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In this report we describe studies with N5-2OH, a carboranyl thymidine analog (CTA), which is a substrate for thymidine kinase 1 (TK1), using the F98 rat glioma model. In vivo BNCT studies have demonstrated that intracerebral (i.c.) osmotic pump infusion of N5-2OH yielded survival data equivalent to those obtained with i.v. administration of boronophenylalanine (BPA). The combination of N5-2OH and BPA resulted in a modest increase in MST of F98 glioma bearing rats compared to a statistically significant increase with the RG2 glioma model, as has been previously reported by us (Barth et al., 2008). This had lead us to synthesize a second generation of CTAs that have improved in vitro enzyme kinetics and in vivo tumor uptake (Agarwal et al., 2015).

In this work, we present experimental results of a novel prompt gamma-ray detector for proton beam range verification. The detection system features an actively shielded cerium-doped lanthanum(III) bromide scintillator, coupled to a digital data acquisition system. The acquisition was synchronized to the cyclotron radio frequency to separate the prompt gamma-ray signals from the later-arriving neutron-induced background. We designed the detector to provide a high energy resolution and an effective reduction of background events, enabling discrete proton-induced prompt gamma lines to be resolved. Measuring discrete prompt gamma lines has several benefits for range verification. As the discrete energies correspond to specific nuclear transitions, the magnitudes of the different gamma lines have unique correlations with the proton energy and can be directly related to nuclear reaction cross sections. The quantification of discrete gamma lines also enables elemental analysis of tissue in the beam path, providing a better prediction of prompt gamma-ray yields. We present the results of experiments in which a water phantom was irradiated with proton pencil-beams in a clinical proton therapy gantry. A slit collimator was used to collimate the prompt gamma-rays, and measurements were performed at 27 positions along the path of proton beams with ranges of 9, 16 and 23 g cm(-2) in water. The magnitudes of discrete gamma lines at 4.44, 5.2 and 6.13 MeV were quantified. The prompt gamma lines were found to be clearly resolved in dimensions of energy and time, and had a reproducible correlation with the proton depth-dose curve. We conclude that the measurement of discrete prompt gamma-rays for in vivo range verification of clinical proton beams is feasible, and plan to further study methods and detector designs for clinical use.

Research related to fabrication of novel lanthanide halide scintillators in large physical sizes, using time- and cost-efficient methods, has been an ongoing process. The principal emphasis is on fabrication to derive novel light-conserving morphologies that are required for room-temperature radioisotope identification and other demanding spectrographic and imaging applications. Our fabrication technique addresses each of the many serious limitations of current growth methods, allows rapid large-volume synthesis at a substantially reduced cost versus current techniques, and is equally effective for manufacturing other advanced inorganic and solid state semiconductor materials. Here we report on the growth of CeBr3 scintillator using hot wall evaporation. Under favorable deposition conditions, this material could be grown in polycrystalline form suitable for spectroscopic applications, or even in the microcolumnar form desirable for high spatial resolution gamma ray imaging. The work carried out so far shows that films produced using this approach are self-activated and possess all of the excellent properties of their melt-grown crystal counterparts. The scintillation properties discussed in this report are relative light yield, energy resolution, spectroscopic emission, light emission uniformity and detection of alphas using as-deposited CeBr3 specimen. This paper will further discuss fabrication technique and its advantages.

Colloidal semiconductor nanocrystals exhibit physical properties that are characteristic of intermediate size scales between molecular states and solid state materials, and are often called quantum dots. Solid state semiconductor materials have been used extensively as scintillation detectors for ionizing radiation. We describe the use of semiconductor quantum dot-organic polymer composites for use as scintillation detectors and report the use of quantum dot-polymer composite thin films for X-ray imaging.

Boron neutron capture therapy (BNCT) is based on the nuclear capture and fission reactions that occur when non-radioactive 10B is irradiated with low energy thermal neutrons to produce α-particles (10B[n,α]7Li). Carboranylporphyrins are a class of substituted porphyrins containing multiple carborane clusters. Three of these have been evaluated in the present study: 5,10,15,20-tetra-(4-nido-carboranyphenyl)tetrabenzoporphyrin (H2TBP), 5,10,15,20-tetra-(4-nido-carboranylphenyl)porphyrin (H2TCP) and 5,15-di-[3,5-(nido-carboranylmethyl)phenyl]-porphyrin (H2DCP). The goals of this study were two-fold. First, to determine the biodistribution of H2TBP, H2TCP and H2DCP following intracerebral (i.c.) administration by means of short term (30 min) convection enhanced delivery (CED) or sustained delivery over 24 h by osmotic pumps to F98 glioma bearing rats. Second, to determine the efficacy of H2TCP and H2TBP as boron delivery agents for BNCT in F98 glioma bearing rats. Tumor boron concentrations immediately after i.c. osmotic pump delivery were high (36–88 µg/g) and they remained so at 24 h (62–103 µg/g) The corresponding normal brain concentrations were low (0.8–5.2 µg/g) and the blood and liver concentrations were all undetectable. Based on these data, therapy studies were initiated at the Massachusetts Institute of Technology (MIT) Research Reactor (MITRR) with H2TCP and H2TBP 24 h after CED or osmotic pump delivery. Mean survival times (MST) of untreated and irradiated control rats were 23±3 and 27±3 d, respectively, while animals that received H2TCP or H2TBP, followed by BNCT, had a MST of 35±4 d and 44±10 d, respectively, which were better than those obtained following i.v. administration of boronophenylalanine (37±3 d). However, since the tumor boron concentrations of the carboranylporphyrins were 3–5X > i.v. BPA (~25 µg/g), we had expected that the MSTs would have been greater. Histopathologic examination of brains of BNCT treated rats revealed that there were large numbers of porphyrin-laden macrophages, as well as extracellular accumulations of porphyrins indicating that the seemingly high tumor boron concentrations did not represent the true tumor cellular uptake. Our data are the first to show that carboranyl porphyrins are effective delivery agents for BNCT of an experimental brain tumor. Based on these results, we now are in the process of evaluating carboranylporphyrins that could have enhanced cellular uptake following administration and improved therapeutic efficacy.

We have recently fabricated tellurium-doped zinc selenide (ZnSe:Te) in a robust optical ceramic form, in the first synthesis of this remarkable material from a precursor powder, using powder consolidation techniques. We utilized two techniques in particular - hot uniaxial and hot isostatic pressing - in order to achieve the desired physical and chemical properties, and we are continuing our efforts to refine processing methodologies and parameters to improve this material's physical characteristics and performance. ZnSe:Te promises major advances in radiation imaging and spectroscopy applications with its potentially higher brightness than current scintillators such as CsI:Tl and NaI:Tl, fast emission (~3 μs and ~40 μs), negligible afterglow ( 5.2 g/cm), and light emission in the visible range (610-650 nm). This paper will describe our fabrication methods and report our preliminary performance characterization results.

Gadolinium has the highest thermal neutron absorption cross section of any naturally occurring element, and emits conversion electrons as well as atomic X-rays in over 50% of its neutron captures, which makes it a useful dopant in scintillators for detecting thermal neutrons. Gadolinium isopropoxide was studied as a possible dopant for styrene-based plastic scintillators as a convenient and inexpensive method to produce high-efficiency thermal neutron detectors. Plastic scintillators with gadolinium weight concentrations of up to 3% were transparent, uniform and defect-free and were characterized with spectral measurements performed under x-ray and neutron irradiation. The new material has the same characteristic emission of styrene with a maximum at approximately 425 nm, and a light output of 76% relative to the undoped plastic. A 13 mm thick sample containing 0.5% gadolinium by weight detected 46% of incident thermal neutrons, which makes this an attractive material for a variety of applications.

In the present report we have summarized studies carried out over the past five years on molecular targeting of the epidermal growth factor receptor (EGFR) and its mutant isoform, EFGRvIII, for BNCT of genetically engineered F98 rat gliomas, expressing either wildtype (F98(EGFR)) or mutant receptors (F98(npEGFRvIII)). EGF or the monoclonal antibodies (mAbs), cetuximab (IMC-C225) and L8A4, which recognize wildtype EGFR and EGFRvIII, respectively, were heavily boronated using polyamidoamine (PAMAM) dendrimers (BD) linked to the targeting vehicles by means of heterobifunctional reagents. Boronated EGF or mAbs, alone or in combination with i.v. boronophenylalanine (BPA), were administered intracerebrally (i.c.) by either intratumoral (i.t.) injection or convection enhanced delivery (CED) to rats bearing F98 gliomas following which BNCT was initiated. The best survival data were obtained in rats bearing F98(npEGFRvIII) gliomas that had received CED of BD-L8A4 either alone or in combination with i.v. boronophenylalanine (BPA). Studies carried out in rats bearing composite tumors (F98(EGFR)/F98(npEGFRvIII)) demonstrated that it was essential to target both tumor cell populations in order to obtain an optimal therapeutic effect. Based on these observations, we have concluded that EGFR targeting vehicles are useful, but not stand-alone boron delivery agents due to the heterogeneity of receptor expression in brain tumors. They could, however, be quite useful in combination with the two drugs that currently are being used clinically, BPA and sodium borocaptate (BSH) for BNCT of either brain tumors or head and neck cancers.

The meaningful sharing and combining of clinical results from different centers in the world performing boronneutron capture therapy (BNCT) requires improved precision in dose specification between programs. To this end absorbed dose normalizations were performed for the European clinical centers at the Joint Research Centre of the European Commission, Petten (The Netherlands), Nuclear Research Institute, Rez (Czech Republic), VTT, Espoo (Finland), and Studsvik, Nykoping (Sweden). Each European group prepared a treatment plan calculation that was benchmarked against Massachusetts Institute of Technology (MIT) dosimetry performed in a large, water-filled phantom to uniformly evaluate dose specifications with an estimated precision of ± 2 % – 3 % . These normalizations were compared with those derived from an earlier exchange between Brookhaven National Laboratory (BNL) and MIT in the USA. Neglecting the uncertainties related to biological weighting factors, large variations between calculated and measured dose are apparent that depend upon the B 10 uptake in tissue. Assuming a boron concentration of 15 μ g g − 1 in normal tissue, differences in the evaluated maximum dose to brain for the same nominal specification of 10 Gy ( w ) at the different facilities range between 7.6 and 13.2 Gy ( w ) in the trials using boronophenylalanine (BPA) as the boron delivery compound and between 8.9 and 11.1 Gy ( w ) in the two boron sulfhydryl (BSH) studies. Most notably, the value for the same specified dose of 10 Gy ( w ) determined at the different participating centers using BPA is significantly higher than at BNL by 32% (MIT), 43% (VTT), 49% (JRC), and 74% (Studsvik). Conversion of dose specification is now possible between all active participants and should be incorporated into future multi-center patient analyses.

The purpose of the present study was to evaluate the effectiveness of a 3-carboranyl thymidine analogue (3CTA), 3-[5-{2-(2,3-dihydroxyprop-1-yl)- o -carboran-1-yl}pentan-1-yl] thymidine, designated N5–2OH, for boron neutron capture therapy (BNCT) of brain tumors using the RG2 rat glioma model. Target validation was established using the thymidine kinase (TK) 1(+) wild-type, murine L929 cell line and its TK1(−) mutant counterpart, which were implanted s.c. (s.c.) into nude mice. Two intratumoral (i.t.) injections of 10 B-enriched N5–2OH were administered to tumor-bearing mice at 2-hour intervals, after which BNCT was carried out at the Massachusetts Institute of Technology (MIT) Research Reactor. Thirty days after BNCT, mice bearing TK1(+) L929 tumors had a 15× reduction in tumor volume compared with TK1(−) controls. Based on these favorable results, BNCT studies were then initiated in rats bearing intracerebral (i.c.) RG2 gliomas, after i.c. administration of N5–2OH by Alzet osmotic pumps, either alone or in combination with i.v. (i.v.) boronophenylalanine (BPA), a drug that has been used clinically. The mean survival times (MSTs) of RG2 glioma bearing rats were 45.6 ± 7.2 days, 35.0 ± 3.3days, and 52.9 ± 8.9 days, respectively, for animals that received N5–2OH, BPA, or both. The differences between the survival plots of rats that received N5–2OH and BPA alone were highly significant ( P = 0.0003). These data provide proof-of-principle that a 3CTA can function as a boron delivery agent for NCT. Further studies are planned to design and synthesize 3CTAs with enhanced chemical and biological properties, and increased therapeutic efficacy.

A dosimetry intercomparison between the boron neutron capture therapy groups of the Massachusetts Institute of Technology (MIT) and the Comisión Nacional de Energía Atómica (CNEA), Argentina was performed to enable combined analyses of NCT patient data between the different centers. In-air and dose versus depth measurements in a rectangular water phantom were performed at the hyperthermal neutron beam facility of the RA-6 reactor, Bariloche. Calculated dose profiles from the CNEA treatment planning system NCTPlan that were calibrated against in-house measurements required normalizations of 1.0 (thermal neutrons), 1.13 (photons), and 0.74 (fast neutrons) to match the dosimetry of MIT.

Normalisation of prescribed dose in boron neutron capture therapy (BNCT) is needed to facilitate combining clinical data from different centres in the world to help expedite development of the modality. The approach being pursued within the BNCT community is based upon improving precision in the measurement and specification of absorbed dose. Beam characterisations using a common method are complete as are comparative dosimetry measurements between clinical centres in Europe and the USA. Results from treatment planning systems at these centres have been compared with measurements performed by MIT, and the scale factors determined are being confirmed with independent tests using measurements in an ellipsoidal water phantom. Dose normalisations have successfully been completed and applied to retrospectively analyse treatment plans from Brookhaven National Laboratory (1994-99) so that reported doses are consistently expressed with the trials performed during 1994-2003 at Harvard-MIT. Dose response relationships for adverse events and other endpoints can now be more accurately established.

Purpose: This report addresses the incidence of vascular endothelial cell apoptosis in the mouse small intestine in relation to the radiation-induced gastrointestinal (GI) syndrome. Methods and Materials: Nonanesthetized mice received whole-body irradiation at doses above and below the threshold for death from the GI syndrome with 250 kVp X-rays, 137 Cs gamma rays, epithermal neutrons alone, or a unique approach for selective vascular irradiation using epithermal neutrons in combination with boronated liposomes that are restricted to the blood. Both terminal deoxynucleotidyl transferase biotin-dUTP nick end labeling (TUNEL) staining for apoptosis and dual-fluorescence staining for apoptosis and endothelial cells were carried out in jejunal cross-sections at 4 h postirradiation. Results: Most apoptotic cells were in the crypt epithelium. The number of TUNEL-positive nuclei per villus was low (1.62 ± 0.03, mean ± SEM) for all irradiation modalities and showed no dose–response as a function of blood vessel dose, even as the dose crossed the threshold for death from the GI syndrome. Dual-fluorescence staining for apoptosis and endothelial cells verified the TUNEL results and identified the apoptotic nuclei in the villi as CD45-positive leukocytes. Conclusion: These data do not support the hypothesis that vascular endothelial cell apoptosis is the cause of the GI syndrome.

Purpose: The aim of this study was to construct a 6 Li filter and to improve penetration of thermal neutrons produced by the fission converter–based epithermal neutron beam (FCB) for brain irradiation during boron neutron capture therapy (BNCT). Methods and Materials: Design of the 6 Li filter was evaluated using Monte Carlo simulations of the existing beam line and radiation transport through an ellipsoidal water phantom. Changes in beam performance were determined using three figures of merit: ( 1 ) advantage depth (AD), the depth at which the total biologically weighted dose to tumor equals the maximum weighted dose to normal tissue; ( 2 ) advantage ratio (AR), the ratio of the integral tumor dose to that of normal tissue averaged from the surface to the AD; and ( 3 ) advantage depth dose rate (ADDR), the therapeutic dose rate at the AD. Dosimetry performed with the new filter installed provided calibration data for treatment planning. Past treatment plans were recalculated to illustrate the clinical potential of the filter. Results: The 8-mm-thick Li filter is more effective for smaller field sizes, increasing the AD from 9.3 to 9.9 cm, leaving the AR unchanged at 5.7 but decreasing the ADDR from 114 to 55 cGy min −1 for the 12 cm diameter aperture. Using the filter increases the minimum deliverable dose to deep seated tumors by up to 9% for the same maximum dose to normal tissue. Conclusions: Optional 6 Li filtration provides an incremental improvement in clinical beam performance of the FCB that could help to establish a therapeutic window in the future treatment of deep-seated tumors.

Purpose: The purpose of the present study was to evaluate the anti–epidermal growth factor monoclonal antibody (mAb) cetuximab (IMC-C225) as a delivery agent for boron neutron capture therapy (BNCT) of a human epidermal growth factor receptor (EGFR) gene-transfected rat glioma, designated as F98EGFR. Experimental Design: A heavily boronated polyamidoamine dendrimer was chemically linked to cetuximab by means of the heterobifunctional reagents N-succinimidyl 3-(2-pyridyldithio)-propionate and N-(k-maleimido undecanoic acid)-hydrazide. The bioconjugate, designated as BD-C225, was specifically taken up by F98EGFR glioma cells in vitro compared with receptor-negative F98 wild-type cells (41.8 versus 9.1 μg/g). For in vivo biodistribution studies, F98EGFR cells were implanted stereotactically into the brains of Fischer rats, and 14 days later, BD-C225 was given intracerebrally by either convection enhanced delivery (CED) or direct intratumoral (i.t.) injection. Results: The amount of boron retained by F98EGFR gliomas 24 h following CED or i.t. injection was 77.2 and 50.8 μg/g, respectively, with normal brain and blood boron values Conclusions: The survival data obtained with BD-C225 are comparable with those recently reported by us using boronated mAb L8A4 as the delivery agent. This mAb recognizes the mutant receptor, EGFRvIII. Taken together, these data convincingly show the therapeutic efficacy of molecular targeting of EGFR using a boronated mAb either alone or in combination with BPA and provide a platform for the future development of combinations of high and low molecular weight delivery agents for BNCT of brain tumors.

The possible role of vascular endothelial cell damage in the loss of intestinal crypt stem cells and the subsequent development of the gastrointestinal (GI) syndrome is addressed. Mice received whole-body epithermal neutron irradiation at a dose rate of 0.57 ± 0.04 Gy·min −1 . An additional dose was selectively targeted to endothelial cells from the short-ranged (5–9 μm) particles released from neutron capture reactions in 10 B confined to the blood by incorporation into liposomes 70–90 nm in diameter. Different liposome formulations produced 45 ± 7 or 118 ± 12 μg/g 10 B in the blood at the time of neutron irradiation, which resulted in total absorbed dose rates in the endothelial cells of 1.08 ± 0.09 or 1.90 ± 0.16 Gy·min −1 , respectively. At 3.5 d after irradiation, the intestinal crypt microcolony assay showed that the 2- to 3-fold increased doses to the microvasculature, relative to the nonspecific whole-body neutron beam doses, caused no additional crypt stem cell loss beyond that produced by the neutron beam alone. The threshold dose for death from the GI syndrome after neutron-beam-only irradiation was 9.0 ± 0.6 Gy. There were no deaths from the GI syndrome, despite calculated absorbed doses to endothelial cells as high as 27.7 Gy, in the groups that received neutron beam doses of

Cetuximab (IMC-C225) is a monoclonal antibody directed against both the wild-type and mutant vIII isoform of the epidermal growth factor receptor (EGFR). The purpose of the present study was to evaluate the monoclonal antibody (MoAb), cetuximab, as a boron delivery agent for neutron capture therapy (NCT) of brain tumors. Twenty-four hours following intratumoral (i.t.) administration of boronated cetuximab (C225-G5-B(1100)), the mean boron concentration in rats bearing either F98(EGFR) or F98(WT) gliomas were 92.3+/-23.3 microg/g and 36.5+/-18.8 microg/g, respectively. In contrast, the uptake of boronated dendrimer (G5-B(1000)) was 6.7+/-3.6 microg/g. Based on its favorable in vivo uptake, C225-G5-B(1100) was evaluated as a delivery agent for BNCT in F98(EGFR) glioma bearing rats. The mean survival time (MST) of rats that received C225-G5-B(1100), administered by convection enhanced delivery (CED), was 45+/-3d compared to 25+/-3d for untreated control animals. A further enhancement in MST to >59d was obtained by administering C225-G5-B(1100) in combination with i.v. boronophenylalanine (BPA). These data are the first to demonstrate the efficacy of a boronated MoAb for BNCT of an intracerebral (i.c.) glioma and are paradigmatic for future studies using a combination of boronated MoAbs and low molecular weight delivery agents.

A Phase I/II clinical trial of neutron capture therapy (NCT) was conducted at Harvard–MIT using a fission converter epithermal neutron beam. This epithermal neutron beam has nearly ideal performance characteristics (high intensity and purity) and is well-suited for clinical use. Six glioblastoma multiforme (GBM) patients were treated with NCT by infusion of the tumor-selective amino acid boronophenylalanine-fructose (BPA-F) at a dose of 14.0 g/m 2 body surface area over 90 min followed by irradiation with epithermal neutrons. Treatments were planned using NCTPlan and an accelerated version of the Monte Carlo radiation transport code MCNP 4B. Treatments were delivered in two fractions with two or three fields. Field order was reversed between fractions to equalize the average blood boron concentration between fields. The initial dose in the dose escalation study was 7.0 RBE Gy, prescribed as the mean dose to the whole brain volume. This prescription dose was increased by 10% to 7.7 RBE Gy in the second cohort of patients. A pharmacokinetic model was used to predict the blood boron concentration for determination of the required beam monitor units with good accuracy; differences between prescribed and delivered doses were 1.5% or less. Estimates of average tumor doses ranged from 33.7 to 83.4 RBE Gy (median 57.8 RBE Gy), a substantial improvement over our previous trial where the median value of the average tumor dose was 25.8 RBE Gy.

The tissue substitute A-181 plastic, which has an elemental composition matching both the constituent hydrogen and nitrogen of brain tissue, was assessed for dosimetry in boron neutron capture therapy (BNCT). The sensitivity of an A-181 walled ionization chamber relative to photons for all neutrons in a clinical epithermal beam was calculated to vary between 0.79 +/- 0.04 in-air and 0.95 +/- 0.01 at depths of 4 cm and greater in-phantom. Differences in the total neutron doses measured with A-150 and A-181 plastic-walled chambers were attributed, within experimental error, to the dose produced by thermal neutron capture reactions from the different concentrations of nitrogen in the two tissue substitutes. The response of the A-181 chamber was converted to total neutron dose with an uncertainty increasing with depth in-phantom from 13 to 23% the magnitude of which is determined by the subtraction of a relatively large photon dose. The use of A-181 in place of A-150 plastic will no longer require partitioning the measured neutron dose by energy and should simplify dose reporting in BNCT.

A patient collimator for the fission converter based epithermal neutron beam (FCB) at the Massachusetts Institute of Technology Research Reactor (MITR-II) was built for clinical trials of boron neutron capture therapy (BNCT). A design was optimized by Monte Carlo simulations of the entire beam line and incorporates a modular construction for easy modifications in the future. The device was formed in-house by casting a mixture of lead spheres (7.6 mm diameter) in epoxy resin loaded with either 140 mg cm(-3) of boron carbide or 210 mg cm(-3) of lithium fluoride (95% enriched in 6Li). The cone shaped collimator allows easy field placement anywhere on the patient and is equipped with a laser indicator of central axis, beam's eye view optics and circular apertures of 80, 100, 120 and 160 mm diameter. Beam profiles and the collateral dose in a half-body phantom were measured for the 160 mm field using fission counters, activation foils as well as tissue equivalent (A-150) and graphite walled ionization chambers. Leakage radiation through the collimator contributes less than 10% to the total collateral dose up to 0.15 m beyond the edge of the aperture and becomes relatively more prominent with lateral displacement. The measured whole body dose equivalent of 24 +/- 2 mSv per Gy of therapeutic dose is comparable to doses received during conventional therapy and is due principally (60-80%) to thermal neutron capture reactions with boron. These findings, together with the dose distributions for the primary beam, demonstrate the suitability of this patient collimator for BNCT.

Microdosimetric measurements have been performed at the clinical beam intensities in two epithermal neutron beams, the Brookhaven Medical Research Reactor and the M67 beam at the Massachusetts Institute of Technology Research Reactor, which have been used to treat patients with Boron Neutron Capture Therapy (BNCT). These measurements offer an independent assessment of the dosimetry used at these two facilities, as well as provide information about the radiation quality not obtainable from conventional macrodosimetric techniques. Moreover, they provide a direct measurement of the absorbed dose resulting from the BNC reaction. BNC absorbed doses measured within this study are approximately 15% lower than those estimated using foil activation at both MIT and BNL. Finally, an intercomparison of the characteristics and radiation quality of these two clinical beams is presented. The techniques described here allow an accurate quantitative comparison of the physical absorbed dose as well as a measure of the biological effectiveness of the absorbed dose delivered by different epithermal beams. No statistically significant differences were observed in the predicted RBEs of these two beams. The methodology presented here can help to facilitate the effective sharing of clinical results in an effort to demonstrate the clinical utility of BNCT.

A pre-clinical characterization of the first fission converter based epithermal neutron beam (FCB) designed for boron neutron capture therapy (BNCT) has been performed. Calculated design parameters describing the physical performance of the aluminium and Teflon filtered beam were confirmed from neutron fluence and absorbed dose rate measurements performed with activation foils and paired ionization chambers. The facility currently provides an epithermal neutron flux of 4.6 x 10(9) n cm(-2) s(-1) in-air at the patient position that makes it the most intense BNCT source in the world. This epithermal neutron flux is accompanied by very low specific photon and fast neutron absorbed doses of 3.5 +/- 0.5 and 1.4 +/- 0.2 x 10(-13) Gy cm2, respectively. A therapeutic dose rate of 1.7 RBE Gy min(-1) is achievable at the advantage depth of 97 mm when boronated phenylalanine (BPA) is used as the delivery agent, giving an average therapeutic ratio of 5.7. In clinical trials of normal tissue tolerance when using the FCB, the effective prescribed dose is due principally to neutron interactions with the nonselectively absorbed BPA present in brain. If an advanced compound is considered, the dose to brain would instead be predominately from the photon kerma induced by thermal neutron capture in hydrogen and advantage parameters of 0.88 Gy min(-1), 121 mm and 10.8 would be realized for the therapeutic dose rate, advantage depth and therapeutic ratio, respectively. This study confirms the success of a new approach to producing a high intensity, high purity epithermal neutron source that attains near optimal physical performance and which is well suited to exploit the next generation of boron delivery agents.

The status of fission reactor-based neutron beams for neutron capture therapy (NCT) is reviewed critically. Epithermal neutron beams, which are favored for treatment of deep-seated tumors, have been constructed or are under construction at a number of reactors worldwide. Some of the most recently constructed epithermal neutron beams approach the theoretical optimum for beam purity. Of these higher quality beams, at least one is suitable for use in high through-put routine therapy. It is concluded that reactor-based epithermal neutron beams with near optimum characteristics are currently available and more can be constructed at existing reactors. Suitable reactors include relatively low power reactors using the core directly as a source of neutrons or a fission converter if core neutrons are difficult to access. Thermal neutron beams for NCT studies with small animals or for shallow tumor treatments, with near optimum properties have been available at reactors for many years. Additional high quality thermal beams can also be constructed at existing reactors or at new, small reactors. Furthermore, it should be possible to design and construct new low power reactors specifically for NCT, which meet all requirements for routine therapy and which are based on proven and highly safe reactor technology.

A two-compartment open model has been developed for predicting 10B concentrations in blood following intravenous infusion of the L-p-boronophenylalanine-fructose complex in humans and derived from pharmacokinetic studies of 24 patients in Phase I clinical trials of boron neutron capture therapy. The 10B concentration profile in blood exhibits a characteristic rise during the infusion to a peak of approximately 32 microg/g (for infusion of 350 mg/kg over 90 min) followed by a biexponential disposition profile with harmonic mean half-lives of 0.32 +/- 0.08 and 8.2 +/- 2.7 h, most likely due to redistribution and primarily renal elimination, respectively. The mean model rate constants k12, k21, and k10 are (mean +/- SD) 0.0227 +/- 0.0064 min(-1), 0.0099 +/- 0.0027 min(-1), 0.0052 +/- 0.0016 min(-1), respectively, and the central compartment volume of distribution V1 is 0.235 +/- 0.042 L/kg. In anticipation of the initiation of clinical trials using an intense neutron beam with concomitantly short irradiations, the ability of this model to predict, in advance, the average blood 10B concentration during brief irradiations was simulated in a retrospective analysis of the pharmacokinetic data from these patients. The prediction error for blood boron concentration and its effect on simulated dose delivered for each irradiation field are reported for three different prediction strategies. In this simulation, error in delivered dose (or, equivalently, neutron fluence) for a given single irradiation field resulting from error in predicted blood 10B concentration was limited to less than 10%. In practice, lower dose errors can be achieved by delivering each field in two fractions (on two separate days) and by adjusting the second fraction's dose to offset error in the first.

A new epithermal neutron irradiation facility, based on a fission converter assembly placed in the thermal column outside the reactor core, has been put into operation at the Massachusetts Institute of Technology Research Reactor (MITR). This facility was constructed to provide a high-intensity, forward-directed beam for use in neutron capture therapy with an epithermal flux of [approximately equal to]10{sup 10} n/cm{sup 2}.s at the medical room entrance with negligible fast neutron and gamma-ray contamination. The fission converter assembly consists of 10 or 11 MITR fuel elements placed in an aluminum tank and cooled with D{sub 2}O. Thermal-hydraulic criteria were established based on heat deposition calculations. Various startup tests were performed to verify expected neutronic and thermal-hydraulic behavior. Flow testing showed an almost flat flow distribution across the fuel elements with

Purpose : A Phase I trial of cranial neutron capture therapy (NCT) was conducted at Harvard-MIT. The trial was designed to determine maximum tolerated NCT radiation dose to normal brain. Methods and Materials : Twenty-two patients with brain tumors were treated by infusion of boronophenylalanine-fructose (BPA-f) followed by exposure to epithermal neutrons. The study began with a prescribed biologically weighted dose of 8.8 RBE (relative biologic effectiveness) Gy, escalated in compounding 10% increments, and ended at 14.2 RBE Gy. BPA-f was infused at a dose 250–350 mg/kg body weight. Treatments were planned using MacNCTPlan and MCNP 4B. Irradiations were delivered as one, two, or three fields in one or two fractions. Results : Peak biologically weighted normal tissue dose ranged from 8.7 to 16.4 RBE Gy. The average dose to brain ranged from 2.7 to 7.4 RBE Gy. Average tumor dose was estimated to range from 14.5 to 43.9 RBE Gy, with a mean of 25.7 RBE Gy. Conclusions : We have demonstrated that BPA-f-mediated NCT can be precisely planned and delivered in a carefully controlled manner. Subsequent clinical trials of boron neutron capture therapy at Harvard and MIT will be initiated with a new high-intensity, high-quality epithermal neutron beam.

A new type of epithermal neutron irradiation facility for use in neutron capture therapy has been designed, constructed, and put into operation at the Massachusetts Institute of Technology Research...

The performance of the prompt gamma neutron activation analysis (PGNAA) facility at the MIT Research Reactor has been improved by a series of modifications. These modifications have increased the flux by a factor of three at the sample position to 1.7 × 107 n/cm2 s, and have increased the sensitivity, on average, by a factor of 2.5. The background for many samples of interest is dominated by unavoidable neutron interactions that occur in or near the sample. Other background components comprise only 20% of the total background count rate. The implementation of fast electronics has helped to keep dead time reasonable, in spite of the increased count rates. The PGNAA facility at the MIT Research Reactor continues to serve as a major analytical tool for quantifying 10B in biological samples for Boron Neutron Capture Therapy (BNCT) research. The sensitivity for boron-10 in water is 18 750 cps/mg. The sensitivity for pure elements suitable for PGNAA analysis is reported. Possible further improvements are discussed.

In this chapter, a brief overview is provided of fission reactor-based epithermal neutron irradiation facilities designed for neutron capture therapy. The overview is intended to give those who are interested in establishing this type of facility some perspective and guidance concerning the desirable performance characteristics and features. Requirements for clinical BNCT are described in the Introduction together with a review of beam design studies. This is followed by a section describing two different approaches for producing an epithermal neutron beam for clinical BNCT and a description of currently available facilities. A state-of-the-art neutron beam facility is highlighted that satisfies all of the desired beam performance criteria and is capable of supporting more advanced clinical studies where higher patient throughput is needed. Existing reactor-based neutron irradiation facilities satisfy the needs currently anticipated for clinical research in BNCT while using proven and readily available technology. Some of these facilities possess many of the features of modern radiotherapy machines and employ modular designs to enable beamline modifications. This flexibility in beam delivery is needed to realize advances derived from future clinical accrual or translational research to develop improved methods for treating different tumors. Additional facilities can be constructed in the near term if needed by modifying available research reactors or by constructing small, ultrasafe reactors that are dedicated to BNCT.

In this report we have summarized our studies to optimize the delivery of boronophenylalanine (BPA) and sodium borocaptate (BSH) for boron neutron capture therapy (BNCT) of F98 glioma bearing rats. These results have been compared to a chemoradiotherapeutic approach using the same tumor model. The best survival data from our BNCT studies were obtained using a combination of BPA and sodium borocaptate BSH administered via the internal carotid artery, in combination with blood-brain barrier disruption (BBB-D). This treatment resulted in a mean survival time (MST) of 140 d with a 25% cure rate. The other approach combined intracerebral administration of carboplatin by either convection enhanced delivery (CED) or Alzet pump infusion, followed by external beam photon irradiation. This resulted in MSTs of 83 d and 112 d, respectively, with a cure rate of 40% for the latter. However, a significant problem that must be solved for both BNCT and this new chemoradiotherapeutic approach is how to improve drug uptake and microdistribution within the tumor.

Modern day research in a variety of disciplines requires sensitive neutron detectors having a high spatial resolution that are able to discriminate against unwanted gamma ray events. A novel detector concept comprising cylindrical plastic scintillators embedded in a fiber optic array was designed and developed to determine if the desired performance can be attained. Monte-Carlo design studies were performed to optimize detector geometry and calculate the anticipated neutron detection efficiency. Prototype detectors were characterized by measuring detection efficiency and pulse height spectra using isotopic neutron and gamma-ray sources. Images of neutron absorbing phantoms were acquired with a lens-coupled EMCCD viewing the sample during neutron irradiation via a surface coated 45o mirror. Specimens with areas up to 6 × 6 cm2 were fabricated by submerging fiberoptic arrays with a capillary diameter of 100 μm and a relative open area of 83% in a polymer of the desired mixture and curing slowly. Increasing the concentration of boron was observed to reduce light output by as much as 28% for the highest boron concentrations tested. Pulse height spectra from the samples exhibited a peak characteristic of neutron capture in boron at an energy (electron equivalent) of approximately 90 keV and the detection efficiency for a 5.7 mm thick scintillator containing 5% o-carborane was 40%, which agrees with calculations. The spatial resolution of these detectors is 250 μm as determined from the modulation transfer function at 10% modulation.

Colloidal semiconductor nanocrystals exhibit physical properties that are characteristic of intermediate size scales between molecular states and solid state materials, and are often called quantum dots. Solid state semiconductor materials have been used extensively as scintillation detectors for ionizing radiation. We describe the use of semiconductor quantum dot — organic polymer composites for use as scintillation detectors and report the first use of quantum dot — polymer composite thin films for X-ray imaging. We have prepared quantum dot — polymer thin film samples using both aqueous CdTe quantum dots in polyvinyl alcohol and non-aqueous CdSe quantum dots in polystyrene. Optical absorption spectra and emission spectra are used to characterize the quantum dot morphology in the polymer film and to evaluate the impact of the host polymer matrix on the quantum dot dopant. We report the fluorescence lifetime changes of the quantum dots in the polymer host and discuss the impact on high frame rate X-ray imaging. The emission spectrum of the X-ray induced luminescence is found to have the same spectral dependence as the laser induced fluorescence. The details of the quantum dot — polymer composite scintillator fabrication and characterization will be discussed. The thin film substrates are coupled to a CCD camera and used to record X-ray images.

Scientific applications of neutrons ranging from protein crystallography to non-destructive inspections require sensitive neutron detectors having a high spatial resolution that are able to discriminate against unwanted gamma ray events. To address this problem, 2 and 5 mm thick prototype detectors were fabricated as a bundled array of 120 μm diameter cerium activated lithium silicate glass fibers cast in a low-index epoxy resin that helps improve light transmission. Performance of this detector was determined from measured pulse height spectra of isotopic gamma-ray sources and a moderated 10 Ci Am/Li neutron source. Imaging experiments were also performed in a polychromatic neutron beam using an electron-multiplying CCD. 1.5 MeV of electron equivalent light output was determined from pulse height spectra of the bulk glass which is comparable to commercial glasses. Light output for neutron events in the 2 mm thick bundled array was about 50% lower than the bulk sample but gamma rays were similarly affected. The 5 mm thick sample exhibited poorer light output with some asymmetry in the neutron capture peak that is associated with light losses in the fiber bundle. The neutron detection efficiency of the 2 and 5 mm thick detectors was 68 and 98%, respectively. Both detectors successfully imaged patterns fashioned from cadmium neutron absorbers and indicate a spatial resolution of approximately 250 μm. These data demonstrate the feasibility of this approach and further studies are underway to improve overall light output and spatial resolution.

In the present study, we have evaluated a boronated dendrimer-epidermal growth factor (BD-EGF) bioconjugate as a molecular targeting agent for boron neutron capture therapy (BNCT) of the human EGFR gene-transfected F98 rat glioma, designated F98(EGFR). EGF was chemically linked to a heavily boronated polyamidoamine dendrimer (BD) by means of the heterobifunctional reagent, mMBS. Biodistribution studies were carried out at 6 h and 24 h following intratumoral (i.t.) injection or intracerebral (i.c.) convection enhanced delivery (CED) of (125)I-labeled or unlabeled BD-EGF (40 microg (10)B/10 microg EGF) to F98 glioma bearing rats. At 24 h. there was 43% more radioactivity in EGFR(+) tumors following CED compared to i.t. injection, and a doubling of the tumor boron concentration (22.3 microg/g vs. 11.7 microg/g). CED of BD-EGF resulted in a 7.2x increase in the volume of distribution within the infused cerebral hemisphere and a 1.9x increase in tumor uptake of BD-EGF compared with i.t. injection. Based on these favorable biodistribution data, BNCT was carried out at the Massachusetts Institute of Technology nuclear reactor 14 days following i.c. tumor implantation and 24 h. after CED of BD-EGF. These animals had a MST of 54.1 +/- 4.7 days compared to 43.0 +/- 2.8 days following i.t. injection. Rats that received BD-EGF by CED in combination with i.v. boronophenylalanine (BPA), which has been used in both experimental and clinical studies, had a MST of 86.0 +/- 28.1 days compared to 39.8 +/- 1.6 days for i.v. BPA alone (P0.01), 30.9 +/- 1.4 days for irradiated controls and 25.1 +/- 1.0 days for untreated controls (overall P0.0001). These data have demonstrated that the efficacy of BNCT was significantly increased (P0.006), following i.c CED of BD-EGF compared to i.t injection, and that the survival data were equivalent to those previously reported by us using the boronated anti-human-EGF mAb, C225 (cetuximab).

Purpose: The purpose of the present study was to evaluate the anti–epidermal growth factor receptor (EGFR) monoclonal antibody (mAb), cetuximab, (IMC-C225) and the anti-EGFRvIII mAb, L8A4, used in combination as delivery agents for boron neutron capture therapy (BNCT) of a rat glioma composed of a mixture of cells expressing either wild-type (F98EGFR) or mutant receptors(F98npEGFRvIII).Experimental Design: A heavily boronated polyamidoamine dendrimer (BD) was linked by heterobifunctional reagents to produce the boronated mAbs, BD-C225 and BD-L8A4. For in vivo biodistribution and therapy studies, a mixture of tumor cells were implanted intracerebrally into Fischer rats. Biodistribution studies were carried out by administering 125I-labeled bioconjugates via convection-enhanced delivery (CED), and for therapy studies, nonradiolabeled bioconjugates were used for BNCT. This was carried out 14 days after tumor implantation and 24 h after CED at the Massachusetts Institute of Technology nuclear reactor.Results: Following CED of a mixture of 125I-BD-C225 and 125I-BD-L8A4 to rats bearing composite tumors, 61.4% of the injected dose per gram (ID/g) was localized in the tumor compared with 30.8% ID/g for 125I-BD-L8A4 and 34.7% ID/g for 125I-BD-C225 alone. The corresponding calculated tumor boron values were 24.4 μg/g for rats that received both mAbs, and 12.3 and 13.8 μg/g, respectively, for BD-L8A4 or BD-C225 alone. The mean survival time of animals bearing composite tumors, which received both mAbs, was 55 days (P < 0.0001) compared with 36 days for BD-L8A4 and 38 days for BD-C225 alone, which were not significantly different from irradiated controls.Conclusions: Both EGFRvIII and wild-type EGFR tumor cell populations must be targeted using a combination of BD-cetuximab and BD-L8A4. Although in vitro C225 recognized both receptors, in vivo it was incapable of delivering the requisite amount of 10B for BNCT of EGFRvIII-expressing gliomas.

The motivation for this work was an unexpected occurrence of lung side effects in two human subjects undergoing cranial boron neutron capture therapy (BNCT). The objectives were to determine experimentally the biological weighting factors in rat lung for the high-LET dose components for a retrospective assessment of the dose to human lung during cranial BNCT. Lung damage after whole-thorax irradiation was assessed by serial measurement of breathing rate and evaluation of terminal lung histology. A positive response was defined as a breathing rate 20% above the control group mean and categorized as occurring either early (110 days) or late (110 days). The ED(50) values derived from probit analyses of the early breathing rate dose-response data for X rays and neutrons were 11.4+/-0.4 and 9.2+/-0.6 Gy, respectively, and were similar for the other end points. The ED(50) values for irradiation with neutrons plus p-boronophenylalanine were 8.7+/-1.0 and 6.7+/-0.4 for the early and late breathing rate responses, respectively, and 7.0+/-0.5 Gy for the histological response. The RBEs for thermal neutrons ranged between 2.9+/-0.7 and 3.1+/-1.2 for all end points. The weighting factors for the boron component of the dose differed significantly between the early (1.4+/-0.3) and late (2.3+/-0.3) breathing rate end points. A reassessment of doses in patients during cranial BNCT confirmed that the maximum weighted doses were well below the threshold for the onset of pneumonitis in healthy human lung.

Purpose: The purpose of the present study was to evaluate a boronated EGFRvIII-specific monoclonal antibody, L8A4, for boron neutron capture therapy (BNCT) of the receptor-positive rat glioma, F98npEGFRvIII. Experimental Design: A heavily boronated polyamido amine (PAMAM) dendrimer (BD) was chemically linked to L8A4 by two heterobifunctional reagents, N-succinimidyl 3-(2-pyridyldithio)propionate and N-(k-maleimidoundecanoic acid)hydrazide. For in vivo studies, F98 wild-type receptor-negative or EGFRvIII human gene-transfected receptor-positive F98npEGFRvIII glioma cells were implanted i.c. into the brains of Fischer rats. Biodistribution studies were initiated 14 days later. Animals received [125I]BD-L8A4 by either convection enhanced delivery (CED) or direct i.t. injection and were euthanized 6, 12, 24, or 48 hours later. Results: At 6 hours, equivalent amounts of the bioconjugate were detected in receptor-positive and receptor-negative tumors, but by 24 hours the amounts retained by receptor-positive gliomas were 60.1% following CED and 43.7% following i.t. injection compared with 14.6% ID/g by receptor-negative tumors. Boron concentrations in normal brain, blood, liver, kidneys, and spleen all were at nondetectable levels (6 months) and those that received BD-L8A4 alone had a mean ± SE survival time of 70.4 ± 11.1 days with 10% long-term survivors compared with 40.1 ± 2.2 days for i.v. BPA and 30.3 ± 1.6 and 26.3 ± 1.1 days for irradiated and untreated controls, respectively. Conclusions: These data convincingly show the therapeutic efficacy of molecular targeting of EGFRvIII using either boronated monoclonal antibody L8A4 alone or in combination with BPA and should provide a platform for the future development of combinations of high and low molecular weight delivery agents for BNCT of brain tumors.

The RBE of the new MIT fission converter epithermal neutron capture therapy (NCT) beam has been determined using intestinal crypt regeneration in mice as the reference biological system. Female BALB/c mice were positioned separately at depths of 2.5 and 9.7 cm in a Lucite phantom where the measured total absorbed dose rates were 0.45 and 0.17 Gy/ min, respectively, and irradiated to the whole body with no boron present. The gamma-ray (low-LET) contributions to the total absorbed dose (low- + high-LET dose components) were 77% (2.5 cm) and 90% (9.7 cm), respectively. Control irradiations were performed with the same batch of animals using 6 MV photons at a dose rate of 0.83 Gy/min as the reference radiation. The data were consistent with there being a single RBE for each NCT beam relative to the reference 6 MV photon beam. Fitting the data according to the LQ model, the RBEs of the NCT beams were estimated as 1.50 +/- 0.04 and 1.03 +/- 0.03 at depths of 2.5 and 9.7 cm, respectively. An alternative parameterization of the LQ model considering the proportion of the high- and low-LET dose components yielded RBE values at a survival level corresponding to 20 crypts (16.7%) of 5.2 +/- 0.6 and 4.0 +/- 0.7 for the high-LET component (neutrons) at 2.5 and 9.7 cm, respectively. The two estimates are significantly different (P = 0.016). There was also some evidence to suggest that the shapes of the curves do differ somewhat for the different radiation sources. These discrepancies could be ascribed to differences in the mechanism of action, to dose-rate effects, or, more likely, to differential sampling of a more complex dose-response relationship.

A comparison of seven epithermal neutron beams used in clinical studies of boron neutron capture therapy (BNCT) in Sweden (Studsvik), Finland (Espoo), Czech Republic (ReZ), The Netherlands (Petten) and the U.S. (Brookhaven and Cambridge) was performed to facilitate sharing of preclinical and clinical results. The physical performance of each beam was measured using a common dosimetry method under conditions pertinent to brain irradiations. Neutron fluence and absorbed dose measurements were performed with activation foils and paired ionization chambers on the central axis both in air and in an ellipsoidal water phantom. The overall quality of each beam was assessed by figures of merit determined from the total weighted dose profiles that assumed the presence of boron in tissue. The in-air specific beam contamination from both fast neutrons and gamma rays ranged between 8 and 65 x 10(-11) cGy(w) cm2 for the different beams and the epithermal neutron flux intensities available at the patient position differed by more than a factor of 20 from 0.2-4.3 x 10(9) n cm(-2) s(-1). Percentage depth dose profiles measured in-phantom for the individual photon, thermal and fast-neutron dose components differed only subtly in shape between facilities. Assuming uptake characteristics consistent with the currently used boronated phenylalanine, all the epithermal beams exhibit a useful penetration of 8 cm or greater that is sufficient to irradiate a lesion seated at the brain midline. The performance of the existing facilities will benefit from the introduction of advanced compounds through improved beam penetrability. This could increase by as much as 2 cm for the purest of beams, although the beam intensities generally need to be increased to between 2-5 x 10(9) n cm(-2) s(-1) to maintain manageable irradiation times. These data provide the first consistent measurement of beam performance at the different centers and will enable a preliminary normalization of the calculated patient dosimetry.

Neutron capture therapy (NCT) research encompasses a wide range of preclinical and clinical studies needed to develop this promising but complex cancer treatment. Many specialized facilities and capabilities including thermal and epithermal neutron irradiation facilities, boron analysis, specialized mixed-field dosimetry, animal care facilities and protocols, cell culture laboratories, and, for human clinical studies, licenses and review board approvals are required for NCT research. Such infrastructure is essential, but much of it is not readily available within the community. This is especially true for neutron irradiation facilities, which often require significant development and capital investment too expensive to duplicate at each site performing NCT research. To meet this need, the NCT group at the Massachusetts Institute of Technology (MIT) has established a User Center for NCT researchers that is already being accessed successfully by various groups. This paper describes the facilities, capabilities and other resources available at MIT and how the NCT research community can access them.

An international collaboration was organized to undertake a dosimetry exchange to enable the future combination of clinical data from different centers conducting neutron capture therapy trials. As a first step (Part I) the dosimetry group from the Americas, represented by MIT, visited the clinical centers at Studsvik (Sweden), VTT Espoo (Finland), and the Nuclear Research Institute (NRI) at Rez (Czech Republic). A combined VTT/NRI group reciprocated with a visit to MIT. Each participant performed a series of dosimetry measurements under equivalent irradiation conditions using methods appropriate to their clinical protocols. This entailed in-air measurements and dose versus depth measurements in a large water phantom. Thermal neutron flux as well as fast neutron and photon absorbed dose rates were measured. Satisfactory agreement in determining absorbed dose within the experimental uncertainties was obtained between the different groups although the measurement uncertainties are large, ranging between 3% and 30% depending upon the dose component and the depth of measurement. To improve the precision in the specification of absorbed dose amongst the participants, the individually measured dose components were normalized to the results from a single method. Assuming a boron concentration of 15 mu g g(-1) that is typical of concentrations realized clinically with the boron delivery compound boronophenylalanine-fructose, systematic discrepancies in the specification of the total biologically weighted dose of up to 10% were apparent between the different groups. The results from these measurements will be used in future to normalize treatment plan calculations between the different clinical dosimetry protocols as Part II of this study. (c) 2005 American Association of Physicists in Medicine. (Less)

Data from the Harvard-MIT and the BNL Phase I and Phase I/II clinical trials, conducted between 1994 and 1999, have been analyzed and combined, providing the most complete data set yet available on the tolerance of the normal human brain to BPA-mediated boron neutron capture therapy. Both peak (1cm(3)) dose and average whole-brain dose show a steep dose-response relationship using somnolence syndrome as the clinical endpoint. Probit analysis indicates that the doses associated with a 50% incidence for somnolence (ED(50)+/-SE) were 6.2+/-1.0 Gy(w) for average whole-brain dose and 14.1+/-1.8 Gy(w) for peak brain dose.

The international collaboration that was organized to undertake a dosimetry exchange for purposes of combining clinical data from different facilities conducting neutron capture therapy has continued since its founding at the 9th ISNCT symposium in October 2000. The thrust towards accumulating physical dosimetry data for comparison between different participants has broadened to include facilities in Japan and the determination of spectral descriptions of different beams. Retrospective analysis of patient data from the Brookhaven Medical Research Reactor is also being considered for incorporation into this study to increase the pool of available data. Meanwhile the next essential phase of comparing measurements of visiting dosimetry groups with treatment plan calculations from the host institutes has commenced. Host centers from Petten, Finland and the Czech Republic in Europe and MIT in the USA have applied the regular calculations and clinical calibrations from their current clinical studies, to generate treatment plans in the large standard phantom used for measurements by visiting participants. These data have been exchanged between the participants and scaling factors to relate the separate dose components between the different institutes are being determined. Preliminary normalization of measured and calculated dosimetry for patients is nearing completion to enable the physical radiation doses that comprise a treatment prescription at a host institute to be directly related to the corresponding measured doses of a visiting group. This should serve as an impetus for the direct comparison of patient data although the clinical requirements for achieving this need to be clearly defined. This may necessitate more extensive comparisons of treatment planning calculations through the solution of test problems and clarification regarding the question of dose specification from treatment calculations in general.

The purpose of the present study was to further evaluate a boronated dendrimer (BD)-epidermal growth factor bioconjugate (BD-EGF), administered by means of convection enhanced delivery (CED), as a molecular targeting agent for boron neutron capture therapy (BNCT) of the F98 EGFR glioma. Twenty-four hours following CED of 125 I-labeled BD-EGF 47.4% of the injected dose (ID) was retained in F98 EGFR gliomas compared to 12.3% in F98 WT (wildtype) receptor negative tumors. Normal brain values were in the range of 5.9–10.1% ID in the tumor bearing cerebral hemisphere. Boron concentrations in F98 EGFR gliomas were 22.3 and 11.7 μg/g following CED and i.t. injection, respectively. Based on these results, BNCT studies were initiated at the Massachusetts Institute of Technology nuclear reactor (MITRII). The mean survival time (MST) of rats that received BD-EGF either alone or in combination with boronophenylalanine (BPA), injected i.v., were 53±13 d and >61±14 d, respectively, compared to 40±5 d for BPA alone and 31±4 d for irradiated controls. These data show that CED improved the radiobiological effectiveness of BD-EGF and lay the groundwork for future studies using combinations of boron delivery agents for NCT of EGFR(+) gliomas.

Boron neutron capture therapy (BNCT) is based on the preferential targeting of tumor cells with10 B and subsequent activation with thermal neutrons to produce a highly localized radiation. In theory, it is possible to selectively irradiate a tumor and the associated infiltrating tumor cells with large single doses of high-LET radiation while sparing the adjacent normal tissues. The mixture of high- and low-LET dose components created in tissue during neutron irradiation complicates the radiobiology of BNCT. Much of the complexity has been unravelled through a combination of preclinical experimentation and clinical dose escalation experience. Over 350 patients have been treated in a number of different facilities worldwide. The accumulated clinical experience has demonstrated that BNCT can be delivered safely but is still defining the limits of normal brain tolerance. Several independent BNCT clinical protocols have demonstrated that BNCT can produce median survivals in patients with glioblastoma that appear to be equivalent to conventional photon therapy. This review describes the individual components and methodologies required for effect BNCT: the boron delivery agents; the analytical techniques; the neutron beams; the dosimetry and radiation biology measurements; and how these components have been integrated into a series of clinical studies. The single greatest weakness of BNCT at the present time is non-uniform delivery of boron into all tumor cells. Future improvements in BNCT effectiveness will come from improved boron delivery agents, improved boron administration protocols, or through combination of BNCT with other modalites.

A phase I trial was designed to evaluate normal tissue tolerance to neutron capture therapy (NCT); tumor response was also followed as a secondary endpoint. Between July 1996 and May 1999, 24 subjects were entered into a phase I trial evaluating cranial NCT in subjects with primary or metastatic brain tumors. Two subjects were excluded due to a decline in their performance status and 22 subjects were irradiated at the MIT Nuclear Reactor Laboratory. The median age was 56 years (range 24-78). All subjects had a pathologically confirmed diagnosis of either glioblastoma (20) or melanoma (2) and a Karnofsky of 70 or higher. Neutron irradiation was delivered with a 15 cm diameter epithermal beam. Treatment plans varied from 1 to 3 fields depending upon the size and location of the tumor. The 10B carrier, L-p-boronophenylalanine-fructose (BPA-f), was infused through a central venous catheter at doses of 250 mg kg(-1) over 1 h (10 subjects), 300 mg kg(-1) over 1.5 h (two subjects), or 350 mg kg(-1) over 1.5-2 h (10 subjects). The pharmacokinetic profile of 10B in blood was very reproducible and permitted a predictive model to be developed. Cranial NCT can be delivered at doses high enough to exhibit a clinical response with an acceptable level of toxicity. Acute toxicity was primarily associated with increased intracranial pressure; late pulmonary effects were seen in two subjects. Factors such as average brain dose, tumor volume, and skin, mucosa, and lung dose may have a greater impact on tolerance than peak dose alone. Two subjects exhibited a complete radiographic response and 13 of 17 evaluable subjects had a measurable reduction in enhanced tumor volume following NCT.

Boron neutron capture therapy (BNCT) is a bimodal radiation therapy used primarily for highly malignant gliomas. Tissue-equivalent proportional counter (TEPC) microdosimetry has proven an ideal dosimetry technique for BNCT, facilitating accurate separation of the photon and neutron absorbed dose components, assessment of radiation quality and measurement of the BNC dose. A miniature dual-TEPC system has been constructed to facilitate microdosimetry measurements with excellent spatial resolution in high-flux clinical neutron capture therapy beams. A 10 B-loaded TEPC allows direct measurement of the secondary charged particle spectrum resulting from the BNC reaction. A matching TEPC fabricated from brain-tissue-equivalent plastic allows evaluation of secondary charged particle spectra from photon and neutron interactions in normal brain tissue. Microdosimetric measurements performed in clinical BNCT beams using these novel miniature TEPCs are presented, and the advantages of this technique for such applications are discussed.

An intercomparison of physical dosimetry methods used at the Massachusetts Institute of Technology (MIT) and Brookhaven National Laboratory was completed to enable retrospective analysis of BNCT trials. Measurements were performed under reference conditions pertinent to clinical irradiations at the epithermal neutron beam facility of the Brookhaven Medical Research Reactor (BMRR) using procedures developed at MIT during similar trials. Thermal neutron flux was determined from gold foil activation experiments and good agreement was found between the depth profiles measured in-phantom by the two groups. At a depth of 3.5 cm where the measured flux is greatest, the ratio of the MIT/BMRR measurements is 1.01+/-0.10 if the same reporting procedures are applied. Photon and fast neutron absorbed dose rates were assessed using ionization chambers with separate graphite and A-150 plastic walls. Measurement of the in-phantom photon depth dose component agreed favorably with that previously reported by the BMRR group using thermoluminescent dosimeters. At a depth of 3.5 cm the ratio of the MIT measurements to those made by the BMRR group was 0.89+/-0.12. In-air measurements of the fast neutron and photon absorbed dose rates agreed within the limits of experimental uncertainty. Additional studies were performed in the ellipsoidal water phantom regularly used for beam characterizations at MIT. No significant differences in the thermal neutron flux measured in either a solid PMMA cube or an ellipsoidal shaped water phantom were observed on the central axis of the beam. This study confirms the reproducibility and uniformity of dosimetry measurements performed by the two independent groups undertaking BNCT trials in the USA and provides the physical data necessary to compare BMRR treatment protocols with those applied at Harvard-MIT.

An open two-compartment model has been developed for predicting (10)B concentrations in blood after intravenous infusion of the l-p-boronophenylalanine-fructose complex (BPA-F) in humans and derived from studies of pharmacokinetics in 24 patients in the Harvard-MIT Phase I clinical trials of BNCT. The (10)B concentration profile in blood exhibits a characteristic rise during the infusion to a peak of approximately 32 microg/g (for infusion of 350 mg/kg over 90 min) followed by a biphasic exponential clearance profile with half-lives of 0.34 +/- 0.12 and 9.0 +/- 2.7 h, due to redistribution and primarily renal elimination, respectively. The model rate constants k(1), k(2) and k(3) are 0.0227 +/- 0.0064, 0.0099 +/- 0.0027 and 0.0052 +/- 0.0016 min(-1), respectively, and the central compartment volume of distribution, V(1), is 0.235 +/- 0.042 kg/kg. The validity of this model was demonstrated by successfully predicting the average pharmacokinetic response for a cohort of patients who were administered BPA-F using an infusion schedule different from those used to derive the parameters of the model. Furthermore, the mean parameters of the model do not differ for cohorts of patients infused using different schedules.

We have investigated the suitability of fluorinated hydrocarbon polytetrafluoroeth-ylene (PTFE) for application in the filter/moderator of an epithermal beam. We show that the neutronics performance, cost, and fabricability of Al and PTFE compares favor- ably with other good filter/moderator materials such as Al/Al2O3, Al/C, and Fluental ®. In this study, we have carried out irradiation tests to evaluate the performance of PTFE in the mixed gamma and fast neutron environment expected for the MIT Fission Con- verter epithermal neutron beam application. The irradiation stability was found to be more than adequate for the planned application.