norton Sound; integration of circulation data in the Beaufort Sea; numerical modeling of storm surges in the Beaufort and Chukchi Seas; numerical modeling of storm surges in Norton Sound; Yukon delta oceanography and meteorology; and superstructure icing and wave hindcast statistics in the Navarin and St. George Basin areas

  17. Using a profiling process to insure program quality: Volume I - a self-instructional manual

    Energy Technology Data Exchange (ETDEWEB)

    Kaser, J.S.; Roody, D.S.; Raizen, S.A.

    1996-11-01

    Between 1990 and 1995 the U.S. Department of Energy (DOE) and the National Center for Improving Science Education (National Center) developed a system for ongoing evaluation of K-12 educational programs in the DOE-supported national energy Laboratories. As part of the formative evaluation component of this collaborative endeavor, field staff in the Laboratories began creating profiles of their programs. However, many individuals within DOE Headquarters were not familiar with this profiling process and were unprepared to use the valuable information that the profiles generated. This manual was produced to orient Headquarters staff to profiling. It focuses on how Headquarters staff can use the profiling process to help their funded programs establish and/or maintain high quality. Its purpose, then, is not to train Headquarters staff to become proficient in profiling, but to show them how to draw on the Laboratories` use of profiling to bring about program improvement. Profiling is the process of systematically examining and describing a program`s elements against a set of components that define Effective Practice. The instrument used to capture the data for analysis is called a template, and most of this manual focuses on the templates and how to read and interpret them. However, since it is important to understand these data in context, the authors also describe what should accompany each template in a complete profiling packet and offer guidelines for reviewing complete packets and providing feedback to program managers.

  18. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  19. Research programs at the Department of Energy National Laboratories. Volume 2: Laboratory matrix

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    For nearly fifty years, the US national laboratories, under the direction of the Department of Energy, have maintained a tradition of outstanding scientific research and innovative technological development. With the end of the Cold War, their roles have undergone profound changes. Although many of their original priorities remain--stewardship of the nation`s nuclear stockpile, for example--pressing budget constraints and new federal mandates have altered their focus. Promotion of energy efficiency, environmental restoration, human health, and technology partnerships with the goal of enhancing US economic and technological competitiveness are key new priorities. The multiprogram national laboratories offer unparalleled expertise in meeting the challenge of changing priorities. This volume aims to demonstrate each laboratory`s uniqueness in applying this expertise. It describes the laboratories` activities in eleven broad areas of research that most or all share in common. Each section of this volume is devoted to a single laboratory. Those included are: Argonne National Laboratory; Brookhaven National Laboratory; Idaho National Engineering Laboratory; Lawrence Berkeley Laboratory; Lawrence Livermore National Laboratory; Los Alamos National Laboratory; National Renewable Energy Laboratory; Oak Ridge National Laboratory; Pacific Northwest Laboratory; and Sandia National Laboratories. The information in this volume was provided by the multiprogram national laboratories and compiled at Lawrence Berkeley Laboratory.

  20. Budget estimates: Fiscal year 1994. Volume 3: Research and program management

    Science.gov (United States)

    1994-01-01

    The research and program management (R&PM) appropriation provides the salaries, other personnel and related costs, and travel support for NASA's civil service workforce. This FY 1994 budget funds costs associated with 23,623 full-time equivalent (FTE) work years. Budget estimates are provided for all NASA centers by categories such as space station and new technology investments, space flight programs, space science, life and microgravity sciences, advanced concepts and technology, center management and operations support, launch services, mission to planet earth, tracking and data programs, aeronautical research and technology, and safety, reliability, and quality assurance.

  1. Subseabed disposal program annual report, January-December 1979. Volume I. Summary and status

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-08-01

    This is the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program, which was begun in June 1973. The program was initiated by Sandia National Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world's oceans as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans. Summaries are presented in the following areas: systems analysis; barrier system characterization and assessment; environmental studies; emplacement; sampling and instrumentation development; and transportation studies

  2. Low Cost High Performance Generator Technology Program. Volume 5. Heat pipe topical, appendices

    International Nuclear Information System (INIS)

    1975-07-01

    Work performed by Dynatherm Corporation for Teledyne Isotopes during a program entitled ''Heat Pipe Fabrication, Associated Technical Support and Reporting'' is reported. The program was initiated on November 29, 1972; the main objectives were accomplished with the delivery of the heat pipes for the HPG. Life testing of selected heat pipe specimens is continuing to and beyond the present date. The program consisted of the following tasks: Heat Pipe Development of Process Definition; Prototype Heat Pipes for Fin Segment Test; HPG Heat Pipe Fabrication and Testing; Controlled Heat Pipe Life Test; and Heat Pipe Film Coefficient Determination

  3. 201Tl/99mTc-MIBI SPECT to evaluate therapy effect of BNCT with BSH and BPA for malignant brain tumor

    International Nuclear Information System (INIS)

    Shibata, Yasushi; Katayama, Wataru; Yamamoto, Tetsuya; Nakai, Kei; Endo, Kiyoshi; Matsuda, Masahide; Matsushita, Akira; Matsumura, Akira

    2006-01-01

    201 Tl/ 99m Tc-MIBI SPECT are imaging modalities to evaluate the malignancy and viability of brain tumor. We reviewed these SPECT findings before and after BNCT, and evaluated the usefulness of SPECT. The study includes total 11 patients admitted in our hospital between 1999 and 2005, 8 with glioblastoma, 2 with anaplastic astrocytoma and 2 with anaplastic oligodendroglioma. SPECT was taken with multidetector SPECT at 15 minutes and 3 hours after intravenous injection of Tl 74 MBq or MIBI 740 MBq. Region of interests were set on tumor and contralateral white matter and radioactivity ratios were calculated as Tl, MIBI indexes. For patients with no residual tumor in MRI, Tl/MIBI indexes were low. For patients with large residual tumor the indexes were high. For the patients with recurrent tumor the indexes were very high. Tl/MIBI indexes before BNCT correlated with survival and progression-free period after BNCT. SPECT indexes decreased after BNCT. For 8 patients with recurrent tumor, the indexes increased. Tl and MIBI SPECT are valuable to evaluate malignancy, viability, survival and recurrence of malignant glioma in BNCT. (author)

  4. Selection methodology for LWR safety programs and proposals. Volume 2. Methodology application

    International Nuclear Information System (INIS)

    Ritzman, R.L.; Husseiny, A.A.

    1980-08-01

    The results of work done to update and apply a methodology for selecting (prioritizing) LWR safety technology R and D programs are described. The methodology is based on multiattribute utility (MAU) theory. Application of the methodology to rank-order a group of specific R and D programs included development of a complete set of attribute utility functions, specification of individual attribute scaling constants, and refinement and use of an interactive computer program (MAUP) to process decision-maker inputs and generate overall (multiattribute) program utility values. The output results from several decision-makers are examined for consistency and conclusions and recommendations regarding general use of the methodology are presented. 3 figures, 18 tables

  5. Report on Activities and Programs for Countering Proliferation and NBC Terrorism. Volume 1. Executive Summary

    National Research Council Canada - National Science Library

    2006-01-01

    This Report on Activities and Programs for Countering Proliferation and NBC Terrorism is submitted to the United States Congress as required by the 1994 National Defense Authorization Act (NDAA) (as amended...

  6. History of the AFRL/USC DARPA Program on Polynitrogen Chemistry. Volume 2

    National Research Council Canada - National Science Library

    Christe, Karl O; Vij, Ashwani

    2004-01-01

    In the course of the High Energy Density Matter (HEDM) Program, which was initiated in 1986 by the Air Force, the potential of polynitrogen compounds for HEDM was recognized by numerous theoretical studies...

  7. MoDOT pavement preservation research program volume IV, pavement evaluation tools-data collection methods.

    Science.gov (United States)

    2015-10-01

    The overarching goal of the MoDOT Pavement Preservation Research Program, Task 3: Pavement Evaluation Tools Data : Collection Methods was to identify and evaluate methods to rapidly obtain network-level and project-level information relevant to :...

  8. Waste isolation in the U.S., technical programs and public education. Volume 2 - low level waste, volume reduction methodologies and economics. Vol. 2

    International Nuclear Information System (INIS)

    Post, R.G.

    1984-01-01

    This volume presents information regarding low-level waste, volume reduction methodologies and economics. Topics include: public education on nuclear waste; economics of low-level waste management systems; operating experience with advanced volume reduction techniques; solidification of waste; operating experience with advanced volume reduction techniques--incineration; regional plans for the disposal of low-level waste; radwaste system modifications at nuclear power plants; operating experience with advanced volume reduction techniques--operations and on-site storage issues; and economic impact of 10CFR61

  9. Medical University of South Carolina Environmental Hazards Assessment Program. Volume 5: Annual report, July 1, 1993--June 30, 1994 deliverables

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Medical University of South Carolina`s vision is to become the premier national resource for medical information and for environmental/health risk assessment. A key component to the success of the many missions of the Environmental Hazards Assessment Program (EHAP) is timely access to large volumes of data. This study documents the results of the needs assessment effort conducted to determine the information access and processing requirement of EHAP. The following topics are addressed in this report: environmental medicine and risk communication: curriculum and a professional support network-Department of Family Medicine; environmental hazards assessment and education program in pharmacy graduate education in risk assessment; and graduate education risk assessment.

  10. Learning from Experience, Volume 3: Lessons from the United Kingdom’s Astute Submarine Program

    Science.gov (United States)

    2011-01-01

    Growing future program managers and technical personnel within the MOD and the Royal Navy requires planning and implementation far in advance of...recognize problems that were growing in the program. At the same time, the program’s payment clauses were tied to production metrics such as length of...Ursula Laid down Launch Commission Unicorn Osiris Opportune Valiant Valiant Spartan Swiftsure Splendid Trafalgar Triumph Renown Repulse Vanguard

  11. Lightweight two-stroke cycle aircraft diesel engine technology enablement program, volume 2

    Science.gov (United States)

    Freen, P. D.; Berenyi, S. G.; Brouwers, A. P.; Moynihan, M. E.

    1985-01-01

    An experimental Single Cylinder Test Engine Program is conducted to confirm the analytically projected performance of a two-stroke cycle diesel engine for aircraft applications. Testing confirms the ability of a proposed 4-cylinder version of such an engine to reach the target power at altitude in a highly turbocharged configuration. The experimental program defines all necessary parameters to permit a design of a multicylinder engine for eventual flight applications.

  12. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide. Final Report

    International Nuclear Information System (INIS)

    Pelaccio, D.G.; Scheil, C.M.; Petrosky, L.J.

    1993-03-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner

  13. Directory of certificates of compliance for radioactive materials packages. Volume 3, revision 1. Summary report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1981-12-01

    The directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

  14. Ion channels involved in cell volume regulation: effects on migration, proliferation, and programmed cell death in non adherent EAT cells and adherent ELA cells.

    Science.gov (United States)

    Hoffmann, Else Kay

    2011-01-01

    This mini review outlines studies of cell volume regulation in two closely related mammalian cell lines: nonadherent Ehrlich ascites tumour cells (EATC) and adherent Ehrlich Lettre ascites (ELA) cells. Focus is on the regulatory volume decrease (RVD) that occurs after cell swelling, the volume regulatory ion channels involved, and the mechanisms (cellular signalling pathways) that regulate these channels. Finally, I shall also briefly review current investigations in these two cell lines that focuses on how changes in cell volume can regulate cell functions such as cell migration, proliferation, and programmed cell death. Copyright © 2011 S. Karger AG, Basel.

  15. Evaluation of neutron irradiation fields for BNCT by using absorbed dose in a phantom

    International Nuclear Information System (INIS)

    Aizawa, O.

    1993-01-01

    In a previous paper, the author defined the open-quotes irradiation timeclose quotes as the time of irradiation in which the maximum open-quotes total background doseclose quotes becomes 2,500 RBE-cGy. In this paper, he has modified the definition a little as the time of irradiation in which the maximum open-quotes lμg/g B-10 doseclose quotes becomes 3,000 RBE-cGy, because he assumed that normal tissue contained 1μg/g B-10. Moreover, he has modified the dose criteria for BNCT as follows: The open-quotes eye doseclose quotes, open-quotes total body doseclose quotes and open-quotes except-head doseclose quotes should be less that 200, 100 and 50 RBE-cGy, respectively. He has added one more criterion for BNCT that the thermal neutron fluence at the tumor position should be over 2.5x10 12 n/cm 2 at the open-quotes irradiation timeclose quotes. The distance from the core side to the irradiation port in the open-quotes old configurationclose quotes of the Musashi reactor (TRIGA-II, 100kW) was 160 cm. He is now planning to design an eccentric core and to move the reactor core nearer to the irradiation port, distance between the core side and the irradiation port to be 140, 130 and 120cm. The other assumptions used in this paper are as follows: (1) The B-10 concentrations in tumor are 30 and/or 10μg/g. (2) The depth of the tumor is 5.0 cm to 5.5 cm from the surface. (3) The RBE values used are 1.0 for all gamma rays and 2.3 for B 10 (n,α) reaction products. (4) The RBE values for neutrons are the following three cases: the first case is using 1.6 for all neutrons; the second one is using 3.2 for non-thermal neutrons and 1.6 for thermal neutrons; the third case is using 4.8 for fast neutrons, 3.2 for faster epithermal and epithermal neutrons, and 1.6 for thermal neutrons

  16. United States Air Force Summer Research Program 1991. Graduate Student Research Program (GSRP) Reports. Volume 9. Wright Laboratory

    Science.gov (United States)

    1992-01-09

    plotting mode shapes. All programs are written in FORTRAN for use on the VAX system. A flowchart of the entire analytical prediction method is shown...in Figure 1. below. RBDAT.FOR ’Lx [RBIN.DAT RBUP2.FOR ,. MODE.DAT --- ---- -4- -- RBOUT.DAT ~ I MODPLT.PRO II MODPLT.LN3 Figure 1. Flowchart for...CMES is LK Tool’s own derivation of DMIS; therefore, the only documentation is from LK Tool. I received a reference manual and a beginners training

  17. Fifteenth annual meeting of the Society for Organic Petrology. Abstracts and program. Volume 15

    Energy Technology Data Exchange (ETDEWEB)

    Mukhopadhyay, P.K.; Avery, M.P.; Calder, J.H.; Goodarzi, F. (eds.)

    1998-01-01

    The theme of the conference was 'Sailing into the new millennium'. Abstracts of the papers are included in this volume. Topics covered included: environmental implications of fossil fuel use - geochemical and petrological perspectives; environment, coal structure, and applied coal petrology; new innovations in coal microscopy and petrology/geochemistry of coal and coke; Eastern Canadian basins with implications for hydrocarbon resources; and organic petrology/geochemistry and petroleum system - world basin perspectives. Abstracts of the poster presentations are also included. Papers will be published in an issue of the International Journal of Coal Geology.

  18. Proceedings of the 1996 U.S. DOE hydrogen program review. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The 29 papers contained in Volume 1 are related to systems analysis and hydrogen production. Papers in the systems analysis section discuss utility markets, comparison of hydrogen with other alternative fuels, hydrogen vehicles, renewable hydrogen production, storage, and detection, and hydrogen storage systems development. Hydrogen production methods include the use of algae, photosynthesis, glucose dehydrogenase, syngas, photoelectrochemical reactions, photovoltaics, water electrolysis, solar photochemical reactions, pyrolysis, catalytic steam reforming, municipal solid wastes, thermocatalytic cracking of natural gas, and plasma reformers. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  19. The Environment for Application Software Integration and Execution (EASIE), version 1.0. Volume 2: Program integration guide

    Science.gov (United States)

    Jones, Kennie H.; Randall, Donald P.; Stallcup, Scott S.; Rowell, Lawrence F.

    1988-01-01

    The Environment for Application Software Integration and Execution, EASIE, provides a methodology and a set of software utility programs to ease the task of coordinating engineering design and analysis codes. EASIE was designed to meet the needs of conceptual design engineers that face the task of integrating many stand-alone engineering analysis programs. Using EASIE, programs are integrated through a relational data base management system. In volume 2, the use of a SYSTEM LIBRARY PROCESSOR is used to construct a DATA DICTIONARY describing all relations defined in the data base, and a TEMPLATE LIBRARY. A TEMPLATE is a description of all subsets of relations (including conditional selection criteria and sorting specifications) to be accessed as input or output for a given application. Together, these form the SYSTEM LIBRARY which is used to automatically produce the data base schema, FORTRAN subroutines to retrieve/store data from/to the data base, and instructions to a generic REVIEWER program providing review/modification of data for a given template. Automation of these functions eliminates much of the tedious, error prone work required by the usual approach to data base integration.

  20. Review of DOE waste package program. Subtask 1.1 - National Waste Package Program, October 1983-March 1984. Volume 6

    International Nuclear Information System (INIS)

    Soo, P.

    1985-03-01

    The present effort is part of an ongoing task to review the national high-level waste package effort. It includes evaluation of reference waste form, container, and packing material components with respect to determining how they may contribute to the containment and controlled release of radionuclides after waste packages have been emplaced in salt, basalt, tuff, and granite repositories. In the current Biannual Report a review of progress in the new crystalline repository (granite) program is described. Other foreign data for this host rock have also been outlined where relevant. The use of crushed salt, and bentonite- and zeolite-containing packing materials is discussed. The effects of temperature and gamma irradiation are shown to be important with respect to defining the localized environmental conditions around a waste package and the long-term integrity of the packing

  1. Automated design and optimization of flexible booster autopilots via linear programming, volume 1

    Science.gov (United States)

    Hauser, F. D.

    1972-01-01

    A nonlinear programming technique was developed for the automated design and optimization of autopilots for large flexible launch vehicles. This technique, which resulted in the COEBRA program, uses the iterative application of linear programming. The method deals directly with the three main requirements of booster autopilot design: to provide (1) good response to guidance commands; (2) response to external disturbances (e.g. wind) to minimize structural bending moment loads and trajectory dispersions; and (3) stability with specified tolerances on the vehicle and flight control system parameters. The method is applicable to very high order systems (30th and greater per flight condition). Examples are provided that demonstrate the successful application of the employed algorithm to the design of autopilots for both single and multiple flight conditions.

  2. Evaluation of Public Service Electric & Gas Company`s standard offer program, Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Goldman, C.A.; Kito, M.S.; Moezzi, M.M.

    1995-07-01

    In May 1993, Public Service Electric and Gas (PSE&G), the largest investor-owned utility in New Jersey, initiated the Standard Offer program, an innovative approach to acquiring demand-side management (DSM) resources. In this program, PSE&G offers longterm contracts with standard terms and conditions to project sponsors, either customers or third-party energy service companies (ESCOs), on a first-come, first-serve basis to fill a resource block. The design includes posted, time-differentiated prices which are paid for energy savings that will be verified over the contract term (5, 10, or 15 years) based on a statewide measurement and verification (M&V) protocol. The design of the Standard Offer differs significantly from DSM bidding programs in several respects. The eligibility requirements and posted prices allow ESCOs and other energy service providers to market and develop projects among customers with few constraints on acceptable end use efficiency technologies. In contrast, in DSM bidding, ESCOs typically submit bids without final commitments from customers and the utility selects a limited number of winning bidders who often agree to deliver a pre-specified mix of savings from various end uses in targeted markets. The major objectives of the LBNL evaluation were to assess market response and customer satisfaction; analyze program costs and cost-effectiveness; review and evaluate the utility`s administration and delivery of the program; examine the role of PSE&G`s energy services subsidiary (PSCRC) in the program and the effect of its involvement on the development of the energy services industry in New Jersey; and discuss the potential applicability of the Standard Offer concept given current trends in the electricity industry (i.e., increasing competition and the prospect of industry restructuring).

  3. MODIFIED N.R.C. VERSION OF THE U.S.G.S. SOLUTE TRANSPORT MODEL. VOLUME 2. INTERACTIVE PREPROCESSOR PROGRAM

    Science.gov (United States)

    The methods described in the report can be used with the modified N.R.C. version of the U.S.G.S. Solute Transport Model to predict the concentration of chemical parameters in a contaminant plume. The two volume report contains program documentation and user's manual. The program ...

  4. Design of Training Systems, Phase II Report, Volume III; Model Program Descriptions and Operating Procedures. TAEG Report No. 12-2.

    Science.gov (United States)

    Naval Training Equipment Center, Orlando, FL. Training Analysis and Evaluation Group.

    The Design of Training Systems (DOTS) project was initiated by the Department of Defense (DOD) to develop tools for the effective management of military training organizations. Volume 3 contains the model and data base program descriptions and operating procedures designed for phase 2 of the project. Flow charts and program listings for the…

  5. KAPSE (Kernel ADA Programming Support Environment) Interface Team Public Report. Volume 5.

    Science.gov (United States)

    1985-08-01

    terination of a child . It was pointed out, .howmver, that CAIS processes are closely analogous to Ada programs, which may include nwiny tasks, so this...NMlc)) - Write a single haractesr end cojp; end PM;/ 5.3.8.10 Easing a qualified area pr~zocedueRSEA( PORN : in ont PO TYP); Purposes This procedure

  6. The Survey of College Marketing Programs. Volume 2: Print Advertising and Marketing.

    Science.gov (United States)

    Primary Research Group, Inc., New York, NY.

    This report presents 213 tables detailing findings regarding types and costs of advertising within marketing programs at 68 colleges and universities. Highlights of this report include the following: these colleges print a mean number of 19,270 viewbooks and 16,380 catalogs; and advertise in newspapers (86.6 percent), in magazines (45.4 percent),…

  7. National Waste Terminal Storage Program: configuration management plan. Volume II. Plan description

    International Nuclear Information System (INIS)

    1977-05-01

    Purpose of the Configuration Management Plan is to provide the management discipline through which the integrity and continuity of program cost and schedule trade-off decisions which are made concerning the site selections and facilities performance, producibility, operability and supportability are recorded, communicated, and controlled by the Office of Waste Isolation

  8. National Waste Terminal Storage Program Information Management Plan. Volume I. Management summary

    International Nuclear Information System (INIS)

    1977-05-01

    A comprehensive information management plan is needed for the processing of the large amount of documentation that will accumulate in the National Waste Terminal Storage program over the next decade. The plan will apply to all documentation from OWI contractors, subcontractors, and suppliers, and to external documentation from OWI organizations

  9. Universal Documentation System Handbook. Volume 2: Program Requirements and Operations Requirements Documents

    Science.gov (United States)

    1979-11-01

    plane. The local horizontal plane is de- lined as a plane normal to the geocentric position vector. Boxes 11J and UJ are the angles measured east...support the program/mission. BOX 1-9 Follow instructions for Pa«« 1010. BOX 10 LOCATION: Enter the areas or locations that are to be staffed with

  10. National Waste Terminal Storage Program: planning and control plan. Volume II. Plan description

    International Nuclear Information System (INIS)

    1977-05-01

    Objective of the NWTS program planning and control plan is to provide the information necessary for timely and effective OWI management decisions. Purpose is to describe the concepts and techniques that will be utilized by OWI to establish structured, completely planned and controlled technical, cost, and schedule NWTS baselines from which performance or progress can be accurately measured

  11. Water Treatment Plant Operation. Volume II. A Field Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  12. Water Treatment Plant Operation. Volume I. A Field Study Training Program.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  13. Operation of Wastewater Treatment Plants. Volume 1. A Field Study Training Program. Third Edition. Revised.

    Science.gov (United States)

    California State Univ., Sacramento. Dept. of Civil Engineering.

    The purpose of this wastewater treatment field study training program is to: (1) develop new qualified wastewater treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  14. Water Treatment Plant Operation Volume 2. A Field Study Training Program. Revised.

    Science.gov (United States)

    California State Univ., Sacramento. School of Engineering.

    The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

  15. Seabed disposal program. Annual report, January--December 1977. Volume 1

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1979-01-01

    At the conclusion of the fourth year of the program, it can again be stated that no technological or environmental reasons have been identified that would preclude the possibility of successful disposal of HLW or spent fuel in stable, sedimentary formations beneath the abyssal floors of the deep oceans

  16. Regulatory Oversight Program, July 1, 1993 - March 3, 1997. Volume 1

    International Nuclear Information System (INIS)

    1997-09-01

    On July 1, 1993, a Regulatory Oversight (RO) organization was established within the United States Department of Energy (DOE), Oak Ridge Operations (ORO) to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the RO program was to ensure continued plant safety, safeguards and security while the Paducah and Portsmouth gaseous diffusion plants (GDPs) transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). These activities were performed under the authority of the lease agreement between DOE and USEC until NRC issued a Certificate of Compliance or approved a Compliance Plan pursuant to Section 1701 of the Atomic Energy Act of 1954, as amended, and assumed regulatory responsibility. This report chronicles the formal development, operation and key activities of the RO organization from its beginning in July 1993, until the turnover of the regulatory oversight responsibility to the NRC on March 3, 1997. Through its evolution to closure, the RO program was a formal, proceduralized effort designed to provide consistent regulation and to facilitate transition to NRC. The RO Program was also a first-of-a-kind program for DOE. The process, experience, and lessons learned summarized herein should be useful as a model for transition of other DOE facilities to privatization or external regulation

  17. Secretary's annual report to Congress. Volume I. Posture statement, outlook and program review

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-01

    Activities of all elements of the Department of Energy (DOE) except those of FERC are reported. Chapter I, the Posture Statement, gives an overview of the policies, programs, and strategies of DOE. It describes the national energy policy and its effects, sets out the current state of energy supply and demand in the US and around the world, describes the present assessment of future energy availability, and outlines the strategy for 1982. Additional chapters detail the major programs in the following Offices or Assistant Secretaryships: Conservation, Fossil Fuel, Nuclear Energy, Renewable Energy Resources, Electric Energy Systems and Energy Storage, Environment, Energy Supporting Research, Energy Production and Power Marketing, Energy Information, Economic Regulation, General Science, Defense, International Programs, Nuclear Non-Proliferation, Energy Contingency Planning, and Administration. Information is included in appendices on foreign direct investment in US energy sources and supplies for 1979, exports of energy resources by foreign companies, major recipients of DOE funding, DOE actions taken regarding disclosure of energy assets by DOE employees, and financial assistance programs. (MCW)

  18. National waste terminal storage program: configuration management plan. Volume I. Management summary

    International Nuclear Information System (INIS)

    1977-05-01

    Objective of the Configuration Management Plan is to describe the Office of Waste Isolation's approach for the systematic identification, change control, status accounting, and auditing of: documents defining the NWTS Program and the plans for attaining the defined objectives; physical and functional characteristics of each storage site, facility, systems and equipment; and associated costs and schedules

  19. Regulatory Oversight Program, July 1, 1993--March 3, 1997. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    On July 1, 1993, a Regulatory Oversight (RO) organization was established within the United States Department of Energy (DOE), Oak Ridge Operations (ORO) to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the RO program was to ensure continued plant safety, safeguards and security while the Paducah and Portsmouth gaseous diffusion plants (GDPs) transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). These activities were performed under the authority of the lease agreement between DOE and USEC until NRC issued a Certificate of Compliance or approved a Compliance Plan pursuant to Section 1701 of the Atomic Energy Act of 1954, as amended, and assumed regulatory responsibility. This report chronicles the formal development, operation and key activities of the RO organization from its beginning in July 1993, until the turnover of the regulatory oversight responsibility to the NRC on March 3, 1997. Through its evolution to closure, the RO program was a formal, proceduralized effort designed to provide consistent regulation and to facilitate transition to NRC. The RO Program was also a first-of-a-kind program for DOE. The process, experience, and lessons learned summarized herein should be useful as a model for transition of other DOE facilities to privatization or external regulation.

  20. National Waste Terminal Storage Program: critical element management concept. Volume II. Concept description

    International Nuclear Information System (INIS)

    1977-05-01

    The objective of the CEM Concept is to describe techniques for systematically identifying, evaluating, and influencing those technical, social, economic, political and institutional factors (i.e., events, trends and conditions) that are perceived as being probable uncertainties to the attainment of planned program objectives