DOCSLIB.ORG

Current Status of Neutron Capture Therapy

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Current Status of Neutron Capture Therapy IAEA-TECDOC-1223 Current status of neutron capture therapy May 2001 The originating Sections of this publication in the IAEA was: Applied Radiation Biology and Radiotherapy Section Dosimetry and Medical Radiation Physics Section Division of Human Health and the Physics Section Division of Physical and Chemical Sciences International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria CURRENT STATUS OF NEUTRON CAPTURE THERAPY IAEA, VIENNA, 2001 IAEA-TECDOC-1223 ISSN 1011–4289 © IAEA, 2001 Printed by the IAEA in Austria May 2001 FOREWORD There are about 6000 new glioblastoma multiform brain tumours diagnosed each year in the United States of America alone. This cancer is usually fatal within six months of diagnosis even with current standard treatments. Research on boron neutron capture therapy (BNCT) has been considered as a method of potentially curing such cancers. There is a great interest at under-utilised research reactors institutions to identify new medical utilization, attractive to the general public. Neutron capture therapy is a true multidisciplinary topic with a large variety of individuals involved. This publication attempts to provide current information for all those thinking about being involved with NCT, based on the knowledge and experience of those who have pioneered the treatment. It covers the whole range of NCT from designing reactor conversions or new facilities, through to clinical trials and their effectiveness. However, since most work has been done with boron capture therapy for brain tumours using modified thermal research reactors, this tends to be the focus of the report. One of the factors which need to be addressed at the beginning is the timing of the further development of NCT facilities. It should be emphasised that all current work is still at the research stage. Many of those now involved believe that there is little need for many more research facilities until such time as the treatment shows more promising results. For this and other reasons discussed in the report, very serious consideration should be given by research reactor owners and operators before spending large sums of money converting their facilities for NCT. Papers presented at the Technical Committee Meeting on Current Issues Related to Neutron Capture Therapy, held in Vienna from 14 to 18 June 1999, are given in the annexes. The contribution of the participants to the drafting of this publication is gratefully acknowledged. The consultant editorial group which significantly contributed to this publication comprised: D. Rorer of the Brookhaven National Laboratory, USA, A. Wambersie of the Université Catholique de Louvain, Belgium, G. Whitmore of the Ontario Cancer Institute, Princess Margret Hospital, Canada and R. Zamenhof of the Beth Israel Deaconess Medical Center, USA. The IAEA staff members responsible for the preparation of this publication were V. Levin and P. Andreo of the Division of Human Health and B. Dodd of the Division of Physical and Chemical Sciences. EDITORIAL NOTE In preparing this publication for press, staff of the IAEA have made up the pages from the original manuscript(s). The views expressed do not necessarily reflect those of the IAEA, the governments of the nominating Member States or the nominating organizations. Throughout the text names of Member States are retained as they were when the text was compiled. The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. CONTENTS OVERVIEW ...............................................................................................................................1 1. DESIRED NEUTRON BEAM PARAMETERS....................................................................6 1.1. General beam properties..................................................................................................6 1.2. Epithermal beam intensity...............................................................................................7 1.3. Incident beam quality ......................................................................................................7 1.3.1. The fast neutron component..................................................................................8 1.3.2. The gamma ray component ...................................................................................8 1.3.3. The ratio between the thermal flux and the epithermal flux .................................8 1.3.4. The ratio between the total neutron current and the total neutron flux. ................8 1.4. Beam size ........................................................................................................................8 2. NEUTRON SOURCES FOR CAPTURE THERAPY...........................................................9 2.1. Possible sources of neutrons ...........................................................................................9 2.2. Converted thermal reactors using spectrum shifting and filtering ..................................9 2.3. Fast reactors.....................................................................................................................9 2.4. New reactor designs ........................................................................................................9 2.5. Fission converters..........................................................................................................10 2.6. Accelerators...................................................................................................................10 2.7. Californium ...................................................................................................................10 References to Section 2 ........................................................................................................12 3. REACTOR AND BEAM DESIGN CONSIDERATIONS...................................................13 3.1. Core reflector.................................................................................................................13 3.2. Spectrum shift vs. filtered beam....................................................................................13 3.3. Core-to-patient distance ................................................................................................13 3.4. Beam intensity and current-to-flux ratio .......................................................................14 3.5. Undesirable radiation components in the incident epithermal beam ............................15 3.5.1. Gamma contamination ........................................................................................15 3.5.2. Thermal neutron contamination ..........................................................................15 3.5.3. Fast neutron contamination .................................................................................16 3.6. Moderators ....................................................................................................................16 3.7. Filters.............................................................................................................................16 3.8. Collimators....................................................................................................................16 3.9. Shutters..........................................................................................................................17 3.10. Fission converters........................................................................................................17 3.11. Reactor beam design analysis......................................................................................18 3.12. Beam monitoring.........................................................................................................19 References to Section 3 ........................................................................................................20 4. IRRADIATION FACILITY OPERATION AND MANAGEMENT...................................21 4.1. Operation of the facility ................................................................................................21 4.1.1. Reliability............................................................................................................21 4.1.2. Availability..........................................................................................................21 4.1.3. Single versus multiple users................................................................................21 4.1.4. Continuous versus intermittent operations..........................................................21 4.2. Personnel at the NCT facility........................................................................................21 4.2.1. Staffing needs......................................................................................................22 4.2.2. Responsibilities ...................................................................................................22 4.3. Technical co-operation and communication .................................................................23 4.3.1. Between reactor operation
Load more

Recommended publications
  • Understanding the Potentiality of Accelerator
    Bortolussi et al. Radiation Oncology (2017) 12:130 DOI 10.1186/s13014-017-0860-6 RESEARCH Open Access Understanding the potentiality of accelerator based-boron neutron capture therapy for osteosarcoma: dosimetry assessment based on the reported clinical experience Silva Bortolussi1,2* , Ian Postuma2, Nicoletta Protti2, Lucas Provenzano3,4, Cinzia Ferrari5,2, Laura Cansolino5,6, Paolo Dionigi5,6, Olimpio Galasso7, Giorgio Gasparini7, Saverio Altieri1,2, Shin-Ichi Miyatake8 and Sara J. González3,4 Abstract Background: Osteosarcoma is the most frequent primary malignant bone tumour, and its incidence is higher in children and adolescents, for whom it represents more than 10% of solid cancers. Despite the introduction of adjuvant and neo-adjuvant chemotherapy that markedly increased the success rate in the treatment, aggressive surgery is still needed and a considerable percentage of patients do not survive due to recurrences or early metastases. Boron Neutron Capture Therapy (BNCT), an experimental radiotherapy, was investigated as a treatment that could allow a less aggressive surgery by killing infiltrated tumour cells in the surrounding healthy tissues. BNCT requires an intense neutron beam to ensure irradiation times of the order of 1 h. In Italy, a Radio Frequency Quadrupole (RFQ) proton accelerator has been designed and constructed for BNCT, and a suitable neutron spectrum was tailored by means of Monte Carlo calculations. This paper explores the feasibility of BNCT to treat osteosarcoma using this neutron source based on accelerator. Methods: The therapeutic efficacy of BNCT was analysed evaluating the dose distribution obtained in a clinical case of femur osteosarcoma. Mixed field dosimetry was assessed with two different formalisms whose parameters were specifically derived from radiobiological experiments involving in vitro UMR-106 osteosarcoma cell survival assays and boron concentration assessments in an animal model of osteosarcoma.
    [Show full text]
  • Neutron Interactions and Dosimetry Outline Introduction Tissue
    Outline • Neutron dosimetry Neutron Interactions and – Thermal neutrons Dosimetry – Intermediate-energy neutrons – Fast neutrons Chapter 16 • Sources of neutrons • Mixed field dosimetry, paired dosimeters F.A. Attix, Introduction to Radiological • Rem meters Physics and Radiation Dosimetry Introduction Tissue composition • Consider neutron interactions with the majority tissue elements H, O, C, and N, and the resulting absorbed dose • Because of the short ranges of the secondary charged particles that are produced in such interactions, CPE is usually well approximated • Since no bremsstrahlung x-rays are generated, the • The ICRU composition for muscle has been assumed in absorbed dose can be assumed to be equal to the most cases for neutron-dose calculations, lumping the kerma at any point in neutron fields at least up to 1.1% of “other” minor elements together with oxygen to an energy E ~ 20 MeV make a simple four-element (H, O, C, N) composition Neutron kinetic energy Neutron kinetic energy • Neutron fields are divided into three • Thermal neutrons, by definition, have the most probable categories based on their kinetic energy: kinetic energy E=kT=0.025eV at T=20C – Thermal (E<0.5 eV) • Neutrons up to 0.5eV are considered “thermal” due to simplicity of experimental test after they emerge from – Intermediate-energy (0.5 eV<E<10 keV) moderator material – Fast (E>10 keV) • Cadmium ratio test: • Differ by their primary interactions in tissue – Gold foil can be activated through 197Au(n,)198Au interaction and resulting biological effects
    [Show full text]
  • Neutrons and Fundamental Symmetries Experimental II: Edms Chen-Yu Liu Indiana University [email protected]
    Neutrons and Fundamental Symmetries Experimental II: EDMs Chen-Yu Liu Indiana University [email protected] June 20, 2018 NNPSS 1 Topics I will cover: Lecture 1: beta-decay • A brief history of the electroweak theory---the precursor to the Standard Model. • Neutron decay to test the V-A theory & beyond the SM interactions • Current status with neutron experiments on gA & lifetime • Physics is Symmetries Lecture 2: EDM Q: Why does EDM violate T? • CP violation • Electric Dipole Moments: Highly sensitive low-energy probes of new Physics • muon- g-2 Lecture 3: other symmetry violation measurements/tests • Baryogenesis & symmetry violations • Nnbar oscillation: B violation • Hadronic weak interactions: P violation • NOPTREX: T violation • Neutron interferometry: Lorentz symmetry violation Chen-Yu Liu 2 Mirror (leftright) “Signatures of the Artist,” by S. Vigdor, Oxford University Press(2018) Challenge: Can you find the differences (in three places) between the final and the original picture? Mirror (up down) “Plane-filling motif with reptiles” by M.C. Escher P Blackwhite CP 3 CP T Since time symmetry requires that these time-reversed relative directions be equally probable, it requires that there be no average charge separation along the spin direction, so the EDM must vanish. or If an non-zero EDM is found, then the time reversal symmetry is violated, and through the CPT theorem, the CP is violated by the same amount. 4 Electric Dipole Moment of polar molecules NH3 molecule has two ground states. They are of the same energies (degenerate). Time Reversal J J d d d d J J Electric Dipole Moment of polar molecules NH3 molecule has two ground states.
    [Show full text]
  • Neutron Activation and Prompt Gamma Intensity in Ar/CO $ {2} $-Filled Neutron Detectors at the European Spallation Source
    Neutron activation and prompt gamma intensity in Ar/CO2-filled neutron detectors at the European Spallation Source E. Diana,b,c,∗, K. Kanakib, R. J. Hall-Wiltonb,d, P. Zagyvaia,c, Sz. Czifrusc aHungarian Academy of Sciences, Centre for Energy Research, 1525 Budapest 114., P.O. Box 49., Hungary bEuropean Spallation Source ESS ERIC, P.O Box 176, SE-221 00 Lund, Sweden cBudapest University of Technology and Economics, Institute of Nuclear Techniques, 1111 Budapest, M}uegyetem rakpart 9. dMid-Sweden University, SE-851 70 Sundsvall, Sweden Abstract Monte Carlo simulations using MCNP6.1 were performed to study the effect of neutron activation in Ar/CO2 neutron detector counting gas. A general MCNP model was built and validated with simple analytical calculations. Simulations and calculations agree that only the 40Ar activation can have a considerable effect. It was shown that neither the prompt gamma intensity from the 40Ar neutron capture nor the produced 41Ar activity have an impact in terms of gamma dose rate around the detector and background level. Keywords: ESS, neutron detector, B4C, neutron activation, 41Ar, MCNP, Monte Carlo simulation 1. Introduction Ar/CO2 is a widely applied detector counting gas, with long history in ra- diation detection. Nowadays, the application of Ar/CO2-filled detectors is ex- tended in the field of neutron detection as well. However, the exposure of arXiv:1701.08117v2 [physics.ins-det] 16 Jun 2017 Ar/CO2 counting gas to neutron radiation carries the risk of neutron activa- tion. Therefore, detailed consideration of the effect and amount of neutron ∗Corresponding author Email address: [email protected] (E.
    [Show full text]
  • Not All Superheroes Were Created Equal
    00 gresh fm i-xii, 1-6 8/13/04 1:54 PM Page i THE SCIENCE OF SUPERVILLAINS Lois H. Gresh Robert Weinberg John Wiley & Sons, Inc. 00 gresh fm i-xii, 1-6 8/13/04 1:54 PM Page ii Copyright © 2005 by Lois H. Gresh and Robert Weinberg. All rights reserved Introduction © Chris Claremont. All rights reserved Published by John Wiley & Sons, Inc., Hoboken, New Jersey Published simultaneously in Canada No part of this publication may be reproduced, stored in a retrieval system, or transmitted in any form or by any means, electronic, mechanical, photocopying, recording, scanning, or otherwise, except as permitted under Section 107 or 108 of the 1976 United States Copyright Act, without either the prior written permission of the Publisher, or authorization through payment of the appropriate per-copy fee to the Copyright Clearance Center, 222 Rosewood Drive, Danvers, MA 01923, (978) 750-8400, fax (978) 646-8600, or on the web at www.copyright.com. Requests to the Publisher for permission should be addressed to the Permissions Department, John Wiley & Sons, Inc., 111 River Street, Hoboken, NJ 07030, (201) 748-6011, fax (201) 748-6008. Limit of Liability/Disclaimer of Warranty: While the publisher and the author have used their best efforts in preparing this book, they make no representations or warranties with respect to the accuracy or completeness of the contents of this book and specifically disclaim any implied war- ranties of merchantability or fitness for a particular purpose. No warranty may be created or extended by sales representatives or written sales materials.
    [Show full text]
  • AKA Clark Kent) Middle Name Is Joseph
    Superman’s (AKA Clark Kent) Middle Name Is Joseph. What’s that?! There in the sky? Is it a bird? Is it a plane? No! It’s the Man of Tomorrow! Superman has gone by many names over the years, but one thing has remained the same. He has always stood for what’s best about humanity, all of our potential for terrible destructive acts, but also our choice to not act on the level of destruction we could wreak. Superman was first created in 1933 by Joe Shuster and Jerry Siegel, the writer and artist respectively. His first appearance was in Action Comics #1, and that was the beginning of a long and illustrious career for the Man of Steel. In his unmistakable blue suit with red cape, and the stylized red S on his chest, the figure of Superman has become one of the most recognizable in the world. The original Superman character was a bald telepathic villain that was focused on world domination. It was like a mix of Lex Luthor and Professor X. Superman’s powers include incredible strength, the ability to fly. X-ray vision, super speed, invulnerability to most attacks, super hearing, and super breath. He is nearly unstoppable. However, Superman does have one weakness, Kryptonite. When exposed to this radioactive element from his home planet, he becomes weak and helpless. Superman’s alter ego is mild-mannered reporter Clark Kent. He lives in the city of Metropolis and works for the newspaper the Daily Planet. Clark is in love with fellow reporter Lois Lane.
    [Show full text]
  • All Batman References in Teen Titans
    All Batman References In Teen Titans Wingless Judd boo that rubrics breezed ecstatically and swerve slickly. Inconsiderably antirust, Buck sequinedmodernized enough? ruffe and isled personalties. Commie and outlined Bartie civilises: which Winfred is Behind Batman Superman Wonder upon The Flash Teen Titans Green. 7 Reasons Why Teen Titans Go Has Failed Page 7. Use of teen titans in batman all references, rather fitting continuation, red sun gauntlet, and most of breaching high building? With time throw out with Justice League will wrap all if its members and their powers like arrest before. Worlds apart label the bleak portentousness of Batman v. Batman Joker Justice League Wonder whirl Dark Nights Death Metal 7 Justice. 1 Cars 3 Driven to Win 4 Trivia 5 Gallery 6 References 7 External links Jackson Storm is lean sleek. Wait What Happened in his Post-Credits Scene of Teen Titans Go knowing the Movies. Of Batman's television legacy in turn opinion with very due respect to halt late Adam West. To theorize that come show acts as a prequel to Batman The Animated Series. Bonus points for the empire with Wally having all sorts of music-esteembody image. If children put Dick Grayson Jason Todd and Tim Drake in inner room today at their. DUELA DENT duela dent batwoman 0 Duela Dent ideas. Television The 10 Best Batman-Related DC TV Shows Ranked. Say is famous I'm Batman line while he proceeds to make references. Spoilers Ahead for sound you missed in Teen Titans Go. The ones you essential is mainly a reference to Vicki Vale and Selina Kyle Bruce's then-current.
    [Show full text]
  • TUTORIAL on NEUTRON PHYSICS in DOSIMETRY S. Pomp1
    TUTORIAL ON NEUTRON PHYSICS IN DOSIMETRY S. Pomp1,* 1 Department of physics and astronomy, Uppsala University, Box 516, 751 20 Uppsala, Sweden. *Corresponding author. E‐mail address: [email protected] (S.Pomp) Abstract: Almost since the time of the discovery of the neutron more than 70 years ago, efforts have been made to understand the effects of neutron radiation on tissue and, eventually, to use neutrons for cancer treatment. In contrast to charged particle or photon radiations which directly lead to release of electrons, neutrons interact with the nucleus and induce emission of several different types of charged particles such as protons, alpha particles or heavier ions. Therefore, a fundamental understanding of the neutron‐nucleus interaction is necessary for dose calculations and treatment planning with the needed accuracy. We will discuss the concepts of dose and kerma, neutron‐nucleus interactions and have a brief look at nuclear data needs and experimental facilities and set‐ups where such data are measured. Keywords: Neutron physics; nuclear reactions; kerma coefficients; neutron beams; Introduction Dosimetry is concerned with the ability to determine the absorbed dose in matter and tissue resulting from exposure to directly and indirectly ionizing radiation. The absorbed dose is a measure of the energy deposited per unit mass in the medium by ionizing radiation and is measured in Gray, Gy, where 1 Gy = 1 J/kg. Radiobiology then uses information about dose to assess the risks and gains. A risk is increased probability to develop cancer due to exposure to a certain dose. A gain is exposure of a cancer tumour to a certain dose in order to cure it.
    [Show full text]
  • Development of a Dual-Particle Imaging System for Nonproliferation Applications
    Development of a Dual-Particle Imaging System for Nonproliferation Applications By Alexis Pierre Valère Poitrasson-Rivière A dissertation submitted in partial fulfillement of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering and Radiological Sciences) in the University of Michigan 2016 Doctoral Committee: Professor Sara A. Pozzi, Chair Assistant Professor Marek Flaska, Penn State University Professor Zhong He Associate Professor David D. Wentzloff © Alexis Pierre Valère Poitrasson-Rivière 2016 Dedication This work is dedicated to my rock and my wind. ii Acknowledgements I would first of all like to thank my family and friends for supporting me throughout my doctoral studies. I would also like to thank my advisor, my committee members, the faculty and staff at the Nuclear Engineering & Radiological Sciences department, as well as all the students I had the chance to interact with, for making this experience fulfilling and enjoyable from start to finish. I would finally like to thank the different sponsors that have helped make this work possible. This work is supported, in part, by the U.S. Defense Threat Reduction Agency under Grant No. HDTRA1-09-C-0012, by the National Nuclear Security Administration through NA-22 funding opportunity DE-FOA-0000568, and by the National Science Foundation and the Domestic Nuclear Detection Office of the Department of Homeland Security through the Academic Research Initiative Award #CMMI 0938909. The prototype systems described in this work are funded by the Department of Energy,
    [Show full text]
  • Concrete Analysis by Neutron-Capture Gamma Rays Using Californium 252
    CONCRETE ANALYSIS BY NEUTRON-CAPTURE GAMMA RAYS USING CALIFORNIUM 252 Dick Duffey, College of Engineering, University of Maryland; Peter F. Wiggins, Naval Systems Engineering Department, U.S. Naval Academy; Frank E. Senftle, U.S. Geological Survey; and A. A. El Kady, United Arab Republic Atomic Energy Establishment, Cairo The feasibility of analyzing concrete and cement by a measurement of the neutron-capture or prompt gamma rays was investigated; a 100-ug californium-252 source was used to supply the neutrons. A lithium drifted germanium crystal detected the capture gamma rays emitted. The capture gamma rays from cement, sand, and 3 coarse aggregates-quartzite gravel, limestone, and diabase--:were studied. Concrete blocks made from these materials were then tested. The capture gamma ray response of the calcium, silicon, and iron in the concrete blocks was in accord with the elements identified in the mix materials. The principal spectral lines used were the 6.42 MeV line of calcium, the 4.93 MeV line of silicon, and the doublet of iron at about 7 .64 MeV. The aluminum line at 7. 72 MeV was ob­ served in some cases but at a lower intensity with the limited electronic equipment available. This nuclear spectroscopic technique offers a possi­ ble method of determining the components of sizable concrete samples in a nondestructive, in situ manner. In addition, the neutron-capture gamma ray technique might find application in control of the concrete and cement processes and furnish needed information on production operations and inventories. • FROM THE point of view of the geochemical analyst, concrete may be considered as rock relocated and reformed at the convenience of the engineer.
    [Show full text]
  • Conceptual Design Report Jülich High
    General Allgemeines ual Design Report ual Design Report Concept Jülich High Brilliance Neutron Source Source Jülich High Brilliance Neutron 8 Conceptual Design Report Jülich High Brilliance Neutron Source (HBS) T. Brückel, T. Gutberlet (Eds.) J. Baggemann, S. Böhm, P. Doege, J. Fenske, M. Feygenson, A. Glavic, O. Holderer, S. Jaksch, M. Jentschel, S. Kleefisch, H. Kleines, J. Li, K. Lieutenant,P . Mastinu, E. Mauerhofer, O. Meusel, S. Pasini, H. Podlech, M. Rimmler, U. Rücker, T. Schrader, W. Schweika, M. Strobl, E. Vezhlev, J. Voigt, P. Zakalek, O. Zimmer Allgemeines / General Allgemeines / General Band / Volume 8 Band / Volume 8 ISBN 978-3-95806-501-7 ISBN 978-3-95806-501-7 T. Brückel, T. Gutberlet (Eds.) Gutberlet T. Brückel, T. Jülich High Brilliance Neutron Source (HBS) 1 100 mA proton ion source 2 70 MeV linear accelerator 5 3 Proton beam multiplexer system 5 4 Individual neutron target stations 4 5 Various instruments in the experimental halls 3 5 4 2 1 5 5 5 5 4 3 5 4 5 5 Schriften des Forschungszentrums Jülich Reihe Allgemeines / General Band / Volume 8 CONTENT I. Executive summary 7 II. Foreword 11 III. Rationale 13 1. Neutron provision 13 1.1 Reactor based fission neutron sources 14 1.2 Spallation neutron sources 15 1.3 Accelerator driven neutron sources 15 2. Neutron landscape 16 3. Baseline design 18 3.1 Comparison to existing sources 19 IV. Science case 21 1. Chemistry 24 2. Geoscience 25 3. Environment 26 4. Engineering 27 5. Information and quantum technologies 28 6. Nanotechnology 29 7. Energy technology 30 8.
    [Show full text]
  • Nuclear Data for Medical Applications ° ° INM-5: Nuklearchemie,INM-5: Forschungszentrum Germjülich, Abteilung Nuklearchemie, Zu Germanuniversitätköln, ° Syed M
    Mitglied der Helmholtz-Gemeinschaft derMitglied Nuclear Data for Medical Applications ° Syed M. Qaim ° INM-5: Nuklearchemie, Forschungszentrum Jülich, Germany; ° Abteilung Nuklearchemie, Universität zu Köln, Germany Plenary Lecture given at a Workshop in the 7 th Framework Programme of the European Union on “Solving Challenges in Nuclear Data for the Safety of Nuclear Facilities (CHANDA)”, Paul Scherrer Institute, Villigen, Switzerland, 23 to 25 November 2015 Outline ° Introduction - external radiation therapy - internal radionuclide applications ° Commonly used radionuclides - status of nuclear data - alternative routes for production of 99m Tc - standardisation of production data ° Research oriented radionuclides - non-standard positron emitters - novel therapeutic radionuclides ° New directions in radionuclide applications ° Future data needs ° Summary and conclusions Nuclear Data Research for Medical Use Aim ° Provide fundamental database for - external radiation therapy - internal radionuclide applications Areas of Work ° Experimental measurements ° Nuclear model calculations ° Standardisation and evaluation of existing data Considerable effort is invested worldwide in nuclear data research External Radiation Therapy • Biological changes under the impact of radiation • Of significance is linear energy transfer (LET) to tissue Types of Therapy • Photon therapy : use of 60 Co or linear accelerator (low-LET radiation ) most common • Fast neutron therapy : accelerator with E p or E d above 50 MeV (high-LET radiation ) being abandoned
    [Show full text]