We explored the potential for clinical research of computed tomography (CT) with monochromatic x-rays using the preclinical multiple energy computed tomography (MECT) system at the National Synchrotron Light Source. MECT has a fixed, horizontal fan beam with a subject apparatus rotating about a vertical axis; it will be used for imaging the human head and neck. Two CdWO4-photodiode array detectors with different spatial resolutions were used. A 10.5 cm diameter acrylic phantom was imaged with MECT at 43 keV and with a conventional CT (CCT) at 80 kVp: spatial resolution approximately equal to 6.5 line pairs (lp)/cm for both; slice height, 2.6 mm for MECT against 3.0 mm for CCT; surface dose, 3.1 cGy for MECT against 2.0 cGy for CCT. The resultant image noise was 1.5 HU for MECT against 3 HU for CCT. Computer simulations of the same images with more precisely matched spatial resolution, slice height and dose indicated an image-noise ratio of 1.4:1.0 for CCT against MECT. A 13.5 cm diameter acrylic phantom imaged with MECT at approximately 0.1 keV above the iodine K edge and with CCT showed, for a 240 micrograms I ml-1 solution, an image contrast of 26 HU for MECT and 13 and 9 HU for the 80 and 100 kVp CCT, respectively. The corresponding numbers from computer simulation of the same images were 26, 12, and 9 HU, respectively. MECT's potential for use in clinical research is discussed.

To improve beam penetration into a head allowing the treatment of deeper seated tumors, two neutron collimators were built sequentially and tested for use in the clinical boron neutron capture therapy (BNCT) program at the epithermal neutron irradiation facility of the Brookhaven Medical Research Reactor. The collimators were constructed from lithium-impregnated polyethylene, which comprises Li2CO3 powder (approximately 93% enriched isotopic 6Li) uniformly dispersed in polyethylene to a total 6Li content of 7.0 wt. %. The first collimator is 7.6 cm thick with a conical cavity 16 cm in diameter on the reactor core side tapering to 8 cm facing the patient's head. The second collimator is 15.2 cm thick with a conical cavity 20 cm in diameter tapering to 12 cm. A clinical trial of BNCT for patients with malignant brain tumors is underway using the first collimator. Results of phantom dosimetry and Monte Carlo computations indicate that the new 15.2 cm thick collimator will improve the neutron beam penetration. Thus, the second collimator was made and will be used in an upcoming clinical trial. In-air and in-phantom mixed-field dosimetric measurements were compared to Monte Carlo computations for both collimators. The deeper penetration is achieved but at a sacrifice in beam intensity. In this report, a performance comparison of both collimators regarding various fluence rate and absorbed dose distributions in a head model is presented and discussed.

The spectra of diagnostic x-ray beams were measured with a germanium semiconductor dectector. With this system it was possible to define the K-alpha-1, K-alpha-2, K-beta-2 characteristic peaks of the tungsten target. The effects of various filters on the beam using characteristic absorption edges to create a "bandpass" effect were studied. Gadolinium filtration of the diagnostic beam used for contrast studies selectively removed both higher energy photons (greater than 50 keV) and lower energy photons (less than 33 keV) thus enhancing contst for iodine and barium while substantially reducing radiation dose.

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.

In order to predict the efficacy of boronated compounds for neutron capture therapy (NCT), it is mandatory that the boron concentration in tissues be known. Various techniques for measurement of trace amounts of boron (1-100 ppm) are available, including chemical and physical procedures. Experience has shown that, with the polyhedral boranes and carboranes in particular, the usual colorimetric and spark emission spectroscopic methods are not reliable. Although these compounds may be traced with additional radiolabels, direct physical detection of boron by nondestructive methods is clearly preferable. Boron analysis via detection of the prompt-gamma ray from the 10B(n, alpha)7Li reaction has been shown to be a reliable technique. Two prompt-gamma facilities developed at Brookhaven National Laboratory are described. One, at the 60-MW high flux beam reactor, uses sophisticated beam extraction techniques to enhance thermal neutron intensity and reduce fast neutron and gamma contamination. The other was constructed at Brookhaven's 5-MW medical research reactor and uses conventional shielding and electronics to provide an "on-line" boron analysis facility adjacent to beams designed for NCT, thus satisfying one of the requisites for clinical application of this procedure. Technical restrictions attendant upon the synthesis and testing of boronated biomolecules often require the measurement of trace amounts of boron in extremely small (mg) samples. A track-etching technique capable of detecting ng amounts of boron in mg liquid or cell samples is described. Thus it is possible to measure the boron content in small amounts (mg samples) of antibodies, or boron uptake in cells grown in tissue culture.