Design and Performance Of A Thermal Neutron Beam for Boron Neutron Capture Therapy At The University Of Missouri Research Reactor

Similar documents
Radiation Dosimetry at the BNL High Flux Beam Reactor and Medical Research Reactor

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

Study on Microdosimetry for Boron Neutron Capture Therapy

Progress in Reactor and Accelerator Based BNCT at Kyoto University Research Reactor Institute

Optimization of an accelerator-based epithermal neutron source for neutron capture therapy

COMPARING THE RESPONSES OF TLD 100, TLD 600, TLD 700 AND TLD 400 IN MIXED NEUTRON-GAMMA FIELDS

A Feasibility Study of the SLOWPOKE-2 Reactor as a Neutron Source for Boron Neutron Cancer Treatment

Preliminary study of MAGAT polymer gel dosimetry for boron-neutron capture therapy

THE HIGH-CURRENT DEUTERON ACCELERATOR FOR THE NEUTRON THERAPY. S.V. Akulinichev, A. V. Andreev, V.M. Skorkin

Neutrons. ρ σ. where. Neutrons act like photons in the sense that they are attenuated as. Unlike photons, neutrons interact via the strong interaction

Boron Neutron Capture Therapy (BNCT) - Low-Energy Neutron Spectrometer for Neutron Field Characterization - )

Study of neutron-dna interaction at the IPEN BNCT Research facility ABSTRACT

On the optimal energy of epithermal neutron beams for BNCT

Djoko S. Pudjorahardjo, Widarto, Isman Mulyadi T

Simulation of the BNCT of Brain Tumors Using MCNP Code: Beam Designing and Dose Evaluation

Neutron - a tool in the cancer treatment - C. Paunoiu

RPI DOSIMETRY. Therefore the description of the work is grouped in two main areas:

Figure 3. DS02 point-wise kerma coefficients (see Table 2) and DS02 fine group kerma coefficients (see Table 5) for photons in soft tissue.

THERMOLUMINESCENT (TL) DOSIMETRY OF SLOW-NEUTRON FIELDS AT RADIOTHERAPY DOSE LEVEL

Numerical optimisation of the fission-converter and the filter/moderator arrangement for the Boron Neutron Capture Therapy (BNCT)

Design of a BSA for Producing Epithermal Neutron for BNCT

Neutron Interactions Part 2. Neutron shielding. Neutron shielding. George Starkschall, Ph.D. Department of Radiation Physics

Bulaksumur, Yogyakarta 55281, Indonesia. Indonesia.

Single Photon Emission Tomography Approach for Online Patient Dose Assessment in Boron Neutron Capture Therapy

University of Wollongong. Research Online

Feasibility study to develop BNCT facility at the Indonesian research reactor

Design of Moderator Neutron for Boron Neutron Capture Therapy in Kartini Nuclear Reactor Using Monte Carlo N Particle 5 Simulation

Application of the Multi-Model Monte-Carlo Treatment Planning System Combined with PHITS to Proton Radiotherapy

Neutron sources from Nuclear Reactors

Development of LINAC-Based Neutron Source for Boron Neutron Capture Therapy in University of Tsukuba )

IPPE Iron shell transmission experiment with 14 MeV neutron source and its analysis by the Monte-Carlo method

Title. Author(s)Ishikawa, Masayori; Tanaka, Kenichi; Endo, Satrou; H. CitationJournal of Radiation Research, 56(2): Issue Date

Epithermal neutron beams from the 7 Li(p,n) reaction near the threshold for neutron capture therapy

RDHA710FR10A1NK. Neutron and Total Ionizing Dose Test Report. October 2009

Option D: Medicinal Chemistry

Radiation Protection in BNCT Patients

On Optimizing the 7Li(p,n) Proton Beam Energy and Moderator Materid for BNCT

Introduction. Measurement of Secondary Radiation for Electron and Proton Accelerators. Introduction - Photons. Introduction - Neutrons.

PhD értekezés tézisei PHASE I CLINICAL STUDY ON BORON NEUTRON CAPTURE THERAPY. Dr Katalin Hideghéty. A Doktori Iskola vezetıje Prof. Dr.

Indonesian Journal of Physics and Nuclear Applications Volume 2, Number 2, June 2017, p ISSN X, FSM UKSW Publication

The ARN Critical Dosimetry System. Gregori, B.N.; Papadópulos, S.; Cruzate, J.A.; Equillor, H.E. and Kunst, J.J.

Thin Beryllium target for 9 Be(d,n)- driven BNCT

Strategy for Sustainable Utilization of IRT-Sofia Research Reactor

Today, I will present the second of the two lectures on neutron interactions.

The physics of boron neutron capture therapy: an emerging and innovative treatment for glioblastoma and melanoma

SOME RECENT DEVELOPMENTS IN TREATMENTPLANNING SOFTWARE A N D METHODOLOGY FOR BNCT

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

A D-D/D-T Fusion Reaction Based Neutron Generator System for Liver Tumor BNCT

EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH. Proposal to the ISOLDE and Neutron Time-of-Flight Committee

7. Radioisotopes in Medicine

AUTHOR QUERIES - TO BE ANSWERED BY THE CORRESPONDING AUTHOR

Future Utilization of the Research Reactor IRT in Sofia after its Reconstruction

VIII. RESEARCH ACTIVITIES

FINAL TECHNICAL REPORT MICRODOSIMETRY FOR BORON NEUTRON CAPTURE THERAPY DE - FG02-96ER62217

Development of a Thermal Neutron Source based on a Medical Electron Linac

Accelerator Based Epithermal Neutron Source by using Thin Layered Solid Lithium Target

GDR in Radiotherapy Treatment Fields with 18 MV Accelerators

Comparison between proton boron fusion therapy (PBFT) and boron neutron capture therapy (BNCT): a Monte Carlo study

The Albedo Dosimeter for Personnel Monitoring in Fast-Neutron Radiation Fields

Distribution of Water Phantom BNCT Kartini Research Reactor Based Using PHITS

EPITHERMAL NEUTRON BEAM GENERATOR DESIGN FOR BNCT

Real Time Spectrometer for thermal neutrons from Radiotherapic Accelerators

Non-target dose from radiotherapy: Magnitude, Evaluation, and Impact. Stephen F. Kry, Ph.D., D.ABR.

Chapter Introduction

BORON NEUTRON CAPTURE THERAPY SETUP FOR A LINEAR ACCELERATOR

Medical Physics 4 I3 Radiation in Medicine

Treatment planning system and patient positioning for boron neutron capture therapy

Application of MCNP4C Monte Carlo code in radiation dosimetry in heterogeneous phantom

The Therapeutic Ratio in BNCT: Assessment using the Rat 9L Gliosarcoma Brain Tumor and Spinal Cord Models

Neutron Induced Radiation Damage in BaF 2, LYSO and PWO Scintillation Crystals

V. 4. Design and Benchmark Experiment for Cyclotron-based Neutron Source for BNCT

The title of the presentation is: Neutron production with clinical LINACs for BNCT studies in physical, medical and biological fields.

Radiation Protection Dosimetry (2007), Vol. 126, No. 1 4, pp Advance Access publication 21 May 2007

MODELLING A GAMMA IRRADIATION PROCESS USING THE MONTE CARLO METHOD

SOLUTIONS FOR CLINICAL IMPLEMENTATION OF BORON NEUTRON CAPTURE THERAPY IN FINLAND

Application of Neutron Capture Therapy to Widespread Tumours

Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010

LA-UR- Title: Author(s): Submitted to: Approved for public release; distribution is unlimited.

Neutron Radiotherapy: Past, Present, and Future Directions

Binary therapies in the treatment of cancer

Determination of Iodine in Biological Materials using Instrumental Neutron Activation and Anti-coincidence Gamma-ray Spectrometry

Dose distribution and dosimetry parameters calculation of MED3633 palladium-103 source in water phantom using MCNP

8/3/2016. The EPID Strikes Back! - EPID In-Vivo Dosimetry. EPID Research Number of Publications. Why EPID in-vivo? Detectable errors: patient

SUMITOMO Particle Therapy Technologies

Calibration of Radiation Instruments Used in Radiation Protection and Radiotherapy in Malaysia

CALIBRATION OF A TLD ALBEDO INDIVIDUAL NEUTRON MONITOR

Mathematical Optimization Methodology for Neutron Filters

Implantable MOSFET dosimeter response to 192 Ir HDR radiation

Calculation of Dose Distribution Around a Clinical 252. Cf Source for Neutron Therapy Based on AAPM, TG-43 Protocol

JRPR. Quenching Effect in an Optical Fiber Type Small Size Dosimeter Irradiated with 290 MeV u -1 Carbon Ions. Original Research.

PET Guidance of Therapy for BNCT and in vivo B-10 imaging

Dosimetric characteristics of 137 Cs sources used in after loading Selectron system by Monte Carlo method

Dosimetry comparison of orthovoltage x-ray and 137 Cs irradiation of the murine bone marrow compartment Matthew Belley

CALCULATION OF BACKSCATTER FACTORS FOR LOW ENERGY X-RAYS USING THE TOPAS MONTE CARLO CODE

Development of Electron Beam and X Ray Applications for Food Irradiation

Measurement of Dose to Implanted Cardiac Devices in Radiotherapy Patients

Characterization and implementation of Pencil Beam Scanning proton therapy techniques: from spot scanning to continuous scanning

Department of Electrical & Computer Engineering, The Ohio State University, 205 Dreese Lab, 2015

IAEA-TECDOC Current status of neutron capture therapy

PREDICTION OF ABSORBED DOSE DISTRIBUTIONS AND NEUTRON DOSE EQUIVALENT VALUES IN PROTON BEAM RADIATION THERAPY

Transcription:

Design and Performance Of A Thermal Neutron Beam for Boron Neutron Capture Therapy At The University Of Missouri Research Reactor J.D. Brockman J.C. McKibben

In situ activation reaction, 10 B(n, a) 7 Li; releases ionizing energy within volume of single cancer cell: Targets of traditional and current interest: High-grade Glioma Primary and Metastatic Melanoma Neutron 5 mm 10 mm 7Li(+3) (0.85 MeV) 10 B Gamma (0.48 MeV) Current FDA approved boron delivery agents: BSH: Sodium Borocaptate BPA: Boronophenylalanine GB-10: Na 2 B 10 H 10 Head and Neck Tumors Metastatic Liver Tumors a (+2) (1.49 MeV)

Thermal neutron beam Au cadmium ratio >100 Th flux ~1X10 9 n/cm 2 /s Minimize gamma dose Irradiation facility accessible during reactor operation Irradiate small animals up to large dogs

Key Design Feature: Single Crystal Silicon and Single Crystal Bismuth Neutron Filters Silicon Bismuth

Silicon and Bismuth Total Cross Sections (Amorphous) Si (Natural) 209Bi 1 ev 1 ev Source: OECD-NEA (Janis)

Thermal Cross Sections for Silicon and Bismuth Source: Kim et al. Phys. Med. Bio (2007) Lee, Byung-Chul, 2007 KAERI, Private communication. Freund (1983)

KAERI Data for S.C. Si and Bi ENDF/B Nuclear Data ENDF/B Nuclear Data MCNP5 Monte Carlo Angular Neutron Flux at Silicon Filter Entrance Neutron Flux at Irradiation location COMBINE 7.1 (W.Yoon, INL) 59-Group ENDF/B VII Custom Library DORT 2D S n S. R. Slattery, D. W. Nigg, J. D. Brockman, M. F. Hawthrone, PHYSOR, May 9 2010, Pittsburg, Pa

59 group Source from DORT calculation

1e+10 1e+9 1e+8 Flux/lethargy 1e+7 1e+6 1e+5 Empty Beam Tube 50 cm Silicon Crystal 50 cm Si + 8 cm Bi 1e+4 1e-9 1e-8 1e-7 1e-6 1e-5 1e-4 1e-3 1e-2 1e-1 1e+0 1e+1 1e+2 Energy, MeV

1. Voided Beam 2. 50 cm Silicon crystal 3. 8 cm Bismuth Crystal 4. 50 cm Silicon + 8 cm Bismuth Crystal

Measured Thermal Flux (n/cm 2 -s) Calculated Thermal Flux DORT + MCNP5 (n/cm 2 -s) Cadmium Ratio Wire saturation activity ratio (Au/Cu) Voided Beamline 9.8 x 10 9 (11%) 9.4 x 10 9 (10%) 3.18 (7%) 8 cm Bi Crystal 3.4 x 10 9 (8%) 3.8 x 10 9 (10%) 5.10 (7%) 50 cm Si Crystal 2.6 x 10 9 (8%) 2.2 x 10 9 (10%) 65.3 (7%) 50 cm Si + 8 cm Bi 9.4 x 10 8 (8%) 9.6 x 10 8 (10%) 105.5 (7%) 36.4 28.4 22.4 22.4

Neutron Interaction 197 Au (n, γ) Bare Foil 55 Mn (n, γ) Bare Foil Thermal Thermal Energy Range of Primary Response 411 847 Activation Gamma Energy (kev) 115 In (n, γ) Cd Cover 1 ev Resonance 1293 2 6 Group spectrum 1 197 Au (n, γ) Cd Cover 5 ev Resonance 411 3 186 W (n, γ) Cd Cover 18 ev Resonance 686 4 55 Mn (n, γ) Cd Cover 340 ev Resonance 847 5 63 Cu (n, γ) Cd Cover 1 kev Resonance 511 (Positron) 5 115 In (n,n') Boron Sphere 300 kev Threshold 336 6

Flux/Lethargy 1.E+09 6 Group spectrum 2012 1.E+08 Bare Au, Mn 1.E+07 Cd W group 1 group 2 group 3 group 4 1.E+06 Cd In Cd Au Cd Cu, Mn B In group 5 group 6 A-Priori 1.E+05 1.E-04 1.E-02 1.E+00 1.E+02 1.E+04 1.E+06 1.E+08 Energy, ev Nigg, et al, Med Phys. 27 359-367

Measured Φ th 2012 = 7.65 x 10 8 n/cm2-s (±8.6%) Measured Φ th 2009 = 8.85 x 10 8 n/cm2-s (±8.3%) Measured Φ th 2008 = 8.18 x 10 8 n/cm2-s (±6.0%) Calculated Φ = 9.6 x 10 8 n/cm2-s (±5%) Cadmium Ratio (Au) = 108 Calculated D γ = 2.12 cgy/min Measured D γ = 3.4 cgy/min (paired ion chamber technique)

1e+8 1e+9 n/cm 2 /s 1e+7 1e+6 Group 6 n/cm 2 /s 1e+5 2008 2009 2012 0 1 2 3 4 5 6 Energy Group 1e+8

Cu/Au wires Mean Au activity: 9.73X10 14 dps/n ± 4% Mean Au/Cu ratio: 22.1 ± 1.7%

Profile flux wire Profile flux wire Phantom A Phantom B Start of Shielding Center, index wire Phantom D Phantom C

Au Activity Relative to center wire 180 Start of Li Carbonate neutron shielding Edge of animal holder 160 140 120 100 80 60 Inside Shielding Phantom inside beam Center of Beam Phantom A Phantom B 40 20 0-4.0-3.0-2.0-1.0 0.0 1.0 2.0 Distance in cm from top edge of black cap

Cu activity, relative to center wire 250 200 150 100 50 Phantom D Front Back Li Shielding Start Cap Start 0 0 2 4 6 8 Length, cm

Tumor Flank downstream thorax in beam thorax down stream Thermal Flux, n/cm^2/s 1.3X10 9 1.9X10 8 1.3X10 8 7.1EX10 7 Thermal Flux Relative to tumor 100% 14% 10% 5% Thorax upstream 6 Li shield Tumor Thorax Down Stream Flank Downstream

Neutron spectrum has not changed since 2008 Radial profile measurements Phantom measurements and animal experiments are underway Acknowledgements Dr. David Nigg INL Dr. Frederick Hawthorne IINMM MURR Staff Operations Health Physics Machine Shop Electrical Shop

[1] J. D. Brockman, D. W. Nigg, M. F. Hawthorne, M.W. Lee, J. C. McKibben, Characterization of a Boron Neutron Capture Therapy Beam Line at the University of Missouri Research Reactor J. Radioanal. Nucl. Ch. 282 157-160 [2] E.C.C. Pozzi, S. Thorp, J. D. Brockman, M. Miller, D. W. Nigg, F. M. Hawthorne, Intercalibration of Physical Neutron Dosimetry for the RA-3 and MURR Thermal Neutron Sources for BNCT Small-Animal Research Appl. Radiat. Isotopes. 69 1921-1923 [3] M. S. Kim, B. C. Lee, S. Y. Hwang, B. J. Jun, Development and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field Phys. Med. Biol. 52 2553-2566 [4] R. F. Barth, et. Al., Current status of boron neutron capture therapy of high grade gliomas and recurrent head and neck cancer Radiat. Oncol. 2012, 7 146-167 [5] J. D. Brockman, D. W. Nigg, M. F. Hawthorne, J. C. McKibben, Spectral performance of a composite single-crystal filtered thermal neutron beam for BNCT research at the University of Missouri Appl. Radiat. Isotopes. 67 S222-S225 [6] B. C. Lee, Korean Atomic Energy Research Institute, Private communication (2007) [7] A. K. Freund, Cross Sections of Materials used as Neutron Monochromators and Filters, Nucl. Instrum. & Methods, 243 495-501. [8] W. A. Rhoades et al., :Tort-Dort: Two and Three-Dimensional Discrete-Ordinates Transport, Radiation Shielding Information Center, Oak Ridge National Laboratory, USA 1980. [9] S. R. Slattery, D. W. Nigg, J. D. Brockman, M. F. Hawthrone, Improved computational characterization of the thermal neutron source for neutron capture therapy at the University of Missouri PHYSOR, May 9 2010, Pittsburg, Pa [10] D. W. Nigg et al., Modification of the University of Washington Neutron Radiotherapy Facility for Optimization of Neutron Capture Enhanced Fast Neutron Therapy Med. Phys. 27 359-367