A convolution model for energy transport in a therapeutic fast neutron beam

A three-dimensional model has been proposed that uses Monte Carlo and fast Fourier transform convolution techniques to calculate the dose distribution from a fast neutron beam. This method transports scattered neutrons and photons in the forward, lateral, and backward directions and protons, electrons, and positrons in the forward and lateral directions by convolving energy spread kernels with initial interaction available energy distributions. The primary neutron and photon spectrums have been derived from narrow beam attenuation measurements. The positions and strengths of the effective primary neutron, scattered neutron, and photon sources have been derived from dual ion chamber measurements. The size of the effective primary neutron source has been measured using a copper activation technique. Heterogeneous tissue calculations require a weighted sum of two convolutions for each component since the kernels must be invariant for FFT convolution. Comparisons between calculations and measurements were performed for several water and heterogeneous phantom geometries. ^

THE CALIBRATION AND IMPLEMENTATION OF CR-39 NUCLEAR TRACK DETECTOR MATERIAL AS A FAST NEUTRON MICRODOSIMETER

A detailed microdosimetric characterization of the M. D. Anderson 42 MeV (p,Be) fast neutron beam was performed using the techniques of microdosimetry and a 1/2 inch diameter Rossi proportional counter. These measurements were performed at 5, 15, and 30 cm depths on the central axis, 3 cm inside, and 3 cm outside the field edge for 10 $\times$ 10 and 20 $\times$ 20 cm field sizes. Spectra were also measured at 5 and 15 cm depth on central axis for a 6 $\times$ 6 cm field size. Continuous slowing down approximation calculations were performed to model the nuclear processes that occur in the fast neutron beam. Irradiation of the CR-39 was performed using a tandem electrostatic accelerator for protons of 10, 6, and 3 MeV and alpha particles of 15, 10, and 7 MeV incident energy on target at angles of incidence from 0 to 85 degrees. The critical angle as well as track etch rate and normal incidence diameter versus linear energy transfer (LET) were obtained from these measurements. The bulk etch rate was also calculated from these measurements. Dose response of the material was studied, and the angular distribution of charged particles created by the fast neutron beam was measured with CR-39. The efficiency of CR-39 was calculated versus that of the Rossi chamber, and an algorithm was devised for derivation of LET spectra from the major and minor axis dimensions of the observed tracks. The CR-39 was irradiated in the same positions as the Rossi chamber, and the derived spectra were compared directly. ^

MEASUREMENT OF TUMOR BLOOD FLOW FOLLOWING NEUTRON IRRADIATION (ACTIVATION)

Clinical oncologists and cancer researchers benefit from information on the vascularization or non-vascularization of solid tumors because of blood flow's influence on three popular treatment types: hyperthermia therapy, radiotherapy, and chemotherapy. The objective of this research is the development of a clinically useful tumor blood flow measurement technique. The designed technique is sensitive, has good spatial resolution, in non-invasive and presents no risk to the patient beyond his usual treatment (measurements will be subsequent only to normal patient treatment).^ Tumor blood flow was determined by measuring the washout of positron emitting isotopes created through neutron therapy treatment. In order to do this, several technical and scientific questions were addressed first. These questions were: (1) What isotopes are created in tumor tissue when it is irradiated in a neutron therapy beam and how much of each isotope is expected? (2) What are the chemical states of the isotopes that are potentially useful for blood flow measurements and will those chemical states allow these or other isotopes to be washed out of the tumor? (3) How should isotope washout by blood flow be modeled in order to most effectively use the data? These questions have been answered through both theoretical calculation and measurement.^ The first question was answered through the measurement of macroscopic cross sections for the predominant nuclear reactions in the body. These results correlate well with an independent mathematical prediction of tissue activation and measurements of mouse spleen neutron activation. The second question was addressed by performing cell suspension and protein precipitation techniques on neutron activated mouse spleens. The third and final question was answered by using first physical principles to develop a model mimicking the blood flow system and measurement technique.^ In a final set of experiments, the above were applied to flow models and animals. The ultimate aim of this project is to apply its methodology to neutron therapy patients. ^