Dissertationen: „Boron-neutron capture therapy“

1

Howard, William Bruce. „Accelerator-based boron neutron capture therapy“. Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/44479.

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2

Hefne, Jameel. „Neutron spectrum measurement for Boron Neutron Capture Therapy“. Diss., Georgia Institute of Technology, 1996. http://hdl.handle.net/1853/16625.

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3

Goorley, John Timothy 1974. „Boron neutron capture therapy treatment planning improvements“. Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/49670.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.
Includes bibliographical references.
The Boron Neutron Capture Therapy (BNCT) treatment planning process of the Harvard/MIT team used for their clinical Phase I trials is very time consuming. If BNCT proves to be a successful treatment, this process must be made more efficient. Since the Monte Carlo treatment planning calculations were the most time consuming aspect of the treatment planning process, requiring more than thirty six hours for scoping calculations of three to five beams and final calculations for two beams, it was targeted for improvement. Three approaches were used to reduce the calculation times. A statistical uncertainty analysis was performed on doses rates and showed that a fewer number of particles could not be used and still meet uncertainty requirements in the region of interest. Unused features were removed and assumptions specific to the Harvard/MIT BNCT treatment planning calculations were hard wired into MCNP by Los Alamos personnel, resulting in a thirty percent decrease in runtimes. MCNP was also installed in parallel on the treatment planning computers, allowing a factor of improvement by roughly the number of computers linked together in parallel. After theses enhancements were made, the final executable, MCNPBNCT, was tested by comparing its calculated dose rates against the previously used executable, MCNPNEHD. Since the dose rates in close agreement, MCNPBNCT was adopted. The final runtime improvement to a single beam scoping run by linking the two 200MHz Pentium Pro computers was to reduce the wall clock runtime from 2 hours thirty minutes to fifty nine minutes. It is anticipated that the addition of ten 900 MHz CPUs will further reduce this calculation to three minutes, giving the medical physicist or radiation oncologist the freedom to use an iterative approach to try different radiation beam orientations to optimize treatment. Additional aspects of the treatment planning process were improved. The previously unrecognized phenomenon of peak dose movement during irradiation and its potential for overdosing the subject was identified. A method of predicting its occurrence was developed to prevent this from occurring. The calculated dose rate was also used to create dose volume histograms and volume averaged doses. These data suggest an alternative method for categorizing the subjects, rather than by peak tissue dose.
by John Timothy Goorley.
S.M.

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4

Matalka, Khalid Zuhair. „Boron neutron capture therapy of brain tumors /“. The Ohio State University, 1992. http://rave.ohiolink.edu/etdc/view?acc_num=osu148778039326795.

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5

Guidi, Claretta. „Sviluppo e applicazioni della boron neutron capture therapy“. Bachelor's thesis, Alma Mater Studiorum - Università di Bologna, 2017. http://amslaurea.unibo.it/13399/.

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La Boron Neutron Capture Therapy è una tecnica terapeutica altamente selettiva, utilizzata in oncologia, che si basa sulla reazione di cattura neutronica 10B(n,α)7Li . Tale selettività è garantita dal maggior assorbimento di boro, tramite specifici veicolanti, da parte delle cellule tumorali rispetto alle cellule sane, che si mantengono inalterate. I prodotti della reazione di cattura sono particelle ad alto LET, quindi poco penetranti, e questo consente un rilascio energetico letale per i tessuti malati. L'obiettivo di questa tesi è fornire un quadro generale sulla Boron Neutron Capture Therapy, sottolineandone gli aspetti positivi e negativi. In particolare si illustrano, dopo un breve excursus storico, le principali caratteristiche fisiche e chimiche della terapia, quali la reazione di cattura neutronica da parte del boro, gli agenti di trasporto del boro e le sorgenti di neutroni. Si forniscono le principali informazioni riguardo al problema dosimetrico legato alla terapia e si analizzano le principali applicazioni cliniche in Italia e nel mondo, con particolare attenzione sul progetto TAOrMINA. Dal lavoro svolto si può concludere che la BNCT risulta efficace per la cura di molti tumori resistenti alle tradizionali terapie e fornisce una prospettiva positiva alla lotta contro le neoplasie. Tuttavia il raggiungimento della totale efficienza di questa tecnica appare ancora lontano a causa, principalmente, della mancanza di adeguate attrezzature nei centri ospedalieri e della necessità di migliorare ulteriormente la selettività e l'efficacia dei composti veicolanti del boro.

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6

Shah, Jungal (Jugal Kaushik). „Hypoxia-selective compounds for boron neutron capture therapy“. Thesis, Massachusetts Institute of Technology, 2008. http://hdl.handle.net/1721.1/44829.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2008.
"June 2008."
Includes bibliographical references.
Boron neutron capture therapy (BNCT) is a biochemically targeted form of radiotherapy for cancer. In BNCT, a compound labeled with the stable isotope boron-10 is systemically administered, and tumor cells selectively uptake the boron-10 containing compound at higher concentrations than normal cells. A general problem with the tumor seeking compounds is that drug delivery is dependent upon sufficient vascularization within the tumor. To investigate the possibility of delivering boron to hypoxic regions of tumor, a new boronated nitroimidazole delivery agent has been synthesized as a carrier of boron-10 for BNCT. It is expected that this will be used in combination with the existing boron carrier boronophenylalanine-fructose to treat solid tumors. An immunohistochemical protocol to visualize hypoxia was tested and refined to confirm the suitability of two tumor models established in the lab for hypoxia related uptake studies. The immunohistochemical protocol is used to detect pimonidazole, which localizes at hypoxic regions in tissue and is the parent compound for the new hypoxia-selective boron carrier. The protocol was used to test and confirm the suitability of a hypoxic in vivo tumor model. Two tumor lines were tested: SCCVII squamous cell carcinoma and EMT-6 murine mammary carcinoma. Both exhibited hypoxia. Finally, quantitative studies using Inductive Coupled Plasma Atomic Emission Spectrum demonstrated that the synthesized boronated nitroimidazole reaches suitable concentrations in SCCVII and F98 tumor. Future therapeutic studies are required to empirically confirm the effectiveness of this compound.
by Jugal Shah.
S.B.

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7

Wang, Zhonglu. „Design of a Boron Neutron Capture Enhanced Fast Neutron Therapy Assembly“. Diss., Georgia Institute of Technology, 2006. http://hdl.handle.net/1853/14100.

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A boron neutron capture enhanced fast neutron therapy assembly has been designed for the Fermilab Neutron Therapy Facility (NTF). This assembly uses a tungsten filter and collimator near the patient¡¯s head, with a graphite reflector surrounding the head to significantly increase the dose due to boron neutron capture reactions. The assembly was designed using Monte Carlo radiation transport code MCNP version 5 for a standard 20x20 cm2 treatment beam. The calculated boron dose enhancement at 5.7-cm depth in a water-filled head phantom in the assembly with a 5x5 cm2 collimation was 21.9% per 100-ppm B-10 for a 5.0-cm tungsten filter and 29.8% for an 8.5-cm tungsten filter. The corresponding dose rate for the 5.0-cm and 8.5-cm thick filters were 0.221 and 0.127 Gy/min, respectively. To validate the design calculations, a simplified BNCEFNT assembly was built using four lead bricks to form a 5x5 cm2 collimator. Five 1.0-cm thick 20x20 cm2 tungsten plates were used to obtain different filter thicknesses and graphite bricks/blocks were used to form a reflector. Measurements of the dose enhancement of the simplified assembly in a water-filled head phantom were performed using a pair of tissue-equivalent ion chambers. One of the ion chambers is loaded with 1000-ppm natural boron (184-ppm 10B) to measure dose due to boron neutron capture. The measured dose enhancement at 5.0-cm depth in the head phantom for the 5.0-cm thick tungsten filter is (16.6 ¡À 1.8)%, which agrees well with the MCNP simulation of the simplified BNCEFNT assembly, (16.4¡À 0.5)%. The error in the calculated dose enhancement only considers the statistical uncertainties. The total dose rate measured at 5.0-cm depth using the non-borated ion chamber is (0.765 ¡À 0.076) Gy/MU, about 61% of the fast neutron standard dose rate (1.255Gy/MU) at 5.0-cm depth for the standard 10x10 cm2 treatment beam. The increased doses to other organs due to the use of the BNCEFNT assembly were calculated using MCNP5 and a MIRD phantom.

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8

Sweezy, Jeremy Ed. „Development of a boron neutron capture enhanced fast neutron therapy beam“. Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/17107.

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9

Kudchadker, Rajat. „Optimized accelerator based epithermal neutron beams for boron neutron capture therapy /“. free to MU campus, to others for purchase, 1996. http://wwwlib.umi.com/cr/mo/fullcit?p9821332.

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10

Chung, Yoonsun. „Radiobiological evaluation of new boron delivery agents for boron neutron capture therapy“. Thesis, Massachusetts Institute of Technology, 2008. http://hdl.handle.net/1721.1/44784.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2008.
Includes bibliographical references (p. 123-132).
This thesis evaluates the radiobiological effectiveness of three new boron compounds namely a boronated porphyrin (BOPP) and two liposome formulations for neutron capture therapy (BNCT). The methodology utilizes in vitro and in vivo comparisons that characterize compounds relative to boric acid and boronophenylalanine (BPA). In vitro evaluations utilized a colorimetric assay and 96-well plates to minimize the quantities of compound required for testing. The assay was optimized for the murine SCCVII, squamous cell carcinoma to determine the chemical toxicity and relative cellular uptake of a compound. BOPP was toxic at low concentrations and comparisons between the different compounds for thermal neutron irradiations were performed with approximately 5 [mu]g 10B/ml in the culture medium to allow radiation induced effects to govern the observed response. Using less than 300 [mu]g of compound and 250 kVp X-rays as control irradiations, a compound biological effectiveness (CBE) of 3.3 ± 0.7 was determined for BOPP that is comparable to the result for boric acid (3.5 ± 0.5) indicating a non-selective intracellular accumulation of 10B. BPA has a significantly higher CBE of 6.1 + 0.7. Boronated liposomes (MAC-16 and MAC+TAC) were evaluated with the EMT-6 murine mammary carcinoma. Biodistribution studies showed high 10B uptake in tumor (20-40 [mu]g 10B/g) 30 hours after a single i.v. injection (dose 6-20 [mu]g 10B per gram of body weight). Tumor control experiments were performed using thermal neutrons to study the efficacy of the boron delivered by liposomes and BPA. The MAC-16 produced a 16 % tumor control and BPA (dose 43 [mu]g 10B/gbw) 63 % for tumor boron concentrations of approximately 20 [mu]g 10B/g and the same neutron fluence.
(cont.) Liposome doses were limited by injection volume and so two injections were tried 2-hours apart that doubled the boron concentration in tumor compared to a single administration. This improved the therapeutic response to 67 % with less apparent skin damage than with BPA. Microscopic studies using fluorescent labeled liposomes revealed 10B was nonuniformly distributed and concentrated at the edge of the tumor. Based on these studies in the tumor cell lines chosen neither of the compounds appear superior to BPA.
by Yoonsun Chung.
Ph.D.

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11

GASPAR, PRISCILA de F. „Consideracoes sobre o estudo da BNCT (Terapia de captura neutronica por boro)“. reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10384.

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Made available in DSpace on 2014-10-09T12:38:03Z (GMT). No. of bitstreams: 0
Made available in DSpace on 2014-10-09T14:04:46Z (GMT). No. of bitstreams: 1 05585.pdf: 4329322 bytes, checksum: 1e4698a5a96c7426a7fe1f3b5bc39703 (MD5)
Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

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12

Bosko, Andrey. „General Electric PETtrace cyclotron as a neutron source for boron neutron capture therapy“. Diss., Texas A&M University, 2005. http://hdl.handle.net/1969.1/2606.

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This research investigates the use of a PETtrace cyclotron produced by General Electric (GE) as a neutron source for boron neutron capture therapy (BNCT). The GE PETtrace was chosen for this investigation because this type of cyclotron is popular among nuclear pharmacies and clinics in many countries; it is compact and reliable; it produces protons with energies high enough to produce neutrons with appropriate energy and fluence rate for BNCT and it does not require significant changes in design to provide neutrons. In particular, the standard PETtrace 18O target is considered. The cyclotron efficiency may be significantly increased if unused neutrons produced during radioisotopes production could be utilized for other medical modalities such as BNCT at the same time. The resulting dose from the radiation emitted from the target is evaluated using the Monte Carlo radiation transport code MCNP at several depths in a brain phantom for different scattering geometries. Four different moderating materials of various thicknesses were considered: light water, carbon, heavy water, and FluentalTM. The fluence rate tally was used to calculate photon and neutron dose, by applying fluence rate-to-dose conversion factors. Fifteen different geometries were considered and a 30-cm thick heavy water moderator was chosen as the most suitable for BNCT with the GE PETtrace cyclotron. According to the Brookhaven Medical Research Reactor (BMRR) protocol, the maximum dose to the normal brain is set to 12.5 RBEGy, which for the conditions of using a heavy water moderator, assuming a 60 ??A beam current, would be reached with a treatment time of 258 min. Results showed that using a PETtrace cyclotron in this configuration provides a therapeutic ratio of about 2.4 for depths up to 4 cm inside a brain phantom. Further increase of beam current proposed by GE should significantly improve the beam quality or the treatment time and allow treating tumors at greater depths.

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13

Ghani, Zamir. „The physics, dosimetry and microdosimetry of boron neutron capture therapy“. Thesis, University of Birmingham, 2013. http://etheses.bham.ac.uk//id/eprint/4000/.

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A validated experimental and numerical procedure is described detailing macroscopic and microscopic dose calculations forming the basis of a protocol for the pre-clinical biological characterisation of the University of Birmingham’s BNCT facility. Fundamental reference dosimetric measurements have been carried out at the University of Birmingham’s accelerator based NCT facility and the Massachusetts Institute of Technology (MIT) research reactor to characterise macroscopic and microscopic doses and derive correction factors for the irradiation of V79 cells incubated in boric acid and irradiated as monolayers. On and off-axis thermal neutron, fast neutron and photon doses have been measured and calculated with standard macroscopic dosimetry techniques (foils and ion chambers) from which normalised MCNPX calculations are used to derive perturbation factors and off-axis corrections for cell flask irradiations. Microdosimetric correction factors are calculated for the boron dose component using Monte Carlo methods to simulate lithium ion and alpha particle tracks in semi-stochastic geometries representative of cell monolayer irradiations, incubated in a medium with 50ppm boric acid. Further simulations of recoil protons from nitrogen capture reactions allow for the calculation of correction factors for the non-uniform distribution of the nitrogen dose at the cellular level.

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14

Phoenix, Ben. „Synergistic and dose rate effects in Boron Neutron Capture Therapy“. Thesis, University of Birmingham, 2013. http://etheses.bham.ac.uk//id/eprint/4084/.

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An investigation of the factors affecting the biological effectiveness of neutron beams suitable for Boron Neutron Capture Therapy (BNCT) has been carried out. The primary experimental work described in this thesis concerns the degree of interaction, if any, between biological damage caused by low LET radiation and that caused by high LET radiation. The second area investigated concerns the biological impact of delivering a BNCT irradiation at differing dose rates. In mixed photon alpha particle irradiations, no synergistic effect was observed above the response from the separate components. Maximum alpha particle doses delivered were 2.54 Gy. In mixed X-ray and alpha particle exposures, no synergy effect was seen with 2.54 Gy of alpha particles delivered to the cells. At the 3.18Gy alpha particle dose level significantly lower cell survival was observed than would be predicted from survival in single fields. Dose rate experiments were carried out in the Massachusetts Institute of Technology (MIT) Fission Converter neutron Beam (FCB). Cells loaded with boric acid were exposed at dose rates differing by a factor of approximately 15. A dose rate effect was observed at both of the irradiation depths used, although this was only clearly significant at 50 mm treatment depth.

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15

Kiger, Jingli Liu. „Radiobiology of normal rat lung in Boron Neutron Capture Therapy“. Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41286.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.
Includes bibliographical references.
Boron Neutron Capture Therapy (BNCT) is a binary cancer radiation therapy that utilizes biochemical tumor cell targeting and provides a mixed field of high and low Linear Energy Transfer (LET) radiation with differing biological effectiveness. This project investigated the radiobiology of normal rat lung in BNCT and measured the relative biological effectiveness factors for the lung. Rat thorax irradiations were carried out with x-rays and neutrons with or without the boron compound boronophenylalanine-fructose (BPA-F). Monte Carlo radiation transport simulations were used to design the rat lung neutron irradiations. Among the neutron beam facilities available for BNCT at the MIT Research Reactor, the thermal neutron beam facility was found to provide a suitable dose distribution for this project. A delimiter was designed and constructed for the rat lung irradiations as a lithiated-polyethylene plate of 1.5 cm thickness with an aperture tapered from 4 to 3 cm in width to expose the lung to the beam and shield adjacent radiosensitive organs. The simulation design was validated with in-phantom measurements using gold foil activation and the dual ion chamber technique. By using a two-field irradiation, a relatively uniform dose distribution could be delivered to the rat lung. The mean lung dose rate was 18.7 cGy/min for neutron beam only irradiation and 37.5 cGy/min with neutrons plus BPA and a blood boron concentration of 18 gg/g.
(cont.) The delimiter designed for rat lung irradiation, and another similar delimiter, along with the animal holding box, all designed in this project, also serve as the apparatus for other small animal irradiations and cell irradiations at the thermal neutron facility at the MIT Research Reactor. An open-flow whole-body plethysmography system with fully automated signal processing programs was developed to non-invasively measure rat breathing rates and lung functional damage after lung irradiation. Noise reduction was carried out against high frequencies beyond the range of rat breathing frequency and large amplitude spikes due to abnormal animal movement. The denoised breathing signals were analyzed using the Fast Fourier Transform with a circular moving block in combination with the bootstrap for noise suppression and to allow estimation of the statistical uncertainty (standard deviation) of frequency measurements. The major frequency of the mean frequency spectrum was determined as the breathing frequency. The mean control breathing rate was 176 ± 13 (7.4%) min' (mean ± SD), and breathing rates 20% (- 3 SD) above the control average were considered to be abnormally elevated. The mean standard deviation of all measurements (n = 4269) was 2.4%. The dose responses of different irradiation groups with breathing rate elevation as the biological endpoint were evaluated with probit analysis. Two response phases of breathing rate elevation were observed as the early response phase (<100 days) and the late response phase (>100 days). The ED50 values for x-rays, neutrons only, and neutrons plus BPA during the early response phase, and neutrons plus BPA during the late response phase, were 11.5 ± 0.4 Gy, 9.2 + 0.5 Gy, 8.7 ± 0.6 Gy and 6.7 ± 0.4 Gy, respectively.
(cont.) The radiobiological weighting factors for the neutron beam (neutrons and photons), thermal neutrons only, %°B dose component during the early response phase, and 10B dose component during the late response phase were 1.24 ± 0.08, 2.2 ± 0.4, 1.4 ± 0.2, and 2.3 + 0.3, respectively. The histological damage to the lung during the late phase was also quantified with a histological scoring system. A set of linear dose response curves with histological damage as the endpoint was constructed. The radiobiological weighting factors for the different dose components were also determined at a degree of lung histological damage corresponding to a median histological score between the baseline (similar to the control) and the maximum. The weighting factors measured, 1.22 ± 0.09 for the thermal neutron beam and 1.9 + 0.2 for the o1B dose component, are consistent with the corresponding weighting factors measured using functional damage. The knowledge gained in these radiobiological studies of the normal rat lung indicates that the lung complications experienced by two patients in the Harvard-MIT clinical trial of BNCT for brain tumors do not appear to be related to the BNCT irradiations. This project is also helpful for evaluating the feasibility of BNCT for lung cancer.
by Jingli Liu Kiger.
Ph.D.

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16

Pitto-Barry, Anaïs. „Polymers and boron neutron capture therapy(BNCT): a potent combination“. Royal Society of Chemistry, 2021. http://hdl.handle.net/10454/18415.

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Yes
Boron neutron capture therapy (BNCT) has a long history of unfulfilled promises for the treatment of aggressive cancers. In the last two decades, chemists, physicists, and clinical scientists have been coordinating their efforts to overcome practical and scientific challenges needed to unlock its full therapeutic potential. From a chemistry point of view, the two current small-molecule drugs used in the clinic were developed in the 1950s, however, they both lack some of the essential requirements for making BNCT a successful therapeutic modality. Novel strategies are currently used to design new drugs, more selective towards cancer cells and tumours, as well as able to deliver high boron contents to the target. In this context, macromolecules, including polymers, are promising tools to make BNCT an effective, accepted, and front-line therapy against cancer. In this review, we will provide a brief overview of BNCT, and its potential and challenges, and we will discuss the most promising strategies that have been developed so far.

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17

Ceberg, Crister. „Pharmacokinetics and biodistribution of boron compounds foundations for boron neutron capture theory /“. Lund : Dept. of Radiation Physics, Lund University, 1994. http://books.google.com/books?id=wnhrAAAAMAAJ.

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18

Mitchell, Hannah Elizabeth. „An accelerator-based epithermal photoneutron source for boron neutron capture therapy“. Diss., Georgia Institute of Technology, 1996. http://hdl.handle.net/1853/16345.

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19

Frixa, Christophe. „Boronated tetraphenylporphyrins for use in boron neutron capture therapy of cancer“. Thesis, University of Bath, 2002. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.268747.

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20

Kortesniemi, Mika. „Solutions for clinical implementation of boron neutron capture therapy in Finland“. Helsinki : University of Helsinki, 2002. http://ethesis.helsinki.fi/julkaisut/mat/fysik/vk/kortesniemi/.

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21

Dobelbower, Michael Christian. „An integrated design of an accelerator-based neutron source for boron neutron capture therapy /“. The Ohio State University, 1997. http://rave.ohiolink.edu/etdc/view?acc_num=osu148794815862645.

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22

Brown, Adam Vernon. „Development of a high-power neutron producing [lithium] target for boron neutron capture therapy“. Thesis, University of Birmingham, 2000. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.761253.

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23

Basak, Prakitri. „Synthesis of conjugates of L-fucose and ortho-carborane as potential agents for boron neutron capture therapy and synthesis of 2,3-dideoxy-2,3-methanoribofuranoside glycosyl donors and a study of their use in stereocontrolled glycosylation reactions“. Columbus, OH : Ohio State University, 2003. http://rave.ohiolink.edu/etdc/view?acc%5Fnum=osu1041010809.

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Thesis (Ph. D.)--Ohio State University, 2003.
Title from first page of PDF file. Document formatted into pages; contains xiii, 279 p.: ill. (some col.). Includes abstract and vita. Advisor: Todd L. Lowary, Dept. of Chemistry. Includes bibliographical references (p. 150-154).

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24

Ishikawa, Masayori. „Development of New Absorbed Dose Estimation System for Boron Neutron Capture Therapy“. Kyoto University, 2002. http://hdl.handle.net/2433/149649.

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25

Ledesma, Michelle N. (Michelle Nicole) 1975. „Medical room design for a fission converter-based boron neutron capture therapy facility“. Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/50533.

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26

Qu, Tanxia. „A Monte Carlo design study of an accelerator epithermal neutron irradiation facility for boron neutron capture therapy /“. The Ohio State University, 1993. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487844105974799.

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27

Schmitz, Tobias [Verfasser]. „ESR-dosimetry in thermal and epithermal neutron fields for application in Boron Neutron Capture Therapy / Tobias Schmitz“. Mainz : Universitätsbibliothek Mainz, 2016. http://d-nb.info/1112150870/34.

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28

Todd, Jean Ann. „Platinum(II) complexes containing 1,2- and 1,7-carborane ligands for boron neutron capture therapy“. Title page, contents and abstract only, 2001. http://web4.library.adelaide.edu.au/theses/09PH/09pht634.pdf.

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29

Alfuraih, Abdulrahman. „Exploring the use of high energy medical linear accelerator in boron neutron capture therapy“. Thesis, University of Surrey, 2009. http://epubs.surrey.ac.uk/843807/.

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Boron Neutron Capture Therapy (BNCT) is based on the nuclear reaction that occurs when 10B loaded tissue is irradiated with thermal neutron yielding high linear energy transfer alpha particles and recoiling 7Li nuclei. Neutron sources for BNCT are currently limited to research nuclear reactors. However most reactors are not in close proximity to hospitals and their use for clinical trials can be difficult. High energy photon beams from medical Linear accelerators produce undesirable neutrons, beside the clinically useful electron and photon beams, neutrons are produced from the photonuclear reaction of high energy photons with high Z-materials making the accelerator head. Such neutrons have been studied extensively, both in measurements and Monte Carlo calculations mainly from the point of radiation protection. In this work the neutron component from high energy medical linear accelerator, dose, and fluence had been studied for the purpose of shielding patient, staff and the general public from the contaminant neutrons. In this work one major finding is the increase of neutron yield from the medical linac head when jaws are open compared when jaws are closed. Making use of already installed high energy linacs in hospitals used primarily for high energy electron and photon (bremsstrahlung) therapy for neutron production for use in BNCT will be advantageous in the sense that their use is much more acceptable to the public than the use of reactors. It will also mean fewer complications with respect to patient movement and management and will be cost effective. To consider the feasibility of this Monte Carlo simulation of a voxalized head phantom have been undertaken, comparing a reactor source to a medical linac source and comparing different moderator modalities.

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30

Liu, Liang. „Development and Evaluation of Boron Targeting Agents For Neutron Capture Therapy of Brain Tumors /“. The Ohio State University, 1996. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487932351057135.

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31

Woollard, Jeffrey E. „Optimization of a moderator assembly for use in an accelerator-based neutron source for boron neutron capture therapy /“. The Ohio State University, 1997. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487945744571817.

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32

Klee, Kathleen A. „Optimization of an Epi-thermal neutron beam and beam dosimetry for boron neutron capture therapy at the Georgia Tech Research Reactor“. Diss., Georgia Institute of Technology, 1994. http://hdl.handle.net/1853/16405.

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33

Olusanya, Temidayo Olajumoke Bolanle. „Formulation and preliminary evaluation of delivery vehicles for the boron neutron capture therapy of cancer“. Thesis, University of Portsmouth, 2015. https://researchportal.port.ac.uk/portal/en/theses/formulation-and-preliminary-evaluation-of-delivery-vehicles-for-the-boron-neutron-capture-therapy-of-cancer(595b381c-50cc-4a49-9c20-4850a01a43f1).html.

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Boron neutron capture therapy (BNCT) is a method for selectively destroying malignant (normally glioma) cells whilst sparing normal tissue. Irradiation of 10B (large neutron capture cross-section) with thermal neutrons effects the nuclear fission reaction: 10B + 1n → → 7Li+ + α + γ; where the penetration of -particles and 7Li+ is only 8 and 5 μm, respectively, i.e., within a single cell thickness, assuming 10B can be preferentially located within glioma cells. Poor selectivity is the main reason why BNCT has not become a mainstream cancer therapy. Carboranes. a third generation of high boron-containing, low-toxicity, BNCT compounds, are currently being investigated. Towards the aim of increasing malignant cell targeting specificity, this thesis investigates monodispersed dipalmitoylphosphatidylcholine (DPPC) and 1,2-distearoyl-sn-glycero-3-phosphocholine (DSPC) SUV liposome formulations containing carboranes derivatised with delocalised lipophilic cations (DLCs), specifically the dequalinium bis nido carborane salt. AFM studies showed the loaded liposomes appeared stable (63 days, 4°C, if re-probing was employed). The integrity of the liposome membrane in serum, as reflected by %latency and %retention experiments using a fluorescent marker (calcein), was found to be high for both types of liposomes prepared using cholesterol. Successful entrapment of carboranes was demonstrated by the Nile Red method and by ICP-MS measurements. The liposomes were of sufficient size (80-100 nm) to pass through the blood brain barrier (BBB). The cationic moiety of the carborane salt allowed selective targeting of glioma mitochondria, thought to be due to differences in mitochondrial membrane potentials between malignant and non-neoplastic cells. Specific targeting of IN699 (glioma, WHO grade IV) and SC1800 (non-neoplastic astrocyte) cells with the carborane salt was evidenced by live cell (fluorescence) imaging. Spray drying was used as an alternative method of formulating agents for BNCT treatments for liver and lung cancers, where the larger (micrometre-diameter) particles do not need to pass across the BBB. Polyvinylpyrrolidone / o-carborane co-spray-dried microparticles were produced. 1H NMR studies revealed the high temperatures (180 °C) of the spray drying process did not degrade the PVP. Mean particle diameters (x90) were in the 2 – 10 μm range, with finer fractions being present (x10 ≅ 1 – 2 μm), and were therefore considered suitable for delivery to the lungs. SEM imaging showed the particles to be spherical, with dimples and cavities caused by the spray drier nozzle characteristics, as typical with the spray drying process. Some small irregularly-shaped crystalline particles, thought to be o-carborane, were observed by SEM, although the proportion accounted for less that than in the formulation (10 %w/w). An attempt was made to map the boron content in spray-dried powders on a surface using EDS, although the low atomic weight of boron made detection not possible. Cytotoxicity studies, using human glioblastoma U-87 MG (cancerous) and human fetal lung fibroblast MRC-5 (non-neoplastic) cells, revealed the PVP / o-carborane co-spray-dried particles to be non-toxic.

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Calabrese, Gianpiero. „Design, synthesis and preliminary in vitro evaluation of potential agents for Boron Neutron Capture Therapy“. Thesis, University of Portsmouth, 2007. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.478899.

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35

Gao, Wei Ph D. „Lithium-6 filter for a fission converter-based Boron Neutron Capture Therapy irradiation facility beam“. Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/34653.

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Includes bibliographical references (p. 164-165).
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.
(cont.) A storage system was designed to contain the lithium-6 filter safely when it is not in use. A mixed field dosimetry method was used to measure the photon, thermal neutron and fast neutron dose. The measured advantage depth is 9.3 ± 0.1cm without filter and 9.9 ± 0.1cm with 8mm lithium-6 filter. The result is consistent with the result of Monte Carlo calculation.
The design of a lithium-6 filter to be used in Boron Neutron Capture Therapy was developed. The lithium-6 filter increases the average energy of the epithermal neutrons in the epithermal neutron beam. This filter allows the beam to be used for effective BNCT treatment at greater depth in tissue. Based on Monte Carlo calculations, 8mm thick lithium-6 filter was found to be the optimum filter thickness for the MIT fission converter based epithermal neutron beam (FCB). The highly reactive lithium metal filter is sealed with aluminum covers against the humidity and surrounding air. A well shielded and convenient frame was also designed to hold the lithium-6 filter. The frame is separated into two parts. The fixed part of the frame will be mounted into the patient collimator of the FCB and provides a slot for the lithium-6 filter. The filter itself will be connected to the movable part of the frame and slid in and out of the beam through a pair of roller bearing tracks like a vertical drawer. Both parts of the frame are built with borated polyethylene (RICORAD) and steel to insure good shielding. Many safety issues have been considered in the design including tritium production, nuclear heating, pressure from released gases and radiation leakage on the side of the collimator.
by Wei Gao.
S.M.

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Ko, Naonori. „Establishment of quality assurance and quality control measures for Boron Neutron Capture Therapy using microdosimetry“. Kyoto University, 2020. http://hdl.handle.net/2433/253277.

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37

Suzuki, Minoru. „The effects of boron neutron capture therapy on liver tumors and normal hepatocytes in mice“. Kyoto University, 2001. http://hdl.handle.net/2433/150526.

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38

Luguya, Raymond Joseph. „Syntheses of novel porphyrin, chlorin, and corrole macrocycles for application in boron neutron capture therapy and photodynamic therapy /“. For electronic version search Digital dissertations database. Restricted to UC campuses. Access is free to UC campus dissertations, 2004. http://uclibs.org/PID/11984.

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Thesis (Ph. D.)--University of California, Davis, 2005.
Degree granted in Chemistry. Dissertation completed in 2004; degree granted in 2005. Also available via the World Wide Web. (Restricted to UC campuses).

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Byun, Youngjoo. „Thymidine kinase as a molecular target for the development of novel anticancer and antibiotic agents“. Columbus, Ohio : Ohio State University, 2006. http://rave.ohiolink.edu/etdc/view?acc%5Fnum=osu1149008350.

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40

Gupta, Nilendu. „Fabrication and preliminary testing of a moderator assembly for an accelerator-based neutron source for boron neutron capture therapy /“. The Ohio State University, 1995. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487867541731792.

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41

Rogus, Ronald D. (Ronald Daniel). „Design and dosimetry of epithermal neutron beams for clinical trials of boron neutron capture therapy at the MITR-II reactor“. Thesis, Massachusetts Institute of Technology, 1994. http://hdl.handle.net/1721.1/12280.

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42

Wang, Chang-Kwang Chris. „A pilot study of an epithermal neutron source based on a low-energy proton accelerator for boron neutron capture therapy /“. The Ohio State University, 1989. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487672631600438.

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43

White, Susan Marie 1973. „Beam characterization for accelerator-based boron neutron capture therapy using the ⁹Be(d,n) nuclear reaction“. Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/50491.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.
Includes bibliographical references (leaves 62-65).
Use of the ⁹Be(d,n) nuclear reaction for accelerator-based boron neutron capture therapies (AB-BNCT) was investigated. The moderated neutron spectra produced at several deuteron bombarding energies were evaluated in terms of dose rates and dosimetric profiles in a water-filled brain phantom using an existing heavy water moderator and lead reflector assembly. Dosimetry results were obtained using the dual ionization chamber technique coupled with bare and cadmium-covered gold foils. Data have been taken with deuteron beams of 1.3 MeV to 1.8 MeV. As deuteron energy was increased, the tumor dose rate correspondingly improved due to the neutron yield increase. However, the data suggest that the advantage depth decreased, and the ratio of the fast neutron dose rate to the thermal neutron dose rate at a depth of I cm increased, although error bars are significant. All deuteron energies investigated produced a beam that, once moderated, appears viable for AB-BNCT. No conclusion was drawn about the best energy in terms of a high tumor dose rate, a significant advantage depth, and a low fast to thermal neutron dose rate ratio. Treatment times assuming 20 Gy to a tumor located 4 cm deep using a 4 mA accelerator ranged from 18 - 59 minutes, assuming a tumor boron concentration of 40 ppm and RBE values of 1.0 for photons, 3.2 for neutrons, and 3.8 for boron in tumor tissue. The average advantage depth was 6.4 ± 0.7 cm, so these moderated beams could be used to treat tumors near the brain centerline. The ⁹Be(d,n) nuclear reaction is exothermic, and is accessible to inexpensive, small particle accelerators.
by Susan Marie White.
S.M.

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Ryynänen, Päivi. „Kinetic mathematical modesl for the 111In-labelled bleomycin complex and 10B in boron neutron capture therapy“. Helsinki : University of Helsinki, 2002. http://ethesis.helsinki.fi/julkaisut/mat/fysik/vk/ryynanen/.

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45

Niemkiewicz, John. „A study on the use of removal-diffusion theory to calculate neutron distributions for dose determination in boron neutron capture therapy /“. The Ohio State University, 1996. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487934589976468.

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46

MAGNI, CHIARA. „Experimental and computational studies for an Accelerator-Based Boron Neutron Capture Therapy clinical facility: a multidisciplinary approach“. Doctoral thesis, Università degli studi di Pavia, 2022. http://hdl.handle.net/11571/1447823.

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The work described in this thesis has been carried out in the field of AB-BNCT, Accelerator-Based Boron Neutron Capture Therapy. BNCT is a binary radiotherapy combining the enrichment of tumour with boron-10 and its subsequent irradiation with low energy neutrons, exploiting the high cross section of neutron capture in boron-10. With a selective accumulation of boron-10 in the tumour by a suitable borated drug, the products of the reaction release a therapeutic dose in the tumour while sparing the surrounding healthy tissues. This biological selectivity makes BNCT a promising therapy for the treatment of diffuse, infiltrated or metastatic tumors. Recently, the possibility to obtain suitable neutron beams from accelerators has opened a new frontier: AB-BNCT could now become accessible in many hospitals, with improvements in quality of life and clinical outcome for several patients. The context of this work is the design of a clinical BNCT facility based on a Radio Frequency Quadrupole proton accelerator, manufactured by the Italian National Institute of Nuclear Physics (INFN). Such machine can provide a neutron beam suitable for the treatment of deep-seated tumors when coupled to a beryllium target and a Beam Shaping Assembly whose main constituent is solid lithiated aluminum fluoride. Alliflu, densified lithiated aluminum fluoride, is a new material created on purpose at the University and INFN of Pavia through an innovative sintering process on powders of lithium and aluminum fluoride. The work here presented aimed to cover different aspects from the installation of the facility to its clinical applications, and is characterized by a multidisciplinary approach: it includes studies in the field of material science and engineering for the production and analysis of the new material, computational and experimental nuclear physics for the validation of its moderation properties, radiation protection evaluations for the design of an optimized treatment room, and finally a medical physics application consisting in the treatment planning of a realistic clinical case. This work presents a contribution to the implementation of a AB-BNCT facility, demonstrating that R&D has great potential to optimize BNCT quality and to promote a new era of clinical applications.

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MANGUEIRA, THYAGO F. „Avaliacao dosimetrica da solucao fricke gel usando a tecnica de espectrofotometria para aplicacao na dosimetria de eletrons e neutrons“. reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9447.

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Made available in DSpace on 2014-10-09T12:26:53Z (GMT). No. of bitstreams: 0
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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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Roux, Lionel. „Conception et synthèse d'inhibiteurs de l'Aminopeptidase membranaire N ([EC. 3.4.11.2], APN ou CD13)“. Thesis, Mulhouse, 2010. http://www.theses.fr/2010MULH4691/document.

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La lutte contre le cancer est l'un des défis majeurs du XXème siècle. Pour que les tumeurs puissent se développer dans l'organisme, elles ont besoin d'un apport en nutriment par le biais de vaisseaux sanguins pour se faire, elles vont avoir recours au processus angiogénique. Lors de ce processus, les cellules endothéliales qui tapissent la paroi des vaisseaux sanguins vont se multiplier et créer de nouveaux vaisseaux sanguins qui vont permettre la vascularisation des tumeurs. L'angiogenèse constitue donc aujourd'hui un axe de recherche pour la lutte contre la progression tumorale et donc contre le cancer. Lors de ce développement tumoral, une enzyme, l'aminopeptidase neutre APN est surexprimée sur les parois des cellules endothéliales. Différentes études ont été menées et montrent que l'inhibition de cette enzyme bloque la progression tumorale. Mon travail au sein de l'équipe du Pr Céline Tarnus consistait en la conception et la synthèse d'inhibiteurs de l'APN. Une relation structure activité de nos composés vis-à-vis de l'APN a tout d'abord été effectuée. Le développement de synthèse du composé le plus actif ont été faite, puis la synthèse d'inhibiteurs d'APN ayant pour objectif l'utilisation de la BNCT a été abordée
The fight against the cancer is one of the most important struggles of this century. For the development of the tumors inside the body, they need to receive nutriments by the blood vessels and they use the angiogenic process. During this process, the endothelial cells being shown on the wall of the blood vessel will multiply and design new blood vessel, which will allow the tumor's vascularisation. Today, the angiogenesis is an axis of research for the fight against the cancer. During the tumoral development, the aminopeptidase N (APN) is overexpressed on the wall of endothelial cells. Various studies have shown that the inhibition of this enzyme stops the tumoral progression. My work in the Pr. Céline Tarnus Team consists in the conception and the synthesis of APN's inhibitors. In a first time, a structure activity relationship has been realized. Syntheses of a subnamolar compound have been developed, and then the synthesis of APN's inhibitors with the use of BNCT has been got onto

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49

Sakamoto, Shuichi. „Sensitivity studies of the neutronic design of a fission converter-based ephithermal beam for boron neutron capture therapy“. Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/46089.

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50

Gibson, Christopher R. „Pharmacokinetics, metabolism, and dose optimization simulation studies of Sodium Borocaptate for Boron Neutron capture therapy of Malignant Gliomas /“. The Ohio State University, 2001. http://rave.ohiolink.edu/etdc/view?acc_num=osu148639916010674.

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