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PubMed1996

Targeted drug delivery for boron neutron capture therapy.

PURPOSE: Boron neutron capture therapy (BNCT) is a form of radiochemotherapy that is becoming increasingly important for the treatment of malignant gliomas, malignant melanomas and other forms of cancer. Targeted delivery of boron to tumors is a critical prerequisite for successful BNCT. METHODS: Strategies that involve synthetic chemical approaches and biochemical and biophysical approaches are employed to meet this requirement. Compounds developed for targeting to tumors include borocaptate sodium (BSH) and p-boronophenylalanine (BPA) which are currently in clinical use. RESULTS: Boronated porphyrins, nucleosides, nucleotides and other boronated compounds show potentials as targeting molecules. Conjugation of boron compounds to macromolecules such as monoclonal antibodies, epidermal growth factor and dextran is also employed for active or passive tumor targeting. CONCLUSIONS: Boron delivery via microparticulate carriers such as liposomes, high density lipoproteins and microcapsules is also attractive for its potential application in BNCT.

Animals↗
PubMed1995

A novel approach to the microdosimetry of neutron capture therapy. Part I. High-resolution quantitative autoradiography applied to microdosimetry in neutron capture therapy.

A novel approach to the microdosimetry of neutron capture therapy has been developed using high-resolution quantitative autoradiography (HRQAR) and two-dimensional Monte Carlo simulation. This approach has been applied using actual cell morphology (nuclear and cytoplasmic cell structures) and the measured microdistribution of boron-10 in a transplanted murine brain tumor (GL261) containing p-boronophenylalanine (BPA) as the boron compound. The 2D Monte Carlo transport code for the alpha and 7Li charged particles from the 10B(n,alpha)7Li reactions has been developed as a surrogate to a full 3D approach to calculate a variety of different microdosimetric parameters. The HRQAR method and the surrogate 2D Monte Carlo approach are described in detail and examples of their use are presented.

Animals↗
PubMed1987

Preliminary study for application of anti-alpha-fetoprotein monoclonal antibody to boron-neutron capture therapy.

Boron-neutron capture therapy (BNCT) has been applied clinically, especially in brain-neuro surgery. We intended to expand the application of BNCT for the treatment of abdominal cancers and tried to determine whether MoAb (monoclonal antibody) against AFP (alpha-fetoprotein) could be useful tool to deliver boron-10 (10B) to AH-66 hepatoma cells for BNCT. Firstly, MoAb was boronated by mixing with 10B-compound (Cs2 10B12H11SH) by using N-succinimidyl 3(2-pyridyldithio)propionate (SPDP). Numbers of 10B atoms bound to an antibody molecule were in proportion to the dose of 10B-compound added, and maximum number of 10B atoms conjugated to an antibody molecule was approximately 1240. Secondly, using this boronated MoAb, 10B was delivered to AH-66 cells, and 11 X 10(9) 10B atoms were estimated to be on and/or in an AH-66 cell. After the irradiation with thermal neutron, boronated AH-66 cells showed decreasing uptake of [3H]TdR in proportion to the number of 10B atoms bound to and/or incorporated into the tumor cells. These results indicate that 10B atoms delivered by MoAb exert cytotoxic effect on AH-66 cells in a dose dependent manner by thermal neutron irradiation.

Animals↗
PubMed2001

Atomic emission method for total boron in blood during neutron-capture therapy.

BACKGROUND: Boron neutron-capture therapy (BNCT) is a drug-targeted binary radiotherapy for cancer. The (10)B capture of thermal neutrons induces secondary radiation within cells during irradiation. The most widely used boron carrier is 4-dihydroxyborylphenylalanine (BPA). The duration and timing of the irradiation is adjusted by monitoring (10)B concentrations in whole blood. METHODS: We developed a new method for boron determination that uses inductively coupled plasma atomic emission spectrometry (ICP-AES) and protein removal with trichloroacetic acid before analysis. This method was compared with the established but tedious inductively coupled plasma mass spectrometry (ICP-MS), which uses wet ashing as sample pretreatment. Erythrocyte boron concentrations were determined indirectly on the basis of plasma and whole blood boron concentrations and the hematocrit. The hematocrit was determined indirectly by measuring calcium concentrations in plasma and whole blood. RESULTS: Within- and between-day CVs were <5%. The recoveries for boron in whole blood were 95.6-96.2%. A strong correlation was found between results of the ICP-AES and ICP-MS (r = 0.994). Marked differences in plasma and erythrocyte boron concentrations were observed during and after infusion of BPA fructose complex. CONCLUSIONS: The present method is feasible, accurate, and one of the fastest for boron determination during BNCT. Our results indicate that it is preferable to determine boron in plasma and in whole blood. Indirect erythrocyte-boron determination thus becomes possible and avoids the impact of preanalytical confounding factors, such as the influence of the hematocrit of the patient. Such an approach enables a more reliable estimation of the irradiation dose.

Adult↗
PubMed2004

Fast neutron beams for boron neutron capture therapy?

In view of Boron Neutron Capture Enhanced Fast Neutron Therapy (BNCEFNT) of brain tumours, the spatial distributions of thermal flux and fast neutron plus photon dose were measured in a hydrogenous cylinder phantom under conditions varying with respect to neutron energy, field size, and irradiation technique. The behaviour of the ratio thermal fluence per unit total dose leads to the conclusion that an appreciable dose contribution from the BNC reaction can be expected only with low energies and large fields. Beams from small apertures (< 6 x 6 cm2) produce only marginal BNC dose contributions, and might gain therapeutic relevance only in combination with a very effective tumour-seeking Boron-10 carrier.

Boron Neutron Capture Therapy↗
PubMed1993

RBE in fast neutron therapy and in boron neutron capture therapy. A useful concept or a misuse?

In high-LET radiation therapy, radiation quality and radiation quality differences have to be taken into account and specified. In fast neutron therapy, an operational approach has been adopted which is based on the concept of "clinical RBE". The paper discusses the quantities of RBE (relative biological effectiveness), reference RBE and clinical RBE and their relationship and significance in radiation therapy. In particular, the difference between the well defined RBE in radiation biology and the clinical RBE which is based on the judgement of radiotherapists is elucidated and emphasized. The clinical RBE is based on the reference RBE and implicitly includes differences in physical selectivity of the irradiation beams and clinical experience. The particular aspects of radiation quality in boron neutron capture therapy (BNCT) are due to the poor penetration of the primary beam, the inhomogeneity of the spatial distribution of 10B nuclides in the irradiated tissue and the short range of the alpha-particles emitted after neutron capture in 10B. The related problems in accounting for radiation quality in BNCT and in the applicability of the clinical RBE concept are discussed.

Boron Neutron Capture Therapy↗
PubMed1994

[Neutron capture therapy for cancer].

Boron neutron capture therapy (BNCT) is a selective radiotherapy using boron-10 which absorbs thermal neutrons and releases high LET alpha particles by 10B(n, alpha)7Li reaction. In this paper, the present status of BNCT for malignant melanoma was introduced. As a melanoma-targetting 10B-compound, 10B-paraboronophylalanine (BPA) was used. It was administered by multiple subcutaneous injection or intravenous drip infusion. We adopted the maximum tolerance dose to the skin as a therapeutic dose regardless of the tumor 10B concentration, because we cannot directly measure it. For this purpose, an approximation of skin concentration was made using blood data just after the administration. We treated 14 melanoma patients in this way and obtained good local control of the tumor with tolerable skin reaction. More experience with logical analysis and basic research is necessary for further development of this therapy.

Boron Compounds↗
PubMed2004

A shielding design for an accelerator-based neutron source for boron neutron capture therapy.

Research in boron neutron capture therapy (BNCT) at The Ohio State University Nuclear Engineering Department has been primarily focused on delivering a high quality neutron field for use in BNCT using an accelerator-based neutron source (ABNS). An ABNS for BNCT is composed of a proton accelerator, a high-energy beam transport system, a (7)Li target, a target heat removal system (HRS), a moderator assembly, and a treatment room. The intent of this paper is to demonstrate the advantages of a shielded moderator assembly design, in terms of material requirements necessary to adequately protect radiation personnel located outside a treatment room for BNCT, over an unshielded moderator assembly design.

Boron Neutron Capture Therapy↗
PubMed1999

Boron neutron capture therapy (BNCT): implications of neutron beam and boron compound characteristics.

The potential efficacy of boron neutron capture therapy (BNCT) for malignant glioma is a significant function of epithermal-neutron beam biophysical characteristics as well as boron compound biodistribution characteristics. Monte Carlo analyses were performed to evaluate the relative significance of these factors on theoretical tumor control using a standard model. The existing, well-characterized epithermal-neutron sources at the Brookhaven Medical Research Reactor (BMRR), the Petten High Flux Reactor (HFR), and the Finnish Research Reactor (FiR-1) were compared. Results for a realistic accelerator design by the E. O. Lawrence Berkeley National Laboratory (LBL) are also compared. Also the characteristics of the compound p-Boronophenylaline Fructose (BPA-F) and a hypothetical next-generation compound were used in a comparison of the BMRR and a hypothetical improved reactor. All components of dose induced by an external epithermal-neutron beam fall off quite rapidly with depth in tissue. Delivery of dose to greater depths is limited by the healthy-tissue tolerance and a reduction in the hydrogen-recoil and incident gamma dose allow for longer irradiation and greater dose at a depth. Dose at depth can also be increased with a beam that has higher neutron energy (without too high a recoil dose) and a more forward peaked angular distribution. Of the existing facilities, the FiR-1 beam has the better quality (lower hydrogen-recoil and incident gamma dose) and a penetrating neutron spectrum and was found to deliver a higher value of Tumor Control Probability (TCP) than other existing beams at shallow depth. The greater forwardness and penetration of the HFR the FiR-1 at greater depths. The hypothetical reactor and accelerator beams outperform at both shallow and greater depths. In all cases, the hypothetical compound provides a significant improvement in efficacy but it is shown that the full benefit of improved compound is not realized until the neutron beam is fully optimized.

Biophysics↗
PubMedDate not supplied

A critical assessment of boron neutron capture therapy: an overview.

Boron neutron capture therapy (BNCT) is based on the nuclear reaction that occurs when boron-10 is irradiated with neutrons of the appropriate energy to produce high-energy alpha particles and recoiling lithium-7 nuclei. BNCT has been used clinically to treat patients with high-grade gliomas, and a much smaller number with primary and metastatic melanoma. The purpose of this special issue of the Journal of Neuro-Oncology is to provide a critical and realistic assessment of various aspects of basic and clinical BNCT research in order to better understand its present status and future potential. Topics that are covered include neutron sources, tumor-targeted boron delivery agents, brain tumor models to assess therapeutic efficacy, computational dosimetry and treatment planning, results of clinical trails in the United States, Japan and Europe, pharmacokinetic studies of sodium borocaptate and boronophenylalanine (BPA), positron emission tomography imaging of BPA for treatment planning, and finally an overview of the challenges and problems that must be faced if BNCT is to become a useful treatment modality for brain tumors. Clinical studies have demonstrated the safety of BNCT. The next challenge is an unequivocal demonstration of therapeutic efficacy in one or more of the clinical trails that either are in progress or are planned over the next few years.

Animals↗
PubMedDate not supplied

Prediction of boron concentrations in blood from patients on boron neutron capture therapy.

BACKGROUND: In boron neutron capture therapy, blood boron concentration is the key factor to calculate radiation dose, however, blood sampling is difficult during neutron irradiation. MATERIALS AND METHODS: The prediction of blood boron concentrations for BNCT treatment planning has been prospectively investigated using patient data obtained at first craniotomy after the infusion of a low dose of sodium undecahydroclosododecaborate. RESULTS: The boron biodistribution data showed a biexponential pharmacokinetic profile. If the final boron concentration at 6 or 9 hours after the end of the infusion is within the 95% confidence interval of the prediction, direct prediction from biexponential fit will reduce the error of blood boron concentrations during irradiation to around 6%. CONCLUSION: Actual boron concentrations during BNCT were reasonably and accurately predictable from the test data.

Adult↗
PubMed1994

Concomitant boron-neutron capture therapy during fast-neutron irradiation of a rat glioma.

PURPOSE: Fast-neutron irradiation and boron-neutron capture therapy (BNCT) have been independently investigated as treatments for malignant disease. This study tested the feasibility of enhancing fast-neutron irradiation with concomitant BNCT. MATERIALS AND METHODS: Seventeen male Fisher rats, each weighing 180-200 g and bearing 36B10 gliomas, were irradiated with graded doses of fast-neutron radiation. Half of the animals received an L-para-boronophenylalanine (BPA) fructose complex prior to treatment. An in vitro colony-forming assay was used to measure surviving fraction. RESULTS: A significantly lower surviving fraction was noted in the tumors from the BPA group compared with those receiving neutrons alone at the three lower neutron doses (P < .005). With use of a linear quadratic curve fit of cell survival, the dose modifying factor was 1.32 at the 0.10 surviving fraction. Mean tumor boron concentration was 68.4 micrograms/g. CONCLUSIONS: BNCT enhancement of fast-neutron irradiation is feasible in an in vivo tumor system.

Animals↗
PubMed2003

Computational assessment of improved cell-kill by gadolinium-supplemented boron neutron capture therapy.

Potential improvement in neutron capture therapy (NCT) by utilizing both 157Gd and 10B is assessed considering two parameters calculated in transport models in MCNP4B, the dose to quiescent cells and the therapeutic ratio. Improved sterilization of quiescent or more generally non-uptaking cells is demonstrated with the addition of 157Gd to conventional 10B loading. The improved dose delivery to non-uptaking cells from concurrent administration of 157Gd and 10B is weighed against a second index, degradation in the therapeutic ratio resulting from the longer interaction lengths of the 157Gd capture products. Optimal concentrations of 157Gd are determined considering varying assumptions for boron uptake levels and selectivity. By analysing the dosimetry results of varying 157Gd concentrations applied concurrently with BPA-delivered boron in NCT, this work seeks to determine a balance between the high tumour-specific dose provided by BPA and the high dose to quiescent cells provided by potential gadolinium agents. Depending upon the assumptions for drug specificity, tumour size and fraction of quiescent cells, NCT with low levels of 157Gd (125 microg g(-1)) supplementing 10B loadings was shown to be superior to treatments applying 10B alone.

Apoptosis↗
PubMedDate not supplied

Neutron-induced gamma dose from a reactor beam filter for boron neutron capture therapy.

For the boron neutron capture therapy (NCT) of deep-seated metastatic melanoma, an epithermal (up to a few keV energy) neutron beam from a reactor horizontal facility could be useful if the inherent contamination from fast neutrons and gamma rays could be minimised. Calculations for ANSTO's 10 MW research reactor HIFAR have shown that, even though a filter material such as AlF3 attenuates the fast neutron dose, the beam quality improvement is counteracted by a relative increase in the gamma dose because of the gammas arising from neutron captures in the filter material, particularly the aluminium. The aluminium gammas, most of which arise from thermal neutron capture, are hard and cannot be attenuated by lead or bismuth without comparable attenuation of the epithermal neutron flux. Addition of an absorber such as 6Li to the AlF3 filter was investigated as a means of reducing the hard gamma dose, but the improvement in beam quality was small and at considerable cost to dose intensity. Dose characteristics calculations confirmed the superiority of a tangential beam over a radial beam with better results from an unfiltered tangential beam than from an AlF3 filter in a radial beam. This study showed conclusively that assessments of filter assemblies based on the effect of individual components on either the neutron or gamma dose in isolation are inadequate. In assessing any epithermal neutron filter, thermal neutron shield, and gamma shield combination, the total effect of each on the neutron, gamma, and boron-10 dose must be considered.

Boron↗
PubMed1990

[Principles of therapy with fission neutrons and boron neutron capture therapy for radioresistant head-neck malignancies].

Neutron therapy has proven to be clinically useful in cases of advanced, slow-growing radioresistant head and neck carcinoma. Therapeutic effects might be based on direct DNA damaging and thus immediate cell-killing, on the generation of free oxygen radicals and, among others, on the fact that heavy particle radiation is said to be less dependent on the presence of oxygen than gamma rays, i.e. on a lower oxygen enhancement ratio (OER). The smaller difference in reaction between oxygenated and nonoxygenated cells could entail advantages as well as disadvantages, depending on the characteristics of the tumor cell population and of the normal tissue. It is therefore essential to select patients and tumours with an expectedly high therapeutic gain factor. Fission neutrons for tumour therapy: As evaluated by several in vitro and in vivo studies (11/13) the biological efficiency (RBE) of the RENT (Reactor Neutron Therapy) beam in Munich seems to be among the highest of all clinically used neutron beams. For a single dose range between 2 and 8 Gy the RBE for chronic radiation damage is relatively small (2). Consequently, patients with recurrent or metastatic carcinomas of the head and neck are treated with a single dose of 200-250 cGy after previous surgery and/or combined radiochemotherapy. The main limitation of fission neutrons is the small penetration depth. Possibilities of clinical implementation of boron neutron capture therapy (BNCT) in otorhinolaryngology: In near surface tumours it is possible to administer high doses of 10boron not selectively, i.e. no selective tumour-seeking compound is needed. Animal experiments with intratumoural injection of 10boron glycine have shown a strong effect on tumour growth delay (18).(ABSTRACT TRUNCATED AT 250 WORDS)

Boron Compounds↗
PubMed2003

Relative biological effectiveness and tolerance dose of fission neutrons in canine skin for a potential combination of neutron capture therapy and fast-neutron therapy.

To investigate the potential efficacy of fission neutrons from a fast-neutron reactor for the treatment of radioresistant tumors, the relative biological effectiveness (RBE) and tolerance dose of fission neutrons in canine skin were determined. The forelimbs of 34 healthy mongrel dogs received a single dose of fission neutrons (5.6, 6.8, 8.2, 9.6 or 11 Gy) or 137Cs gamma rays (10, 15, 20, 25 or 30 Gy). Based on observations of radiodermatitis for each radiation, the single-fraction RBE of fission neutrons in the sixth month was calculated as approximately 3. The tolerance doses of fission neutrons and gamma rays, defined as the highest doses giving no moist desquamation on the irradiated skin in the recovery phase, were estimated as 7.6 Gy and 20 Gy, respectively. The tolerance dose of 7.6 Gy of fission neutrons included 5.0 Gy of fast neutrons possessing high anti-tumor effects and 1.4 x 10(12) n/cm2 of thermal neutrons, which could be applicable to neutron capture therapy (NCT). The combination of fast-neutron therapy and NCT using a fast-neutron reactor might be useful for the treatment of radioresistant tumors.

Animals↗