Download or read book A Shielding Design for an Accelerator based Neutron Source for Boron Neutron Capture Therapy written by Andrew E. Hawk and published by . This book was released on 2003 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book An Integrated Design of an Accelerator based Neutron Source for Boron Neutron Capture Therapy written by Michael Christian Dobelbower and published by . This book was released on 1997 with total page 438 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Shielding and Patient Organ Dose Study for an Accelerator Based BNCT Facility at LBNL written by and published by . This book was released on 1996 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: This study considers the radiation safety aspects of several designs discussed in a previous report of an accelerator-based source of neutrons, based on the [sup 7]Li(p, n) reaction, for a Boron Neutron Capture Therapy (BNCT) Facility at Lawrence Berkeley National Laboratory (LBNL). determines the optimal radiation shield thicknesses for the patient treatment room. Since this is an experimental facility no moderator or reflector is considered in the bulk wall shield design. This will allow the flexibility of using any postulated moderator/reflector design and assumes sufficient shielding even in the absence of a moderator/reflector. In addition the accelerator is assumed to be capable of producing 100 mA of 2.5 MeV proton beam current. The addition of 1% and 2% [sup 10]B (by weight) to the concrete is also investigated. The second part of this paper determines the radiation dose to the major organs of a patient during a treatment. Simulations use the MIRD 5 anthropomorphic phantom to calculate organ doses from a 20 mA proton beam assuming various envisioned moderator/reflector in place. Doses are tabulated by component and for a given uniform [sup 10]B loading in all organs. These are presented in for a BeO moderator and for an Al/AlF[sub 3] moderator. Dose estimates for different [sup 10]B loadings may be scaled.

Download or read book Frontiers in Neutron Capture Therapy written by M. Frederick Hawthorne and published by Springer. This book was released on 2013-11-11 with total page 1389 pages. Available in PDF, EPUB and Kindle. Book excerpt: Frontiers in Neutron Capture Therapy contains current research results originally presented at the Eighth International Symposium on Neutron Capture Therapy for Cancer in La Jolla, CA. This comprehensive collection of peer-reviewed manuscripts is showcased in two volumes covering all aspects of the development of this multidisciplinary approach to cancer therapy. Volume I of this work includes clinical results and current progress in treatment planning, neutron sources and dosimetry, while Volume II presents the synthesis, pharmacology and tissue-targeting design of boron compounds, including work on preclinical dosimetry and radiobiology. Intended for researchers and clinicians involved with or interested in new modes of cancer therapy, this volume will also serve as a useful guideline for scientists, students, and practitioners in the field.

Download or read book Shielding Design of the Treatment Room for an Accelerator Neutron Source for BNCT written by Jeffrey Frank Evans and published by . This book was released on 1994 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Design of an Intense Accelerator based Epithermal Neutron Beam Prototype for BNCT Using Near threshold Reactions written by Charles Leon Lee and published by . This book was released on 1998 with total page 219 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Neutron Beam Design Development and Performance for Neutron Capture Therapy written by Otto K. Harling and published by Springer Science & Business Media. This book was released on 2013-03-08 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt: For this Workshop, the organizers have attempted to invite experts from all known centers which are engaged in neutron beam development for neutron capture therapy. The Workshop was designed around a series of nineteen invited papers which dealt with neutron source design and development and beam characterization and performance. Emphasis was placed on epithermal beams because they offer clinical advantages and are more challenging to implement than thermal beams. Fission reactor sources were the basis for the majority of the papers; however three papers dealt with accelerator neutron sources. An additional three invited papers provided a summary of clinical results of Ncr therapy in Japan between 1968 and 1989 and overviews of clinical considerations for neutron capture therapy and of the status of tumor targeting chemical agents for Ncr. Five contributed poster papers dealing with NCT beam design and performance were also presented. A rapporteurs' paper was prepared after the Workshop to attempt to summarize the major aspects, issues, and conclusions which resulted from this Workshop. Many people contributed to both the smooth functioning of the Workshop and to the preparation of these proceedings. Special thanks are reserved for Ms. Dorothy K.

Download or read book Optimal Neutron Source Beam Shaping Assembly for Boron Neutron Capture Therapy written by and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: There were three objectives to this project: (1) The development of the 2-D Swan code for the optimization of the nuclear design of facilities for medical applications of radiation, radiation shields, blankets of accelerator-driven systems, fusion facilities, etc. (2) Identification of the maximum beam quality that can be obtained for Boron Neutron Capture Therapy (BNCT) from different reactor-, and accelerator-based neutron sources. The optimal beam-shaping assembly (BSA) design for each neutron source was also to e obtained. (3) Feasibility assessment of a new neutron source for NCT and other medical and industrial applications. This source consists of a state-of-the-art proton or deuteron accelerator driving and inherently safe, proliferation resistant, small subcritical fission assembly.

Download or read book Neutronics and Shielding Design of an Accelerator based Neutron Source for Neutron Activation Analysis written by Carl Alexander Willis and published by . This book was released on 2005 with total page 182 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: Neutronics and radiation shielding of an accelerator-based neutron source (ABNS) for a neutron activation analysis application were designed with the aid of the Monte Carlo particle transport simulation package MCNP. Neutrons are generated in the proposed ABNS via the 7Li (p,n) reaction with 2.5 MeV protons from an RFQ-RFI linac. The neutronics comprise a polyethylene moderator and carousel--to hold sample vials undergoing activation analysis--and a graphite neutron reflector. Shielding to protect personnel consists of a commercially- available neutron-absorbing borated plastic surrounded by ordinary concrete. MCNP models show dependence in activating certain test nuclides on the thickness of the graphite reflector; based on the models, a choice for reflector dimensions is suggested. MCNP was also used to establish the position of the sample carousel about the target for optimal uniformity in activation of certain test nuclides, and to model activation of the ABNS components themselves. Finally, MCNP simulations of neutron and gamma shielding are presented relating shielding thickness to dose rates to personnel. Results are discussed in the context of conforming to ICRP and federal regulations for radiological worker protection, accounting for potentially large differences in system duty cycle among various users.

Download or read book Examination of a Delimiter Design for an ABNS for BNCT written by Joshua Peter Sroka and published by . This book was released on 2005 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The purpose of this work has been to examine the design of a delimiter for an Accelerator Based Neutron Source (ABNS) for Boron Neutron Capture Therapy (BNCT). The purpose of the delimiter is to shape the neutron field within a patients head in order to spare healthy tissue while delivering radiation to tumor cells and to simultaneously provide some degree of shielding to the patients body in order to reduce whole body exposure during treatment. In this evaluation, three previously developed assessment tools for delimiter performance have been combined to provide a more complete picture of the function of the delimiter in performing its dual roles. The first assessment tools that was used was the objective function (F) which provides a score based on the competing goals of sparing normal tissue and delivering high dose to tumor cells. The goal of the delimiter design is to achieve the highest F-score within an acceptable treatment time. The second assessment tool that was used was the beam assessment parameters of tumor dose and treatment time, where the goal is to achieve the highest possible tumor dose within an acceptable treatment time. The third assessment tool that was used was the whole body absorbed dose to the red bone marrow which measures the degree of shielding that the delimiter provides to the whole body of the patient. Here the goal of the design was to limit the whole body absorbed dose to the red bone marrow to values below the non-stochastic annual dose limit for radiation workers. Two parameters of delimiter design have been examined. The first parameter is the diameter of the treatment port and the second parameter is the axial thickness of the delimiter. As a basis for comparison, an Idealized Neutron Source with a 1/E energy spectrum was evaluated. For the Idealized Neutron Source the best beam diameter, of those evaluated, was found to be 15cm. For the delimiter the best configuration, of those evaluated, turned out to be a 15cm treatment port with an axial thickness of 13cm.

Download or read book Optimization of a Moderator Assembly for Use in an Accelerator based Neutron Source for Boron Neutron Capture Therapy written by Jeffrey E. Woollard and published by . This book was released on 1997 with total page 754 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Design of an Accelerator based Epithermal Neutron Beam for Boron Neuton Capture Therapy written by Xiao-Lin Zhou and published by . This book was released on 1990 with total page 422 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Design of the Target Heat Removal System for an Accelerator based Neutron Source for Boron Capture Neutron Therapy written by Cristian G. Marciulescu and published by . This book was released on 2002 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Low Energy Accelerator based Neutron Sources for Neutron Capture Therapy written by Hsinshun (Terry) Wu and published by . This book was released on 1992 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Shielding Design of BNCT Treatment Room for D T Neutron Source written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fabrication and Preliminary Testing of a Moderator Assembly for an Accelerator based Neutron Source for Boron Neutron Capture Therapy written by Nilendu Gupta and published by . This book was released on 1995 with total page 410 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of a Heat Removal System for an Accelerator Based Neutron Source Used for Boron Neutron Capture Therapy written by Anders Fernström and published by . This book was released on 2004 with total page 94 pages. Available in PDF, EPUB and Kindle. Book excerpt: