Chandrasekhar Kota

Simultaneous macro and micro dosimetry with MOSFETs

The application of MOSFET dosimeters in complicated mixed radiation fields for measurement of absorbed dose distribution in tissue equivalent phantoms has been studied. The spectra of secondary charged particles have been measured simultaneously with average absorbed doses by the same MOSFET dosimeter. A good correlation has been observed between neutron depth dose distribution in a water phantom obtained using MOSFETs in integral mode and a tissue equivalent (T.E.) ionisation chamber. Such MOSFET dosimeters are a promising tool for micro-macro dosimetry in Boron Neutron Capture Therapy (BNCT) and Fast Neutron Therapy (FNT). Paired MOSFETs with one of the dosimeters covered by /sup 10/B have been applied for measuring of average boron dose distribution and microdosimetric spectra due to alpha particles and /sup 7/Li ions throughout a perspex phantom exposed in the epithermal neutron beam at the Brookhaven Medical Research Reactor (BMRR).

Miniature tissue‐equivalent proportional counters for BNCT and BNCEFNT dosimetry

A dual miniature tissue-equivalent proportional counter (TEPC) system has been developed to facilitate microdosimetry for Boron Neutron Capture Therapy (BNCT). This system has been designed specifically to allow the analysis of the single event charged particle spectrum in phantom in high intensity BNCT beams and to provide this microdosimetric information with excellent spatial resolution. Paired A-150 and 10B-loaded A-150 TEPCs with 12.3 mm3 collecting volumes have been constructed. These TEPCs allow more accurate neutron dosimetry than current techniques, offer a direct measure of the boron neutron capture dose, and provide a framework for predicting the biological effectiveness of the absorbed dose. Design aspects and characterization of these detectors are reviewed, along with an exposition of the advantages of microdosimetry using these detectors over conventional dosimetry methods. In addition, the utility of this technique for boron neutron capture enhancement of fast neutron therapy (BNCEFNT) is discussed.

A microdosimetric study of the dose enhancement in a fast neutron beam due to boron neutron capture

The dose enhancement due to the 10B thermal neutron capture reaction in a fast neutron therapy beam of mean energy 20.4 MeV has been measured using a microdosimetric technique with paired Rossi tissue-equivalent-plastic proportional counters. The enhancement in a simulated tissue volume of 2 mu m diameter for a concentration of 50 ppm of 10B has been measured in 10 cm*10 cm and 15 cm*15 cm fields at various depths in a water phantom. The physical dose enhancement due to the high LET alpha particles and Li recoil ions ranges from approximately 1% to approximately 2% depending on the depth and field size. Correction factors for the absence of 10B in the counter gas and for the RBE advantage of the enhanced dose have been estimated to be*1.25 and*2, respectively. The total dose enhancement using these factors ranges from approximately 2.5% to approximately 5%.

Use of low-pressure tissue equivalent proportional counters for the dosimetry of neutron beams used in BNCT and BNCEFNT

The absorbed dose in a phantom or patient in boron neutron capture therapy (BNCT) and boron neutron capture enhanced fast neutron therapy (BNCEFNT) is deposited by gamma rays, neutrons of a range of energies and the 10B reaction products. These dose components are commonly measured with paired (TE/Mg) ion chambers and foil activation technique. In the present work, we have investigated the use of paired tissue equivalent (TE) and TE+ l0B proportional counters as an alternate and complementary dosimetry technique for use in these neutron beams. We first describe various aspects of counter operation, uncertainties in dose measurement, and interpretation of the data. We then present measurements made in the following radiation fields: An epithermal beam at the University of Birmingham in the United Kingdom, a d(48.5) + Be fast neutron therapy beam at Harper Hospital in Detroit, and a 252Cf radiation field. In the epithermal beam, our measured gamma and neutron dose rates compare very well with the values calculated using Monte Carlo methods. The measured 10B dose rates show a systematic difference of approximately 35% when compared to the calculations. The measured neutron+gamma dose rates in the fast neutron beam are in good agreement with those measured using a calibrated A-150 TEP (tissue equivalent plastic) ion chamber. The measured 10B dose rates compare very well with those measured using other methods. In the 252Cf radiation field, the measured dose rates for all three components agree well with other Monte Carlo calculations and measurements. Based on these results, we conclude that the paired low-pressure proportional counters can be used to establish an independent technique of dose measurement in these radiation fields.

Experimental determination of the thermal neutron flux around two different types of high intensity 252Cf sources.

The application of neutron emitting radioisotopes in brachytherapy facilitates the use of the higher biological effectiveness of neutrons compared to photons in treating some cancers. Different types of high intensity 252Cf sources are in use for the treatment of different cancers. To improve the therapy of bulky tumors the dose can be augmented by the additional use of the boron capture reaction of thermal neutrons. This requires information about the thermal neutron dose component around the Cf source. In this work, a Mg/Ar-ionization chamber internally coated with 10B was used to measure the thermal neutrons. These measurements were performed on two different 252Cf sources, one in use in the Gershenson Radiation Oncology Center at Harper Hospital in Detroit, MI, and one at the University Hospital of Chiang Mai in Chiang Mai, Thailand. The results of these measurements are compared and indicate that the differences in the construction of the sources influence the thermal dose component.

A conducting plastic simulating brain tissue.

A new conducting plastic has been composed which accurately simulates the photon and neutron absorption properties of brain tissue. This tissue-equivalent (TE) plastic was formulated to match the hydrogen and nitrogen constituents recommended by ICRU Report #44 for brain tissue. Its development was initiated by the inability of muscle tissue-equivalent plastic to closely approximate brain tissue with respect to low-energy neutron interactions. This new plastic is particularly useful as an electrode in TE dosimetry devices for boron neutron capture therapy (BNCT), which utilizes low-energy neutrons for radiotherapy of the brain. Absorbed dose measurements in a clinical BNCT beam using a proportional counter constructed from this TE plastic show good agreement with Monte Carlo calculations.

Characterization of miniature tissue-equivalent proportional counters for neutron radiotherapy applications

A miniature tissue-equivalent proportional counter (TEPC) system has been developed to facilitate microdosimetric measurements in high-flux mixed fields. Counters with collecting volumes of 12.3 and 2.65 mm3 have been constructed using various tissue-equivalent wall materials, including those loaded with 10B for evaluation of the effects of the boron neutron capture reaction. These counters provide a measure of both the absorbed dose and associated radiation quality, allowing an assessment of the utility and relative effectiveness of various neutron radiotherapy techniques such as boron neutron capture therapy (BNCT), boron neutron capture enhanced fast neutron therapy (BNCEFNT) and intensity modulated neutron radiotherapy (IMNRT). An evaluation of the physical parameters affecting the measured microdosimetric spectrum, the gas multiplication characteristics and the measurement of absorbed dose is presented. In addition, important aspects of the calibration and low energy extrapolation techniques for the microdosimetric spectrum are provided.

A measurement of the fast-neutron sensitivity of a Geiger - Müller detector in the pulsed neutron beam from a superconducting cyclotron

The kU value of a commercially available miniature energy compensated Geiger-Müller (GM) detector has been determined using the modified lead attenuation method of Hough. The measurements were made in a d(48.5)-Be neutron beam produced by the superconducting cyclotron based neutron therapy facility at Harper Hospital. The unique problems associated with making measurements in a 2 ms duration pulsed beam with a 20% duty cycle are discussed. The beam monitoring system, which allows the beam pulse shape at low beam intensities to be measured, is described. By gating the GM output with a discriminator pulse derived from the beam pulse shape, the gamma-ray count rates and dead-time corrections within the 2 ms pulse and between pulses can be measured separately. The kU value of (0.0245 +/- 0.0015) determined for this GM detector is consistent with the values measured by other workers with identical and similar detectors in neutron beams with comparable, but not identical, neutron spectra.

Microdosimetric intercomparison of BNCT beams at BNL and MIT

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.

Paired Mg and Mg(B) ionization chambers for the measurement of boron neutron capture dose in neutron beams.

The use of the boron neutron capture (BNC) reaction to provide a dose enhancement in fast neutron therapy is currently under investigation at the Gershenson Radiation Oncology Center of Harper Hospital in Detroit, MI. The implementation of this treatment modality presents unique challenges in dosimetry. In addition to the measurement of photon and neutron doses in the mixed field, a measure of the thermal neutron flux and the associated boron neutron capture dose throughout the treatment volume is desired. A pair of small-volume magnesium ionization chambers has been constructed with the aim of providing this information. One of the chambers, denoted the Mg(B) chamber, is lined with a boron-loaded foil. The ionization response of this chamber has been calibrated in terms of BNC dose per ppm loading of 10B. These paired chambers can be used to map the local BNC response in neutron beams. From this data and an estimation of the boron concentration in the tumor and normal tissue, the boron neutron capture enhancement may be evaluated.