Photon Dose Equivalents Research Articles

Tolerance of the normal canine brain to epithermal neutron irradiation in the presence of p-boronophenylalanine.

Twelve normal dogs underwent brain irradiation in a mixed-radiation, mainly epithermal neutron field at the Brookhaven Medical Research Reactor following intravenous infusion of 950 mg of 10B-enriched BPA/kg as its fructose complex. The 5 x 10 cm irradiation aperture was centered over the left hemisphere. For a subgroup of dogs reported previously, we now present more detailed analyses including dose-volume relationships, longer follow-ups, MRIs, and histopathological observations. Peak doses (delivered to 1 cm3 of brain at the depth of maximum thermal neutron flux) ranged from 7.6 Gy (photon-equivalent dose: 11.8 Gy-Eq) to 11.6 Gy (17.5 Gy-Eq). The average dose to the brain ranged from 3.0 Gy (4.5 Gy-Eq) to 8.1 Gy (11.9 Gy-Eq) and to the left hemisphere, 6.6 Gy (10.1 Gy-Eq) to 10.0 Gy (15.0 Gy-Eq). Maximum tolerated 'threshold' doses were 6.7 Gy (9.8 Gy-Eq) to the whole brain and 8.2 Gy (12.3 Gy-Eq) to one hemisphere. The threshold peak brain dose was 9.5 Gy (14.3 Gy-Eq). At doses below threshold, some dogs developed subclinical MRI changes. Above threshold, all dogs developed dose-dependent MRI changes, neurological deficits, and focal brain necrosis.

The Direct Ion Storage Dosemeter for the Measurement of Photon, Beta and Neutron Dose Equivalents

The physical basis for the DIS (Direct Ion Storage) dosemeter is reviewed along with some of the issues associated with the expected long-term stability and reliability of the MOSFET structure under various operating conditions. Recent data from tests performed to assess the dosimetric accuracy, stability and reliability of the first commercially produced units for photon and beta radiation is presented. Special detectors have been developed for neutron dosimetry. Their design may be optimised either for a flat energy response or for a very high sensitivity at thermal neutron energy. Results of test irradiations in neutron fields from thermal up to 45 MeV neutron energy are presented with indication of dependence of the detection limit for neutrons on the photon dose for various dosemeter designs.

Postneoadjuvant hormone PSA levels and prognosis in locally advanced prostate cancer

Objectives. To determine whether the response to hormonal therapy before radiation predicts the rate of biochemical relapse in patients with locally advanced prostate cancer. Methods. Between October 1991 and December 1997, 105 patients with locally advanced adenocarcinoma of the prostate received radiotherapy in two dose-escalation studies. Sixty-seven patients received neoadjuvant hormonal therapy. The mean and median duration of hormonal therapy before radiotherapy was 4 months each. All treatments were designed using three-dimensional conformal therapy. The total dose to the gross tumor volume ranged from 73 to 87 Gy in 2 Gy per fraction photon equivalent dose. The median follow-up time was 30 months (range 1 to 66). Results. The median prostate-specific antigen (PSA) nadir after neoadjuvant hormonal therapy but before radiotherapy was 1.7 ng/mL (range less than 0.05 to 71.2). The median nadir after radiation for patients who did and did not receive neoadjuvant androgen deprivation was 0.25 ng/mL (range less than 0.05 to 6.2) and 1.35 ng/mL (range 0.08 to 10), respectively. Median time to achieve nadir was 6 months (range 1 to 42) with and 12 months (range 1 to 48) without hormonal therapy. There was no significant difference in the rate of biochemical failure for patients with a posthormone (before irradiation) PSA nadir less than 1 ng/mL versus 1 ng/mL or greater (overall P = 0.9). However, there was a significant difference in biochemical no evidence of disease rates between those with a PSA nadir less than 1 ng/mL and those with a PSA nadir of 1 ng/mL or greater after radiation (63% versus 22% at 3 years, overall P <0.001). Conclusions. Our data showed that the initial response to hormonal therapy before radiation, as indicated by the PSA level, did not impact on the rate of recurrence. However, the time to reach nadir and the absolute nadir level achieved were lower in patients who did receive hormonal therapy.

Design for an accelerator-based orthogonal epithermal neutron beam for boron neutron capture therapy.

This paper is concerned with the proposed Birmingham accelerator-based epithermal neutron beam for boron neutron capture therapy (BNCT). In particular, the option of producing a therapy beam at an orthogonal direction to the incoming protons is considered. Monte Carlo radiation transport simulations, both with and without a head phantom, have shown that an orthogonal beam geometry is not only acceptable but is indeed beneficial, in terms of a lower mean neutron energy and an enhanced therapeutic ratio for the same useful neutron fluence in the therapy beam. Typical treatment times for various beam options have been calculated, and range from 20 to 48 min with a 5 mA beam of 2.8 MeV protons, if the maximum photon-equivalent dose delivered to healthy tissue is to be 12.6 Gy Eq. The effects of proton beam diameter upon the therapy beam parameters have also been considered.

In vivo neutron activation analysis of sodium and chlorine in tumor tissue after fast neutron therapy

In 12 patients with recurrences and metastases of different primaries (head and neck cancer, breast cancer, malignant melanoma, and osteosarcoma) who were treated with reactor fission neutrons the photon emission of irradiated tissue was measured after each radiotherapy fraction. Spectral analyses of the decay rates resulted in data for the exchange of sodium (Na) and chlorine (Cl) between the irradiated tissue and the body. About 60% of Na and Cl exchanged rapidly with a turnover half-life of 13 +/- 2 min. New defined mass exchange rates for Na and Cl amount to an average of 0.8 mval/min/kg of soft tissue. At the beginning of radiotherapy the turnover of the electrolytes in tissues with large tumor volumes was about twice that in tissues with small tumor volumes. Depending on the dose, neutron therapy led in all cases to variation in the metabolism. A maximum of Cl exchange and a minimum of Na exchange occurred after 10 Gy of neutrons (group of six previously untreated patients) or after 85 Gy (photon equivalent dose) of combined photon-neutron therapy. A significant increase in non-exchangeable fraction of Na from about 40 to 80% was observed in three tumors after a neutron dose of 10 Gy administered in five fractions correlated with a rapid reduction of tissue within 4 weeks after end of therapy. These results demonstrate for the first time the local response of the electrolyte metabolism to radiotherapy.

Determination of Neutron and Photon Dose Equivalent at Workplaces in Nuclear Facilities in Sweden (A joint SSI-EURADOS Comparison Exercise)

The accuracy of the dosimetry (personal and area monitoring) has been investigated inside the containment buildings of two pressurised water reactors and in the environment of a transport cask with spent fuel elements. The dosimetric quantities of main interest were ambient dose equivalent and personal dose equivalent, as operational quantities, and effective dose equivalent, as limit quantity. They were either directly determined by means of instruments and dosemeters or calculated from the experimentally determined directional spectral neutron fluences. Several groups employing different techniques carried out the investigations. The comprehensive comparison exercise has shown that a well specified Bonner sphere spectrometer and a set of proton recoil detectors are well-suited to determine the neutron field for reference purposes. The neutron fields were rather soft with up to 70% of the neutron dose equivalent contributed by neutrons of energies less than 100 keV. On account of their energy dependence, rem counters overestimate, and TEPC systems underestimate, the neutron dose equivalent, even if calibrated in the field of a D2O-moderated 252Cf source. Only a recently developed active dosemeter, based on superheated drop detectors (only used outside the containment), measured the ambient dose equivalent in good agreement with the results obtained with Bonner spheres). Measurements with several personal dosemeters irradiated on a phantom were used to estimate the directional properties of the neutron field. This is required for the calculation of personal and effective dose equivalent values. Some personal dosemeters gave dose equivalent results in satisfactory agreement (±20%) with reference values. In any case the measured dose equivalent values were conservative estimates of the corresponding effective dose equivalent values. The application of the new recommendations of the International Commission on Radiological Protection (ICRP) will result in about 50% higher values of neutron ambient dose equivalent. In the determination of the photon ambient dose equivalent, which amounts to about 30% of the total dose equivalent, differences up to 50% were observed between the readings of GM counters and TEPC's, chiefly caused by high energy photons present in the containment building.

Determination of Neutron and Photon Dose Equivalent at Workplaces in Nuclear Facilities in Sweden (A joint SSI-EURADOS Comparison Exercise)

Determination of Neutron and Photon Dose Equivalent at Workplaces in Nuclear Facilities in Sweden (A joint SSI-EURADOS Comparison Exercise)

A proposed four-element neutron-photon-beta thermoluminescence dosimeter.

It is common practice for a worker exposed to a mixed field with neutrons to wear both a photon-beta dosimeter and a neutron dosimeter. In this study, a thermoluminescence dosimeter has been designed and is proposed for use in mixed fields. The maximum applicable ranges of the mixed field can have photons with unknown energy from 20 keV to 2 MeV, betas with unknown energy from 147Pm to 90Sr-Y, and neutrons of known energy from thermal to 15 MeV. This proposed dosimeter (a combination of Harshaw beta-gamma thermoluminescence dosimeter and albedo neutron thermoluminescence dosimeter) has an advantage of using a minimum number of thermoluminescence dosimeter elements (therefore, making it less costly) to measure the dose equivalents in a mixed field of neutron, photon, and beta radiation. The basic dosimeter design consists of four thermoluminescence elements of TLD-600 and TLD-700 with different filtrations. Using the high-temperature peak methodology for TLD-600 and a filtration algorithm, the neutron, photon, and beta dose equivalents in a mixed field can be determined. The design, detection principle, and three dosimetric algorithms for three versions of the basic design of the four-element dosimeter are presented and discussed. The work that is required for the proposed dosimeter to be usable when it is made is also presented.

Dose Rate Constants for New Dose Quantities

Conceptual changes and new quantities made it necessary to reassess dose rate quantities. Calculations of the dose rate constant were carried out for air kerma, ambient dose equivalent and directional dose equivalent. The number of radionuclides is more than 200. The threshold energy is selected as 20 keV for the dose equivalent constants. The dose rate constant for the photon equivalent dose as used mainly in German speaking countries as a temporary quantity is also included.

Sensitivity of helium beam‐modulator design to uncertainties in biological data

The goal in designing beam-modulating devices for heavy charged-particle therapy is to achieve uniform biological effects across the spread-peak region of the beam. To accomplish this, the linear-quadratic model for cell survival has been used to describe the biological response of the target cells to charged-particle radiation. In this paper, the sensitivity of the beam-modulator design in the high-dose region to the values of the linear-quadratic variables alpha and beta has been investigated for a 215-MeV/u helium beam, and implications for higher LET beams are discussed. The major conclusions of this work are that, for helium over the LET range of 2 to 16 keV/mu, uncertainties in measuring alpha and beta for a given cell type which are of the order of 20% or less have a negligible effect on the beam-modulator design (i.e., on the slope of the spread Bragg peak); uncertainties less than or equal to 10% in the dose-averaged LET at each depth are unimportant; and, if the linear-quadratic variables for the tumor differ from those used in the beam-modulator design by a constant factor between about 0.5 and 3, then the resultant nonuniformity in the photon-equivalent dose delivered to the tumor is within +/- 25%. It is also shown that for any ion, if the nominal values of alpha or beta used by the beam-modulator design program differ from their actual values by a constant factor, then the maximum errors possible in the beam-modulator design may be characterized by two limiting depth-dose curves such that the ratio of the dose at the proximal end of the spread Bragg curve to the dose at the distal end of the spread peak is given by alpha distal/alpha prox for the steepest curve, and square root of beta distal/beta prox for the flattest curve.

Neutron interstitial brachytherapy for malignant gliomas: a pilot study.

Fifty-six patients with malignant glioma were treated with implantation of the neutron-emitting element californium-252 (252Cf) within 2 weeks after surgical debulking of the tumor. Implantation was performed using computerized tomography-guided placement of afterloading catheters, and the 252 Cf sources were removed after approximately 300 neutron rads were delivered. Patients then received 6000 to 7000 conventional photon rads by external beam. The total photon-equivalent dose to the tumor ranged from 8100 to 9100 rads. The median survival time was 10 months, with 18-and 24-month survival rates of 28% and 19%, respectively. The results of reoperation or autopsy showed that patients had recurrence of the tumor but that radiation necrosis was restricted to the area of the original tumor. Serious complications occurred in five patients (9%) and consisted of wound infections in three, cerebral edema in one, and radiation necrosis beyond the original tumor margin in one. Previous studies using external-beam neutron radiation have shown that neutrons are capable of totally eradicating malignant gliomas; however, in most cases, unacceptable widespread radiation necrosis has resulted. Neutron implants are a logical way to increase the dose to the tumor and decrease the dose to normal brain. Interstitial neutron radiation can be given safely with 252Cf, and the survival results achieved by radiation alone using relatively low doses of interstitial neutron radiation from 252Cf implants plus conventional photon radiation were equal to the results attained with any currently available conventional therapy.

Neutron and photon measurements through concrete from a 15 GeV electron beam on a target — Comparison with models and calculations

Measurements of neutron and phonon dose equivalents from a 15 GeV electron beam striking an iron target inside a scale model of a PEP IR hall are described, and compared with analytic-empirical calculations and with the Monte Carlo code, MORSE. The MORSE code is able to predict both absolute neutron and photon dose equivalents for geometries where the shield is relatively thin, but fails as the shield thickness is increased. An intermediate energy source term is postulated for analytic-empirical neutron shielding calculations to go along with the giant resonance and high energy terms, and a new source term due to neutron capture is postulated for analytic-empirical photon shielding calculations. The source strengths for each energy source term, and each type, are given from analysis of the measurements.

The lateral spread of high-energy (⩽ 400 MeV) neutron beams and earthshine

Calculated results obtained using the method of discrete ordinates are presented for the cases of zero-width beams of 100- and 400-MeV neutrons normally incident along the axis of a cylindrical shield of silicon dioxide with 5% water by weight. The results include the omnidirectional neutron flux per unit energy as a function of depth and radius in the shield and the neutron and photon dose equivalents as a function of depth and radius in the shield. In the vicinity of well shielded target areas of high-energy accelerators, the neutrons and protons which diffuse through the ground under the shield, “earthshine”, often pose a radiation hazard. Calculated results of the earthshine from a 400-MeV neutron source in a specific geometry are presented and discussed.